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Sample records for lng facility siting

  1. 49 CFR 193.2019 - Mobile and temporary LNG facilities.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS General § 193.2019 Mobile and temporary LNG facilities. (a) Mobile and temporary LNG facilities for peakshaving application, for service maintenance... 49 Transportation 3 2014-10-01 2014-10-01 false Mobile and temporary LNG facilities....

  2. 49 CFR 193.2019 - Mobile and temporary LNG facilities.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS General § 193.2019 Mobile and temporary LNG facilities. (a) Mobile and temporary LNG facilities for peakshaving application, for service maintenance... 49 Transportation 3 2012-10-01 2012-10-01 false Mobile and temporary LNG facilities....

  3. 49 CFR 193.2019 - Mobile and temporary LNG facilities.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS General § 193.2019 Mobile and temporary LNG facilities. (a) Mobile and temporary LNG facilities for peakshaving application, for service maintenance... 49 Transportation 3 2013-10-01 2013-10-01 false Mobile and temporary LNG facilities....

  4. 49 CFR 193.2019 - Mobile and temporary LNG facilities.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS General § 193.2019 Mobile and temporary LNG facilities. (a) Mobile and temporary LNG facilities for peakshaving application, for service maintenance... 49 Transportation 3 2011-10-01 2011-10-01 false Mobile and temporary LNG facilities....

  5. 49 CFR 193.2019 - Mobile and temporary LNG facilities.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS General § 193.2019 Mobile and temporary LNG facilities. (a) Mobile and temporary LNG facilities for peakshaving application, for service maintenance... 49 Transportation 3 2010-10-01 2010-10-01 false Mobile and temporary LNG facilities....

  6. Analysis of LNG peakshaving-facility release-prevention systems

    SciTech Connect

    Pelto, P.J.; Baker, E.G.; Powers, T.B.; Schreiber, A.M.; Hobbs, J.M.; Daling, P.M.

    1982-05-01

    The purpose of this study is to provide an analysis of release prevention systems for a reference LNG peakshaving facility. An overview assessment of the reference peakshaving facility, which preceeded this effort, identified 14 release scenarios which are typical of the potential hazards involved in the operation of LNG peakshaving facilities. These scenarios formed the basis for this more detailed study. Failure modes and effects analysis and fault tree analysis were used to estimate the expected frequency of each release scenario for the reference peakshaving facility. In addition, the effectiveness of release prevention, release detection, and release control systems were evaluated.

  7. 75 FR 54025 - Revision of LNG and LHG Waterfront Facility General Requirements

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-03

    ... final rule entitled ``Revision of LNG and LHG Waterfront Facility General Requirements'' (75 FR 29420... SECURITY Coast Guard 33 CFR Part 127 RIN 1625-AB13 Revision of LNG and LHG Waterfront Facility General... (WSA) requirements for liquefied natural gas (LNG) and liquefied hazardous gas (LHG) facilities....

  8. Raley's LNG Truck Site Final Data Report

    SciTech Connect

    Battelle

    1999-07-01

    Raley's is a 120-store grocery chain with headquarters in Sacramento, California, that has been operating eight heavy-duty LNG trucks (Kenworth T800 trucks with Cummins L10-300G engines) and two LNG yard tractors (Ottawa trucks with Cummins B5.9G engines) since April 1997. This report describes the results of data collection and evaluation of the eight heavy-duty LNG trucks compared to similar heavy-duty diesel trucks operating at Raley's. The data collection and evaluation are a part of the U.S. Department of Energy (DOE)/National Renewable Energy Laboratory (NREL) Alternative Fuel Truck Evaluation Project.

  9. Survey of fire-protection systems at LNG facilities. Topical report, July-November 1990

    SciTech Connect

    Atallah, S.; Borows, K.A.

    1991-04-05

    The objectives of the study were to collect and analyze data relating to the types, costs, and operational problems of gas leak and fire detection devices and of fire prevention and suppression systems used at LNG facilities operating in the United States. Data from 39 LNG facilities, which accounted for 45% of the total U.S. storage capacity, were collected. The report provides information relating to equipment manufacturers, site applications, operational problems, initial installation costs, annual operational costs, and equipment lifetime. Equipment of interest included fixed gas leak, fire and cryogenic detection systems, water deluge and barrier systems, thermal radiation walls and protective coatings, and fixed high expansion foam, dry chemical, carbon dioxide and halon fire suppression systems. In addition, internal fire fighting capabilities were reviewed.

  10. 75 FR 29420 - Revision of LNG and LHG Waterfront Facility General Requirements

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-05-26

    ... proposed rulemaking entitled ``Revision of LNG and LHG Waterfront Facility General Requirements'' (74 FR... easily be obtained from the facility-design specifications'' (60 FR ] 39788). Every LOI provided by an... Regulatory Commission FR Federal Register LHG Liquefied hazardous gas LNG Liquefied natural gas LOI Letter...

  11. 18 CFR 157.21 - Pre-filing procedures and review process for LNG terminal facilities and other natural gas...

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... and review process for LNG terminal facilities and other natural gas facilities prior to filing of... COMMISSION, DEPARTMENT OF ENERGY REGULATIONS UNDER NATURAL GAS ACT APPLICATIONS FOR CERTIFICATES OF PUBLIC CONVENIENCE AND NECESSITY AND FOR ORDERS PERMITTING AND APPROVING ABANDONMENT UNDER SECTION 7 OF THE...

  12. 18 CFR 157.21 - Pre-filing procedures and review process for LNG terminal facilities and other natural gas...

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 33 CFR 127.007, and a Preliminary Waterway Suitability Assessment (WSA) with the U.S. Coast Guard... and review process for LNG terminal facilities and other natural gas facilities prior to filing of... COMMISSION, DEPARTMENT OF ENERGY REGULATIONS UNDER NATURAL GAS ACT APPLICATIONS FOR CERTIFICATES OF...

  13. 18 CFR 157.21 - Pre-filing procedures and review process for LNG terminal facilities and other natural gas...

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 33 CFR 127.007, and a Preliminary Waterway Suitability Assessment (WSA) with the U.S. Coast Guard... and review process for LNG terminal facilities and other natural gas facilities prior to filing of... COMMISSION, DEPARTMENT OF ENERGY REGULATIONS UNDER NATURAL GAS ACT APPLICATIONS FOR CERTIFICATES OF...

  14. 18 CFR 157.21 - Pre-filing procedures and review process for LNG terminal facilities and other natural gas...

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... and review process for LNG terminal facilities and other natural gas facilities prior to filing of... COMMISSION, DEPARTMENT OF ENERGY REGULATIONS UNDER NATURAL GAS ACT APPLICATIONS FOR CERTIFICATES OF PUBLIC CONVENIENCE AND NECESSITY AND FOR ORDERS PERMITTING AND APPROVING ABANDONMENT UNDER SECTION 7 OF THE...

  15. 18 CFR 157.21 - Pre-filing procedures and review process for LNG terminal facilities and other natural gas...

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 33 CFR 127.007, and a Preliminary Waterway Suitability Assessment (WSA) with the U.S. Coast Guard... and review process for LNG terminal facilities and other natural gas facilities prior to filing of... COMMISSION, DEPARTMENT OF ENERGY REGULATIONS UNDER NATURAL GAS ACT APPLICATIONS FOR CERTIFICATES OF...

  16. Adapting British gas LNG facilities to varying gas compositions: The SELEXOL {reg_sign} process and cryogenic separation

    SciTech Connect

    Dewing, R.A.; Waring, S.; Burns, D.

    1996-12-31

    The original design of the UK National Transmission System (NTS) included five peak shave LNG storage sites strategically located around the country. They now form part of the Storage business that offers gas services to gas transportation companies-these include non British Gas companies as well as other parts of British Gas itself. At these sites, natural gas can be taken from the NTS at the request of the gas transportation companies, treated to cryogenic specifications, and liquefied for storage. LNG can then be re-vaporized and re-injected into the NTS or local mains as required. In this way the whole NTS does not have to be sized for peak rates and increases in demand can be met very quickly. Each peak-shave site was originally designed to handle natural gas with CO{sub 2} levels of up to 1 mol% and with ethane and higher hydrocarbon (C{sub 2}+) levels that needed only limited reduction. However, as different natural gas reservoirs came on stream in the early 1990`s the level of CO{sub 2} and C{sub 2}+ in the NTS network began to rise, and significant modifications were required at four of the five LNG sites. 3 refs., 2 figs., 2 tabs.

  17. National Ignition Facility site requirements

    SciTech Connect

    1996-07-01

    The Site Requirements (SR) provide bases for identification of candidate host sites for the National Ignition Facility (NIF) and for the generation of data regarding potential actual locations for the facilities. The SR supplements the NIF Functional Requirements (FR) with information needed for preparation of responses to queries for input to HQ DOE site evaluation. The queries are to include both documents and explicit requirements for the potential host site responses. The Sr includes information extracted from the NIF FR (for convenience), data based on design approaches, and needs for physical and organization infrastructure for a fully operational NIF. The FR and SR describe requirements that may require new construction or may be met by use or modification of existing facilities. The SR do not establish requirements for NIF design or construction project planning. The SR document does not constitute an element of the NIF technical baseline.

  18. 33 CFR 127.321 - Release of LNG.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Release of LNG. 127.321 Section... Waterfront Facilities Handling Liquefied Natural Gas Operations § 127.321 Release of LNG. (a) The operator of the waterfront facility handling LNG shall ensure that— (1) No person releases LNG into the...

  19. 33 CFR 127.321 - Release of LNG.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 33 Navigation and Navigable Waters 2 2011-07-01 2011-07-01 false Release of LNG. 127.321 Section... Waterfront Facilities Handling Liquefied Natural Gas Operations § 127.321 Release of LNG. (a) The operator of the waterfront facility handling LNG shall ensure that— (1) No person releases LNG into the...

  20. 76 FR 78188 - Reconsideration of Letters of Recommendation for Waterfront Facilities Handling LNG and LHG

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-16

    ..., 2008, issue of the Federal Register (73 FR 3316). D. Public Meeting We do not now plan to hold a public... the Port DHS Department of Homeland Security FR Federal Register LHG Liquefied hazardous gas LNG... changed that process in a rule updating the letter of intent and LOR regulations (75 FR 29420, Revision...

  1. 77 FR 70886 - Reconsideration of Letters of Recommendation for Waterfront Facilities Handling LNG and LHG

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-11-28

    ... information about the safety and security of the waterway (76 FR 78190). In our NPRM we provided notice and... Commission FR Federal Register LHG Liquefied hazardous gas LNG Liquefied natural gas LOI Letter of Intent LOR... the Federal Register (76 FR ] 78188). We received two letters commenting on the proposed rule....

  2. Optimize facility-siting evaluations

    SciTech Connect

    Wallace, S.J.; Hunter, B.L. )

    1994-05-01

    Case histories show how to combine hazard-evaluation tools that effectively assess facility siting. Depending on the complexity of the process and equipment, more than one tool and hazard analysis method (HAZOP, FMEA, etc.) may be needed. Operating facilities must use all possible resources such as checklists, plot plans/elevation drawings, models, tours, etc., when performing a process hazard analysis (PHA). More importantly, the facility-siting evaluation techniques must be cost-effective, user friendly and results oriented. Facility siting, mandated by federal regulation (OSHA 1910.119), calls for a how to methodology. Because it is an interpretation of risk due to location, facility siting has no single correct method. Operating companies must equip their PHA teams with an optimum combination of hazard-evaluation methods that address actual process consequences and their effects on worker safety. This paper discusses the use of these resources in hazard analysis, then illustrates the methods with several case histories from a refinery, a papermill, and a manufacturing facility.

  3. Site maps and facilities listings

    SciTech Connect

    Not Available

    1993-11-01

    In September 1989, a Memorandum of Agreement among DOE offices regarding the environmental management of DOE facilities was signed by appropriate Assistant Secretaries and Directors. This Memorandum of Agreement established the criteria for EM line responsibility. It stated that EM would be responsible for all DOE facilities, operations, or sites (1) that have been assigned to DOE for environmental restoration and serve or will serve no future production need; (2) that are used for the storage, treatment, or disposal of hazardous, radioactive, and mixed hazardous waste materials that have been properly characterized, packaged, and labelled, but are not used for production; (3) that have been formally transferred to EM by another DOE office for the purpose of environmental restoration and the eventual return to service as a DOE production facility; or (4) that are used exclusively for long-term storage of DOE waste material and are not actively used for production, with the exception of facilities, operations, or sites under the direction of the DOE Office of Civilian Radioactive Waste Management. As part of the implementation of the Memorandum of Agreement, Field Offices within DOE submitted their listings of facilities, systems, operation, and sites for which EM would have line responsibility. It is intended that EM facility listings will be revised on a yearly basis so that managers at all levels will have a valid reference for the planning, programming, budgeting and execution of EM activities.

  4. Facility siting and public opposition

    SciTech Connect

    O'Hare, M.H.; Bacow, L.; Sanderson, D.

    1983-01-01

    This book shows developers how to avoid expensive siting disputes that arise over regionally beneficial but locally undesirable facilities, such as prisons, landfills, and oil refineries. It explains the strategy by offering compensation to communities. Guidelines are included for keeping the public informed without increasing opposition.

  5. Development of polymer concrete for dike insulation at LNG (Liquid Natural Gas) facilities. Final report, August 1983-July 1984

    SciTech Connect

    Fontana, J.J.; Steinberg, M.

    1984-11-01

    An insulating polymer concrete (IPC) composite has been developed for possible use as a dike insulation material at Liquid Natural Gas (LNG) storage facilities. Using hermetically sealed glass nodules or expanded perlite aggregates and unsaturated polyester resins, a new class of lightweight polymer concretes can be manufactured. Two application procedures have been identified and shown to be feasible in laboratory studies. Precast IPC composite panels 1-in thick can be bonded to concrete substrates using epoxy gel type adhesives or mortars. Cast-in-place IPC to concrete substrates have been shown to have good bonding and insulating characteristics. Modifications of the mix design to improve the workability and sagging of the IPC for installation on vertical or sloped surfaces is necessary.

  6. LNG risk management

    NASA Astrophysics Data System (ADS)

    Martino, P.

    1980-12-01

    A general methodology is presented for conducting an analysis of the various aspects of the hazards associated with the storage and transportation of liquefied natural gas (LNG) which should be considered during the planning stages of a typical LNG ship terminal. The procedure includes the performance of a hazards and system analysis of the proposed site, a probability analysis of accident scenarios and safety impacts, an analysis of the consequences of credible accidents such as tanker accidents, spills and fires, the assessment of risks and the design and evaluation of risk mitigation measures.

  7. Research of design challenges and new technologies for floating LNG

    NASA Astrophysics Data System (ADS)

    Lee, Dong-Hyun; Ha, Mun-Keun; Kim, Soo-Young; Shin, Sung-Chul

    2014-06-01

    With the rate of worldwide LNG demand expected to grow faster than that of gas demand, most major oil companies are currently investing their resources to develop floating LNG-FLNG (i.e. LNG FSRU and LNG FPSO). The global Floating LNG (FLNG) market trend will be reviewed based on demand and supply chain relationships. Typical technical issues associated with FLNG design are categorized in terms of global performance evaluation. Although many proven technologies developed through LNG carrier and oil FPSO projects are available for FLNG design, we are still faced with several technical challenges to clear for successful FLNG projects. In this study, some of the challenges encountered during development of the floating LNG facility (i.e. LNG FPSO and FSRU) will be reviewed together with their investigated solution. At the same time, research of new LNG-related technologies such as combined containment system will be presented.

  8. Preliminary siting characterization Salt Disposition Facility - Site B

    SciTech Connect

    Wyatt, D.

    2000-01-04

    A siting and reconnaissance geotechnical program has been completed in S-Area at the Savannah River Site in South Carolina. This program investigated the subsurface conditions for the area known as ``Salt Disposition Facility (SDF), Site B'' located northeast of H-Area and within the S-Area. Data acquired from the Site B investigation includes both field exploration and laboratory test data.

  9. Strategic evaluation central to LNG project formation

    SciTech Connect

    Nissen, D.; DiNapoli, R.N.; Yost, C.C.

    1995-07-03

    An efficient-scale, grassroots LNG facility of about 6 million metric tons/year capacity requires a prestart-up outlay of $5 billion or more for the supply facilities--production, feedgas pipeline, liquefaction, and shipping. The demand side of the LNG chain requires a similar outlay, counting the import-regasification terminal and a combination of 5 gigawatts or more of electric power generation or the equivalent in city gas and industrial gas-using facilities. There exist no well-developed commodity markets for free-on-board (fob) or delivered LNG. A new LNG supply project is dedicated to its buyers. Indeed, the buyers` revenue commitment is the project`s only bankable asset. For the buyer to make this commitment, the supply venture`s capability and commitment must be credible: to complete the project and to deliver the LNG reliably over the 20+ years required to recover capital committed on both sides. This requirement has technical, economic, and business dimensions. In this article the authors describe a LNG project evaluation system and show its application to typical tasks: project cost of service and participant shares; LNG project competition; alternative project structures; and market competition for LNG-supplied electric power generation.

  10. Development of polymer concrete for dike insulation at LNG facilities: Phase 4, Low cost materials

    SciTech Connect

    Kukacka, L.E.

    1991-01-01

    Earlier GRI-sponsored work at Brookhaven National Laboratory has resulted in the development and utilization of insulating polymer concrete composites (IPC) as a means of reducing the evaporation rate of liquified natural gas in the event of a spill into a containment dike, thereby improving the safety at these sites. Although all of the required properties can be attained with the IPC, it was estimated that a low-cost replacement for the expensive organic binder would be necessary before use of the material would be cost-effective. In the current program, several latex modified cement formulations were evaluated and the most promising one identified. A mixture of two carboxylated styrene-butadiene latexes was selected for use in detailed laboratory property characterizations and a subsequent field evaluation. When compared to the properties of IPC, the latex-modified insulating materials display somewhat higher thermal conductivities, greater permeability to water, and reduced strength. However, these properties still meet most of the performance criteria, and the unit cost of the material is less than one-fifth that of IPC made with epoxy binders. When installed as a 0.75-in. thick overlay, material costs are estimated to be $1.00/ft{sup 2}.

  11. Nevada Test Site Sensor Test Facility

    SciTech Connect

    Gomez, B.J.; Boyer, W.B.

    1996-12-01

    A Sensor Test Facility (STF) was recently established at the Department of Energy`s Nevada Test Site (NTS). It has been used for a series of sensor tests that have demonstrated the usefulness of the testbed. The facility consists of a cut-and-cover bunker complex and the two square mile surrounding area. The STF was developed as a scientific testbed optimized for the development and evaluation of advanced sensor systems, including ground sensor systems designed to identify and detect hardened underground facilities. This was accomplished by identifying a facility in a remote location where seismic, acoustic, and electromagnetic interference would be minimal, establishing a testbed that would be accommodating to field testing, and conducting a thorough geophysical characterization of the area surrounding the facility in order to understand the local geology and its effects on geophysical signals emanating from the facility. The STF is representative of a number of cut-and-cover bunkers around the world that are used for the manufacture and/or storage of weapons of mass destruction. This paper provides a general description of the Nevada Test Site, the Sensor Test Facility, and the Geophysical Site Characterization.

  12. Regional analysis of energy facility siting

    SciTech Connect

    Lipfert, F W; Meier, P M; Kleinman, L I

    1980-01-01

    This paper has examined some of the regional environmental parameters of energy facility siting, with emphasis on air quality impacts. An example of a siting optimization study was presented, and it was shown how difficult it presently is to specify an environmental objective function that is universally applicable. The importance of regional background effects was discussed, and long-range transport models were used to analyze the relative importance of local and long-range impacts.

  13. LNG fire and vapor control system technologies

    SciTech Connect

    Konzek, G.J.; Yasutake, K.M.; Franklin, A.L.

    1982-06-01

    This report provides a review of fire and vapor control practices used in the liquefied natural gas (LNG) industry. Specific objectives of this effort were to summarize the state-of-the-art of LNG fire and vapor control; define representative LNG facilities and their associated fire and vapor control systems; and develop an approach for a quantitative effectiveness evaluation of LNG fire and vapor control systems. In this report a brief summary of LNG physical properties is given. This is followed by a discussion of basic fire and vapor control design philosophy and detailed reviews of fire and vapor control practices. The operating characteristics and typical applications and application limitations of leak detectors, fire detectors, dikes, coatings, closed circuit television, communication systems, dry chemicals, water, high expansion foam, carbon dioxide and halogenated hydrocarbons are described. Summary descriptions of a representative LNG peakshaving facility and import terminal are included in this report together with typical fire and vapor control systems and their locations in these types of facilities. This state-of-the-art review identifies large differences in the application of fire and vapor control systems throughout the LNG industry.

  14. National Ignition Facility Project Site Safety Program

    SciTech Connect

    Dun, C

    2003-09-30

    This Safety Program for the National Ignition Facility (NIF) presents safety protocols and requirements that management and workers shall follow to assure a safe and healthful work environment during activities performed on the NIF Project site. The NIF Project Site Safety Program (NPSSP) requires that activities at the NIF Project site be performed in accordance with the ''LLNL ES&H Manual'' and the augmented set of controls and processes described in this NIF Project Site Safety Program. Specifically, this document: (1) Defines the fundamental NIF site safety philosophy. (2) Defines the areas covered by this safety program (see Appendix B). (3) Identifies management roles and responsibilities. (4) Defines core safety management processes. (5) Identifies NIF site-specific safety requirements. This NPSSP sets forth the responsibilities, requirements, rules, policies, and regulations for workers involved in work activities performed on the NIF Project site. Workers are required to implement measures to create a universal awareness that promotes safe practice at the work site and will achieve NIF management objectives in preventing accidents and illnesses. ES&H requirements are consistent with the ''LLNL ES&H Manual''. This NPSSP and implementing procedures (e.g., Management Walkabout, special work procedures, etc.,) are a comprehensive safety program that applies to NIF workers on the NIF Project site. The NIF Project site includes the B581/B681 site and support areas shown in Appendix B.

  15. Nuclear facility decommissioning and site remedial actions

    SciTech Connect

    Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

    1989-09-01

    The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords.

  16. Nuclear facility decommissioning and site remedial actions

    SciTech Connect

    Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

    1990-09-01

    The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies.

  17. 20 CFR 638.303 - Site selection and facilities management.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... center, facilities engineering and real estate management will be conducted by the Job Corps Director or... 20 Employees' Benefits 3 2012-04-01 2012-04-01 false Site selection and facilities management. 638... Facilities Management § 638.303 Site selection and facilities management. (a) The Job Corps Director...

  18. Cold vacuum drying facility site evaluation report

    SciTech Connect

    Diebel, J.A.

    1996-03-11

    In order to transport Multi-Canister Overpacks to the Canister Storage Building they must first undergo the Cold Vacuum Drying process. This puts the design, construction and start-up of the Cold Vacuum Drying facility on the critical path of the K Basin fuel removal schedule. This schedule is driven by a Tri-Party Agreement (TPA) milestone requiring all of the spent nuclear fuel to be removed from the K Basins by December, 1999. This site evaluation is an integral part of the Cold Vacuum Drying design process and must be completed expeditiously in order to stay on track for meeting the milestone.

  19. 49 CFR 193.2623 - Inspecting LNG storage tanks.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 49 Transportation 3 2010-10-01 2010-10-01 false Inspecting LNG storage tanks. 193.2623 Section 193.2623 Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS... GAS FACILITIES: FEDERAL SAFETY STANDARDS Maintenance § 193.2623 Inspecting LNG storage tanks. Each...

  20. 49 CFR 193.2623 - Inspecting LNG storage tanks.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 3 2011-10-01 2011-10-01 false Inspecting LNG storage tanks. 193.2623 Section 193.2623 Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS... GAS FACILITIES: FEDERAL SAFETY STANDARDS Maintenance § 193.2623 Inspecting LNG storage tanks. Each...

  1. 75 FR 11169 - AES Sparrows Point LNG, LLC; Mid-Atlantic Express, LLC; Notice of Availability of the Revised...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-10

    ... Sparrows Point LNG Terminal and Pipeline Project March 1, 2010. The staff of the Federal Energy Regulatory... operation of a liquefied natural gas (LNG) import terminal and natural gas pipeline proposed by AES Sparrows... LNG terminal and natural gas pipeline facilities: A ship unloading facility, with two berths,...

  2. 75 FR 353 - AES Sparrows Point LNG, LLC and Mid-Atlantic Express, LLC; Notice of Availability of the Final...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-05

    ... Terminal and Pipeline Project December 29, 2009. The staff of the Federal Energy Regulatory Commission... natural gas (LNG) import terminal and natural gas pipeline proposed by AES Sparrows Point LNG, LLC and Mid... operation of the following LNG terminal and natural gas pipeline facilities: A ship unloading facility,...

  3. Method for siting detectors within a facility

    DOEpatents

    Gleason, Nathaniel Jeremy Meyer

    2007-12-11

    A method, system and article of manufacture of siting one or more detectors in a facility represented with zones are provided. Signals S.sub.i,j representing an effect in zone j in response to a release of contaminant in zone i for one or more flow conditions are provided. A candidate architecture has one or more candidate zones. A limiting case signal is determined for each flow condition for multiple candidate architectures. The limiting case signal is a smallest system signal of multiple system signals associated with a release in a zone. Each system signal is a maximum one of the signals representing the effect in the candidate zones from the release in one zone for the flow condition. For each candidate architecture, a robust limiting case signal is determined based on a minimum of the limiting case signals. One candidate architecture is selected based on the robust limiting case signals.

  4. 20 CFR 638.303 - Site selection and facilities management.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 20 Employees' Benefits 3 2011-04-01 2011-04-01 false Site selection and facilities management. 638.303 Section 638.303 Employees' Benefits EMPLOYMENT AND TRAINING ADMINISTRATION, DEPARTMENT OF LABOR JOB CORPS PROGRAM UNDER TITLE IV-B OF THE JOB TRAINING PARTNERSHIP ACT Funding, Site Selection, and Facilities Management § 638.303 Site...

  5. 20 CFR 638.303 - Site selection and facilities management.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 20 Employees' Benefits 3 2010-04-01 2010-04-01 false Site selection and facilities management. 638.303 Section 638.303 Employees' Benefits EMPLOYMENT AND TRAINING ADMINISTRATION, DEPARTMENT OF LABOR JOB CORPS PROGRAM UNDER TITLE IV-B OF THE JOB TRAINING PARTNERSHIP ACT Funding, Site Selection, and Facilities Management § 638.303 Site...

  6. Comparative safety analysis of LNG storage tanks

    SciTech Connect

    Fecht, B.A.; Gates, T.E.; Nelson, K.O.; Marr, G.D.

    1982-07-01

    LNG storage tank design and response to selected release scenarios were reviewed. The selection of the scenarios was based on an investigation of potential hazards as cited in the literature. A review of the structure of specific LNG storage facilities is given. Scenarios initially addressed included those that most likely emerge from the tank facility itself: conditions of overfill and overflow as related to liquid LNG content levels; over/underpressurization at respective tank vapor pressure boundaries; subsidence of bearing soil below tank foundations; and crack propagation in tank walls due to possible exposure of structural material to cryogenic temperatures. Additional scenarios addressed include those that result from external events: tornado induced winds and pressure drops; exterior tank missile impact with tornado winds and rotating machinery being the investigated mode of generation; thermal response due to adjacent fire conditions; and tank response due to intense seismic activity. Applicability of each scenario depended heavily on the specific tank configurations and material types selected. (PSB)

  7. 24 CFR 984.204 - On-site facilities.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 24 Housing and Urban Development 4 2011-04-01 2011-04-01 false On-site facilities. 984.204 Section 984.204 Housing and Urban Development REGULATIONS RELATING TO HOUSING AND URBAN DEVELOPMENT (CONTINUED... § 984.204 On-site facilities. Each PHA may, subject to the approval of HUD, make available and...

  8. Trainer Guide: Site and Facilities Managerial. Camp Administration Series.

    ERIC Educational Resources Information Center

    Farley, Elizabeth, Ed.

    Composed of two units, the managerial trainer guide addresses the planning and maintenance of camp site and facilities. Designed to provide the camp director with the knowledge and skills necessary to plan and maintain the site and facilities, the guide includes a pre-assessment checklist, performance objectives, suggested activities and…

  9. 77 FR 60125 - Generic Drug Facilities, Sites and Organizations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-02

    ... HUMAN SERVICES Food and Drug Administration Generic Drug Facilities, Sites and Organizations AGENCY: Food and Drug Administration, HHS. ACTION: Notice of Requirement. SUMMARY: The Food and Drug Administration (FDA) is notifying generic drug facilities, and certain sites and organizations identified in...

  10. Site and Facilities: A Resource Book for Camps.

    ERIC Educational Resources Information Center

    Ball, Armand, Ed.; Ball, Beverly, Ed.

    This resource book draws together articles on the development and maintenance of camp sites and facilities. The articles, previously published by "Camping Magazine" and "Journal of Christian Camping," cover (1) site planning and long-range development, including redesigning multiple camp facilities for year-round programs, remodeling and…

  11. Monitored retrievable storage facility site screening and evaluation report

    SciTech Connect

    none,

    1985-05-01

    The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed site and facility designs...'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluated potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the task force presented in this report includes: site screening (Sections 3, 4, and 5), the MRS facilities which are to be sited are described; the criteria, process and outcome of the screening process is presented; and descriptions of the candidate MRS facility sites are given, and site evaluations (Sections 6 through 9) where the rational for the site evaluations are presented, along with each evaluation and findings of the Task Force.

  12. Savannah River Site Surplus Facilities Available for Reuse

    SciTech Connect

    Clarke, R.M.; Owens, M.B.; Lentz, D.W.

    1995-09-14

    The purpose of this document is to provide a current, centralized list of Savannah River Site facilities, which are surplus and available for reuse. These surplus facilities may be made available for other DOE site missions, commercial economic development reuse, or other governmental reuse. SRS procedures also require that before new construction can be approved, available surplus facilities are screened for possible reuse in lieu of the proposed new construction.

  13. The Asia Pacific LNG trade: Status and technology development

    SciTech Connect

    Hovdestad, W.R.

    1995-10-01

    The Asia Pacific Region is experiencing a period of sustained economic expansion. Economic growth has led to an increasing demand for energy that has spurred a rapid expansion of baseload liquefied natural gas (LNG) facilities in this region. This is illustrated by the fact that seven of the ten baseload facilities in existence provide LNG for markets in the Asia Pacific region. With the three exceptions having been initially commissioned in 1972 and earlier, it is fair to observed that most advances in LNG technology have been developed and applied for this market. The paper presents the current status and identified future trends for the Asia Pacific LNG trade. Technology development in terms of application to onstream production, processing and transportation facilities, including LNG tankers, is presented. The potential of future advances to applied technology and operational practices to improve the cost-effectiveness of new and existing facilities is discussed. Current design data and methods as actually used are examined in terms of identifying where fundamental research and basic physical data are insufficient for optimization purposes. These findings are then summarized and presented in terms of the likely evolution of future and existing LNG projects in the Asia Pacific region.

  14. Hanford Site existing irradiated fuel storage facilities description

    SciTech Connect

    Willis, W.L.

    1995-01-11

    This document describes facilities at the Hanford Site which are currently storing spent nuclear fuels. The descriptions provide a basis for the no-action alternatives of ongoing and planned National Environmental Protection Act reviews.

  15. Site Selection for Surplus Plutonium Disposition Facilities at the Savannah River Site

    SciTech Connect

    Wike, L.D.

    2000-08-17

    A site selection study was conducted to evaluate locations for the proposed Surplus Plutonium Disposition Facilities. Facilities to be located include the Mixed Oxide (MOX) Fuel Fabrication Facility, the Pit Disassembly and Conversion Facility (PDCF), and the Plutonium Immobilization Project (PIP) facility. Objectives of the study include: (1) Confirm that the Department of Energy (DOE) selected locations for the MOX and PDCF were suitable based on selected siting criteria, (2) Recommend a site in the vicinity of F Area that is suitable for the PIP, and (3) Identify alternative suitable sites for one or more of these facilities in the event that further geotechnical characterization or other considerations result in disqualification of a currently proposed site.

  16. 78 FR 22553 - Generic Drug Facilities, Sites, and Organizations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-04-16

    ... HUMAN SERVICES Food and Drug Administration Generic Drug Facilities, Sites, and Organizations AGENCY: Food and Drug Administration, HHS. ACTION: Notice. SUMMARY: The Food and Drug Administration (FDA) is announcing that the generic drug facility self-identification reporting period for fiscal year (FY) 2014...

  17. Facility Siting as a Decision Process at the Savannah River Site

    SciTech Connect

    Wike, L.D.

    2001-07-24

    This document is based upon previous site selection exercises conducted for a variety of proposed facilities. It develops the logic and basis for the methods employed, and standardizes the process and terminology for future site selection efforts.

  18. Qualitative Risk Assessment for an LNG Refueling Station and Review of Relevant Safety Issues

    SciTech Connect

    Siu, N.; Herring, J.S.; Cadwallader, L.; Reece, W.; Byers, J.

    1998-02-01

    This report is a qualitative assessment of the public and worker risk involved with the operation of a liquefied natural gas (LNG) vehicle refueling facility. This study includes facility maintenance and operations, tank truck deliveries, and end-use vehicle fueling; it does not treat the risks of LNG vehicles on roadways. Accident initiating events are identified by using a Master Logic Diagram, a Failure Modes and Effects Analysis, and historical operating experiences. The event trees were drawn to depict possible sequences of mitigating events following the initiating events. The phenomenology of LNG and other vehicle fuels is discussed to characterize the hazard posed by LNG usage. Based on the risk modeling and analysis, recommendations are given to improve the safety of LNG refueling stations in the areas of procedures and training, station design, and the dissemination of ``best practice`` information throughout the LNG community.

  19. Interim qualitative risk assessment for an LNG refueling station and review of relevant safety issues

    SciTech Connect

    Siu, N.; Herring, S.; Cadwallader, L.; Reece, W.; Byers, J.

    1997-07-01

    This report is a qualitative assessment of the public and worker risk involved with the operation of a liquefied natural (LNG) vehicle refueling facility. This study includes facility maintenance and operations, tanker truck delivers and end-use vehicle fueling; it does not treat the risks of LNG vehicles on roadways. Accident initiating events are identified by using a Master Logic Diagram, a Failure Modes and Effects analysis and historical operating experiences. The event trees were drawn to depict possible sequences of mitigating events following the initiating events. The phenomenology of LNG and other vehicle fuels is discussed to characterize the hazard posed by LNG usage. Based on the risk modeling and analysis, recommendations are given to improve the safety of LNG refueling stations in the areas of procedures and training, station design, and the dissemination of best practice information throughout the LNG community.

  20. Overview study of LNG release prevention and control systems

    SciTech Connect

    Pelto, P.J.; Baker, E.G.; Holter, G.M.; Powers, T.B.

    1982-03-01

    The liquefied natural gas (LNG) industry employs a variety of release prevention and control techniques to reduce the likelihood and the consequences of accidental LNG releases. A study of the effectiveness of these release prevention and control systems is being performed. Reference descriptions for the basic types of LNG facilities were developed. Then an overview study was performed to identify areas that merit subsequent and more detailed analyses. The specific objectives were to characterize the LNG facilities of interest and their release prevention and control systems, identify possible weak links and research needs, and provide an analytical framework for subsequent detailed analyses. The LNG facilities analyzed include a reference export terminal, marine vessel, import terminal, peakshaving facility, truck tanker, and satellite facility. A reference description for these facilities, a preliminary hazards analysis (PHA), and a list of representative release scenarios are included. The reference facility descriptions outline basic process flows, plant layouts, and safety features. The PHA identifies the important release prevention operations. Representative release scenarios provide a format for discussing potential initiating events, effects of the release prevention and control systems, information needs, and potential design changes. These scenarios range from relatively frequent but low consequence releases to unlikely but large releases and are the principal basis for the next stage of analysis.

  1. Making or Breaking Waste Facility Siting Successes with a Siting Framework

    NASA Astrophysics Data System (ADS)

    Zeiss, Chris; Lefsrud, Lianne

    1996-01-01

    Waste facility siting successes depend on many linked factors of facility design and impacts, site characteristics, and community beliefs and values. A facility siting framework is constructed to combine important elements and cause-effect linkages that affect the siting outcome. The framework consists of three main components: (1) core elements of facility design, effects, and community beliefs, attitude and response; (2) contributing factors of site and community characteristics, community beliefs and values that affect the interpretation of the facility and its effects; and (3) siting management interventions to manage the process and facility impacts. The framework is applied in an unsuccessful and a successful siting case to determine the key elements that contribute to siting outcome: (1) thorough need justification for the facility from the proponent’s and the community’s perspective; (2) careful facility design and prediction of the impacts and to select impact management compensation measures; (3) screening and selection of communities where the beliefs and values are compatible with the type of facility and its effects, (4) cooperatively selected impact reduction (i.e., prevention, control, and mitigation) measures followed by compensation and incentives; and (5) intensive process management to balance the community characteristics and values with the proponent’s efforts to plan, design, assess and manage impacts, and ultimately, gain approval of the facility. The siting framework provides a comprehensive and robust structure of key factors that contribute to siting outcome and, therefore, provides the tool to identify, evaluate, and design siting interventions to enhance the chances of successful siting outcome.

  2. Introduction to LNG vehicle safety

    NASA Astrophysics Data System (ADS)

    Bratvold, Delma; Friedman, David; Chernoff, Harry; Farkhondehpay, Dariush; Comay, Claudia

    1994-03-01

    Basic information on the characteristics of liquefied natural gas (LNG) is assembled to provide an overview of safety issues and practices for the use of LNG vehicles. This document is intended for those planning or considering the use of LNG vehicles, including vehicle fleet owners and operators, public transit officials and boards, local fire and safety officials, manufacturers and distributors, and gas industry officials. Safety issues and mitigation measures that should be considered for candidate LNG vehicle projects are addressed.

  3. Monitored Retrievable Storage facility site screening and evaluation report

    SciTech Connect

    none,

    1985-05-01

    The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs {hor ellipsis}'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report, all site evaluations (sections 13 through 16) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This is Volume 3 of a three volume document. References are also included in this volume.

  4. Monitored retrievable storage facility site screening and evaluation report

    SciTech Connect

    none,

    1985-05-01

    The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs{hor ellipsis}'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report include: site evaluations (sections 10 through 12) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This in Volume 2 of a three volume document.

  5. Mixed waste disposal facilities at the Savannah River Site

    SciTech Connect

    Wells, M.N.; Bailey, L.L.

    1991-12-31

    The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE`s Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site`s waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission.

  6. Hanford tank initiative test facility site selection study

    SciTech Connect

    Staehr, T.W.

    1997-04-03

    The Hanford Tanks Initiative (HTI) project is developing equipment for the removal of hard heel waste from the Hanford Site underground single-shell waste storage tanks. The HTI equipment will initially be installed in the 241-C-106 tank where its operation will be demonstrated. This study evaluates existing Hanford Site facilities and other sites for functional testing of the HTI equipment before it is installed into the 241-C-106 tank.

  7. NN-SITE: A remote monitoring testbed facility

    SciTech Connect

    Kadner, S.; White, R.; Roman, W.; Sheely, K.; Puckett, J.; Ystesund, K.

    1997-08-01

    DOE, Aquila Technologies, LANL and SNL recently launched collaborative efforts to create a Non-Proliferation Network Systems Integration and Test (NN-Site, pronounced N-Site) facility. NN-Site will focus on wide area, local area, and local operating level network connectivity including Internet access. This facility will provide thorough and cost-effective integration, testing and development of information connectivity among diverse operating systems and network topologies prior to full-scale deployment. In concentrating on instrument interconnectivity, tamper indication, and data collection and review, NN-Site will facilitate efforts of equipment providers and system integrators in deploying systems that will meet nuclear non-proliferation and safeguards objectives. The following will discuss the objectives of ongoing remote monitoring efforts, as well as the prevalent policy concerns. An in-depth discussion of the Non-Proliferation Network Systems Integration and Test facility (NN-Site) will illuminate the role that this testbed facility can perform in meeting the objectives of remote monitoring efforts, and its potential contribution in promoting eventual acceptance of remote monitoring systems in facilities worldwide.

  8. Mixed waste disposal facilities at the Savannah River Site

    SciTech Connect

    Wells, M.N.; Bailey, L.L.

    1991-01-01

    The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE's Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site's waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission.

  9. New instrument calibration facility for the DOE Savannah River Site

    SciTech Connect

    Wilkie, W.H.; Polz, E.J.

    1993-12-31

    A new laboratory facility is being designed, constructed, and equipped at the Savannah River Site (SRS) as a fiscal year 1992 line item project. This facility will provide space and equipment for test, evaluation, repair, maintenance, and calibration of radiation monitoring instrumentation. The project will replace an obsolete facility and will allow implementation of program upgrades necessary to meet ANSI N323 requirements and National Voluntary Laboratory Accreditation Program (NVLAP) criteria for accreditation of federally owned secondary calibration laboratories. An outline of the project is presented including description, scope, cost, management organization, chronology, and current status. Selected design criteria and their impacts on the project are discussed. The upgraded SRS calibration program is described, and important features of the new facility and equipment that will accommodate this program are listed. The floor plan for the facility is shown, and equipment summaries and functional descriptions for each area are provided.

  10. Insulating LNG (liquified natural gas) storage tank containment dikes with a lightweight polymer concrete

    SciTech Connect

    Fontana, J.J.

    1987-08-01

    The natural gas industry has always been concerned ith accidental spills of liquified natural gas (LNG) from storage tanks into surrounding containment dikes. The LNG that is leaked to the dike area boils off and the vapors mix with the atmosphere forming a hazardous explsoive mixture within the dike walls. These hazardous mixtures can travel long distances into industrial or residential areas surroungind LNG storage facilities. Studies by the natural gas industry indicate that the hazards associated with accidental spills of LNG from storage tanks can be makedly reduced by insulating the diked areas surrounding these tanks. In this manner, the heat transfer from the dike surface to the LNG is reduced. The insulating composite is used to construct a thermal barrier between the walls and floor of the dike an the spilled LNG. The thermal conductivity, porosity, and compression strength of a concrete, polymer composite insulating material is discussed. 6 refs., 8 figs., 5 tbs.

  11. 77 FR 73627 - 2012 LNG Export Study

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-11

    ... Charles Exports, LLC, FE Docket No. 11-59-LNG, 76 FR 34212 (June 13, 2011); Dominion Cove Point LNG, LP, FE Docket No. 11-128-LNG, 76 FR 76698 (December 8, 2011); Carib Energy (USA) LLC, FE Docket No. 11-141-LNG, 76 FR 80913 (December 12, 2011); Freeport LNG Expansion, L.P. and FLNG Liquefaction, LLC,...

  12. Partial site release at a power reactor facility.

    PubMed

    Darman, Joseph; Whitney, Michael; Dubiel, Richard

    2004-01-01

    U.S. NRC licensed facilities undergoing decommissioning may wish to remove portions of their site from the jurisdiction of their license, prior to final license termination. The method of partial site release, relevant to radiological conditions, described herein employs NUREG-1505 methodology for demonstrating indistinguishability from background. The partial site release process was also informed by NRC Regulatory Issue Summary 2000-19 "Partial Release of Reactor Site for Unrestricted Use Before NRC Approval of the License Termination Plan." However, the focus of this discussion is the radiological aspects of partial site release, relevant to the implementation of NUREG-1505 methodology for demonstrating indistinguishability from background, based on the 137Cs concentrations at the site and a suitable background reference area. This type of approach was found acceptable by the NRC, and the partial site release was granted. PMID:14695009

  13. Facility siting as a decision process at the Savannah River Site

    SciTech Connect

    Wike, L.D.

    1995-12-31

    Site selection for new facilities at Savannah River Site (SRS) historically has been a process dependent only upon specific requirements of the facility. While this approach is normally well suited to engineering and operational concerns, it can have serious deficiencies in the modern era of regulatory oversight and compliance requirements. There are many issues related to the site selection for a facility that are not directly related to engineering or operational requirements; such environmental concerns can cause large schedule delays and budget impact,s thereby slowing or stopping the progress of a project. Some of the many concerns in locating a facility include: waste site avoidance, National Environmental Policy Act requirements, Clean Water Act, Clean Air Act, wetlands conservation, US Army Corps of Engineers considerations, US Fish and Wildlife Service statutes including threatened and endangered species issues, and State of South Carolina regulations, especially those of the Department of Health and Environmental Control. In addition, there are SRS restrictions on research areas set aside for National Environmental Research Park (NERP), Savannah River Ecology Laboratory, Savannah River Forest Station, University of South Carolina Institute of Archaeology and Anthropology, Southeastern Forest Experimental Station, and Savannah River Technology Center (SRTC) programs. As with facility operational needs, all of these siting considerations do not have equal importance. The purpose of this document is to review recent site selection exercises conducted for a variety of proposed facilities, develop the logic and basis for the methods employed, and standardize the process and terminology for future site selection efforts.

  14. Risk management study for the retired Hanford Site facilities: Qualitative risk evaluation for the retired Hanford Site facilities. Volume 3

    SciTech Connect

    Coles, G.A.; Shultz, M.V.; Taylor, W.E.

    1993-09-01

    This document provides a risk evaluation of the 100 and 200 Area retired, surplus facilities on the Hanford Site. Also included are the related data that were compiled by the risk evaluation team during investigations performed on the facilities. Results are the product of a major effort performed in fiscal year 1993 to produce qualitative information that characterizes certain risks associated with these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1,450-km{sup 2} (570-mi{sup 2}) Hanford Site. The Hanford Site is a semiarid tract of land in southeastern Washington State. The nearest population center is Richland, Washington, (population 32,000) 30-km (20 mi) southeast of the 200 Area. During walkdown investigations of these facilities, data on real and potential hazards that threatened human health or safety or created potential environmental release issues were identified by the risk evaluation team. Using these findings, the team categorized the identified hazards by facility and evaluated the risk associated with each hazard. The factors contributing to each risk, and the consequence and likelihood of harm associated with each hazard also are included in this evaluation.

  15. LNG annotated bibliography

    SciTech Connect

    Bomelburg, H.J.; Counts, C.A.; Cowan, C.E.; Davis, W.E.; DeSteese, J.G.; Pelto, P.J.

    1982-09-01

    This document updates the bibliography published in Liquefied Gaseous Fuels Safety and Environmental Control Assessment Program: third status report (PNL-4172) and is a complete listing of literature reviewed and reported under the LNG Technical Surveillance Task. The bibliography is organized alphabetically by author.

  16. Earthquake research for the safer siting of critical facilities

    SciTech Connect

    Cluff, J.L.

    1980-01-01

    The task of providing the necessities for living, such as adequate electrical power, water, and fuel, is becoming more complicated with time. Some of the facilities that provide these necessities would present potential hazards to the population if serious damage were to occur to them during earthquakes. Other facilities must remain operable immediately after an earthquake to provide life-support services to people who have been affected. The purpose of this report is to recommend research that will improve the information available to those who must decide where to site these critical facilities, and thereby mitigate the effects of the earthquake hazard. The term critical facility is used in this report to describe facilities that could seriously affect the public well-being through loss of life, large financial loss, or degradation of the environment if they were to fail. The term critical facility also is used to refer to facilities that, although they pose a limited hazard to the public, are considered critical because they must continue to function in the event of a disaster so that they can provide vital services.

  17. The Phoenix series large scale LNG pool fire experiments.

    SciTech Connect

    Simpson, Richard B.; Jensen, Richard Pearson; Demosthenous, Byron; Luketa, Anay Josephine; Ricks, Allen Joseph; Hightower, Marion Michael; Blanchat, Thomas K.; Helmick, Paul H.; Tieszen, Sheldon Robert; Deola, Regina Anne; Mercier, Jeffrey Alan; Suo-Anttila, Jill Marie; Miller, Timothy J.

    2010-12-01

    The increasing demand for natural gas could increase the number and frequency of Liquefied Natural Gas (LNG) tanker deliveries to ports across the United States. Because of the increasing number of shipments and the number of possible new facilities, concerns about the potential safety of the public and property from an accidental, and even more importantly intentional spills, have increased. While improvements have been made over the past decade in assessing hazards from LNG spills, the existing experimental data is much smaller in size and scale than many postulated large accidental and intentional spills. Since the physics and hazards from a fire change with fire size, there are concerns about the adequacy of current hazard prediction techniques for large LNG spills and fires. To address these concerns, Congress funded the Department of Energy (DOE) in 2008 to conduct a series of laboratory and large-scale LNG pool fire experiments at Sandia National Laboratories (Sandia) in Albuquerque, New Mexico. This report presents the test data and results of both sets of fire experiments. A series of five reduced-scale (gas burner) tests (yielding 27 sets of data) were conducted in 2007 and 2008 at Sandia's Thermal Test Complex (TTC) to assess flame height to fire diameter ratios as a function of nondimensional heat release rates for extrapolation to large-scale LNG fires. The large-scale LNG pool fire experiments were conducted in a 120 m diameter pond specially designed and constructed in Sandia's Area III large-scale test complex. Two fire tests of LNG spills of 21 and 81 m in diameter were conducted in 2009 to improve the understanding of flame height, smoke production, and burn rate and therefore the physics and hazards of large LNG spills and fires.

  18. Insulating polymer concrete for LNG impounding dikes. [Polymer concretes

    SciTech Connect

    Fontana, J.J.; Steinberg, M.

    1986-03-01

    An insulating polymer concrete (IPC) composite has been developed under contract to the Gas Research Institute for possible use as a dike insulation material at Liquid Natural Gas (LNG) storage facilities. In the advent of an LNG spill into the impounding dike area, the boiloff rate of the LNG can be substantially reduced if the surfaces of the dike are insulated. This increased safety at the LNG facility will tend to reduce the hazardous explosive mixture with atmospheric air in the surrounding region. The dike insulation material must have a low thermal conductivity and be unaffected by environmental conditions. The IPC composites developed consist of perlite or glass nodule aggregates bound together as a closed cell structure with a polyester resin. In addition to low thermal conductivity and porosity, these composites have correspondingly high strengths and, therefore, can carry transient loads of workmen and maintenance equipment. Prefabricated IPC panels have been installed experimentally and at least one utility is currently considering a complete installation at its LNG facility. 5 refs., 5 tabs.

  19. Perceived risk impacts from siting hazardous waste facilities

    SciTech Connect

    Hemphill, R.C.; Edwards, B.K.; Bassett, G.W. Jr.

    1992-08-01

    This paper describes methods for evaluating perception-based economic impacts resulting from siting hazardous waste facilities. Socioeconomic impact analysis has devoted increasing attention to the potential implications of changed public perceptions of risk due to an activity or situation. This contrasts with traditional socioecconomic impact analysis, which has been limited to measuring direct and indirect consequences of activities, e.g., the employment effects of placing a military base in a specified location. Approaches to estimating economic impacts due to changes in public perceptions are ex ante or ex post. The former predict impacts prior to the construction and operation of a facility, while the later is based on impacts that become evident only when the facility is up and running. The theoretical foundations and practical requirements for demonstrating impacts, resulting from the siting of a hazardous facility are described. The theoretical rationale supporting the study of perceived risk research is presented along with discussion of problems that arise in demonstrating the existence and measuring the quantitative importance of economic impacts due to changes in perceived risk. The high-level nuclear waste facility being considered in Nevada is presented as an example in which there is potential for impacts, but where the link between perceived risk and economic conditions has not yet been developed.

  20. Steady-state and dynamic simulation study on boil-off gas minimization and recovery strategies at LNG exporting terminals

    NASA Astrophysics Data System (ADS)

    Kurle, Yogesh

    Liquefied natural gas (LNG) is becoming one of the prominent clean energy sources with its abundance, high calorific value, low emission, and price. Vapors generated from LNG due to heat leak are called boil-off gas (BOG). As world-wide LNG productions are increasing fast, BOG generation and handling problems are becoming more critical. Also, due to stringent environmental regulations, flaring of BOG is not a viable option. In this study, typical Propane-and-Mixed-Refrigerant (C3-MR) process, storage facilities, and loading facilities are modeled and simulated to study BOG generation at LNG exporting terminals, including LNG processing, storage, and berth loading areas. Factors causing BOG are presented, and quantities of BOG generated due to each factor at each location are calculated under different LNG temperatures. Various strategies to minimize, recover, and reuse BOG are also studied for their feasibility and energy requirements. Rate of BOG generation during LNG loading---Jetty BOG (JBOG)---changes significantly with loading time. In this study, LNG vessel loading is simulated using dynamic process simulation software to obtain JBOG generation profile and to study JBOG recovery strategies. Also, fuel requirements for LNG plant to run steam-turbine driven compressors and gas-turbine driven compressors are calculated. Handling of JBOG generated from multiple loadings is also considered. The study would help proper handling of BOG problems in terms of minimizing flaring at LNG exporting terminals, and thus reducing waste, saving energy, and protecting surrounding environments.

  1. Risk management study for the Hanford Site facilities: Risk reduction cost comparison for the retired Hanford Site facilities. Volume 4

    SciTech Connect

    Coles, G.A.; Egge, R.G.; Senger, E.; Shultz, M.W.; Taylor, W.E.

    1994-02-01

    This document provides a cost-comparison evaluation for implementing certain risk-reduction measures and their effect on the overall risk of the 100 and 200 Area retired, surplus facilities. The evaluation is based on conditions that existed at the time the risk evaluation team performed facility investigations, and does not acknowledge risk-reduction measures that occurred soon after risk identification. This evaluation is one part of an overall risk management study for these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1450-km{sup 2} Hanford Site. The Hanford Site is a semiarid tract of land in southeastern Washington State. The nearest population center is Richland, Washington, (population 32,000) 30 km southeast of the 200 Area. This cost-comparison evaluation (1) determines relative costs for reducing risk to acceptable levels; (2) compares the cost of reducing risk using different risk-reduction options; and (3) compares the cost of reducing risks at different facilities. The result is an identification of the cost effective risk-reduction measures. Supporting information required to develop costs of the various risk-reduction options also is included.

  2. FACILITY DEACTIVATION AND DECOMMISSIONING AT THE SAVANNAH RIVER SITE

    SciTech Connect

    Gilmour, J; William Austin, W; Cathy Sizemore, C

    2007-01-31

    In February 2002, the U.S. Department of Energy initiated actions to expedite Cleanup, focus on significant and early risk reduction, and reduce costs at the Savannah River Site (SRS). In response SRS started on a project focused on completing the decommissioning of inactive facilities in T, D, and M Areas, areas that on the perimeter of the Site, by the end of 2006. In June 2003, the Department of Energy Savannah River Operations Office (DOE-SR), the South Carolina Department of Health and Environmental Control (SCDHEC), and the Environmental Protection Agency, Region 4 (EPA-4) endorsed a Memorandum of Agreement (MOA) concerning cleanup at the Savannah River Site (SRS). The vision of the Agreement is that SRS will reduce its operations footprint to establish a buffer zone at the perimeter if the Site, while the central core area of the Site will be reserved for continuing or future long-term operations. DOE-SR, EPA-4, and SCDHEC agreed that establishing this buffer zone and appropriately sequencing environmental restoration and decommissioning activities can lead to greater efficiency and accelerate completion of entire site areas. This vision is embodied in the concept of Area Completion--which integrated operations, deactivation and decommissioning (D&D), and soils and groundwater cleanup into a time-phased approach to completing all the work necessary to address the Cold War legacy. D&D addresses the ''footprint'' of the building or structure, while the soils and groundwater project addresses any environmental remediation that may be required in the underlying and surrounding soils and groundwater. Since then, {approx}250 facilities have been decommissioned at the SRS, ranging from guard stations to nuclear fuel production facilities.

  3. Expedited site characterization for remedial investigations at federal facilities

    SciTech Connect

    Burton, J.C.

    1994-04-01

    Argonne National Laboratory`s Expedited Side Characterization (ESC) methodology gives federal agencies a process for producing high-quality CERCLA and RCRA site characterizations and remedial investigations in a cost- and time-efficient manner. The ESC process has been successfully tested and applied at numerous federal facilities. Examples include expanded site investigations for the Department of Interior`s Bureau of Land Management and remedial investigations for the Commodity Credit Corporation/US Dept. of Agriculture (CCC/USDA). In particular, the CCC/USDA has been the major sponsor in the development of the ESC process at Argonne. The technical successes and the cost and time savings of the ESC process for these programs have been detailed in previous papers. The Argonne ESC is currently being implemented at a Department of Energy facility (Pantex) and is schedules for implementation in the Department of Defense base closure program in order to meet accelerated schedules for remedial actions by these agencies.

  4. Incentives and the siting of radioactive waste facilities

    SciTech Connect

    Carnes, S.A.; Copenhaver, E.D.; Reed, J.H.; Soderstrom, E.J.; Sorensen, J.H.; Peelle, E.; Bjornstad, D.J.

    1982-08-01

    The importance of social and institutional issues in the siting of nuclear waste facilities has been recognized in recent years. Limited evidence from a survey of rural Wisconsin residents in 1980 indicates that incentives may help achieve the twin goals of increasing local support and decreasing local opposition to hosting nuclear waste facilities. Incentives are classified according to functional categories (i.e., mitigation, compensation, and reward) and the conditions which may be prerequisites to the use of incentives are outlined (i.e., guarantee of public health and safety, some measure of local control, and a legitimation of negotiations during siting). Criteria for evaluating the utility of incentives in nuclear waste repository siting are developed. Incentive packages may be more useful than single incentives, and nonmonetary incentives, such as independent monitoring and access to credible information, may be as important in eliciting support as monetary incentives. Without careful attention to prerequisites in the siting process it is not likely that incentives will facilitate the siting process.

  5. Federal Facilities Compliance Act, Conceptual Site Treatment Plan. Part 1

    SciTech Connect

    1993-10-29

    This Conceptual Site Treatment Plan was prepared by Ames Laboratory to meet the requirements of the Federal Facilities Compliance Act. Topics discussed in this document include: general discussion of the plan, including the purpose and scope; technical aspects of preparing plans, including the rationale behind the treatability groupings and a discussion of characterization issues; treatment technology needs and treatment options for specific waste streams; low-level mixed waste options; TRU waste options; and future waste generation from restoration activities.

  6. Nuclear facility decommissioning and site remedial actions: a selected bibliography

    SciTech Connect

    Owen, P.T.; Knox, N.P.; Fielden, J.M.; Johnson, C.A.

    1982-09-01

    This bibliography contains 693 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. Foreign, as well as domestic, literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Uranium Mill Tailings Remedial Action Program, Grand Junction Remedial Action Program, and Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General Studies. The references within each chapter are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for (1) author; (2) corporate affiliation; (3) title; (4) publication description; (5) geographic location; and (6) keywords. An appendix of 202 bibliographic references without abstracts or indexes has been included in this bibliography. This appendix represents literature identified but not abstracted due to time constraints.

  7. Sensor test facilities and capabilities at the Nevada Test Site

    SciTech Connect

    Boyer, W.B.; Burke, L.J.; Gomez, B.J.; Livingston, L.; Nelson, D.S.; Smathers, D.C.

    1996-12-31

    Sandia National Laboratories has recently developed two major field test capabilities for unattended ground sensor systems at the Department of energy`s Nevada Test Site (NTS). The first capability utilizes the NTS large area, varied terrain, and intrasite communications systems for testing sensors for detecting and tracking vehicular traffic. Sensor and ground truth data can be collected at either of two secure control centers. This system also includes an automated ground truth capability that consists of differential Global Positioning Satellite (GPS) receivers on test vehicles and live TV coverage of critical road sections. Finally there is a high-speed, secure computer network link between the control centers and the Air Force`s Theater Air Command and Control Simulation Facility in Albuquerque NM. The second capability is Bunker 2-300. It is a facility for evaluating advanced sensor systems for monitoring activities in underground cut-and-cover facilities. The main part of the facility consists of an underground bunker with three large rooms for operating various types of equipment. This equipment includes simulated chemical production machinery and controlled seismic and acoustic signal sources. There has been a thorough geologic and electromagnetic characterization of the region around the bunker. Since the facility is in a remote location, it is well-isolated from seismic, acoustic, and electromagnetic interference.

  8. Liquefied Natural Gas (LNG) dispenser verification device

    NASA Astrophysics Data System (ADS)

    Xiong, Maotao; Yang, Jie-bin; Zhao, Pu-jun; Yu, Bo; Deng, Wan-quan

    2013-01-01

    The composition of working principle and calibration status of LNG (Liquefied Natural Gas) dispenser in China are introduced. According to the defect of weighing method in the calibration of LNG dispenser, LNG dispenser verification device has been researched. The verification device bases on the master meter method to verify LNG dispenser in the field. The experimental results of the device indicate it has steady performance, high accuracy level and flexible construction, and it reaches the international advanced level. Then LNG dispenser verification device will promote the development of LNG dispenser industry in China and to improve the technical level of LNG dispenser manufacture.

  9. 49 CFR 193.2181 - Impoundment capacity: LNG storage tanks.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS Design Impoundment Design and Capacity § 193.2181... minimum volumetric liquid impoundment capacity of: (a) 110 percent of the LNG tank's maximum liquid... largest tank's maximum liquid capacity, whichever is greater, for the impoundment serving more than...

  10. 49 CFR 193.2181 - Impoundment capacity: LNG storage tanks.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS Design Impoundment Design and Capacity § 193.2181... minimum volumetric liquid impoundment capacity of: (a) 110 percent of the LNG tank's maximum liquid... largest tank's maximum liquid capacity, whichever is greater, for the impoundment serving more than...

  11. 49 CFR 193.2181 - Impoundment capacity: LNG storage tanks.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS Design Impoundment Design and Capacity § 193.2181... minimum volumetric liquid impoundment capacity of: (a) 110 percent of the LNG tank's maximum liquid... largest tank's maximum liquid capacity, whichever is greater, for the impoundment serving more than...

  12. LNG Observer: Second Qatargas train goes onstream

    SciTech Connect

    1997-01-01

    The January-February, 1997 issue of the LNG Observer is presented. The following topics are discussed: second Qatargas train goes onstream; financing for the eighth Indonesian liquefaction train; Koreans take stakes in Oman LNG; US imports and exports of LNG in 1996; A 60% increase in proved reserves on the North West Shelf; proposals for Indian LNG terminal CEDIGAZ forecasts world LNG trade by 2010; growth for North African gas production and exports; and new forecast sees strong growth for Asian gas.

  13. Monitoring, safety systems for LNG and LPG operators

    SciTech Connect

    True, W.R.

    1998-11-16

    Operators in Korea and Australia have chosen monitoring and control systems in recent contracts for LNG and LPG storage. Korea Gas Corp. (Kogas) has hired Whessoe Varec, Calais, to provide monitoring systems for four LNG storage tanks being built at Kogas` Inchon terminal. For Elgas Ltd., Port Botany, Australia, Whessoe Varec has already shipped a safety valve-shutdown system to a new LPG cavern-storage facility under construction. The paper describes the systems, terminal monitoring, dynamic approach to tank management, and meeting the growing demand for LPG.

  14. Health, safety and environmental criteria for siting of laboratory facilities.

    PubMed

    Lees, P S; Corn, M

    1983-04-01

    The development of applicable criteria for assessing the suitability of a site for construction of full and partial containment laboratories for the analysis of unknown and highly toxic chemicals is described. The criteria, based on considerations of health, safety and environmental factors, are used to define critical considerations in site selection to minimize the risk to non-laboratory personnel and the surrounding environment. Criteria are synthesized from several sources using the assumption of a worst-case chemical release. Mechanical failures, human failures, critical events and social/legal limitations are investigated, as are the characteristics of a site which may limit construction of such a facility. A detailed description is made of the various types of laboratories and the types of samples analyzed in them. The final recommendations are summarized for five typical laboratory settings; they are based primarily on the potential impacts on people, property and natural resources. A single occupancy building in a rural setting is recommended as the most suitable site for a full containment laboratory. A single occupancy building in an industrial park setting is acceptable, while multiple occupancy buildings and sites which are more highly developed are unacceptable. Similar recommendations are made for partial containment and conventional laboratories. PMID:6858856

  15. CEOS database of worldwide calibration facilities and validation test sites

    NASA Astrophysics Data System (ADS)

    Butler, James J.; Wanchoo, Lalit; Le, Truong

    2001-02-01

    12 Since 1995, the CEOS Calibration/Validation (Cal/Val) Database has provided the international Earth remote sensing science community with a) a central repository for information on current and planned Calibration/Validation activities and b) a means to foster collaboration on common Cal/Val issues. The Cal/Val Database uses an ORACLE relation database management system to store the data and is accessed via the World Wide Web (WWW) using PERL scripts to search and query the database. The search queries are structured such that users can define any combination of fields, either through selection of valids, or by directly typing the information. All query results are displayed in the text form. The text displays are interactive allowing the user to point and click to access more detailed information. System functionality provides an on-line form of all of the three questionnaires for submitting new information and allows a user with the assigned password to edit archived information for their facility. This functionality allows users to update information, as it becomes available. In 2000, the Cal/Val database was updated through a process of additional surveying of existing and planned Cal/Val capabilities to support the NASA's Earth Science Enterprise (ESE) and other international Earth observing missions. A set of three updated questionnaires was prepared: one for calibration laboratories, one for test sites, and one for field instruments. The information requested included: a description of the facility, instruments available, instrument characteristics, types of measurements performed, programs/projects that have used the facility, etc. These questionnaires with cover letter were mailed to over 250 research groups that included CEOS members and facilities within the USA. The information collected from worldwide facilities was used to construct and update this on-line database for use not only by the CEOS members, but also the broader international Earth

  16. Site selection and assessment for a nuclear storage facility

    SciTech Connect

    Rutherford, D.A.; Zardecki, A.

    1996-09-01

    We investigate the structure and accuracy of the decision making process in finding an optimal location for stored nuclear materials for 25-50 years. Using a well-documented facility design, benefit hierarchy is set up for different sites to rank a given site for different options. Criteria involve safeguards standards, technical viability, environmental effects, economics, political impact, and public acceptance. Problem faced here is multi-criterion decision making. Two approaches are investigated: analytic hierarchy process (AHP) of Saaty, and fuzzy logic approach of Yager. Whereas AHP requires a pairwise comparison of criteria and pairwise comparison of alternatives, in Yager`s approach each alternative is considered independently, allowing one to extend the analysis without performing time-consuming computation.

  17. Consolidated Incineration Facility, Savannah River Site. Environmental Assessment

    SciTech Connect

    Not Available

    1992-12-01

    This environmental assessment (EA) was prepared by the US Department of Energy (DOE) to assess the potential impacts associated with the siting, construction, and operation of the proposed Consolidated Incineration Facility (CIF), at the Savannah River Site, Aiken, South Carolina. The text of the document is unchanged from the EA issued in June 1992, with the following three exceptions: (1) Section 2.1 refers to recent solid waste forecast information; (2) Section 4.5.1 deletes the reference to dioxin emission standards; and (3) a footnote to Section 4.6.2 includes the results of a morr, conservative risk factor. An additional appendix has also been added to the EA. Appendix B presents comments received on the June 1992 EA and the Proposed FONSI from federal, state, and local agencies, interest groups, and individuals. Appendix B also contains both general and specific DOE responses to these comments.

  18. 5 CFR 2604.201 - Public reading room facility and Web site.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 5 Administrative Personnel 3 2013-01-01 2013-01-01 false Public reading room facility and Web site... DISCLOSURE REPORTS FOIA Public Reading Room Facility and Web Site; Index Identifying Information for the Public § 2604.201 Public reading room facility and Web site. (a)(1) Location of public reading...

  19. 5 CFR 2604.201 - Public reading room facility and Web site.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 5 Administrative Personnel 3 2012-01-01 2012-01-01 false Public reading room facility and Web site... DISCLOSURE REPORTS FOIA Public Reading Room Facility and Web Site; Index Identifying Information for the Public § 2604.201 Public reading room facility and Web site. (a)(1) Location of public reading...

  20. 5 CFR 2604.201 - Public reading room facility and Web site.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 5 Administrative Personnel 3 2014-01-01 2014-01-01 false Public reading room facility and Web site... DISCLOSURE REPORTS FOIA Public Reading Room Facility and Web Site; Index Identifying Information for the Public § 2604.201 Public reading room facility and Web site. (a)(1) Location of public reading...

  1. 5 CFR 2604.201 - Public reading room facility and Web site.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 5 Administrative Personnel 3 2011-01-01 2011-01-01 false Public reading room facility and Web site... DISCLOSURE REPORTS FOIA Public Reading Room Facility and Web Site; Index Identifying Information for the Public § 2604.201 Public reading room facility and Web site. (a)(1) Location of public reading...

  2. 5 CFR 2604.201 - Public reading room facility and Web site.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 5 Administrative Personnel 3 2010-01-01 2010-01-01 false Public reading room facility and Web site... DISCLOSURE REPORTS FOIA Public Reading Room Facility and Web Site; Index Identifying Information for the Public § 2604.201 Public reading room facility and Web site. (a)(1) Location of public reading...

  3. Sludge treatment facility preliminary siting study for the sludge treatment project (A-13B)

    SciTech Connect

    WESTRA, A.G.

    1999-06-24

    This study evaluates various sites in the 100 K area and 200 areas of Hanford for locating a treatment facility for sludge from the K Basins. Both existing facilities and a new standalone facility were evaluated. A standalone facility adjacent to the AW Tank Farm in the 200 East area of Hanford is recommended as the best location for a sludge treatment facility.

  4. Los Alamos studies of the Nevada test site facilities for the testing of nuclear rockets

    NASA Technical Reports Server (NTRS)

    Hynes, Michael V.

    1993-01-01

    The topics are presented in viewgraph form and include the following: Nevada test site geographic location; location of NRDA facilities, area 25; assessment program plan; program goal, scope, and process -- the New Nuclear Rocket Program; nuclear rocket engine test facilities; EMAD Facility; summary of final assessment results; ETS-1 Facility; and facilities cost summary.

  5. DECOMMISSIONING OF NUCLEAR FACILITIES IN GERMANY - STATUS AT BMBF SITES

    SciTech Connect

    Papp, R.; Komorowski, K.

    2002-02-25

    In a period of approximately 40 years prior to 1994, the German Federal Government had spent about {approx} 15 billion to promote nuclear technology. These funds were earmarked for R&D projects as well as demonstration facilities which took up operation between 1960 and 1980. These BMBF (Federal Ministry for Research) facilities were mainly located at the sites of the federal research centers at Juelich and Karlsruhe (the research reactors AVR, FR2, FRJ-1, KNK, and MZFR, the pilot reprocessing plant WAK) but included also the pilot plants SNR-300 and THTR-300 for fast breeder and high-temperature gas-cooled reactor development, respectively, and finally the salt mine Asse which had been used for waste emplacement prior to conversion into an underground research laboratory. In the meantime, almost all of these facilities were shut down and are now in a state of decommissioning and dismantling. This is mainly due to the facts that R&D needs are satisfied or do not exist any more and that, secondly, the lack of political consensus led to the cancellation of advanced nuclear technology.

  6. Closure End States for Facilities, Waste Sites, and Subsurface Contamination

    SciTech Connect

    Gerdes, Kurt D.; Chamberlain, Grover S.; Wellman, Dawn M.; Deeb, Rula A.; Hawley, Elizabeth L.; Whitehurst, Latrincy; Marble, Justin

    2012-11-21

    The United States (U.S.) Department of Energy (DOE) manages the largest groundwater and soil cleanup effort in the world. DOE’s Office of Environmental Management (EM) has made significant progress in its restoration efforts at sites such as Fernald and Rocky Flats. However, remaining sites, such as Savannah River Site, Oak Ridge Site, Hanford Site, Los Alamos, Paducah Gaseous Diffusion Plant, Portsmouth Gaseous Diffusion Plant, and West Valley Demonstration Project possess the most complex challenges ever encountered by the technical community and represent a challenge that will face DOE for the next decade. Closure of the remaining 18 sites in the DOE EM Program requires remediation of 75 million cubic yards of contaminated soil and 1.7 trillion gallons of contaminated groundwater, deactivation & decommissioning (D&D) of over 3000 contaminated facilities and thousands of miles of contaminated piping, removal and disposition of millions of cubic yards of legacy materials, treatment of millions of gallons of high level tank waste and disposition of hundreds of contaminated tanks. The financial obligation required to remediate this volume of contaminated environment is estimated to cost more than 7% of the to-go life-cycle cost. Critical in meeting this goal within the current life-cycle cost projections is defining technically achievable end states that formally acknowledge that remedial goals will not be achieved for a long time and that residual contamination will be managed in the interim in ways that are protective of human health and environment. Formally acknowledging the long timeframe needed for remediation can be a basis for establishing common expectations for remedy performance, thereby minimizing the risk of re-evaluating the selected remedy at a later time. Once the expectations for long-term management are in place, remedial efforts can be directed towards near-term objectives (e.g., reducing the risk of exposure to residual contamination) instead

  7. Commercial facility site selection simulating based on MAS

    NASA Astrophysics Data System (ADS)

    Chao, Yi; Li, Qingquan; Zheng, Guizhou

    2008-10-01

    The location of commercial facility decides the benefit of the operator to a large degree. Existing location methods can express the static relationships between site selection result and location factors, but there still are some limites when express the dynamic and uncertain relationship between them. Hence, a dynamic, stochastic and forecastable location model should be built which can introduce the customer's behavior into the model and combine the macro pattern and micro spatial interaction. So the authors proposes Geosim-LM based on MAS. Geosim-LM has 3 kinds of agents, CustAgent, SiteAgent and GovAgent. They represent the customers, commercial fercilities and government. The land type, land price and traffic are the model environment. Then Geosim-LM is applied in the bank branches site evaluation and selection in Liwan district, Guangzhou. In existing bank branches site evaluation, there are 70% consistent in score grade between result of Geosim-LM after 200 round runing and actual rebust location. It proves the model is reliable and feasible. The conclusions can be get from the paper. MAS have advantages in location choice than existed methods. The result of Geosim-LM running can powerfully proves that building location model based on MAS is feasible.

  8. National Ignition Facility Project Site Safety Program Appendix A

    SciTech Connect

    Moses, E

    2001-09-30

    These rules apply to all National Ignition Facility (NIF) workers (workers), which include Lawrence Livermore National Laboratory (LLNL) employees, non-LLNL employees (including contract labor, supplemental labor, vendors, personnel matrixed/assigned from other national laboratories, participating guests, visitors and students) and contractors/subcontractors. The General Rules and NIF Code of Safe Practices shall be used by management to promote the prevention of incidents through indoctrination, safety and health training, and on-the-job application. As a condition for contract award, all employers shall conduct an orientation for all newly hired and rehired employees before those workers will be permitted to start work in this facility. This orientation shall include a discussion of the following information. The General Rules and NIF Code of Safe Practices must be posted at a conspicuous location at the job site office or be provided to each supervisory worker who shall have it readily available. Copies of the General Rules and NIF Code of Safe Practices can also be included in employee safety pamphlets. The Environmental, Safety, and Health (ES&H) rules at the NIF Project site are based upon compliance with the most stringent of Department of Energy (DOE), LLNL, Federal Occupational Safety and Health Administration (OSHA), California (Cal)/OSHA, and federal and state environmental requirements.

  9. Closing the US Fuel Cycle: Siting Considerations for the Global Nuclear Energy Partnership Facilities - Siting the Advanced Fuel Cycle Facility

    SciTech Connect

    Griffith, A.; Boger, J.; Perry, J.

    2008-07-01

    The Global Nuclear Energy Partnership (GNEP), launched in February, 2006, proposes to introduce used nuclear fuel recycling in the United States (U.S.) with improved proliferation-resistance and a more effective waste management approach. This program is evaluating ways to close the fuel cycle in a manner that introduces the most advanced technologies of today and builds on recent breakthroughs in U.S. national laboratories while drawing on international and industry partnerships. Central to moving this advanced fuel recycling technology from the laboratory to commercial implementation is the development and siting of three proposed GNEP facilities: the Consolidated Fuel Treatment Center (CFTC), the Advanced Burner Reactor (ABR), and the Advanced Fuel Cycle Facility (AFCF). These three projects are envisioned to introduce used fuel separations, advanced fuel fabrication, and fast reactor technology in a manner that efficiently recycles material, produces the most energy out of the existing inventory of used fuel, and improves our ability to manage nuclear waste. The CFTC and ABR are sited under GNEP but will depend on industry involvement and will not be covered by this paper. This paper will cover considerations for siting the AFCF. The AFCF will provide the U.S. with the capabilities required to evaluate technologies that separate used fuel into reusable material and waste in a proliferation-resistant manner. The separations technology demonstration capability is coupled with a remote transmutation fuel fabrication demonstration capability in an integrated manner that demonstrates advanced safeguard technologies. In conclusion: As a flexible, multi-purpose demonstration facility, the AFCF will provide the U.S. with a powerful and unique capability to quickly bring innovative nuclear fuel recycling technology from the laboratory to the commercial market with high confidence. The siting of AFCF capabilities at one or more of the six DOE laboratories being evaluated

  10. Public participation in energy facility siting. Part 2; Future directions

    SciTech Connect

    Whitlatch, E.E. . Dept. of Civil Engineering)

    1990-08-01

    The first planning era for energy facility siting was typified by technological decision making in a climate of eminent domain. The second planning era, from 1970 to present, involves regulatory/adjudicatory decision making in a climate of adversarial proceedings. However, outcomes are not much different than in the first: Decisions are still largely made on technological grounds, sites are secretly selected and anonymously secured, and public participation has little effect on decisions. The result has been endgame litigation that delays needed projects increases cost, and polarizes participants. Utilities are understandably reluctant to plan large base-load plants, yet almost all projections of electricity use indicate that such plants will be needed after 1996, if not before. The author discusses how it is in the self-interest of all three principal actors---industry, environmental groups, and state and local government---to move beyond confrontation to a third planning era based on negotiation. Unassisted negotiation (open siting or open planning) and assisted negotiation (facilitation and mediation) promise to produce mutual gain for all parties through cooperative and creative problem solving. Most importantly, they lay the groundwork for future productive interaction.

  11. North American LNG Project Sourcebook

    SciTech Connect

    2007-06-15

    The report provides a status of the development of LNG Import Terminal projects in North America, and includes 1-2 page profiles of 63 LNG projects in North America which are either in operation, under construction, or under development. For each project, the sourcebook provides information on the following elements: project description, project ownership, project status, projected operation date, storage capacity, sendout capacity, and pipeline interconnection.

  12. Design control for the Savannah River Site Consolidated Incineration Facility

    SciTech Connect

    Walker, R.E.; Rider, R.L.

    1991-12-31

    The initiation, development, and control of the design for the Consolidated Incineration Facility at the US Department of Energy Savannah River Site has been, from the inception, a precisely and formally controlled process. A plan was developed and implemented to ensure output properly aligned with approved design criteria and conformed to applicable regulations throughout the design process. The key element of design control was the technical baseline which established the benchmark against which all changes to the design was evaluated. During the conceptual design phase of the project, design criteria were written to reflect the project objectives and functional requirements. Governmental regulations were reviewed to determine permitting and licensing actions required. Hazards assessments were performed to establish design classifications. The resulting design criteria, permitting requirements, and facility classifications were incorporated into the design plan which provided the basis for subsequent design activities. As the project proceeded through the various design phases, design control was maintained according to the design plan. Review of all design products was performed by the project team routinely. Formal independent design reviews were accomplished prior to releasing the design for construction. Alignment between criteria and design output was verified periodically throughout the design process. A formal design change control board was invoked to effect design changes impacting technical baselines. All changes to design initiated following issue for construction also were subject to procedural control.

  13. Design control for the Savannah River Site Consolidated Incineration Facility

    SciTech Connect

    Walker, R.E.; Rider, R.L. )

    1991-01-01

    The initiation, development, and control of the design for the Consolidated Incineration Facility at the US Department of Energy Savannah River Site has been, from the inception, a precisely and formally controlled process. A plan was developed and implemented to ensure output properly aligned with approved design criteria and conformed to applicable regulations throughout the design process. The key element of design control was the technical baseline which established the benchmark against which all changes to the design was evaluated. During the conceptual design phase of the project, design criteria were written to reflect the project objectives and functional requirements. Governmental regulations were reviewed to determine permitting and licensing actions required. Hazards assessments were performed to establish design classifications. The resulting design criteria, permitting requirements, and facility classifications were incorporated into the design plan which provided the basis for subsequent design activities. As the project proceeded through the various design phases, design control was maintained according to the design plan. Review of all design products was performed by the project team routinely. Formal independent design reviews were accomplished prior to releasing the design for construction. Alignment between criteria and design output was verified periodically throughout the design process. A formal design change control board was invoked to effect design changes impacting technical baselines. All changes to design initiated following issue for construction also were subject to procedural control.

  14. Not in whose backyard Minority population concentrations and noxious facility sites

    SciTech Connect

    Nieves, L.A.

    1992-01-01

    The NIMBY (not in may backyard) syndrome has become the nemesis of facility siting efforts in the USA. Given people's reluctance to live near noxious facilities, in whose backyard are such facilities located This study employs US county-level data to examine relative concentrations of minorities living near noxious facilities. Facility types analyzed include electric generating plants, manufacturing plants, Superfund sites, and radioactive waste disposal sites. While this study does not address which cam first, the minority population concentration or the noxious facilities, it documents their current degree of association.

  15. Not in whose backyard? Minority population concentrations and noxious facility sites

    SciTech Connect

    Nieves, L.A.

    1992-04-01

    The NIMBY (not in may backyard) syndrome has become the nemesis of facility siting efforts in the USA. Given people`s reluctance to live near noxious facilities, in whose backyard are such facilities located? This study employs US county-level data to examine relative concentrations of minorities living near noxious facilities. Facility types analyzed include electric generating plants, manufacturing plants, Superfund sites, and radioactive waste disposal sites. While this study does not address which cam first, the minority population concentration or the noxious facilities, it documents their current degree of association.

  16. Probability of Liquefaction for Pit Disassembly and Conversion Facility (PDCF) Site, Savannah River Site

    SciTech Connect

    Lee, R.C.

    2003-09-30

    This report documents the probability of liquefaction (POL) for the Pit Disassembly and Conversion Facility (PDCF). The procedure for analysis of a critical layer of interest requires the following basic steps: (1) establish the probability of occurrence (POO) of ranges of 2.5 Hz bedrock motion based on a probabilistic seismic hazard assessment (PSHA); (2) define the critical layer that may be susceptible to liquefaction; (3) estimate distributions of cyclic stress ratio (CSR) (i.e., seismic demand) for the critical layer using site-specific soil properties corresponding to the bedrock motions; (4) estimate capacity of the critical layer based on site-specific cone penetration test (CPT) soundings and standard penetration test (SPT) blowcount data; and (5) sum the probability of liquefaction for each range of bedrock motion using empirical data correlating demand and capacity with liquefaction. The soil layer most susceptible to liquefaction is the critical layer. The critical layer is characterized by relatively low blowcount and low fines content and is established from soil layers below the water table. A key component for seismic demand is the establishment of the soil profile and it's uncertainty. The PDCF site is consistent with the 1997 SRS-specific model used to compute the site amplification database. Thus, previously derived site amplification functions reflecting the uncertainty in site properties and stratigraphy can be used to predict distributions of CSR given a specific earthquake magnitude and level of bedrock motion. The previously developed site amplification database reflects uncertainty in site response based on the large database of site shear-wave velocity profiles. Consequently, for each level of bedrock motion (from the PSHA) the site amplification database is used to establish the distribution of the expected CSR (demand) in the critical layer.

  17. Analysis of LNG import terminal release prevention systems

    SciTech Connect

    Baker, E G

    1982-04-01

    The release prevention systems of liquefied natural gas (LNG) import terminal were analyzed. A series of potential release scenarios were analyzed to determine the frequency of the release events, the probability these releases are not stopped or isolated by emergency shutdown systems, the estimated release quantities, and the critical components of the system. The two plant areas identified as being most significant with respect to safety are the unloading system and the storage system. Rupture of the main transfer line and gross failure of the storage tanks are the two release scenarios of primary safety interest. Reducing the rate of failure by improved design, better maintenance and testing, or adding redundancy of the critical system components for these plant areas and release scenarios will result in improved safety. Several design alternatives which have the potential to significantly reduce the probability of a large release of LNG occurring at an import terminal are identified. These design alternatives would reduce the probability of a large release of LNG by reducing the expected number of failures which could cause a release or by reducing the magnitude of releases that do occur. All of these alternatives are technically feasible and have been used or considered for use in at least one LNG facility. A more rigorous analysis of the absolute risk of LNG import terminal operation is necessary before the benefits of these design alternatives can be determined. In addition, an economic evaluation of these alternatives must be made so the costs and benefits can be compared. It is concludd that for remotely located facilities many of these alternatives are probably not justified; however, for facilities located in highly populated areas, these alternatives deserve serious consideration.

  18. Geologic mapping as a prerequisite to hazardous waste facility siting

    SciTech Connect

    LaMoreaux, P.E. )

    1993-03-01

    The nation's welfare is based on its capability to develop the mineral, water, and energy resources of the land. In addition, these resources must be developed with adequate consideration of environmental impact and the future welfare of the country. Geologic maps are an absolute necessity in the discovery and development of natural resources; for managing radioactive, toxic, and hazardous wastes; and for the assessment of hazards and risks such as those associated with volcanic action, earthquakes, landslides, and subsidence. Geologic maps are the basis for depicting rocks and rock materials, minerals, coal, oil, and water at or near the earth's surface. Hazardous waste facility projects require the preparation of detailed geologic maps. Throughout most of the USA, this type of mapping detail is not available. If these maps were available, it is estimated that the duration of an individual project could be reduced by at least one-fourth (1/4). Therefore, adequate site-specific mapping is required if one is to eliminate environmental problems associated with hazardous, toxic, radioactive, and municipal waste sites.

  19. 76 FR 9573 - Sabine Pass Liquefaction, LLC and Sabine Pass LNG, L.P.; Notice of Application

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-02-18

    ... Energy Regulatory Commission Sabine Pass Liquefaction, LLC and Sabine Pass LNG, L.P.; Notice of Application Take notice that on January 31, 2011, Sabine Pass Liquefaction, LLC and Sabine Pass LNG, L.P... the Commission's Regulations, to site, construct, and operate liquefaction and export...

  20. The effects of refueling system operating pressure on LNG and CNG economics

    SciTech Connect

    Corless, A.J.; Barclay, J.A.

    1996-12-31

    Natural gas (NG) liquefaction and compression are energy intensive processes which make up a significant portion of the overall delivered price of liquefied NG (LNG) and compressed NG (CNG). Increases in system efficiency and/or process changes which reduce the required amount of work will improve the overall economics of NG as a vehicle fuel. This paper describes a method of reducing the delivered cost of LNG by liquefying the gas above ambient pressures. Higher pressure LNG is desirable because OEM NG engine manufacturers would like NG delivered to the engine intake manifold at elevated pressures to avoid compromising engine performance. Producing LNG at higher pressures reduces the amount of work required for liquefaction but it is only practical when the LNG is liquefied on-site. Using a thermo-economic approach, it is shown that NG fuel costs can be reduced by as much as 10% when producing LNG at higher pressures. A reduction in the delivered cost is also demonstrated for CNG produced on-site from high pressure LNG.

  1. White paper: Preliminary assessment of LNG vehicle technology, economics, and safety issues, revision 1

    NASA Astrophysics Data System (ADS)

    Powars, Charles; Lucher, Dan; Moyer, Carl; Browning, Lou

    1992-01-01

    The objective of the study is to evaluate the potential of liquified natural gas (LNG) as a vehicle fuel, to determine market inches, and to identify needed technology improvements. The white paper is being issued when the work is approximately 30 percent complete to preview the study direction, draw preliminary conclusions, and make initial recommendations. Interim findings relative to LNG vehicle technology, economics, and safety are presented. It is important to decide if heavier hydrocarbons should be allowed in LNG vehicle fuel. Development of suitable refueling couplings and vehicle fuel supply pressure systems are recommended. Initial economics analyses considered transit buses and pickup and delivery trucks fueled via onsite liquefiers and imported LNG. Net user costs were more than (but in some cases close to) those for diesel fuel and gasoline. Lowering the cost of small-scale liquefiers would significantly improve the economics of LNG vehicles. New emissions regulations may introduce considerations beyond simple cost comparisons. LNG vehicle safety and available accident data are reviewed. Consistent codes for LNG vehicles and refueling facilities are needed.

  2. Assessment of the facilities on Jackass Flats and other Nevada Test Site facilities for the new nuclear rocket program

    SciTech Connect

    Chandler, G.; Collins, D.; Dye, K.; Eberhart, C.; Hynes, M.; Kovach, R.; Ortiz, R.; Perea, J.; Sherman, D.

    1992-12-01

    Recent NASA/DOE studies for the Space Exploration Initiative have demonstrated a critical need for the ground-based testing of nuclear rocket engines. Experience in the ROVER/NERVA Program, experience in the Nuclear Weapons Testing Program, and involvement in the new nuclear rocket program has motivated our detailed assessment of the facilities used for the ROVER/NERVA Program and other facilities located at the Nevada Test Site (NTS). The ROVER/NERVA facilities are located in the Nevada Research L, Development Area (NRDA) on Jackass Flats at NTS, approximately 85 miles northwest of Las Vegas. To guide our assessment of facilities for an engine testing program we have defined a program goal, scope, and process. To execute this program scope and process will require ten facilities. We considered the use of all relevant facilities at NTS including existing and new tunnels as well as the facilities at NRDA. Aside from the facilities located at remote sites and the inter-site transportation system, all of the required facilities are available at NRDA. In particular we have studied the refurbishment of E-MAD, ETS-1, R-MAD, and the interconnecting railroad. The total cost for such a refurbishment we estimate to be about $253M which includes additional contractor fees related to indirect, construction management, profit, contingency, and management reserves. This figure also includes the cost of the required NEPA, safety, and security documentation.

  3. Recommended research on LNG safety

    SciTech Connect

    Carpenter, H.J.; Gilmore, F.R.

    1981-03-01

    The US Department of Energy (DOE) is conducting research on the safety and other environmental aspects of liquefied energy gases including liquefied natural gas (LNG). The effort reported here was conducted as part of the planning for further research into the safety aspects of transporting and storing LNG, with primary emphasis on public safety. Although the modern LNG industry has enjoyed excellent success in providing for safe operations, significant questions remain on the part of many, the expressions of which were intensified with the addition of marine-based LNG import terminals. Public safety with regard to large-scale importation of this fuel has received widespread attention in the US Congress, state legislatures, county and city governments, and from various individuals and public groups, with coverage in all the news media, including books published on the subject. The safety concerns have centered around the consequences to the public of a large spill of the cryogenic liquid from an ocean tanker or a larger storage tank, either of which might hold as much as 125,000 m/sup 3/ of LNG.

  4. LNG to CNG refueling stations

    SciTech Connect

    Branson, J.D.

    1995-12-31

    While the fleet operator is concerned about the environment, he or she is going to make the choice based primarily on economics. Which fuel provides the lowest total operating cost? The calculation of this costing must include the price-per-gallon of the fuel delivered, as well as the tangible and intangible components of fuel delivery, such as downtime for vehicles during the refueling process, idle time for drivers during refueling, emissions costings resulting from compressor oil blow-by, inclusion of non-combustible constituents in the CNG, and energy consumption during the refueling process. Also, the upfront capital requirement of similar delivery capabilities must be compared. The use of LNG as the base resource for the delivered CNG, in conjunction with the utilization of a fully temperature-compressed LNG/CNG refueling system, eliminates many of the perceived shortfalls of CNG. An LNG/CNG refueling center designed to match the capabilities of the compressor-based station will have approximately the same initial capital requirement. However, because it derives its CNG sales product from the {minus}260 F LNG base product, thus availing itself of the natural physical properties of the cryogenic product, all other economic elements of the system favor the LNG/CNG product.

  5. Preliminary siting activities for new waste handling facilities at the Idaho National Engineering Laboratory

    SciTech Connect

    Taylor, D.D.; Hoskinson, R.L.; Kingsford, C.O.; Ball, L.W.

    1994-09-01

    The Idaho Waste Processing Facility, the Mixed and Low-Level Waste Treatment Facility, and the Mixed and Low-Level Waste Disposal Facility are new waste treatment, storage, and disposal facilities that have been proposed at the Idaho National Engineering Laboratory (INEL). A prime consideration in planning for such facilities is the selection of a site. Since spring of 1992, waste management personnel at the INEL have been involved in activities directed to this end. These activities have resulted in the (a) identification of generic siting criteria, considered applicable to either treatment or disposal facilities for the purpose of preliminary site evaluations and comparisons, (b) selection of six candidate locations for siting,and (c) site-specific characterization of candidate sites relative to selected siting criteria. This report describes the information gathered in the above three categories for the six candidate sites. However, a single, preferred site has not yet been identified. Such a determination requires an overall, composite ranking of the candidate sites, which accounts for the fact that the sites under consideration have different advantages and disadvantages, that no single site is superior to all the others in all the siting criteria, and that the criteria should be assigned different weighing factors depending on whether a site is to host a treatment or a disposal facility. Stakeholder input should now be solicited to help guide the final selection. This input will include (a) siting issues not already identified in the siting, work to date, and (b) relative importances of the individual siting criteria. Final site selection will not be completed until stakeholder input (from the State of Idaho, regulatory agencies, the public, etc.) in the above areas has been obtained and a strategy has been developed to make a composite ranking of all candidate sites that accounts for all the siting criteria.

  6. LNG vehicle technology, economics, and safety assessment

    NASA Astrophysics Data System (ADS)

    Powars, Charles A.; Moyer, Carl B.; Lowell, Douglas D.

    1994-02-01

    Liquid natural gas (LNG) is an attractive transportation fuel because of its high heating value and energy density (i.e., Btu/lb. and Btu/gal.), clean burning characteristics, relatively low cost ($/Btu), and domestic availability. This research evaluated LNG vehicle and refueling system technology, economics, and safety. Prior and current LNG vehicle projects were studied to identify needed technology improvements. Life-cycle cost analyses considered various LNG vehicle and fuel supply options. Safety records, standards, and analysis methods were reviewed. The LNG market niche is centrally fueled heavy-duty fleet vehicles with high fuel consumption. For these applications, fuel cost savings can amortize equipment capital costs.

  7. RCRA Facility Investigation/Remedial Investigation Report for the Grace Road Site (631-22G)

    SciTech Connect

    Palmer, E.

    1998-10-02

    This report summarizes the activities and documents the results of a Resource Conservation and Recovery Act Facility Investigation/Remedial Investigation conducted at Grace Road Site on the Savannah River Site near Aiken, South Carolina.

  8. 46 CFR 160.151-49 - Approval of servicing facilities at remote sites.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... accompany the technician doing the servicing. However, if repair of liferafts will not be attempted at a remote site, equipment needed for repair does not need to be available at that site. A facility must...

  9. 46 CFR 160.151-49 - Approval of servicing facilities at remote sites.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... accompany the technician doing the servicing. However, if repair of liferafts will not be attempted at a remote site, equipment needed for repair does not need to be available at that site. A facility must...

  10. 46 CFR 160.151-49 - Approval of servicing facilities at remote sites.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... accompany the technician doing the servicing. However, if repair of liferafts will not be attempted at a remote site, equipment needed for repair does not need to be available at that site. A facility must...

  11. 46 CFR 160.151-49 - Approval of servicing facilities at remote sites.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... accompany the technician doing the servicing. However, if repair of liferafts will not be attempted at a remote site, equipment needed for repair does not need to be available at that site. A facility must...

  12. 46 CFR 160.151-49 - Approval of servicing facilities at remote sites.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... accompany the technician doing the servicing. However, if repair of liferafts will not be attempted at a remote site, equipment needed for repair does not need to be available at that site. A facility must...

  13. Natural gas and CO2 price variation: impact on the relative cost-efficiency of LNG and pipelines

    PubMed Central

    Ulvestad, Marte; Overland, Indra

    2012-01-01

    This article develops a formal model for comparing the cost structure of the two main transport options for natural gas: liquefied natural gas (LNG) and pipelines. In particular, it evaluates how variations in the prices of natural gas and greenhouse gas emissions affect the relative cost-efficiency of these two options. Natural gas is often promoted as the most environmentally friendly of all fossil fuels, and LNG as a modern and efficient way of transporting it. Some research has been carried out into the local environmental impact of LNG facilities, but almost none into aspects related to climate change. This paper concludes that at current price levels for natural gas and CO2 emissions the distance from field to consumer and the volume of natural gas transported are the main determinants of transport costs. The pricing of natural gas and greenhouse emissions influence the relative cost-efficiency of LNG and pipeline transport, but only to a limited degree at current price levels. Because more energy is required for the LNG process (especially for fuelling the liquefaction process) than for pipelines at distances below 9100 km, LNG is more exposed to variability in the price of natural gas and greenhouse gas emissions up to this distance. If the prices of natural gas and/or greenhouse gas emission rise dramatically in the future, this will affect the choice between pipelines and LNG. Such a price increase will be favourable for pipelines relative to LNG. PMID:24683269

  14. 30 CFR 71.500 - Sanitary toilet facilities at surface work sites; installation requirements.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 1 2011-07-01 2011-07-01 false Sanitary toilet facilities at surface work... SURFACE WORK AREAS OF UNDERGROUND COAL MINES Sanitary Toilet Facilities at Surface Worksites of Surface Coal Mines § 71.500 Sanitary toilet facilities at surface work sites; installation requirements....

  15. 30 CFR 71.500 - Sanitary toilet facilities at surface work sites; installation requirements.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Sanitary toilet facilities at surface work... SURFACE WORK AREAS OF UNDERGROUND COAL MINES Sanitary Toilet Facilities at Surface Worksites of Surface Coal Mines § 71.500 Sanitary toilet facilities at surface work sites; installation requirements....

  16. Radiological safety evaluation for a Savannah River Site Waste Transfer Facility. Revision 1

    SciTech Connect

    Ades, M.J.

    1994-01-01

    This paper describes a radiological safety evaluation performed in support of operation of a typical Waste Transfer Facility (WTF) located at the Savannah River Site (SRS). This facility transfers liquid radioactive waste from and to various waste processing, storage, and treatment facilities.

  17. Environmental Assessment for the construction and operation of the Health Physics Site Support Facility on the Savannah River Site

    SciTech Connect

    1995-07-01

    DOE has prepared an environmental assessment for the proposed construction and operation of the Health Physics Site Support Facility on the Savannah River Site. This (new) facility would meet requirements of the site radiological protection program and would ensure site compliance with regulations. It was determined that the proposed action is not a major Federal action significantly affecting the quality of the environment within the meaning of NEPA. Therefore, a finding of no significant impact is made, and no environmental impact statement is needed.

  18. Development of polymer concrete for dike insulation at LNG facilities: Phase 4, Low cost materials. Final report, September 1, 1987--April 30, 1990

    SciTech Connect

    Kukacka, L.E.

    1991-01-01

    Earlier GRI-sponsored work at Brookhaven National Laboratory has resulted in the development and utilization of insulating polymer concrete composites (IPC) as a means of reducing the evaporation rate of liquified natural gas in the event of a spill into a containment dike, thereby improving the safety at these sites. Although all of the required properties can be attained with the IPC, it was estimated that a low-cost replacement for the expensive organic binder would be necessary before use of the material would be cost-effective. In the current program, several latex modified cement formulations were evaluated and the most promising one identified. A mixture of two carboxylated styrene-butadiene latexes was selected for use in detailed laboratory property characterizations and a subsequent field evaluation. When compared to the properties of IPC, the latex-modified insulating materials display somewhat higher thermal conductivities, greater permeability to water, and reduced strength. However, these properties still meet most of the performance criteria, and the unit cost of the material is less than one-fifth that of IPC made with epoxy binders. When installed as a 0.75-in. thick overlay, material costs are estimated to be $1.00/ft{sup 2}.

  19. 76 FR 40751 - National Environmental Policy Act; Wallops Flight Facility; Site-Wide

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-11

    ... SPACE ADMINISTRATION National Environmental Policy Act; Wallops Flight Facility; Site- Wide AGENCY... Environmental Impact Statement (PEIS) and to conduct scoping for expanding operations at Wallops Flight Facility... addressed to Shari Silbert, Manager, Site-wide PEIS, NASA Goddard Space Flight Center's Wallops...

  20. The Struggle between States and the Federal Government on the Siting of LNG Import Terminals: Has a Red Tide Washed Ashore in the Blue States?

    SciTech Connect

    Desautels, Denise; Ray, Peter

    2005-10-01

    The Energy Policy Act of 2005 transfers, in some circumstances, implementation of the public trust doctrine from the state to the federal government. Implicit in the public trust doctrine is the issue of public safety and environmental concerns. Proponents of such facilities are challenged with weighing such factors to make a successful proposal to federal and state agencies.

  1. D&D Characterization of the 232-F Old Tritium Facility at the Savannah River Site

    SciTech Connect

    Scallon, K.L.; England, J.L.

    1995-01-17

    The 232-F ``Old Tritium Facility`` operated in the 1950s as the first tritium production facility at the Savannah River Site (SRS). In 1957, the 232-F operation ceased with tritium production turned over to a larger, technologically improved facility at SRS. The 232-F Facility was abandoned in 1958 and the process areas have remained contaminated with radiological, hazardous and mixed constituents. Decontamination and decommissioning (D&D) of the 232-F Facility is scheduled to occur in the years 1995-1996. This paper presents the D&D characterization efforts for the 232-F Facility.

  2. Computer-aided Siting of Coal Conversion Facilities

    NASA Technical Reports Server (NTRS)

    Moreno, D. D.

    1982-01-01

    The value of using geographic information systems in site selection for coal conversion plants is discussed. Environmental and cultural factors and capital/operating costs were considered to determine site suitability.

  3. Multidimensional Programming Methods for Energy Facility Siting: Alternative Approaches

    NASA Technical Reports Server (NTRS)

    Solomon, B. D.; Haynes, K. E.

    1982-01-01

    The use of multidimensional optimization methods in solving power plant siting problems, which are characterized by several conflicting, noncommensurable objectives is addressed. After a discussion of data requirements and exclusionary site screening methods for bounding the decision space, classes of multiobjective and goal programming models are discussed in the context of finite site selection. Advantages and limitations of these approaches are highlighted and the linkage of multidimensional methods with the subjective, behavioral components of the power plant siting process is emphasized.

  4. Hanford Site waste tank farm facilities design reconstitution program plan

    SciTech Connect

    Vollert, F.R.

    1994-09-06

    Throughout the commercial nuclear industry the lack of design reconstitution programs prior to the mid 1980`s has resulted in inadequate documentation to support operating facilities configuration changes or safety evaluations. As a result, many utilities have completed or have ongoing design reconstitution programs and have discovered that without sufficient pre-planning their program can be potentially very expensive and may result in end-products inconsistent with the facility needs or expectations. A design reconstitution program plan is developed here for the Hanford waste tank farms facility as a consequence of the DOE Standard on operational configuration management. This design reconstitution plan provides for the recovery or regeneration of design requirements and basis, the compilation of Design Information Summaries, and a methodology to disposition items open for regeneration that were discovered during the development of Design Information Summaries. Implementation of this plan will culminate in an end-product of about 30 Design Information Summary documents. These documents will be developed to identify tank farms facility design requirements and design bases and thereby capture the technical baselines of the facility. This plan identifies the methodology necessary to systematically recover documents that are sources of design input information, and to evaluate and disposition open items or regeneration items discovered during the development of the Design Information Summaries or during the verification and validation processes. These development activities will be governed and implemented by three procedures and a guide that are to be developed as an outgrowth of this plan.

  5. Ground Handling of Batteries at Test and Launch-site Facilities

    NASA Technical Reports Server (NTRS)

    Jeevarajan, Judith A.; Hohl, Alan R.

    2008-01-01

    Ground handling of flight as well as engineering batteries at test facilities and launch-site facilities is a safety critical process. Test equipment interfacing with the batteries should have the required controls to prevent a hazardous failure of the batteries. Test equipment failures should not induce catastrophic failures on the batteries. Transportation requirements for batteries should also be taken into consideration for safe transportation. This viewgraph presentation includes information on the safe handling of batteries for ground processing at test facilities as well as launch-site facilities.

  6. Assessment of the facilities on Jackass Flats and other Nevada test site facilities for the new nuclear rocket program

    NASA Astrophysics Data System (ADS)

    Chandler, George; Collins, Donald; Dye, Ken; Eberhart, Craig; Hynes, Michael; Kovach, Richard; Ortiz, Robert; Perea, Jake; Sherman, Donald

    1993-01-01

    Recent NASA/DOE studies for the Space Exploration Initiative have demonstrated a critical need for the ground-based testing of nuclear rocket engines. Experience in the ROVER/NERVA Program, experience in the Nuclear Weapons Testing Program, and involvement in the new nuclear rocket program has motivated our detailed assessment of the facilities used for the ROVER/NERVA Program and other facilities located at the Nevada Test Site (NTS). The ROVER/NERVA facilities are located in the Nevada Research & Development Area (NRDA) on Jackass Flats at NTS, approximately 85 miles northwest of Las Vegas. To guide our assessment of facilities for an engine testing program we have defined a program goal, scope, and process. In particular we have assumed that the program goal will be to certify a full engine system design as flight test ready. All nuclear and non-nuclear components will be individually certified as ready for such a test at sites remote from the NRDA facilities, the components transported to NRDA, and the engine assembled. We also assume that engines of 25,000-100,000 lb thrust levels will be tested with burn times of 1 hour or longer. After a test, the engine will be disassembled, time critical inspections will be executed, and a selection of components will be transported to remote inspection sites. The majority of the components will be stored for future inspection at Jackass Flats. To execute this program scope and process will require ten facilities. We considered the use of all relevant facilities at NTS including existing and new tunnels as well as the facilities at NRDA. Aside from the facilities located at remote sites and the inter-site transportation system, all of the required facilities are available at NRDA. In particular we have studied the refurbishment of E-MAD, ETS-1, R-MAD, and the interconnecting railroad. The total cost for such a refurbishment we estimate to be about 253M which includes additional contractor fees related to indirect

  7. 78 FR 1851 - Sabine Pass Liquefaction, LLC and Sabine Pass LNG, L.P.; Notice of Intent To Prepare an...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-09

    ... facility; condensate storage, metering and send-out facilities; four gas pipeline meter stations... HRU, condensate storage, and metering facilities would be located within the existing Sabine Pass LNG... wetlands; Cultural resources; Vegetation and wildlife; Air quality and noise; Endangered and...

  8. Public concerns and the public role in siting nuclear and chemical waste facilities

    NASA Astrophysics Data System (ADS)

    Johnson, Branden B.

    1987-09-01

    Nuclear and chemical waste facilities can be successfully sited, despite nimby responses, if siting programs account for the sources of public concern. Irrational fear is not the main source; instead, waste managers must deal with perceived inequities in the distribution of benefits and costs, and concern about facility safety. Benefit-cost inequities may be dealt with in part by keeping wastes where they are generated, through political restrictions, or by providing economic compensation and political incentives (for example, a local veto). Assuring people of facility safety includes allowing local control (monitoring, health assessment, regulation), and enhancing trust of facility managers through such means as rectifying past mistakes, individual-oriented education campaigns, and negotiation of compensation packages with local residents. These means should reduce —without eliminating—public opposition to local siting of nuclear and chemical waste facilities.

  9. ARM Operations and Engineering Procedure Mobile Facility Site Startup

    SciTech Connect

    Voyles, Jimmy W

    2015-05-01

    This procedure exists to define the key milestones, necessary steps, and process rules required to commission and operate an Atmospheric Radiation Measurement (ARM) Mobile Facility (AMF), with a specific focus toward on-time product delivery to the ARM Data Archive. The overall objective is to have the physical infrastructure, networking and communications, and instrument calibration, grooming, and alignment (CG&A) completed with data products available from the ARM Data Archive by the Operational Start Date milestone.

  10. DREDGED MATERIAL RECLAMATION AT THE JONES ISLAND CONFINED DISPOSAL FACILITY SITE CAPSULE

    EPA Science Inventory

    In this SITE demonstration, phytoremediation technology was applied to contaminated dredged materials from the Jones Island Confined Disposal Facility (CDF) located in Milwaukee Harbor, Wisconsin. The Jones Island CDF receives dredged materials from normal maintenance of Milwauke...

  11. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes

    SciTech Connect

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

  12. Lessons learned from the Siting Process of an Interim Storage Facility in Spain - 12024

    SciTech Connect

    Lamolla, Meritxell Martell

    2012-07-01

    On 29 December 2009, the Spanish government launched a site selection process to host a centralised interim storage facility for spent fuel and high-level radioactive waste. It was an unprecedented call for voluntarism among Spanish municipalities to site a controversial facility. Two nuclear municipalities, amongst a total of thirteen municipalities from five different regions, presented their candidatures to host the facility in their territories. For two years the government did not make a decision. Only in November 30, 2011, the new government elected on 20 November 2011 officially selected a non-nuclear municipality, Villar de Canas, for hosting this facility. This paper focuses on analysing the factors facilitating and hindering the siting of controversial facilities, in particular the interim storage facility in Spain. It demonstrates that involving all stakeholders in the decision-making process should not be underestimated. In the case of Spain, all regional governments where there were candidate municipalities willing to host the centralised interim storage facility, publicly opposed to the siting of the facility. (author)

  13. LNG Safety Assessment Evaluation Methods

    SciTech Connect

    Muna, Alice Baca; LaFleur, Angela Christine

    2015-05-01

    Sandia National Laboratories evaluated published safety assessment methods across a variety of industries including Liquefied Natural Gas (LNG), hydrogen, land and marine transportation, as well as the US Department of Defense (DOD). All the methods were evaluated for their potential applicability for use in the LNG railroad application. After reviewing the documents included in this report, as well as others not included because of repetition, the Department of Energy (DOE) Hydrogen Safety Plan Checklist is most suitable to be adapted to the LNG railroad application. This report was developed to survey industries related to rail transportation for methodologies and tools that can be used by the FRA to review and evaluate safety assessments submitted by the railroad industry as a part of their implementation plans for liquefied or compressed natural gas storage ( on-board or tender) and engine fueling delivery systems. The main sections of this report provide an overview of various methods found during this survey. In most cases, the reference document is quoted directly. The final section provides discussion and a recommendation for the most appropriate methodology that will allow efficient and consistent evaluations to be made. The DOE Hydrogen Safety Plan Checklist was then revised to adapt it as a methodology for the Federal Railroad Administration’s use in evaluating safety plans submitted by the railroad industry.

  14. National Ignition Facility subsystem design requirements NIF site improvements SSDR 1.2.1

    SciTech Connect

    Kempel, P.; Hands, J.

    1996-08-19

    This Subsystem Design Requirements (SSDR) document establishes the performance, design, and verification requirements associated with the NIF Project Site at Lawrence Livermore National Laboratory (LLNL) at Livermore, California. It identifies generic design conditions for all NIF Project facilities, including siting requirements associated with natural phenomena, and contains specific requirements for furnishing site-related infrastructure utilities and services to the NIF Project conventional facilities and experimental hardware systems. Three candidate sites were identified as potential locations for the NIF Project. However, LLNL has been identified by DOE as the preferred site because of closely related laser experimentation underway at LLNL, the ability to use existing interrelated infrastructure, and other reasons. Selection of a site other than LLNL will entail the acquisition of site improvements and infrastructure additional to those described in this document. This SSDR addresses only the improvements associated with the NIF Project site located at LLNL, including new work and relocation or demolition of existing facilities that interfere with the construction of new facilities. If the Record of Decision for the PEIS on Stockpile Stewardship and Management were to select another site, this SSDR would be revised to reflect the characteristics of the selected site. Other facilities and infrastructure needed to support operation of the NIF, such as those listed below, are existing and available at the LLNL site, and are not included in this SSDR. Office Building. Target Receiving and Inspection. General Assembly Building. Electro- Mechanical Shop. Warehousing and General Storage. Shipping and Receiving. General Stores. Medical Facilities. Cafeteria services. Service Station and Garage. Fire Station. Security and Badging Services.

  15. Determinations of TSD facility acceptability under the CERCLA Off-Site Rule

    SciTech Connect

    1997-06-01

    On September 22, 1993, the US Environmental Protection Agency (EPA) published the ``Off-Site Rule`` to implement section 121(d)(3) of the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). CERCLA {section}121(d)(3) requires that wastes generated as a result of remediation activities taken under CERCLA authority and transferred off-site be managed only at facilities that comply with the Resource Conservation and Recovery Act. In 1994, the DOE`s Office of Environmental Policy and Assistance (OEPA), RCRA/CERCLA Division (EH-413) published a CERCLA Information Brief titled ``The Off-Site Rule`` which describes the content of the Off-Site Rule and clarifies some of its implications for DOE remedial actions under CERCLA. Additionally, EH-413 published the Guide on Selecting Compliant Off-Site Hazardous Waste Treatment, Storage and Disposal Facilities which provides a regulatory roadmap for accomplishing off-site transfers of environmental restoration and process hazardous waste at DOE facilities in a manner compliant with the Off-Site Rule and other relevant Federal regulations. Those guidance documents concentrate primarily on DOE`s perspective as a hazardous waste generator. The purpose of this Information Brief is to address the implications of the Off-Site Rule for DOE-owned hazardous waste treatment, storage or disposal facilities that accept CERCLA remediation wastes from off-site locations.

  16. 49 CFR 193.2181 - Impoundment capacity: LNG storage tanks.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 3 2011-10-01 2011-10-01 false Impoundment capacity: LNG storage tanks. 193.2181... Impoundment capacity: LNG storage tanks. Each impounding system serving an LNG storage tank must have a minimum volumetric liquid impoundment capacity of: (a) 110 percent of the LNG tank's maximum...

  17. 49 CFR 193.2181 - Impoundment capacity: LNG storage tanks.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 49 Transportation 3 2010-10-01 2010-10-01 false Impoundment capacity: LNG storage tanks. 193.2181... Impoundment capacity: LNG storage tanks. Each impounding system serving an LNG storage tank must have a minimum volumetric liquid impoundment capacity of: (a) 110 percent of the LNG tank's maximum...

  18. Conceptual Design Report: Nevada Test Site Mixed Waste Disposal Facility Project

    SciTech Connect

    NSTec Environmental Management

    2009-01-31

    Environmental cleanup of contaminated nuclear weapons manufacturing and test sites generates radioactive waste that must be disposed. Site cleanup activities throughout the U.S. Department of Energy (DOE) complex are projected to continue through 2050. Some of this waste is mixed waste (MW), containing both hazardous and radioactive components. In addition, there is a need for MW disposal from other mission activities. The Waste Management Programmatic Environmental Impact Statement Record of Decision designates the Nevada Test Site (NTS) as a regional MW disposal site. The NTS has a facility that is permitted to dispose of onsite- and offsite-generated MW until November 30, 2010. There is not a DOE waste management facility that is currently permitted to dispose of offsite-generated MW after 2010, jeopardizing the DOE environmental cleanup mission and other MW-generating mission-related activities. A mission needs document (CD-0) has been prepared for a newly permitted MW disposal facility at the NTS that would provide the needed capability to support DOE's environmental cleanup mission and other MW-generating mission-related activities. This report presents a conceptual engineering design for a MW facility that is fully compliant with Resource Conservation and Recovery Act (RCRA) and DOE O 435.1, 'Radioactive Waste Management'. The facility, which will be located within the Area 5 Radioactive Waste Management Site (RWMS) at the NTS, will provide an approximately 20,000-cubic yard waste disposal capacity. The facility will be licensed by the Nevada Division of Environmental Protection (NDEP).

  19. 76 FR 2677 - Southern LNG Company, LLC; Notice of Public Scoping Meeting for the Proposed LNG Truck Loading...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-14

    ... Energy Regulatory Commission Southern LNG Company, LLC; Notice of Public Scoping Meeting for the Proposed LNG Truck Loading Project January 7, 2011. On February 2, 2011, the Office of Energy Projects staff... Southern LNG Company, LLC's (Southern) LNG Truck Loading Project. We scheduled this meeting to...

  20. 40 CFR 63.7882 - What site remediation sources at my facility does this subpart affect?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 40 Protection of Environment 13 2010-07-01 2010-07-01 false What site remediation sources at my... Remediation What This Subpart Covers § 63.7882 What site remediation sources at my facility does this subpart... remediation as designated by paragraphs (a)(1) through (3) of this section. (1) Process vents. The...

  1. APPROACHES FOR REMEDIATION OF FEDERAL FACILITY SITES CONTAMINATED WITH EXPLOSIVE/RADIOACTIVE WASTE

    EPA Science Inventory

    Military operations have resulted in the contamination of soil and ground water at many federal facility sites. everal of these sites are undergoing corrective action to reduce risk. his handbook covers safety concerns, sampling methods, and treatment and management options for e...

  2. Guidance on risk analysis and safety implications of a large liquefied natural gas (LNG) spill over water.

    SciTech Connect

    Wellman, Gerald William; Melof, Brian Matthew; Luketa-Hanlin, Anay Josephine; Hightower, Marion Michael; Covan, John Morgan; Gritzo, Louis Alan; Irwin, Michael James; Kaneshige, Michael Jiro; Morrow, Charles W.

    2004-12-01

    While recognized standards exist for the systematic safety analysis of potential spills or releases from LNG (Liquefied Natural Gas) storage terminals and facilities on land, no equivalent set of standards or guidance exists for the evaluation of the safety or consequences from LNG spills over water. Heightened security awareness and energy surety issues have increased industry's and the public's attention to these activities. The report reviews several existing studies of LNG spills with respect to their assumptions, inputs, models, and experimental data. Based on this review and further analysis, the report provides guidance on the appropriateness of models, assumptions, and risk management to address public safety and property relative to a potential LNG spill over water.

  3. How Gaz de France optimizes LNG regasification

    SciTech Connect

    Colonna, J.L.; Lecomte, B.; Caudron, S.

    1986-05-05

    A regasification optimization program was implemented at Montoir-de-Bretagne in 1984, and rapidly accepted by the operators. It has been an important tool for decision-making in the optimizing operation of this liquefied natural gas (LNG) storage and regasification terminal. The models used are regularly and easily updated on the basis of equipment behavior: aging or fouling. The Montoir-de-Bretagne LNG terminal is in the port area of Nates-Saint Nazaire on the Atlantic coast. It was commissioned in 1982 by Gaz de France. This terminal is used for receiving, storing, and regasifying the Algerian LNG received under a contract between Gaz de France and Sonatrach, as well as the LNG imported by Belgium and temporarily routed through France. It is designed to receive 25,000 to 200,000 cu m LNG carriers and has three 120,000 cm m LNG storage tanks. The daily sendout ranges between 6.7 million cu m and 36 million cu m. Monitor terminal supplies mainly Brittany and the Paris area. Two identifical berths allow the simultaneous reception of two LNG carriers. LNG is carried to the storage tanks in 32-in. lines at a rate of 12,000 cu m/hr. Each storage tank is equipped with three submerged 450 cu m/hr pumps with which the LNG is sent from the tanks to the secondary pumps at 8 bar. The nine high-pressure (HP) secondary pumps, with a capacity of either 450 cu m/hr or 180 cu m/hr, raise the LNG pressure to a level at least equal to pipeline pressure prior to revaporization.

  4. Compensation for risks: host community benefits in siting locally unwanted facilities

    NASA Astrophysics Data System (ADS)

    Himmelberger, Jeffery J.; Ratick, Samuel J.; White, Allen L.

    1991-09-01

    This article analyzes the recent negotiations connected with siting 24 solid-waste landfills in Wisconsin. We examine the association between the type and amount of compensation paid to host communities by facility developers and the size of facilities, certain facility characteristics, the timing of negotiated agreements, the size of the host community, and the socioeconomic status of the host area. Our findings suggest that the level of compensation after adjusting for landfill capacity is positively associated with the percentage of total facility capacity dedicated to host community use, positively associated with the percentage of people of the host area who are in poverty, and larger for public facilities that accept municipal wastes. Other explanatory variables we examined, whose association with levels of compensation proved statistically insignificant, were facility size, facility status (new vs expansion), facility use (countyonly vs multicounty), timing of negotiation, host community size, and the host area education level, population density, and per capita income. We discuss the policy implications of our principal findings and future research questions in light of the persistent opposition surrounding the siting of solid-waste and other waste-management facilities.

  5. 33 CFR 127.105 - Layout and spacing of marine transfer area for LNG.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 33 Navigation and Navigable Waters 2 2011-07-01 2011-07-01 false Layout and spacing of marine transfer area for LNG. 127.105 Section 127.105 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF... AND LIQUEFIED HAZARDOUS GAS Waterfront Facilities Handling Liquefied Natural Gas § 127.105 Layout...

  6. 33 CFR 127.105 - Layout and spacing of marine transfer area for LNG.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Layout and spacing of marine transfer area for LNG. 127.105 Section 127.105 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF... AND LIQUEFIED HAZARDOUS GAS Waterfront Facilities Handling Liquefied Natural Gas § 127.105 Layout...

  7. 78 FR 933 - Cameron LNG, LLC; Cameron Interstate Pipeline, LLC; Notice of Applications

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-07

    ..., California 92101, filed in Docket No. CP13-25-000 an application, pursuant to section 3 of the Natural Gas... 1.7 billion cubic feet per day (Bcfd) of domestic natural gas. Cameron Interstate requests... Bcfd of domestic natural gas supply to Cameron LNG's liquefaction facilities. Cameron...

  8. Audit of the deactivation, decontamination, and disposal of surplus facilities at the Savannah River Site

    SciTech Connect

    1997-10-23

    Westinghouse Savannah River Company (Westinghouse) is responsible for managing the Department of Energy`s (Department) surplus facilities at the Savannah River Site (Site). In Fiscal Year (FY) 1996, the Site had 162 surplus facilities and anticipated that 118 more would become surplus within the next 5 years. The objective of this audit was to determine whether the Savannah River Operations Office (Operations Office) and Westinghouse had economically and promptly deactivated, decontaminated, and disposed of surplus facilities at the Site. Departmental regulations require that surplus facilities be deactivated, decontaminated, and disposed of economically and promptly. However, Westinghouse only disposed of one facility and did not completely deactivate or decontaminate any of the 162 facilities identified as surplus at the Site in FY 1996. This occurred because the Operations Office did not compile a Site-wide list, establish priorities, or provide sufficient funding for the deactivation, decontamination, and disposal of surplus facilities. As a result, the Department incurred unnecessary costs for the surveillance and maintenance of surplus facilities. For example, the Department could have avoided annual costs of about $1.3 million in surveillance and maintenance costs by spending $1.2 million to perform a deactivation project on the P-Reactor process-water storage tanks. The Operations Office could have funded the project out of its unobligated FY 1996 operating funds. However, it returned the unobligated funds to the Department`s Headquarters at the end of the fiscal year. The Operations Office concurred with the finding and recommendations and initiated corrective action.

  9. Alternative energy facility siting policies for urban coastal areas: executive summary of findings and policy recommendations

    SciTech Connect

    Morell, D; Singer, G

    1980-11-01

    An analysis was made of siting issues in the coastal zone, one of the nation's most critical natural resource areas and one which is often the target for energy development proposals. The analysis addressed the changing perceptions of citizens toward energy development in the coastal zone, emphasizing urban communities where access to the waterfront and revitalization of waterfront property are of interest to the citizen. The findings of this analysis are based on an examination of energy development along New Jersey's urban waterfront and along the Texas-Louisiana Gulf Coast, and on redevelopment efforts in Seattle, San Francisco, Boston, and elsewhere. The case studies demonstrate the significance of local attitudes and regional cooperation in the siting process. In highly urbanized areas, air quality has become a predominant concern among citizen groups and an influential factor in development of alternative energy facility siting strategies, such as consideration of inland siting connected by pipeline to a smaller coastal facility. The study addresses the economic impact of the permitting process on the desirability of energy facility investments, and the possible effects of the location selected for the facility on the permitting process and investment economics. The economic analysis demonstrates the importance of viewing energy facility investments in a broad perspective that includes the positive or negative impacts of various alternative siting patterns on the permitting process. Conclusions drawn from the studies regarding Federal, state, local, and corporate politics; regulatory, permitting, licensing, environmental assessment, and site selection are summarized. (MCW)

  10. Federal Facility Compliance Act, Proposed Site Treatment Plan: Background Volume. Executive Summary

    SciTech Connect

    1995-03-24

    This Federal Facility Compliance Act Site Treatment Plan discusses the options of radioactive waste management for Ames Laboratory. This is the background volume which discusses: site history and mission; framework for developing site treatment plans; proposed plan organization and related activities; characterization of mixed waste and waste minimization; low level mixed waste streams and the proposed treatment approach; future generation of TRU and mixed wastes; the adequacy of mixed waste storage facilities; and a summary of the overall DOE activity in the area of disposal of mixed waste treatment residuals.

  11. Cooperative fish-rearing programs in Hanford Site excess facilities

    SciTech Connect

    Herborn, D.I.; Anderson, B.N.

    1994-05-01

    In, 1993, two successful fish-rearing pilot projects were conducted in Hanford Site 100 K Area water treatment pools (K Pools) that are excess to the US Department of Energy needs. Beginning this spring, two larger cooperative fish programs will be undertaken in the K Pools. One program will involve the Yakama Indian Nation, which will rear, acclimate, and release 500,000 fall chinook salmon. The other program involves the Washington Department of Fish and Wildlife, which will rear warm-water specie (walleye and channel catfish) for planting in state lakes. Renewed economic vitality is the goal expected from these and follow-on fish programs.

  12. Hanford Site near-facility environmental monitoring data report for calendar year 1998

    SciTech Connect

    DIEDIKER, L.P.

    1999-07-29

    This document summarizes the results of the U.S. Department of Energy's Near-Facility Environmental Monitoring program conducted by Waste Management Federal Services of Hanford, Inc. for Fluor Daniel Hanford, Inc. for 1998 in the 100,200/600, and 300/400 Areas of the Hanford Site, in southcentral Washington State. Surveillance activities included sampling and analyses of ambient air, surface water, groundwater, soil, sediments, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. In addition, diffuse sources were monitored to determine compliance with federal, state, and/or local regulations. In general, although effects from nuclear facilities can still be observed on the Hanford Site and radiation levels are slightly elevated when compared to offsite locations, the differences are less than in previous years.

  13. Design report for the interim waste containment facility at the Niagara Falls Storage Site. [Surplus Facilities Management Program

    SciTech Connect

    Not Available

    1986-05-01

    Low-level radioactive residues from pitchblende processing and thorium- and radium-contaminated sand, soil, and building rubble are presently stored at the Niagara Falls Storage Site (NFSS) in Lewiston, New York. These residues and wastes derive from past NFSS operations and from similar operations at other sites in the United States conducted during the 1940s by the Manhattan Engineer District (MED) and subsequently by the Atomic Energy Commission (AEC). The US Department of Energy (DOE), successor to MED/AEC, is conducting remedial action at the NFSS under two programs: on-site work under the Surplus Facilities Managemnt Program and off-site cleanup of vicinity properties under the Formerly Utilized Sites Remedial Action Program. On-site remedial action consists of consolidating the residues and wastes within a designated waste containment area and constructing a waste containment facility to prevent contaminant migration. The service life of the system is 25 to 50 years. Near-term remedial action construction activities will not jeopardize or preclude implementation of any other remedial action alternative at a later date. Should DOE decide to extend the service life of the system, the waste containment area would be upgraded to provide a minimum service life of 200 years. This report describes the design for the containment system. Pertinent information on site geology and hydrology and on regional seismicity and meteorology is also provided. Engineering calculations and validated computer modeling studies based on site-specific and conservative parameters confirm the adequacy of the design for its intended purposes of waste containment and environmental protection.

  14. Applications of remote sensing to wind power facility siting

    NASA Astrophysics Data System (ADS)

    Wade, J. E.; Rosenfeld, C. L.; Maule, P. A.

    A method by which wind energy prospectors can use remote sensing to rapidly examine extensive geographical areas to identify potential wind turbine generators' sites is outlined. Remote sensing in wind prospecting is not being considered as a tool for determining wind power potential but, rather, as an aid in identifying terrestrial, marine, and atmospheric characteristics associated with desirable wind power sites. It is noted that locations with interesting features noted in a regional assessment can be more closely evaluated using medium-scale imagery, which can be acquired from a number of different agencies, among them the U.S. Forest Service, the Bureau of Land Management, Water and Power Resources and the Soil Conservation Service. Once specific locations have been identified from small- and medium-scale imagery, low-level aerial reconnaissance in a locally chartered aircraft can verify the information obtained. Wind-deformed trees, active slip faces on dunes, snow cornices, snow fences, and the slopes of ridges can be evaluated.

  15. Federal Facilities Compliance Act, Draft Site Treatment Plan: Background Volume, Part 2, Volume 1

    SciTech Connect

    1994-08-31

    This Draft Site Treatment Plan was prepared by Ames Laboratory to meet the requirements of the Federal Facilities Compliance Act. Topics discussed include: purpose and scope of the plan; site history and mission; draft plant organization; waste minimization; waste characterization; preferred option selection process; technology for treating low-level radioactive wastes and TRU wastes; future generation of mixed waste streams; funding; and process for evaluating disposal issues in support of the site treatment plan.

  16. Beyond the not-in-my-backyard impasse. [Siting of hazardous waste facilities

    SciTech Connect

    Peelle, E.; Ellis, R.

    1987-01-01

    Key assumptions of past planning in hazardous waste siting are no longer valid. Workable, legitimate solutions to hazardous waste siting will require (1) a comprehensive integrated hazardous waste management strategy giving primary emphasis to waste stream reduction, detoxification, and recycling; (2) extensive interactive communication and participation among citizens, regulators, and waste managers during planning, siting, and operation; and (3) net institutional arrangements and guarantees that instill confidence among citizens about the need for and safety of proposed hazardous waste facilities.

  17. A NOVEL PROCESS TO USE SALT CAVERNS TO RECEIVE SHIP BORNE LNG

    SciTech Connect

    Michael M. McCall; William M. Bishop; Marcus Krekel; James F. Davis; D. Braxton Scherz

    2005-05-31

    This cooperative research project validates use of man made salt caverns to receive and store the cargoes of LNG ships in lieu of large liquid LNG tanks. Salt caverns will not tolerate direct injection of LNG because it is a cryogenic liquid, too cold for contact with salt. This research confirmed the technical processes and the economic benefits of pressuring the LNG up to dense phase, warming it to salt compatible temperatures and then directly injecting the dense phase gas into salt caverns for storage. The use of salt caverns to store natural gas sourced from LNG imports, particularly when located offshore, provides a highly secure, large scale and lower cost import facility as an alternative to tank based LNG import terminals. This design can unload a ship in the same time as unloading at a tank based terminal. The Strategic Petroleum Reserve uses man made salt caverns to securely store large quantities of crude oil. Similarly, this project describes a novel application of salt cavern gas storage technologies used for the first time in conjunction with LNG receiving. The energy industry uses man made salt caverns to store an array of gases and liquids but has never used man made salt caverns directly in the importation of LNG. This project has adapted and expanded the field of salt cavern storage technology and combined it with novel equipment and processes to accommodate LNG importation. The salt cavern based LNG receiving terminal described in the project can be located onshore or offshore, but the focus of the design and cost estimates has been on an offshore location, away from congested channels and ports. The salt cavern based terminal can provide large volumes of gas storage, high deliverability from storage, and is simplified in operation compared to tank based LNG terminals. Phase I of this project included mathematical modeling that proved a salt cavern based receiving terminal could be built at lower capital cost, and would have significantly higher

  18. Comparison of Candidate Sites for installation of Landfill facility at Ignalina NPP Site Using Fuzzy Logic Approach

    SciTech Connect

    Poskas, P.; Kilda, R.; Poskas, G.

    2008-07-01

    There is only one nuclear power plant in Lithuania - Ignalina NPP (Nuclear Power Plant). Two similar units with installed capacity of 1500 MW (each) were commissioned in 1983 and 1987 respectively. But the first Unit of Ignalina NPP was finally shutdown December 31, 2004, and second Unit is planned to be shutdown before 2010. Operational radioactive waste of different activities is generated at Ignalina NPP. After closure of INPP a waste from decommissioning should be managed also. According to Lithuanian regulatory requirements (1) the waste depending on the activity must be managed in different ways. In compliance with this Regulation very low-level radioactive waste (VLLW) could be disposed of in a Landfill facility. In such case very simple engineered barriers are required. A cap on the top of the repository is necessary from long-term safety point of view. Experience has shown that the effective and safe isolation of waste depends on the performance of the overall disposal system, which is formed by three major components: the site, the disposal facility and the waste form. The basic objective of the siting process is to select a suitable site for disposal and demonstrate that this site has characteristics which provide adequate isolation of radionuclides from the biosphere for desired periods of time. The methodology and results on evaluation and comparison of two candidate sites intended for construction of Landfill facility at Ignalina NPP site are presented in the paper. Criteria for comparison are based on the IAEA (International Atomic Energy Agency) recommendations (2). Modeling of the radionuclide releases has been performed using ISAM (Improving of Safety Assessment Methodologies for Near Surface Disposal facilities) methodology (3). For generalization of the information and elaboration of the recommendations Fuzzy Logic approach was used (4). (authors)

  19. Site and facility waste transport planning documents (SPDs) status and findings

    SciTech Connect

    Schmid, S P; Danese, F L; Wankerl, M W

    1993-05-01

    Site and Facility Waste Transportation Services Planning Documents (SPDS) are detailed desk-top reference documents that initiate planning for shipping commercial spent nuclear fuel (SNF) from the sites where it is currently generated and/or stored to another location. Because of the unique design features and individual variations in the spent fuel handling and cask loading operation requirements for each facility, one SPD will be written for each of the commercial facilities currently expected to deliver SNF into the Civilian Radioactive Waste Management System (CRWMS) disposal system. One primary purpose of an SPD is to initiate the discussions that will lead to a determination of the type of spent fuel cask and transport mode that will be used to transport spent fuel from each facility. The initial assessment of which cask type and mode would best serve each facility is based on the principle that the largest possible capacity casks should be used at the greatest number of facilities to reduce the total number of spent fuel shipments. The final selection of cask and transportation mode will be arrived at following discussion with the facility licensed operator. Once agreed upon by OCRWM and the facility owner, the SPD wig be used as a primary input to the development of a Site Specific Servicing Plan (SSSP) that will detail chosen servicing options for the individual site. This paper will discuss the purpose and development of SPDs and the preliminary results of an evaluation of the ability of delivering facilities to handle and ship spent fuel casks within the confines of the local nation infrastructure.

  20. Applications of human factors engineering to LNG release prevention and control

    SciTech Connect

    Shikiar, R.; Rankin, W.L.; Rideout, T.B.

    1982-06-01

    The results of an investigation of human factors engineering and human reliability applications to LNG release prevention and control are reported. The report includes a discussion of possible human error contributions to previous LNG accidents and incidents, and a discussion of generic HF considerations for peakshaving plants. More specific recommendations for improving HF practices at peakshaving plants are offered based on visits to six facilities. The HF aspects of the recently promulgated DOT regulations are reviewed, and recommendations are made concerning how these regulations can be implemented utilizing standard HF practices. Finally, the integration of HF considerations into overall system safety is illustrated by a presentation of human error probabilities applicable to LNG operations and by an expanded fault tree analysis which explicitly recognizes man-machine interfaces.

  1. LNG -- A paradox of propulsion potential

    SciTech Connect

    McKay, D.J.

    1995-12-31

    Liquefied natural gas (LNG) has been demonstrating its viability as a clean-burning alternative fuel for buses and medium- and heavy-duty trucks for the past 30 years. The first known LNG vehicle project began in San Diego in 1965, When San Diego Gas and Electric converted 22 utility trucks and three passenger vehicles to dedicated LNG. A surge in LNG vehicle project activity over the past five years has led to a fairly robust variety of vehicles testing the fuel, from Class 8 tractors, refuse haulers and transit buses to railroad locomotives and ferry boats. Recent technology improvements in engine design, cryogenic tanks, fuel nozzles and other related equipment have made LNG more practical to use than in the 1960s. LNG delivers more than twice the driving range from the same-sized fuel tank as a vehicle powered by compressed natural gas (CNG). Although technical and economic hurdles must be overcome before this fuel can achieve widespread use, various ongoing demonstration projects are showing LNG`s practicality, while serving the vital role of pinpointing those areas of performance that are the prime candidates for improvement.

  2. Comparative approaches to siting low-level radioactive waste disposal facilities

    SciTech Connect

    Newberry, W.F.

    1994-07-01

    This report describes activities in nine States to select site locations for new disposal facilities for low-level radioactive waste. These nine States have completed processes leading to identification of specific site locations for onsite investigations. For each State, the status, legal and regulatory framework, site criteria, and site selection process are described. In most cases, States and compact regions decided to assign responsibility for site selection to agencies of government and to use top-down mapping methods for site selection. The report discusses quantitative and qualitative techniques used in applying top-down screenings, various approaches for delineating units of land for comparison, issues involved in excluding land from further consideration, and different positions taken by the siting organizations in considering public acceptance, land use, and land availability as factors in site selection.

  3. Screening and identification of sites for a proposed Monitored Retrievable Storage Facility

    SciTech Connect

    none,

    1985-04-01

    The Director, Office of Civilian Radioactive Waste Management (OCRWM), Department of Energy (DOE), has identified the Clinch River Breeder Reactor site, the DOE Oak Ridge Reservation and the Tennessee Valley Authority (TVA) Hartsville Nuclear Plant site as preferred and alternative sites, respectively, for development of site-specific designs as part of the proposal for construction of an integrated Monitored Retrievable Storage (MRS) Facility. The proposal, developed pursuant to Section 141 (b) of the Nuclear Waste Policy Act of 1982, will be submitted to Congress in January 1986. The Director expects to propose to Congress that an MRS be constructed at the perferred site. His judgment could change based on information to be developed between now and January 1986. The decision to construct an MRS facility and final site selection are reserved by Congress for itself. The Director's judgment is based on the results of a rigorous site screening and evaluation process described in this report. The three sites were selected from among eleven sites evaluated in detail. The Clinch River Breeder Reactor site, owned by the Tennessee Valley Authority, was identified as the preferred site. It has several particularly desirable features including: (1) federal ownership and control by the Department of Energy; (2) particularly good transportation access (five miles to the nearest interstate highway and direct rail access); (3) site characteristics and current data base judged by the NRC in 1983 as sufficient for granting a limited work authorization for the now cancelled breeder reactor; and (4) a technical community in the vicinity of site which can provide experienced nuclear facility support functions. 6 figs., 2 tabs.

  4. FEM3A simulations of selected LNG vapor barrier verification field tests

    SciTech Connect

    Chan, S.T.

    1990-10-01

    In order to evaluate and eventually predict the possible mitigating effects of vapor fences on the dispersion of the vapor cloud resulting from an accidental liquefied natural gas (LNG) spill in storage areas, a research program was initiated to evaluate methods for predicting LNG dispersion distances for realistic facility configurations. As part of the program, Lawrence Livermore National Laboratory (LLNL) conducted a series of large-scale field experiments called the LNG Vapor Barrier Verification Field Trials (also referred to as the Falcon Series) at the Liquefied Gaseous Fuels Spill Test Facility (LGFSTF), Nevada. Objectives were (1) to provide a data base on LNG vapor dispersion from spill involving complex field obstacles to assist in validation of wind tunnel and mathematical models, and (2) to assess the effectiveness of vapor fences for mitigating LNG vapor dispersion hazards in the events of an accidental spill. Five spill experiments were conducted on water in order to generate vapor at rates equivalent to the liquid spill rates. In this study, the FEM3A model was applied to simulate four of the Falcon experiments. The objectives of this study were, through numerical modeling and a detailed model-data comparison: (1) to improve our understanding of LNG vapor dispersion involving vapor barriers, (2) to assess FEM3A in modeling such complex vapor dispersion scenarios, and (3) to complement the results of field and wind tunnel tests, such as providing plausible explanations for unexpected results and filling in data gaps due to instrument failure or limited array size. Toward these goals, the relevant field measurements were analyzed and several series of 2-D and 3-D simulations were carried out. 11 refs., 93 figs., 11 tabs.

  5. Dismantlement and decontamination of a plutonium-238 facility at the Savannah river site

    SciTech Connect

    Smith, R.H.; Hootman, H.E.

    1994-01-01

    Very little documented decontamination and decommissioning (D&D) experience exists on which to project cleanup costs and schedules for plutonium facilities at DOE sites. A plutonium-238 processing facility at Savannah River Site (SRS) has been undergoing D&D intermittently since 1984. Although this cleanup effort was not originally intended to quantify results, some key data have been accumulated, and the project has demonstrated effective methods of performing D&D work under conditions of high contamination. Some data is presented here; however, more specific tests and data may be obtained during the remainder of this project. This project has been recommended as a candidate test facility for a DOE planned {open_quotes}Integrated D&D Demonstration{close_quotes} managed by EM-50 to develop and demonstrate technology for D&D and surplus facilities deactivation.

  6. Guide to radiological accident considerations for siting and design of DOE nonreactor nuclear facilities

    SciTech Connect

    Elder, J.C.; Graf, J.M.; Dewart, J.M.; Buhl, T.E.; Wenzel, W.J.; Walker, L.J.; Stoker, A.K.

    1986-01-01

    This guide was prepared to provide the experienced safety analyst with accident analysis guidance in greater detail than is possible in Department of Energy (DOE) Orders. The guide addresses analysis of postulated serious accidents considered in the siting and selection of major design features of DOE nuclear facilities. Its scope has been limited to radiological accidents at nonreactor nuclear facilities. The analysis steps addressed in the guide lead to evaluation of radiological dose to exposed persons for comparison with siting guideline doses. Other possible consequences considered are environmental contamination, population dose, and public health effects. Choices of models and parameters leading to estimation of source terms, release fractions, reduction and removal factors, dispersion and dose factors are discussed. Although requirements for risk analysis have not been established, risk estimates are finding increased use in siting of major nuclear facilities, and are discussed in the guide. 3 figs., 9 tabs.

  7. Environmental Assessment for the new Whole Body Counter facility at the Savannah River Site

    SciTech Connect

    Not Available

    1993-01-01

    The U.S. Department of Energy proposes to construct and operate a new in-vivo counting facility at the Savannah River Site for the monitoring of employees for internal radionuclides. The proposed facility, titled the new Whole Body Counter (WBC) facility, would house both the existing and additional new invivo counting equipment and facility support operations. The proposed facility would be sited and located in an area of the SRS in which background radiation levels are sufficiently low to assure accurate in-vivo counts and a location that would assure ease of access for occupational workers. This Environmental Assessment has been prepared in compliance with the National Environmental Policy Act (NEPA) of 1969, as amended, and the requirements of the Council on Environmental Quality Regulations for Implementing NEPA (40 CPR Parts 1500-1508). NEPA requires the assessment of environmental consequences of Federal actions that may affect the quality of the human environment. The proposed action has independent utility to the Savannah River operations and will be necessary to support plant activities regardless of the makeup of the future mission at the site. As such, the proposed new WBC facility is treated as part of the preliminary Reconfiguration Programmatic Environmental Impact Statement ``No Action`` alternative.

  8. Overview of Fiscal Year 2002 Research and Development for Savannah River Site's Salt Waste Processing Facility

    SciTech Connect

    H. D. Harmon, R. Leugemors, PNNL; S. Fink, M. Thompson, D. Walker, WSRC; P. Suggs, W. D. Clark, Jr

    2003-02-26

    The Department of Energy's (DOE) Savannah River Site (SRS) high-level waste program is responsible for storage, treatment, and immobilization of high-level waste for disposal. The Salt Processing Program (SPP) is the salt (soluble) waste treatment portion of the SRS high-level waste effort. The overall SPP encompasses the selection, design, construction and operation of treatment technologies to prepare the salt waste feed material for the site's grout facility (Saltstone) and vitrification facility (Defense Waste Processing Facility). Major constituents that must be removed from the salt waste and sent as feed to Defense Waste Processing Facility include actinides, strontium, cesium, and entrained sludge. In fiscal year 2002 (FY02), research and development (R&D) on the actinide and strontium removal and Caustic-Side Solvent Extraction (CSSX) processes transitioned from technology development for baseline process selection to providing input for conceptual design of the Salt Waste Processing Facility. The SPP R&D focused on advancing the technical maturity, risk reduction, engineering development, and design support for DOE's engineering, procurement, and construction (EPC) contractors for the Salt Waste Processing Facility. Thus, R&D in FY02 addressed the areas of actual waste performance, process chemistry, engineering tests of equipment, and chemical and physical properties relevant to safety. All of the testing, studies, and reports were summarized and provided to the DOE to support the Salt Waste Processing Facility, which began conceptual design in September 2002.

  9. RESEARCH AND DEVELOPMENT ACTIVITIES AT SAVANNAH RIVER SITE'S H CANYON FACILITY

    SciTech Connect

    Sexton, Lindsay; Fuller, Kenneth

    2013-07-09

    The Savannah River Site's (SRS) H Canyon Facility is the only large scale, heavily shielded, nuclear chemical separations plant still in operation in the U.S. The facility's operations historically recovered uranium-235 (U-235) and neptunium-237 (Np-237) from aluminum-clad, enriched-uranium fuel tubes from Site nuclear reactors and other domestic and foreign research reactors. Today the facility, in conjunction with HB Line, is working to provide the initial feed material to the Mixed Oxide Facility also located on SRS. Many additional campaigns are also in the planning process. Furthermore, the facility has started to integrate collaborative research and development (R&D) projects into its schedule. H Canyon can serve as the appropriate testing location for many technologies focused on monitoring the back end of the fuel cycle, due to the nature of the facility and continued operation. H Canyon, in collaboration with the Savannah River National Laboratory (SRNL), has been working with several groups in the DOE complex to conduct testing demonstrations of novel technologies at the facility. The purpose of conducting these demonstrations at H Canyon will be to demonstrate the capabilities of the emerging technologies in an operational environment. This paper will summarize R&D testing activities currently taking place in H Canyon and discuss the possibilities for future collaborations.

  10. Calendar Year 2004 annual site environmental report : Tonopah Test Range, Nevada & Kauai Test Facility, Hawaii.

    SciTech Connect

    Montoya, Amber L.; Wagner, Katrina; Goering, Teresa Lynn; Koss, Susan I.; Salinas, Stephanie A.

    2005-09-01

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, manages TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2004. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 450.1, Environmental Protection Program (DOE 2005) and DOE Order 231.1A, Environment, Safety, and Health Reporting (DOE 2004b).

  11. Site selection modeling system for a production facility at Savannah River site

    SciTech Connect

    Shedrow, C.B.; Shedrow, D.M.

    1996-12-31

    The Savannah River site (SRS) is located along the Savannah River in southwestern South Carolina and encompasses an area of {approximately}832 km (198 344 acres). Major land covers include evergreen and deciduous forests, surface water, wetlands, and administrative/industrial areas. Less than 10% of the site`s surface area is developed. Several endangered and threatened species are found on the SRS, including the red-cockaded woodpecker, the southern bald eagle, the wood stork, and the smooth purple coneflower. With the cessation of the Cold War, the traditional defense-related missions at the SRS have been significantly reduced. The implementation of new missions at the SRS will require the utilization of effective siting and prioritization methodologies to ensure the best use of available land resources and protection of the environment. The objective of this paper is to describe the utilization of the Site Selection Modeling System (SSMS) for the selection of potential industrial development sites within the SRS. The SSMS is a raster geographic information system (GIS)-based system that integrates the graphical interface ArcView 2.1 with the GRID modeling functionality of ARC/INFO. The proposed industrial development being sited is a linear accelerator, which will be used for the accelerator production of tritium.

  12. Seismic analysis of a LNG storage tank isolated by a multiple friction pendulum system

    NASA Astrophysics Data System (ADS)

    Zhang, Ruifu; Weng, Dagen; Ren, Xiaosong

    2011-06-01

    The seismic response of an isolated vertical, cylindrical, extra-large liquefied natural gas (LNG) tank by a multiple friction pendulum system (MFPS) is analyzed. Most of the extra-large LNG tanks have a fundamental frequency which involves a range of resonance of most earthquake ground motions. It is an effective way to decrease the response of an isolation system used for extra-large LNG storage tanks under a strong earthquake. However, it is difficult to implement in practice with common isolation bearings due to issues such as low temperature, soft site and other severe environment factors. The extra-large LNG tank isolated by a MFPS is presented in this study to address these problems. A MFPS is appropriate for large displacements induced by earthquakes with long predominant periods. A simplified finite element model by Malhotra and Dunkerley is used to determine the usefulness of the isolation system. Data reported and statistically sorted include pile shear, wave height, impulsive acceleration, convective acceleration and outer tank acceleration. The results show that the isolation system has excellent adaptability for different liquid levels and is very effective in controlling the seismic response of extra-large LNG tanks.

  13. Site/Systems Operations, Maintenance and Facilities Management of the Department of Energy (DOE) Atmospheric Radiation Measurement (ARM) Southern Great Plains (SGP) Cloud and Radiation Testbed (CART) Site

    SciTech Connect

    Wu, Susan

    2005-08-01

    This contract covered the site/systems operations, maintenance, and facilities management of the DOE Atmospheric Radiation Measurement (ARM) Southern Great Plains (SGP) Cloud and Radiation Testbed (CART) Site.

  14. Environmental Assessment for the Independent Waste Handling Facility, 211-F at the Savannah River Site

    SciTech Connect

    1995-08-01

    Currently, liquid Low Activity Waste (LAW) and liquid High Activity Waste (HAW) are generated from various process operational facilities/processes throughout the Savannah River Site (SRS) as depicted on Figure 2-1. Prior to storage in the F-Area tank farm, these wastes are neutralized and concentrated to minimize their volume. The Waste Handling Facility (211-3F) at Building 211-F Complex (see Figure 2-2) is the only existing facility onsite equipped to receive acidic HAW for neutralization and volume reduction processing. Currently, Building 221-F Canyon (see Figure 2-2) houses the neutralization and evaporation facilities for HAW volume reduction and provides support services such as electric power and plant, process, and instrument air, waste transfer capabilities, etc., for 21 1-F operations. The future plan is to deactivate the 221-F building. DOE`s purpose is to be able to process the LAW/HAW that will continue to be generated on site. DOE needs to establish an alternative liquid waste receipt and treatment capability to support site facilities with a continuing mission. The desire is for Building 211-F to provide the receipt and neutralization functions for LAW and HAW independent of 221-F Canyon. The neutralization capability is required to be part of the Nuclear Materials Stabilization Programs (NMSP) facilities since the liquid waste generated by the various site facilities is acidic. Tn order for Waste Management to receive the waste streams, the solutions must be neutralized to meet Waste Management`s acceptance criteria. The Waste Management system is caustic in nature to prevent corrosion and the subsequent potential failure of tanks and associated piping and hardware.

  15. Environmental Assessment for the Health Protection Instrument Calibration Facility at the Savannah River Site

    SciTech Connect

    Not Available

    1993-08-01

    The purpose of this Environmental Assessment (EA) is to review the possible environmental consequences associated with the construction and operation of a Health Protection Instrument Calibration Facility on the Savannah River Site (SRS). The proposed replacement calibration facility would be located in B Area of SRS and would replace an inadequate existing facility currently located within A Area of SRS (Building 736-A). The new facility would provide laboratories, offices, test equipment and the support space necessary for the SRS Radiation Monitoring Instrument Calibration Program to comply with DOE Orders 5480.4 (Environmental Protection, Safety and Health Protection Standards) and 5480.11 (Radiation Protection for Occupational Workers). The proposed facility would serve as the central site source for the evaluation, selection, inspection, testing, calibration, and maintenance of all SRS radiation monitoring instrumentation. The proposed facility would be constructed on a currently undeveloped portion in B Area of SRS. The exact plot associated with the proposed action is a 1.2 hectare (3 acre) tract of land located on the west side of SRS Road No. 2. The proposed facility would lie approximately 4.4 km (2.75 mi) from the nearest SRS site boundary. The proposed facility would also lie within the confines of the existing B Area, and SRS safeguards and security systems. Archaeological, ecological, and land use reviews have been conducted in connection with the use of this proposed plot of land, and a detailed discussion of these reviews is contained herein. Socioeconomic, operational, and accident analyses were also examined in relation to the proposed project and the findings from these reviews are also contained in this EA.

  16. Gas treating alternatives for LNG plants

    SciTech Connect

    Clarke, D.S.; Sibal, P.W.

    1998-12-31

    This paper covers the various gas treating processes available for treating sour natural gas to specifications required for LNG production. The LNG product specification requires that the total sulfur level be less than 30--40 ppmv, the CO{sub 2} level be less than 50 ppmv and the water level be less than 100 ppmv to prevent freezing problems in the LNG cryogenic column. A wide variety of natural gas compositions are encountered in the various fields and the gas treating process selection is dependent on the type of impurities present in the gas, namely, levels of H{sub 2}S, CO{sub 2}, mercaptans and other organic sulfur compounds. This paper discusses the implications various components in the feed to the LNG plant can have on process selection, and the various treating processes that are available to condition the gas. Process selection criteria, design and operating philosophies are discussed. An economic comparison for two treating schemes is provided.

  17. LNG carrier using membrane tank system delivered

    SciTech Connect

    Not Available

    1993-12-06

    The world's first LNG carrier that incorporates the Technigaz Mark 3 membrane tank system was delivered in October to its owner, Asia LNG Transport Sdn. Bhd., a joint venture between Nippon Yusen K.K. and Perbadanan Nasional Shipping Line Berhad of Malaysia. NKK built the 18,800 cu m, fully double-hull carrier Aman Bintulu at its Tsu works. Construction was completed in September with more than 2 months of sea trials and gas tests using [minus]190 C. Liquid nitrogen and final gas trails with LNG. The orthogonally corrugated stainless membrane primary barrier and the triplex (aluminum foil/fiber glass cloth) composite-material secondary barrier prevent LNG from leaking in the event of an accident.

  18. Norcal Prototype LNG Truck Fleet: Final Results

    SciTech Connect

    Not Available

    2004-07-01

    U.S. DOE and National Renewable Energy Laboratory evaluated Norcal Waste Systems liquefied natural gas (LNG) waste transfer trucks. Trucks had prototype Cummins Westport ISXG engines. Report gives final evaluation results.

  19. Ecological studies related to construction of the Defense Waste Processing Facility on the Savannah River Site

    SciTech Connect

    Scott, D.E.; Pechmann, J.H.K.; Knox, J.N.; Estes, R.A.; McGregor, J.H.; Bailey, K.

    1988-12-01

    The Savannah River Ecology Laboratory has completed 10 years of ecological studies related to the construction of the Defense Waste Processing Facility (DWPF) on the Savannah River Site. This progress report examines water quality studies on streams peripheral to the DWPF construction site and examines the effectiveness of refuge ponds'' in ameliorating the effects of construction on local amphibians. Individual papers on these topics are indexed separately. 93 refs., 15 figs., 15 tabs. (MHB)

  20. Removal site evaluation report for the Isotope Facilities at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1996-07-01

    This removal site evaluation (RmSE) report of the Isotope Facilities at Oak Ridge National Laboratory (ORNL) was prepared to provide the Environmental Restoration Program with information necessary to evaluate whether hazardous and/or radiological contaminants in and around the Isotopes Facility pose a substantial risk to human health or the environment and if remedial site evaluations (RSEs) or removal actions are required. The scope of the project included: (1) a review of historical evidence regarding operations and use of the facility; (2) interviews with facility personnel concerning current and past operating practices; (3) a site inspection; and (4) identification of hazard areas requiring maintenance, removal, or remedial actions. The results of RmSE indicate that no substantial risks exist from contaminants present in the Isotope Facilities because adequate controls and practices exist to protect human health and the environment. The recommended correction from the RmSE are being conducted as maintenance actions; accordingly, this RmSE is considered complete and terminated.

  1. Forging the strategic linkage between facilities management and the corporation -- Production of a sites comprehensive plan

    SciTech Connect

    Petersen, T.P.; Williams, J.L.; Reyes, C.M.

    1997-06-01

    In 1996, Sandia National Laboratories (SNL) undertook a major effort to develop, produce, and execute a Sites Comprehensive Plan. Fundamentally, this document is intended to serve as a tool to clarify the strategic link between (1) current and future mission needs and responsibilities, and (2) the condition, capacity, and required amount of facilities space and infrastructure. It documents the Facilities Group`s response to programmatic requests for capability and makes the case for the required facilities investments through integrated master plans that document SNL`s short- and long-range needs. This paper outlines the history and business environment that led to the writing of the plan, the organizations and committees involved, the steps required to develop and produce it, the challenges encountered in selling it, both internally and externally, and the issues involved in executing the proposed actions set forth in the plan. The paper also articulates the benefits gained by Facilities Management (FM) and the corporation, as well as the lessons learned in producing the plan. SNL has concluded that the Sites Comprehensive Plan was a worthwhile effort in terms of retained facilities investment funding, increased awareness of facility needs, and other measures, despite the significant effort and cost required to produce it.

  2. Environmental Assessment for the ammunition storage facility at the Savannah River Site

    SciTech Connect

    Not Available

    1992-12-01

    The Savannah River Site (SRS), a DOE national defense facility. The SRS maintains an armed and uniformed protective force that performs patrol, guard, and monitoring activities on site. A safe, secure storage facility is needed for the storage of weapons, small arms ammunition, and explosives that may be used in carrying out such activities. This Environmental Assessment assesses the potential environmental and related safety impacts of constructing a small storage facility to replace the existing facility being used to store these munitions. Constructing a new storage facility is necessary to enable SRS to meet DOE requirements and any other applicable standards including DOE Order-6430.1A, General Design Criteria; - 5632.7, Protective Forces; - DOE Manuals-DOE/TIC 11268, Manual for Prediction of Blast and Fragment Loading for Structures; - DOE/EV 06194-5, and Explosives Safety Manual. Additionally, this action is needed because the present facility, the Building 217-F vault, does not comply with the above criteria for storage of munitions and explosives, and has been cited with seven occupational safety violations by DOE safety engineers. The most serious noted violations are due to the existing lack of appropriate storage space: munitions stacked directly against masonry walls, weapons stored in the same magazine as the munitions, inoperable ventilation system, inadequate air circulation, and the existence of electrical fans and switchgear within the magazine.

  3. LIQUID NATURAL GAS (LNG): AN ALTERNATIVE FUEL FROM LANDFILL GAS (LFG) AND WASTEWATER DIGESTER GAS

    SciTech Connect

    VANDOR,D.

    1999-03-01

    This Research and Development Subcontract sought to find economic, technical and policy links between methane recovery at landfill and wastewater treatment sites in New York and Maryland, and ways to use that methane as an alternative fuel--compressed natural gas (CNG) or liquid natural gas (LNG) -- in centrally fueled Alternative Fueled Vehicles (AFVs).

  4. 78 FR 73144 - Acceleration of Broadband Deployment by Improving Wireless Facilities Siting Policies

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-12-05

    ...In this document, the Commission seeks comment on potential measures to expedite the environmental and historic preservation review of new wireless facilities and on rules to implement statutory provisions governing State and local review of wireless siting proposals. By this action, the Commission seeks to promote the deployment of infrastructure that is necessary to provide the public with......

  5. 10. AERIAL VIEW OF CROSSCUT FACILITY SITE, SHOWING STEAM/DIESEL PLANT ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    10. AERIAL VIEW OF CROSSCUT FACILITY SITE, SHOWING STEAM/DIESEL PLANT BUILDING, RUNNING GENERALLY ACROSS PHOTO, AND INDIAN BEND POND IN UPPER RIGHT CORNER. November 7, 1955 - Crosscut Steam Plant, North side Salt River near Mill Avenue & Washington Street, Tempe, Maricopa County, AZ

  6. Nuclear facility decommissioning and site remedial actions: A selected bibliography: Volume 8

    SciTech Connect

    Owen, P.T.; Michelson, D.C.; Knox, N.P.

    1987-09-01

    The 553 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eighth in a series of reports. Foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of energy's remedial action program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Facilities Contaminated with Naturally Occurring Radionuclides, Uranium Mill Tailings Remedial Action Program, Uranium Mill Tailings Management, Technical Measurements Center, and General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. The appendix contains a list of frequently used acronyms and abbreviations.

  7. Social & Economic Issues in Siting a Hazardous Waste Facility: Ideas for Communities and Local Assessment Committees.

    ERIC Educational Resources Information Center

    Hurley, Mike

    This handbook was prepared for communities selected as potential sites for hazardous waste facilities, identifying issues which need to be addressed and suggesting specific and positive steps that communities can take to shape proposals to meet their concerns. Following an introduction, specific areas addressed include: community controls,…

  8. 40 CFR 63.7882 - What site remediation sources at my facility does this subpart affect?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 40 Protection of Environment 13 2011-07-01 2011-07-01 false What site remediation sources at my facility does this subpart affect? 63.7882 Section 63.7882 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) NATIONAL EMISSION STANDARDS FOR HAZARDOUS AIR POLLUTANTS FOR SOURCE CATEGORIES...

  9. 40 CFR 63.7882 - What site remediation sources at my facility does this subpart affect?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 40 Protection of Environment 14 2012-07-01 2011-07-01 true What site remediation sources at my facility does this subpart affect? 63.7882 Section 63.7882 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) NATIONAL EMISSION STANDARDS FOR HAZARDOUS AIR POLLUTANTS FOR SOURCE CATEGORIES (CONTINUED)...

  10. Nuclear facility decommissioning and site remedial actions. Volume 6. A selected bibliography

    SciTech Connect

    Owen, P.T.; Michelson, D.C.; Knox, N.P.

    1985-09-01

    This bibliography of 683 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the sixth in a series of annual reports prepared for the US Department of Energy's Remedial Action Programs. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's remedial action program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Facilities Contaminated with Natural Radioactivity; (5) Uranium Mill Tailings Remedial Action Program; (6) Grand Junction Remedial Action Program; (7) Uranium Mill Tailings Management; (8) Technical Measurements Center; and (9) General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 7 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate affiliation or by publication description.

  11. 10 CFR 26.715 - Recordkeeping requirements for collection sites, licensee testing facilities, and laboratories...

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 1 2012-01-01 2012-01-01 false Recordkeeping requirements for collection sites, licensee testing facilities, and laboratories certified by the Department of Health and Human Services. 26.715 Section 26.715 Energy NUCLEAR REGULATORY COMMISSION FITNESS FOR DUTY PROGRAMS Recordkeeping and Reporting Requirements § 26.715...

  12. 10 CFR 26.715 - Recordkeeping requirements for collection sites, licensee testing facilities, and laboratories...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... testing facilities, and laboratories certified by the Department of Health and Human Services. 26.715... laboratories certified by the Department of Health and Human Services. (a) Collection sites providing services... NRC or by any licensee or other entity for whom services are being provided. (b) Documentation...

  13. 10 CFR 26.715 - Recordkeeping requirements for collection sites, licensee testing facilities, and laboratories...

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... testing facilities, and laboratories certified by the Department of Health and Human Services. 26.715... laboratories certified by the Department of Health and Human Services. (a) Collection sites providing services... NRC or by any licensee or other entity for whom services are being provided. (b) Documentation...

  14. Lessons Learned from the On-Site Distillation of Used Solvents Generated by Health Care Facilities.

    ERIC Educational Resources Information Center

    Huang, Ching-San; Ciesla, John

    1992-01-01

    Discusses the sources of contaminants found in used solvents generated by the histopathological laboratories at health care facilities and the technical problems, corrective measures, and economic analysis associated with the on-site recycling and reusing of these solvents. An appendix contains an economic analysis for a used-solvent recycling…

  15. Hanford Site Near-Facility Environmental Monitoring Data Report for Calendar Year 2005

    SciTech Connect

    Perkins, Craig J.; Dorsey, Michael C.; Mckinney, Stephen M.; Mitchell, Ronald M.

    2006-09-28

    This Appendix contains brief discussions, specific sampling location information, and complete analytical data results for the various near-facility environmental monitoring efforts for 2005. Detailed discussions and summarized analytical results are provided in PNNL-15892, Hanford Site Environmental Report for Calendar Year 2005.

  16. 15 CFR 716.8 - On-site monitoring of Schedule 1 facilities.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 15 Commerce and Foreign Trade 2 2014-01-01 2014-01-01 false On-site monitoring of Schedule 1 facilities. 716.8 Section 716.8 Commerce and Foreign Trade Regulations Relating to Commerce and Foreign Trade (Continued) BUREAU OF INDUSTRY AND SECURITY, DEPARTMENT OF COMMERCE CHEMICAL WEAPONS CONVENTION...

  17. 15 CFR 716.8 - On-site monitoring of Schedule 1 facilities.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 15 Commerce and Foreign Trade 2 2010-01-01 2010-01-01 false On-site monitoring of Schedule 1 facilities. 716.8 Section 716.8 Commerce and Foreign Trade Regulations Relating to Commerce and Foreign Trade (Continued) BUREAU OF INDUSTRY AND SECURITY, DEPARTMENT OF COMMERCE CHEMICAL WEAPONS CONVENTION...

  18. Finding a Place for Energy: Siting Coal Conversion Facilities. Resource Publications in Geography.

    ERIC Educational Resources Information Center

    Calzonetti, Frank J.; Eckert, Mark S.

    The process of identifying, licensing, and developing energy facility sites for the conversion of coal into more useful forms is the focus of this book, intended for geography students, professors, and researchers. The use of domestic coal resources will ameliorate U.S. dependency on imported fuel. However, because coal is a bulky, dirty fuel…

  19. ENERGY FACILITY SITING PROCEDURES, CRITERIA, AND PUBLIC PARTICIPATION IN THE OHIO RIVER BASIN ENERGY STUDY REGION

    EPA Science Inventory

    The report was prepared in support of the Ohio River Basin Energy Study (ORBES), a multidisciplinary policy research program. Findings are presented on the adequacy of current review procedures, criteria, and public participation in energy facility siting (EFS) for nuclear and co...

  20. Descriptions of representative contaminated sites and facilities within the DOE complex

    SciTech Connect

    Short, S.M.; Buck, J.W.; Clark, L.L.; Fletcher, J.F.; Glantz, C.S.; Holdren, G.R.; Huesties, L.R.; Williams, M.D.; Oates, L.

    1994-10-01

    The U.S. Department of Energy (DOE) has initiated efforts to prepare a Programmatic Environmental Impact Statement (PEIS) that will analyze the existing environmental restoration and waste management program and evaluate alternatives for an integrated program. The alternatives being evaluated include (1) a {open_quotes}No Action{close_quotes} alternative as required by the National Environmental Policy Act (NEPA), (2) an Applicable, Relevant, and Appropriate Requirements (ARAR)-driven alternative, (3) a land-use-driven alternative, (4) a health-risk-driven alternative, and (5) a combination land-use and health-risk-driven alternative. The analytical approach being taken to evaluate each of these alternatives is to perform a remedial engineering analysis and human health and ecosystem effects analyses on every contaminated site and facility in the DOE complex. One of Pacific Northwest Laboratory`s (PNL) roles in this approach has been to compile the source term and environmental setting data needed to drive each of these analyses. To date, over 10,000 individual contaminated sites and facilities located throughout the DOE complex of installations have been identified and at least some minimal data compiled on each. The PEIS analyses have been appreciably simplified by categorizing all of these contaminated sites and facilities into six broad categories: (1) contaminated buildings, (2) contaminated soils, (3) solid waste sites (e.g., burial grounds), (4) liquid containment structures (e.g., tanks), (5) surface water sites, and (6) contaminated groundwater sites. A report containing a complete description of each of these thousands of contaminated sites and facilities would be tremendously large and unwildy, as would separate reports describing the application of the analytical methodologies to each.

  1. Resource Conservation and Recovery Act industrial site environmental restoration, site characterization plan: Area 6 Decontamination Pond Facility. Revision 1

    SciTech Connect

    1996-08-01

    This plan presents the strategy for the characterization of the Area 6 Decontamination Pond Facility at the Nevada Test Site which will be conducted for the US Department of Energy, Nevada Operations Office, Environmental Restoration Division. The objectives of the planned activities are to: obtain sufficient, sample analytical data from which further assessment, remediation, and/or closure strategies may be developed for the site; obtain sufficient, sample analytical data for management of investigation-derived waste. The scope of the characterization may include surface radiation survey(s), surface soil sampling, subsurface soil boring (i.e., drilling), and sampling of soil in and around the pond; in situ sampling of the soil within subsurface soil borings; and sample analysis for both site characterization and waste management purposes.

  2. Pollution Prevention Plan for the Y-12 Analytical Chemistry Organization Off-Site Union Valley Facility

    SciTech Connect

    Jackson, J. G.

    2010-03-01

    The Y-12 Analytical Chemistry Organization (ACO) Off-Site Union Valley Facility (Union Valley Facility) is managed by Babcock and Wilcox Technical Services Y-12, L.L.C. (B and W Y-12) through the Y-12 National Security Complex organization. Accordingly, the Y-12 Pollution Prevention Program encompasses the operations conducted at the Union Valley Facility. The Y-12 Program is designed to fully comply with state, federal and U.S. Department of Energy (DOE) requirements concerning waste minimization/pollution prevention as documented in the Y-12 Pollution Prevention Program Plan. The Program is formulated to reduce the generation and toxicity of all Y-12 wastes in all media, including those wastes generated by the Union Valley Facility operations. All regulatory and DOE requirements are met by the Y-12 Program Plan.

  3. THE OHIO RIVER BASIN ENERGY FACILITY SITING MODEL. VOLUME II: SITES AND ON-LINE DATES

    EPA Science Inventory

    The report was prepared as part of the Ohio River Basin Energy Study (ORBES), a multidisciplinary policy research program. The siting model developed for ORBES is specifically designed for regional policy analysis. The region includes 423 counties in an area that consists of all ...

  4. Effects of lng Mutations on LngA Expression, Processing, and CS21 Assembly in Enterotoxigenic Escherichia coli E9034A

    PubMed Central

    Saldaña-Ahuactzi, Zeus; Rodea, Gerardo E.; Cruz-Córdova, Ariadnna; Rodríguez-Ramírez, Viridiana; Espinosa-Mazariego, Karina; González-Montalvo, Martín A.; Ochoa, Sara A.; González-Pedrajo, Bertha; Eslava-Campos, Carlos A.; López-Villegas, Edgar O.; Hernández-Castro, Rigoberto; Arellano-Galindo, José; Patiño-López, Genaro; Xicohtencatl-Cortes, Juan

    2016-01-01

    Enterotoxigenic Escherichia coli (ETEC) is a major cause of morbidity in children under 5 years of age in low- and middle-income countries and a leading cause of traveler's diarrhea worldwide. The ability of ETEC to colonize the intestinal epithelium is mediated by fimbrial adhesins, such as CS21 (Longus). This adhesin is a type IVb pilus involved in adherence to intestinal cells in vitro and bacterial self-aggregation. Fourteen open reading frames have been proposed to be involved in CS21 assembly, hitherto only the lngA and lngB genes, coding for the major (LngA) and minor (LngB) structural subunit, have been characterized. In this study, we investigated the role of the LngA, LngB, LngC, LngD, LngH, and LngP proteins in the assembly of CS21 in ETEC strain E9034A. The deletion of the lngA, lngB, lngC, lngD, lngH, or lngP genes, abolished CS21 assembly in ETEC strain E9034A and the adherence to HT-29 cells was reduced 90%, compared to wild-type strain. Subcellular localization prediction of CS21 proteins was similar to other well-known type IV pili homologs. We showed that LngP is the prepilin peptidase of LngA, and that ETEC strain E9034A has another peptidase capable of processing LngA, although with less efficiency. Additionally, we present immuno-electron microscopy images to show that the LngB protein could be localized at the tip of CS21. In conclusion, our results demonstrate that the LngA, LngB, LngC, LngD, LngH, and LngP proteins are essential for CS21 assembly, as well as for bacterial aggregation and adherence to HT-29 cells. PMID:27536289

  5. Effects of lng Mutations on LngA Expression, Processing, and CS21 Assembly in Enterotoxigenic Escherichia coli E9034A.

    PubMed

    Saldaña-Ahuactzi, Zeus; Rodea, Gerardo E; Cruz-Córdova, Ariadnna; Rodríguez-Ramírez, Viridiana; Espinosa-Mazariego, Karina; González-Montalvo, Martín A; Ochoa, Sara A; González-Pedrajo, Bertha; Eslava-Campos, Carlos A; López-Villegas, Edgar O; Hernández-Castro, Rigoberto; Arellano-Galindo, José; Patiño-López, Genaro; Xicohtencatl-Cortes, Juan

    2016-01-01

    Enterotoxigenic Escherichia coli (ETEC) is a major cause of morbidity in children under 5 years of age in low- and middle-income countries and a leading cause of traveler's diarrhea worldwide. The ability of ETEC to colonize the intestinal epithelium is mediated by fimbrial adhesins, such as CS21 (Longus). This adhesin is a type IVb pilus involved in adherence to intestinal cells in vitro and bacterial self-aggregation. Fourteen open reading frames have been proposed to be involved in CS21 assembly, hitherto only the lngA and lngB genes, coding for the major (LngA) and minor (LngB) structural subunit, have been characterized. In this study, we investigated the role of the LngA, LngB, LngC, LngD, LngH, and LngP proteins in the assembly of CS21 in ETEC strain E9034A. The deletion of the lngA, lngB, lngC, lngD, lngH, or lngP genes, abolished CS21 assembly in ETEC strain E9034A and the adherence to HT-29 cells was reduced 90%, compared to wild-type strain. Subcellular localization prediction of CS21 proteins was similar to other well-known type IV pili homologs. We showed that LngP is the prepilin peptidase of LngA, and that ETEC strain E9034A has another peptidase capable of processing LngA, although with less efficiency. Additionally, we present immuno-electron microscopy images to show that the LngB protein could be localized at the tip of CS21. In conclusion, our results demonstrate that the LngA, LngB, LngC, LngD, LngH, and LngP proteins are essential for CS21 assembly, as well as for bacterial aggregation and adherence to HT-29 cells. PMID:27536289

  6. Hazard ranking system evaluation of CERCLA inactive waste sites at Hanford: Volume 2: Engineered-facility sites (HISS data base)

    SciTech Connect

    Jette, S.J.; Lamar, D.A.; McLaughlin, T.J.; Sherwood, D.R.; Van Houten, N.C.; Stenner, R.D.; Cramer, K.H.; Higley, K.A.

    1988-10-01

    The purpose of this report is to formally document the assessment activities at the US Department of Energy (DOE) Hanford Site. These activities were carried out pursuant to the DOE orders that address the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Program for the cleanup of inactive waste sites. The DOE orders incorporate the US Environmental Protection Agency methodology, which is based on the Superfund Amendments and Reauthorization Act of 1986. This methodology includes: PA/SI, remedial investigation/feasibility study, record of decision, design and implementation of remedial action, operation and monitoring, and verification monitoring. Volume 1 of this report discusses the CERCLA inactive waste-site evaluation process, assumptions, and results of the Hazard Ranking System methodology employed. Volume 2 presents the data on the individual CERCLA engineered-facility sites at Hanford, as contained in the Hanford Inactive Site Surveillance (HISS) Data Base. Volume 3 presents the data on the individual CERCLA unplanned-release sites at Hanford, as contained in the HISS Data Base. 13 refs.

  7. Exergy of LNG regasification - possible utilization method. Case study of LNG - ANG coupling

    NASA Astrophysics Data System (ADS)

    Roszak, E. A.; Chorowski, M.

    2014-01-01

    This article gives an overview on new exergy recovery methods for LNG. The concept is based on coupling the LNG regasification unit with the filling process of Adsorbed Natural Gas (ANG) tanks. The latent heat of the LNG vaporization is directly used for precooling the ANG adsorption bed. This reduces the back pressure from filling ANG tanks due to strong adsorption temperature dependency. This improves the economic attractiveness of ANG storage (no need for compressors, longer lifetime cycle of adsorbent). This case study presents the concept of LNG - ANG coupling. Presented results are based on experimental adsorption data. A brief exergy analysis of the process shows an advantage of this method over others. This LNG-ANG method is worth consideration as a cost optimizing solution, especially for periodically working regasification stations.

  8. Keys to modeling LNG spills on water.

    PubMed

    Hissong, D W

    2007-02-20

    Although no LNG ship has experienced a loss of containment in over 40 years of shipping, it is important for risk management planning to understand the predicted consequences of a spill. A key parameter in assessing the impact of an LNG spill is the pool size. LNG spills onto water generally result in larger pools than land spills because they are unconfined. Modeling of LNG spills onto water is much more difficult than for land spills because the phenomena are more complex and the experimental basis is more limited. The most prevalent practice in predicting pool sizes is to treat the release as instantaneous or constant-rate, and to calculate the pool size using an empirical evaporation or burn rate. The evaporation or burn rate is particularly difficult to estimate for LNG spills on water, because the available data are so limited, scattered, and difficult to extrapolate to the large releases of interest. A more effective modeling of possible spills of LNG onto water calculates, rather than estimating, the evaporation or burn rate. The keys to this approach are to: * Use rigorous multicomponent physical properties. * Use a time-varying analysis of spill and evaporation. * Use a material and energy balance approach. * Estimate the heat transfer from water to LNG in a way that reflects the turbulence. These keys are explained and demonstrated by predictions of a model that incorporates these features. The major challenges are describing the effects of the LNG-water turbulence and the heat transfer from the pool fire to the underlying LNG pool. The model includes a fundamentally based framework for these terms, and the current formulation is based on some of the largest tests to-date. The heat transfer coefficient between the water and LNG is obtained by applying a "turbulence factor" to the value from correlations for quiescent film and transition boiling. The turbulence factor is based on two of the largest unignited tests on water to-date. The heat transfer from

  9. 76 FR 73609 - Cameron LNG, LLC; Notice of Application

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-11-29

    ... operate a boil-off gas (BOG) liquefaction system at its LNG import terminal in Cameron Parish, Louisiana... terminal to liquefy BOG and return such gas in the form of LNG to its storage tanks. Cameron states...

  10. Annual report for RCRA groundwater monitoring projects at Hanford Site facilities for 1995

    SciTech Connect

    Hartman, M.J.

    1996-02-01

    This report presents the annual hydrogeologic evaluation of 19 Resource Conservation and Recovery Act of 1976 facilities and 1 nonhazardous waste facility at the US Department of Energy`s Hanford Site. Although most of the facilities no longer receive dangerous waste, a few facilities continue to receive dangerous waste constituents for treatment, storage, or disposal. The 19 Resource Conservation and Recovery Act facilities comprise 29 waste management units. Nine of the units are monitored under groundwater quality assessment status because of elevated levels of contamination indicator parameters. The impact of those units on groundwater quality, if any, is being investigated. If dangerous waste or waste constituents have entered groundwater, their concentration profiles, rate, and extent of migration are evaluated. Groundwater is monitored at the other 20 units to detect leakage, should it occur. This report provides an interpretation of groundwater data collected at the waste management units between October 1994 and September 1995. Groundwater quality is described for the entire Hanford Site. Widespread contaminants include nitrate, chromium, carbon tetrachloride, tritium, and other radionuclides.

  11. Facility Closure Report for T-Tunnel (U12t), Area 12, Nevada Test Site, Nevada

    SciTech Connect

    NSTec Environmental Restoration

    2008-08-01

    This Facility Closure Report (FCR) has been prepared to document the actions taken to permanently close the remaining accessible areas of U12t-Tunnel (T-Tunnel) in Area 12 of the Nevada Test Site (NTS). The closure of T-Tunnel was a prerequisite to transfer facility ownership from the Defense Threat Reduction Agency (DTRA) to the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Closure of the facility was accomplished with the cooperation and concurrence of both NNSA/NSO and the Nevada Division of Environmental Protection (NDEP). The purpose of this FCR is to document that the closure of T-Tunnel complied with the closure requirements specified in the Facility Closure Plan for N- and T-Tunnels Area 12, Nevada Test Site (Appendix D) and that the facility is ready for transfer to NNSA/NSO. The Facility Closure Plan (FCP) is provided in Appendix D. T-Tunnel is located approximately 42 miles north of Mercury in Area 12 of the NTS (Figure 1). Between 1970 and 1987, T-Tunnel was used for six Nuclear Weapons Effects Tests (NWETs). The tunnel was excavated horizontally into the volcanic tuffs of Rainier Mesa. The T-Tunnel complex consists of a main access drift with two NWET containment structures, a Gas Seal Plug (GSP), and a Gas Seal Door (GSD) (Figure 2). The T-Tunnel complex was mothballed in 1993 to preserve the tunnel for resumption of testing, should it happen in the future, to stop the discharge of tunnel effluent, and to prevent unauthorized access. This was accomplished by sealing the main drift GSD.

  12. Environmental assessment for the Explosive Waste Treatment Facility at Site 300, Lawrence Livermore National Laboratory

    SciTech Connect

    1995-11-01

    Lawrence Livermore National Laboratory proposes to build, permit, and operate the Explosive Waste Treatment Facility (EWTF) to treat explosive waste at LLNL`s Experimental Test Site, Site 300. It is also proposed to close the EWTF at the end of its useful life in accordance with the regulations. The facility would replace the existing Building 829 Open Burn Facility (B829) and would treat explosive waste generated at the LLNL Livermore Site and at Site 300 either by open burning or open detonation, depending on the type of waste. The alternatives addressed in the 1992 sitewide EIS/EIR are reexamined in this EA. These alternatives included: (1) the no-action alternative which would continue open burning operations at B829; (2) continuation of only open burning at a new facility (no open detonation); (3) termination of open burning operations with shipment of explosive waste offsite; and (4) the application of alternative treatment technologies. This EA examines the impact of construction, operation, and closure of the EWTF. Construction of the EWTF would result in the clearing of a small amount of previously disturbed ground. No adverse impact is expected to any state or federal special status plant or animal species (special status species are classified as threatened, endangered, or candidate species by either state or federal legislation). Operation of the EWTF is expected to result in a reduced threat to involved workers and the public because the proposed facility would relocate existing open burning operations to a more remote area and would incorporate design features to reduce the amount of potentially harmful emissions. No adverse impacts were identified for activities necessary to close the EWTF at the end of its useful life.

  13. Clay Cap Test Program for the Mixed Waste Management Facility closure at the Savannah River Site

    SciTech Connect

    Newell, J.W. , Inc., Charlotte, NC )

    1989-01-01

    A 58 acre low-level radioactive waste disposal facility at the Savannah River Site, a Department of Energy facility near Aiken, South Carolina, requires closure with a RCRA clay cap. A three-foot thick can requiring 300,000 cubic yards of local Tertiary Kaolin clay with an in-situ permeability of less than or equal to 1 {times} 10{sup -7} centimeters per second is to be constructed. The Clay Cap Test Program was conducted to evaluate the source, lab permeability, in-situ permeability, compaction characteristics, representative kaolin clays from the Aiken, SC vicinity. 11 refs., 8 figs., 1 tab.

  14. Plutonium production story at the Hanford site: processes and facilities history

    SciTech Connect

    Gerber, M.S., Westinghouse Hanford

    1996-06-20

    This document tells the history of the actual plutonium production process at the Hanford Site. It contains five major sections: Fuel Fabrication Processes, Irradiation of Nuclear Fuel, Spent Fuel Handling, Radiochemical Reprocessing of Irradiated Fuel, and Plutonium Finishing Operations. Within each section the story of the earliest operations is told, along with changes over time until the end of operations. Chemical and physical processes are described, along with the facilities where these processes were carried out. This document is a processes and facilities history. It does not deal with the waste products of plutonium production.

  15. Identifying Potential Areas for Siting Interim Nuclear Waste Facilities Using Map Algebra and Optimization Approaches

    SciTech Connect

    Omitaomu, Olufemi A; Liu, Cheng; Cetiner, Sacit M; Belles, Randy; Mays, Gary T; Tuttle, Mark A

    2013-01-01

    The renewed interest in siting new nuclear power plants in the United States has brought to the center stage, the need to site interim facilities for long-term management of spent nuclear fuel (SNF). In this paper, a two-stage approach for identifying potential areas for siting interim SNF facilities is presented. In the first stage, the land area is discretized into grids of uniform size (e.g., 100m x 100m grids). For the continental United States, this process resulted in a data matrix of about 700 million cells. Each cell of the matrix is then characterized as a binary decision variable to indicate whether an exclusion criterion is satisfied or not. A binary data matrix is created for each of the 25 siting criteria considered in this study. Using map algebra approach, cells that satisfy all criteria are clustered and regarded as potential siting areas. In the second stage, an optimization problem is formulated as a p-median problem on a rail network such that the sum of the shortest distance between nuclear power plants with SNF and the potential storage sites from the first stage is minimized. The implications of obtained results for energy policies are presented and discussed.

  16. Decontamination and decommissioning assessment for the Waste Incineration Facility (Building 232-Z) Hanford Site, [Hanford], WA

    SciTech Connect

    Dean, L.N.

    1994-02-01

    Building 232-Z is an element of the Plutonium Finishing Plant (PFP) located in the 200 West Area of the Hanford Site. From 1961 until 1972, plutonium-bearing combustible materials were incinerated in the building. Between 1972 and 1983, following shutdown of the incinerator, the facility was used for waste segregation activities. The facility was placed in retired inactive status in 1984 and classified as a Limited Control Facility pursuant to DOE Order 5480.5, Safety of Nuclear Facilities, and 6430.1A, General Design Criteria. The current plutonium inventory within the building is estimated to be approximately 848 grams, the majority of which is retained within the process hood ventilation system. As a contaminated retired facility, Building 232-Z is included in the DOE Surplus Facility Management Program. The objective of this Decontamination and Decommissioning (D&D) assessment is to remove Building 232-Z, thereby elmininating the radiological and environmental hazards associated with the plutonium inventory within the structure. The steps to accomplish the plan objectives are: (1) identifying the locations of the most significant amounts of plutonium, (2) removing residual plutonium, (3) removing and decontaminating remaining building equipment, (4) dismantling the remaining structure, and (5) closing out the project.

  17. DECOMMISSIONING OF THE NUCLEAR FACILITIES OF VKTA AT THE ROSSENDORF RESEARCH SITE

    SciTech Connect

    U. Helwig, W. Boessert

    2003-02-27

    VKTA decommissioned the old nuclear facilities of former GDR's (German Democratic Republic) Central Institute of Nuclear Research which was closed end of 1991. VKTA is responsible for fissile material and waste management, environmental and radiation protection and runs an accredited laboratory for environmental and radionuclide analytics. The Rossendorf research site is located east of the city of Dresden. The period from 1982 to about 1997 was mainly characterized by obtaining the necessary licenses for decommissioning and developing a new infrastructure (i.e. waste treatment facility, interim storages for fissile material and waste, clearance monitoring facility). The decommissioning work has been in progress since that time. The decommissioning projects are concentrated on three complexes: (1) the reactors and a fuel development and testing facility, (2) the radioisotope production facilities, and (3) the former liquid and solid waste storage facilities. The status of decommissioning progress and treatment of the residues will be demonstrated. Finally an outlook will be given on the future tasks of VKTA based on the ''Conception VKTA 2000 plus'', which was confirmed by the Saxonian government last year.

  18. Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 5

    SciTech Connect

    Owen, P.T.; Knox, N.P.; Chilton, B.D.; Baldauf, M.F.

    1984-09-01

    This bibliography of 756 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fifth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; (6) Uranium Mill Tailings Management; and (7) Technical Measurements Center. Chapter sections for chapters 1, 2, 4, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. The Appendix contains a list of frequently used acronyms.

  19. Hanford site near-facility environmental monitoring annual report, calendar year 1996

    SciTech Connect

    Perkins, C.J.

    1997-08-05

    This document summarizes the results of the near-facility environmental monitoring results for 1996 in the 100, 200/600, and 300/400 areas of the Hanford Site in south-central Washington State. Surveillance activities included sampling and analyses of ambient air, surface water, groundwater, soil, sediments, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. The monitoring implements applicable portions of DOE Orders 5400.1 (DOE 1988a), 5400.5 (DOE 1990), and 5820.2A (DOE 1988b); Washington Administrative Code (WAC) 246-247; and Title 40 Code of Federal Regulations (CFR) Part 61, Subpart H (EPA 1989). In addition, diffuse sources were monitored to determine compliance with federal, state, and/or local regulations. In general, although effects from nuclear facilities can still be observed on the Hanford Site and radiation levels were slightly elevated when compared to offsite locations, the differences are less than in previous years.

  20. Technical site characterization of the Mercer County Ash Disposal Facility: A case history

    SciTech Connect

    Allen, R.C.; Walton, C.G.; Zweig, L.T. )

    1993-03-01

    The Waste-Tech Services, Inc., Mercer County Ash Disposal Facility is a proposed Resource Conservation and Recovery Act (RCRA) permitted hazardous waste treatment, storage and disposal facility located SW of Princeton, Missouri. The facility is to accept, store, treat and landfill ash residues from RCRA-permitted hazardous waste incineration. The site was characterized for a permit application submitted to the Missouri Department of Natural Resource (MDNR). MDNR was involved during all site characterization stages, including MDNR review, input and oversight during the planning, field execution and report-preparation stages. Both parties agreed upon the needs required for characterizing the sites prior field work, and the MDNR ensured that scope of work stipulations were implemented in the field and reported. Three broad characterization categories were defined: (1) physical characteristics; (2) biological characteristics; and, (3) socio-economic considerations. Physical criteria include the geologic, geotechnical, hydrogeologic and hydrologic site conditions. Threatened and Endangered Species and Wetlands comprised the biologic issues. Socio-economics considered cultural resources, such as history and archeology, market proximity, capacity assurance and transportation.

  1. 78 FR 41047 - UGI LNG, Inc.; Notice of Application

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-09

    ... Energy Regulatory Commission UGI LNG, Inc.; Notice of Application On June 17, 2013, UGI LNG, Inc. (UGI... Ontelaunee Township, Berks County, Pennsylvania. As more fully described in the application, the new.... Questions regarding this application may be directed to Frank H. Markle, Counsel for UGI LNG, by calling...

  2. 75 FR 26744 - Cameron LNG, LLC; Notice of Application

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-05-12

    ... Energy Regulatory Commission Cameron LNG, LLC; Notice of Application May 5, 2010. On April 22, 2010, Cameron LNG, LLC filed with the Federal Energy Regulatory Commission (Commission) an application under... this application may be directed to William D. Rapp, Senior Regulatory Counsel at Cameron LNG, LLC,...

  3. 46 CFR 154.1854 - Methane (LNG) as fuel.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 46 Shipping 5 2014-10-01 2014-10-01 false Methane (LNG) as fuel. 154.1854 Section 154.1854... STANDARDS FOR SELF-PROPELLED VESSELS CARRYING BULK LIQUEFIED GASES Operations § 154.1854 Methane (LNG) as fuel. (a) If methane (LNG) vapors are used as fuel in the main propulsion system of a vessel,...

  4. 46 CFR 154.1854 - Methane (LNG) as fuel.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 46 Shipping 5 2011-10-01 2011-10-01 false Methane (LNG) as fuel. 154.1854 Section 154.1854... STANDARDS FOR SELF-PROPELLED VESSELS CARRYING BULK LIQUEFIED GASES Operations § 154.1854 Methane (LNG) as fuel. (a) If methane (LNG) vapors are used as fuel in the main propulsion system of a vessel,...

  5. 46 CFR 154.1854 - Methane (LNG) as fuel.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 46 Shipping 5 2012-10-01 2012-10-01 false Methane (LNG) as fuel. 154.1854 Section 154.1854... STANDARDS FOR SELF-PROPELLED VESSELS CARRYING BULK LIQUEFIED GASES Operations § 154.1854 Methane (LNG) as fuel. (a) If methane (LNG) vapors are used as fuel in the main propulsion system of a vessel,...

  6. 46 CFR 154.1854 - Methane (LNG) as fuel.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 46 Shipping 5 2010-10-01 2010-10-01 false Methane (LNG) as fuel. 154.1854 Section 154.1854... STANDARDS FOR SELF-PROPELLED VESSELS CARRYING BULK LIQUEFIED GASES Operations § 154.1854 Methane (LNG) as fuel. (a) If methane (LNG) vapors are used as fuel in the main propulsion system of a vessel,...

  7. 46 CFR 154.1854 - Methane (LNG) as fuel.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 46 Shipping 5 2013-10-01 2013-10-01 false Methane (LNG) as fuel. 154.1854 Section 154.1854... STANDARDS FOR SELF-PROPELLED VESSELS CARRYING BULK LIQUEFIED GASES Operations § 154.1854 Methane (LNG) as fuel. (a) If methane (LNG) vapors are used as fuel in the main propulsion system of a vessel,...

  8. Assessment, approval, design and construction of a facility on a Superfund site in 36 months

    SciTech Connect

    Drag, D.J.; Webb, C.K.; Luenenborg, G.W.

    1996-11-01

    The Union Pacific Resources Corporation (UPRC) owned and operated a 600-acre crude oil production field in Wilmington, California. UPRC granted a lease to the TCL Corporation in 1951 for the disposal of oil and gas drilling field wastes. In the 1950s and 1960s, waste materials consisting of oil-free rotary mud, as well as rotary mud containing oil and crude oil tank bottoms were accepted at the site. Site testing and record investigations have shown that some other wastes, inconsistent with those permitted by the agreement between UPRC and TCL, were also disposed of at the site. Soil samples collected from the site in 1981 showed moderately high levels of metals in the soils at the site. In 1983, the site was included on the California State Superfund list of hazardous waste contaminated sites. In 1988, UPRC signed a Consent order Agreement with the Department of Toxic Substance Control (DTSC) whereby UPRC agreed to investigate a 31-acre area of the Study Area and develop a Remedial Action Plan (RAP) with DTSC oversight. The Port of Long Beach (POLB) is assuming the responsibility for implementing subsequent investigative and remedial activities at the portions of the site which they have since purchased from UPRC. The overall project objective was to investigate a 31-acre parcel within the Study Area (TCL site), develop a RAP, remediate the oil sump soils, and develop the parcel as an automobile distribution facility to be used by Toyota Motor Sales (TMS).

  9. LNG systems for natural gas propelled ships

    NASA Astrophysics Data System (ADS)

    Chorowski, M.; Duda, P.; Polinski, J.; Skrzypacz, J.

    2015-12-01

    In order to reduce the atmospheric pollution generated by ships, the International Marine Organization has established Emission Controlled Areas. In these areas, nitrogen oxides, sulphur oxides and particulates emission is strongly controlled. From the beginning of 2015, the ECA covers waters 200 nautical miles from the coast of the US and Canada, the US Caribbean Sea area, the Baltic Sea, the North Sea and the English Channel. From the beginning of 2020, strong emission restrictions will also be in force outside the ECA. This requires newly constructed ships to be either equipped with exhaust gas cleaning devices or propelled with emission free fuels. In comparison to low sulphur Marine Diesel and Marine Gas Oil, LNG is a competitive fuel, both from a technical and economical point of view. LNG can be stored in vacuum insulated tanks fulfilling the difficult requirements of marine regulations. LNG must be vaporized and pressurized to the pressure which is compatible with the engine requirements (usually a few bar). The boil-off must be controlled to avoid the occasional gas release to the atmosphere. This paper presents an LNG system designed and commissioned for a Baltic Sea ferry. The specific technical features and exploitation parameters of the system will be presented. The impact of strict marine regulations on the system's thermo-mechanical construction and its performance will be discussed. The review of possible flow-schemes of LNG marine systems will be presented with respect to the system's cost, maintenance, and reliability.

  10. Federal Facility Compliance Act: Conceptual Site Treatment Plan for Lawrence Livermore National Laboratory, Livermore, California

    SciTech Connect

    Not Available

    1993-10-01

    The Department of Energy (DOE) is required by section 3021(b) of the Resource Conservation and Recovery Act (RCRA), as amended by the Federal Facility Compliance Act (the Act), to prepare plans describing the development of treatment capacities and technologies for treating mixed waste. The Act requires site treatment plans (STPs or plans) to be developed for each site at which DOE generates or stores mixed waste and submitted to the State or EPA for approval, approval with modification, or disapproval. The Lawrence Livermore National Laboratory (LLNL) Conceptual Site Treatment Plan (CSTP) is the preliminary version of the plan required by the Act and is being provided to California, the US Environmental Protection Agency (EPA), and others for review. A list of the other DOE sites preparing CSTPs is included in Appendix 1.1 of this document. Please note that Appendix 1.1 appears as Appendix A, pages A-1 and A-2 in this document.

  11. Savannah River Site RCRA Facility Investigation plan: Road A Chemical Basin

    SciTech Connect

    Not Available

    1989-06-01

    The nature of wastes disposed of at the Road A Chemical Basin (RACB) is such that some degree of soil contamination is probable. Lead has also been detected in site monitoring wells at concentrations above SRS background levels. A RCRA Facility Investigation (RFI) is proposed for the RACB and will include a ground penetrating radar (GPR) survey, collection and chemical and radiological analyses of soil cores, installation of groundwater monitoring wells, collection and chemical and radiological analyses of groundwater samples, and collection of chemical and radiological analyses of surface water and sediment samples. Upon completion of the proposed RFI field work and chemical and radiological analyses, and RFI report should be prepared to present conclusions on the nature and extent of contamination at the site, and to make recommendations for site remediation. If contamination is detected at concentrations above SRS background levels, a receptor analysis should be done to evaluate potential impacts of site contamination on nearby populations.

  12. Hanford Site near-facility environmental monitoring annual report, calendar year 1997

    SciTech Connect

    Perkins, C.J.

    1998-07-28

    Near-facility environmental monitoring provides a means to measure the impacts of operations, waste management, and remediation activities on the environment adjacent to facilities and ensure compliance with local, state, and federal environmental regulations. Specifically, near-facility environmental monitoring monitors new and existing sites, processes, and facilities for potential impacts and releases; fugitive emissions and diffuse sources associated with contaminated areas, facilities (both active and those undergoing surveillance and maintenance), and environmental restoration activities. External radiation, ambient air particulates, ground and surface water, soil, sediment, and biota (plants and animals) are sampled or monitored. Parameters include, as appropriate, radionuclides; radiation fields; chemical or physical constituents, such as nitrates; pH; and water temperature. All ambient air results were below the US Department of Energy (DOE) Derived Concentration Guides (DCGs). Groundwater concentrations at the two wells at the 107-N Facility were below both the DOE DCG and US Environmental Protection Agency Interim Drinking Water Standards for gamma emitting radionuclides. Soil and vegetation results were generally within historic ranges and mostly below the Accessible Soil Concentration limits (included in HNF-PRO-454, Inactive Waste Sites) with the exception of one soil sampling location at 1 00 N Area. External radiation fields continued an overall downward trend. Surface water disposal unit samples (water, sediment, and aquatic vegetation) showed radionuclide concentrations below their respective DCG and Accessible Soil Concentration limits. The 100 N Area Columbia river shoreline springs results were below DCGs with the exception of one Sr concentration. More than 4,600 ha (11,300 acres) of radiologically controlled areas were surveyed in 1997, approximately the same as in 1996.

  13. Safety implications of a large LNG tanker spill over water.

    SciTech Connect

    Hightower, Marion Michael; Gritzo, Louis Alan; Luketa-Hanlin, Anay Josephine

    2005-04-01

    The increasing demand for natural gas in the United States could significantly increase the number and frequency of marine LNG (liquefied natural gas) imports. Although many studies have been conducted to assess the consequences and risks of potential LNG spills, the increasing importance of LNG imports suggests that consistent methods and approaches be identified and implemented to help ensure protection of public safety and property from a potential LNG spill. For that reason the U.S. Department of Energy (DOE), Office of Fossil Energy, requested that Sandia National Laboratories (Sandia) develop guidance on a risk-based analysis approach to assess and quantify potential threats to an LNG ship, the potential hazards and consequences of a large spill from an LNG ship, and review prevention and mitigation strategies that could be implemented to reduce both the potential and the risks of an LNG spill over water. Specifically, DOE requested: (1) An in-depth literature search of the experimental and technical studies associated with evaluating the safety and hazards of an LNG spill from an LNG ship; (2) A detailed review of four recent spill modeling studies related to the safety implications of a large-scale LNG spill over water; (3) Evaluation of the potential for breaching an LNG ship cargo tank, both accidentally and intentionally, identification of the potential for such breaches and the potential size of an LNG spill for each breach scenario, and an assessment of the potential range of hazards involved in an LNG spill; (4) Development of guidance on the use of modern, performance-based, risk management approaches to analyze and manage the threats, hazards, and consequences of an LNG spill over water to reduce the overall risks of an LNG spill to levels that are protective of public safety and property.

  14. Facility preparations for the initial International Atomic Energy Agency Inpsection of Hanford Site excess material

    SciTech Connect

    Johnson, W.C.; Scott, D.D.; Bartlett, W.D.; Delegard, C.H.; McRae, L.P.; Six, D.E.; Amacker, O.P.

    1995-09-01

    In September 1993 President Clinton offered to place excess US nuclear materials under IAEA safeguards. In January 1994, the Hanford Site was identified as the second site in the US to be prepared for placement on the eligibility list for LAEA safeguards selection. Planning and preparation started at Hanford in February 1994. The PFP mission is to provide safe storage of Category 1 and 2 special nuclear material (SNM) and laboratory support to the Hanford Site. The mission includes the stabilizing and packaging of SNM for temporary storage sufficient to support the deactivation and cleanup function of the facility. The storage of Category 1 and 2 SNM at this facility indirectly supports national security interests, and safe storage is accomplished in a manner that ensures the health and safety of the public and employees are not compromised. The PFP is located in the approximate center of the Hanford Site inside the 200 West Area. The PFP is within a designated protected area (PA) and is located approximately 10.5 km from the Columbia River and 34 km northwest of the Richland city limits. The, Hanford Site is located in Southeastern Washington and has been associated with plutonium production since the mid 1940s. Excess plutonium oxide has been placed under IAEA safeguards in a phased approach at the PFP`s Plutonium Storage Vault. This paper is an overview and summary of the many tasks required to meet IAEA safeguards requirements.

  15. Formal analysis of values under conditions of uncertainty applied to the siting of hazardous waste facilities

    SciTech Connect

    Hatfield, T.H.

    1985-01-01

    A major impediment to the siting of hazardous waste facilities is the reaction of the public to such a locally unwanted land use. The siting controversy is exacerbated by uncertainty with information available to evaluate candidate sites. In response to this problem, a normal analysis of values has been developed that treats the siting of hazardous waste facilities as a multiattribute group decision under conditions of uncertainty. The design phase of the formal analysis includes the selection of participants, the structuring of objectives and criteria, and the verification of independence conditions that determine the aggregation rules for the evaluation criteria. The evaluation phase of the formal analysis utilizes a questionnaire to assess the following attitudes of each participant for each criterion: the relative weighting and ranking of each criterion; the participant's values under conditions of certainty for the various levels of a criterion, given as a measurable value function v(x); values under conditions of uncertainty, given as a Von Neumann-Morgenstern utility function, u(x); and risk attitudes towards the uncertain performance of a site, given as the relative risk premium or RRP, where RRP =u(x) - v(x). The aggregation of individual evaluations is also a part of the evaluation phase.

  16. Nuclear facility decommissioning and site remedial actions. Volume 1. A selected bibliography

    SciTech Connect

    Faust, R.A.; Fore, C.S.; Knox, N.P.

    1980-09-01

    This bibliography of 633 references represents the first in a series to be produced by the Remedial Actions Program Information Center (RAPIC) containing scientific, technical, economic, and regulatory information concerning the decommissioning of nuclear facilities. Major chapters selected for this bibliography are Facility Decommissioning, Uranium Mill Tailings Cleanup, Contaminated Site Restoration, and Criteria and Standards. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. When the author is not given, the corporate affiliation appears first. If these two levels of authorship are not given, the title of the document is used as the identifying level. Indexes are provided for (1) author(s), (2) keywords, (3) title, (4) technology development, and (5) publication description. An appendix of 123 entries lists recently acquired references relevant to decommissioning of nuclear facilities. These references are also arranged according to one of the four subject categories and followed by author, title, and publication description indexes. The bibliography was compiled from a specialized data base established and maintained by RAPIC to provide information support for the Department of Energy's Remedial Actions Program, under the cosponsorship of its three major components: Surplus Facilities Management Program, Uranium Mill Tailings Remedial Actions Program, and Formerly Utilized Sites Remedial Actions Program. RAPIC is part of the Ecological Sciences Information Center within the Information Center Complex at Oak Ridge National Laboratory.

  17. Surficial geology and performance assessment for a Radioactive Waste Management Facility at the Nevada Test Site

    SciTech Connect

    Snyder, K.E.; Gustafson, D.L.; Huckins-Gang, H.E.; Miller, J.J.; Rawlinson, S.E.

    1995-02-01

    At the Nevada Test Site, one potentially disruptive scenario being evaluated for the Greater Confinement Disposal (GCD) Facility Performance Assessment is deep post-closure erosion that would expose buried radioactive waste to the accessible environment. The GCD Facility located at the Area 5 Radioactive Waste Management Site (RWMS) lies at the juncture of three alluvial fan systems. Geomorphic surface mapping in northern Frenchman Flat indicates that reaches of these fans where the RWMS is now located have been constructional since at least the middle Quaternary. Mapping indicates a regular sequence of prograding fans with entrenchment of the older fan surfaces near the mountain fronts and construction of progressively younger inset fans farther from the mountain fronts. At the facility, the oldest fan surfaces are of late Pleistocene and Holocene age. More recent geomorphic activity has been limited to erosion and deposition along small channels. Trench and pit wall mapping found maximum incision in the vicinity of the RWMS to be less than 1.5 m. Based on collected data, natural geomorphic processes are unlikely to result in erosion to a depth of more than approximately 2 m at the facility within the 10,000-year regulatory period.

  18. Blanketing effect of expansion foam on liquefied natural gas (LNG) spillage pool.

    PubMed

    Zhang, Bin; Liu, Yi; Olewski, Tomasz; Vechot, Luc; Mannan, M Sam

    2014-09-15

    With increasing consumption of natural gas, the safety of liquefied natural gas (LNG) utilization has become an issue that requires a comprehensive study on the risk of LNG spillage in facilities with mitigation measures. The immediate hazard associated with an LNG spill is the vapor hazard, i.e., a flammable vapor cloud at the ground level, due to rapid vaporization and dense gas behavior. It was believed that high expansion foam mitigated LNG vapor hazard through warming effect (raising vapor buoyancy), but the boil-off effect increased vaporization rate due to the heat from water drainage of foam. This work reveals the existence of blocking effect (blocking convection and radiation to the pool) to reduce vaporization rate. The blanketing effect on source term (vaporization rate) is a combination of boil-off and blocking effect, which was quantitatively studied through seven tests conducted in a wind tunnel with liquid nitrogen. Since the blocking effect reduces more heat to the pool than the boil-off effect adds, the blanketing effect contributes to the net reduction of heat convection and radiation to the pool by 70%. Water drainage rate of high expansion foam is essential to determine the effectiveness of blanketing effect, since water provides the boil-off effect. PMID:25194555

  19. Analysis of 2011 Meteorological Data from the Knolls Atomic Power Laboratory and Kesselring Site Operations Facilities

    SciTech Connect

    Aluzzi, F J

    2012-02-27

    Both the Knolls Atomic Power Laboratory (KAPL) in Schenectady, NY and the Kesselring Site Operations (KSO) facility near Ballston Spa, NY are required to estimate the effects of hypothetical emissions of radiological material from their respective facilities by the US Environmental Protection Agency (EPA), which regulates these facilities. An atmospheric dispersion model known as CAP88, which was developed and approved by the EPA for such purposes, is used by KAPL and KSO to meet this requirement. CAP88 calculations over a given time period are based on statistical data on the meteorological conditions for that period. Both KAPL and KSO have on-site meteorological towers which take atmospheric measurements at a frequency ideal for EPA regulatory model input. However, an independent analysis and processing of the meteorological data from each tower is required to derive a data set appropriate for use in the CAP88 model. The National Atmospheric Release Advisory Center (NARAC) was contracted by KAPL to process the on-site data for the calendar year 2011. The purpose of this document is to: (1) summarize the procedures used in the preparation/analysis of the 2011 meteorological data; and (2) document adherence of these procedures to the guidance set forth in 'Meteorological Monitoring Guidance for Regulatory Modeling Applications', EPA document - EPA-454/R-99-005 (EPA-454). This document outlines the steps in analyzing and processing meteorological data from the Knolls Atomic Power Laboratory and Kesselring Site Operations facilities into a format that is compatible with the steady state dispersion model CAP88. This process is based on guidance from the EPA regarding the preparation of meteorological data for use in regulatory dispersion models. The analysis steps outlined in this document can be easily adapted to process data sets covering time period other than one year. The procedures will need to be modified should the guidance in EPA-454 be updated or revised.

  20. Shrapnel protection testing in support of the proposed Site 300 Contained Firing Facility

    SciTech Connect

    Pastrnak, J W; Baker, C F; Simmons, L F

    1992-08-04

    In preparation for the planned Contained Firing Facility at LLNL's Site 300, various multi-layered shrapnel protection schemes were investigated with the intent of minimizing the amount of material used in the shielding. As a result of testing, it was found that two pieces of 1-in.-thick mild steel plate provide adequate general-purpose protection from shrapnel generated by normal hydrodynamic and cylinder shots at Bunker 801. 8 refs.

  1. Second performance assessment iteration of the Greater Confinement Disposal facility at the Nevada Test Site

    SciTech Connect

    Baer, T.A.; Emery, J.N.; Price, L.L.; Olague, N.E.

    1994-04-01

    The Greater Confinement Disposal (GCD) facility was established in Area 5 at the Nevada Test Site for containment of waste inappropriate for shallow land burial. Some transuranic (TRU) waste has been disposed of at the GCD facility, and compliance of this disposal system with EPA regulation 40 CFR 191 must be evaluated. We have adopted an iterative approach in which performance assessment results guide site data collection, which in turn influences the parameters and models used in performance assessment. The first iteration was based upon readily available data, and indicated that the GCD facility would likely comply with 40 CFR 191 and that the downward flux of water through the vadose zone (recharge) had a major influence on the results. Very large recharge rates, such as might occur under a cooler, wetter climate, could result in noncompliance. A project was initiated to study recharge in Area 5 by use of three environmental tracers. The recharge rate is so small that the nearest groundwater aquifer will not be contaminated in less than 10,000 years. Thus upward liquid diffusion of radionuclides remained as the sole release pathway. This second assessment iteration refined the upward pathway models and updated the parameter distributions based upon new site information. A new plant uptake model was introduced to the upward diffusion pathway; adsorption and erosion were also incorporated into the model. Several modifications were also made to the gas phase radon transport model. Plutonium solubility and sorption coefficient distributions were changed based upon new information, and on-site measurements were used to update the moisture content distributions. The results of the assessment using these models indicate that the GCD facility is likely to comply with all sections of 40 CFR 191 under undisturbed conditions.

  2. Characterization and reclamation assessment for the central shops diesel storage facility at Savannah River Site

    SciTech Connect

    Fliermans, C.B.; Hazen, T.C.; Bledsoe, H.W.

    1994-12-31

    The contamination of subsurface terrestrial environments by organic contaminants is a global phenomenon. The remediation of such environments requires innovative assessment techniques and strategies for successful cleanups. Using innovative approaches, the central Shops Diesel Storage Facility at the Savannah River Site (SRS) was characterized to determine the extent of subsurface diesel fuel contamination. Effective bioremediation techniques for cleaning up of the contaminant plume were established.

  3. Nuclear facility decommissioning and site remedial actions: A selected bibliography, volume 9

    SciTech Connect

    Owen, P.T.; Knox, N.P.; Michelson, D.C.; Turmer, G.S.

    1988-09-01

    The 604 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the ninth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's remedial action programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Subsections for sections 1, 2, 5, and 6 include: Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at (615) 576-0568 or FTS 626-0568.

  4. Site characterization report for the Old Hydrofracture Facility at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1995-01-01

    Several Old Hydrofracture Facility (OHF) structures (i.e., Building 7852, the bulk storage bins, the pump house, water tank T-5, and pump P-3) are surplus facilities at Oak Ridge National Laboratory (ORNL) slated for decontamination and decommissioning (D and D). OHF was constructed in 1963 to allow experimentation and operations with an integrated solids storage, handling, mixing, and grout injection facility. It was shut down in 1980 and transferred to ORNL`s Surveillance and Maintenance Program. The hydrofracture process was a unique disposal method that involved injecting waste materials mixed with grout and additives under pumping pressures of 2,000 psi or greater into a deep, low-permeability shale formation. The injected slurry spread along fractures and bedding planes for hundreds of feet from the injection points, forming thin grout sheets (often less than 1/8 in. thick). The grout ostensibly immobilized and solidified the liquid wastes. Site characterization activities were conducted in the winter and spring of 1994 to collect information necessary to plan the D and D of OHF structures. This site characterization report documents the results of the investigation of OHF D and D structures, presenting data from the field investigation and laboratory analyses in the form of a site description, as-built drawings, summary tables of radiological and chemical contaminant concentrations, and a waste volume estimate. 25 refs., 54 figs., 17 tabs.

  5. Site study plan for Exploratory shaft facilities design foundation boreholes (shaft surface facility foundation borings), Deaf Smith County Site, Texas: Surface-based geotechnical field program: Preliminary draft

    SciTech Connect

    Not Available

    1987-12-01

    This site study plan describes the Exploratory Shaft Facilities (ESF) Design Foundation Boreholes field activities to be conducted during early stages of Site Characterization at the Deaf Smith County, Texas, site. The field program has been designed to provide data useful in addressing information/data needs resulting from federal/state/local regulations, and repository program requirements. Approximately 50 foundation boreholes will be drilled within the ESP location to provide data necessary for design of the ESF and to satisfy applicable shaft permitting requirements. Soils and subsurface rock will be sampled as the foundation boreholes are advanced. Soil samples or rock core will be taken through the Blackwater Draw and Ogallala Formations and the Dockum Group. Hydrologic testing will be performed in boreholes that penetrates the water table. In-situ elastic properties will be determined from both the soil strata and rock units along the length of the boreholes. Field methods/tests are chosen that provide the best or only means of obtaining the required data. The Salt Repository Project (SRP) Networks specify the schedule under which the program will operate. Drilling will not begin until after site ground water baseline conditions have been established. The Technical Field Services Contractor is responsible for conducting the field program of drilling and testing. Samples and data will be handled and reported in accordance with established SRP procedures. A quality assurance program will be utilized to assure that activities affecting quality are performed correctly and that the appropriate documentation is maintained. 25 refs., 10 figs., 6 tabs.

  6. Critical Protection Item classification for a waste processing facility at Savannah River Site

    SciTech Connect

    Ades, M.J.; Garrett, R.J.

    1993-10-01

    This paper describes the methodology for Critical Protection Item (CPI) classification and its application to the Structures, Systems and Components (SSC) of a waste processing facility at the Savannah River Site (SRS). The WSRC methodology for CPI classification includes the evaluation of the radiological and non-radiological consequences resulting from postulated accidents at the waste processing facility and comparison of these consequences with allowable limits. The types of accidents considered include explosions and fire in the facility and postulated accidents due to natural phenomena, including earthquakes, tornadoes, and high velocity straight winds. The radiological analysis results indicate that CPIs are not required at the waste processing facility to mitigate the consequences of radiological release. The non-radiological analysis, however, shows that the Waste Storage Tank (WST) and the dike spill containment structures around the formic acid tanks in the cold chemical feed area and waste treatment area of the facility should be identified as CPIs. Accident mitigation options are provided and discussed.

  7. Radiological safety evaluation for a Waste Transfer Facility at Savannah River Site

    SciTech Connect

    Ades, M.J.

    1993-10-01

    This paper provides a review of the radiological safety evaluation performed for a Waste Transfer Facility (WTF) located at the Savannah River Site (SRS). This facility transfers liquid radioactive waste between various waste processing facilities and waste storage facilities. The WTF includes functional components such as the diversion box and the pump pits, waste transfer lines, and the outside yard service piping and electrical services. The WSRC methodology is used to evaluate the consequences of postulated accidents that result in the release of radioactive material. Such accidents include transfer line breaks, underground liquid pathway release, fire in pump tank cells and HEPA filters, accidents due to natural phenomena, and externally induced events. Chemical hazards accidents are not considered. The analysis results indicate that the calculated mean onsite and offsite radiological consequences are bounded by the corresponding WSRC dose limits for each accident considered. Moreover, the results show that the maximum onsite and offsite doses calculated for the WTF are lower than the maximum doses determined for the whole radioactive waste facility where the WTF is located.

  8. Ecological studies related to construction of the Defense Waste Processing Facility on the Savannah River Site

    SciTech Connect

    Pechmann, J.H.K.; Scott, D.E.; McGregor, J.H.; Estes, R.A.; Chazal, A.C.

    1993-02-01

    The Defense Waste Processing Facility (DWPF) was built on the Savannah River Site (SRS) during the mid-1980's. The Savannah River Ecology Laboratory (SREL) has completed 12 years of ecological studies related to the construction of the DWPF complex. Prior to construction, the 600-acre site (S-Area) contained a Carolina bay and the headwaters of a stream. Research conducted by the SREL has focused primarily on four questions related to these wetlands: (1) Prior to construction, what fauna and flora were present at the DWPF site and at similar, yet undisturbed, alternative sites (2) By comparing the Carolina bay at the DWPF site (Sun Bay) with an undisturbed control Carolina bay (Rainbow Bay), what effect is construction having on the organisms that inhabited the DWPF site (3) By comparing control streams with streams on the periphery of the DWPF site, what effect is construction having on the peripheral streams (4) How effective have efforts been to lessen the impacts of construction, both with respect to erosion control measures and the construction of refuge ponds'' as alternative breeding sites for amphibians that formerly bred at Sun Bay Through the long-term census-taking of biota at the DWPF site and Rainbow Bay, SREL has begun to evaluate the impact of construction on the biota and the effectiveness of mitigation efforts. Similarly, the effects of erosion from the DWPF site on the water quality of S-Area peripheral streams are being assessed. This research provides supporting data relevant to the National Environmental Policy Act (NEPA) of 1969, the Endangered Species Act of 1973, Executive Orders 11988 (Floodplain Management) and 11990 (Protection of Wetlands), and United States Department of Energy (DOE) Guidelines for Compliance with Floodplain/Wetland Environmental Review Requirements (10CFR1022).

  9. Analysis of 2014 Meteorological Data from the Knolls Atomic Power Laboratory and Kesselring Site Operations Facilities

    SciTech Connect

    Aluzzi, Fernando J.

    2015-02-25

    Both the Knolls Atomic Power Laboratory (KAPL) in Schenectady, N.Y. and the Kesselring Site Operations (KSO) facility near Ballston Spa, N.Y. are required to estimate the effects of hypothetical emissions of radiological material from their respective facilities by the U.S. Environmental Protection Agency (EPA), which regulates both sites. An atmospheric dispersion model known as CAP88, which was developed and approved by the EPA for such purposes, is used by KAPL and KSO to meet this requirement. CAP88 calculations over a given time period are based on statistical data on the meteorological conditions for that period. Both KAPL and KSO have on-site meteorological towers which take atmospheric measurements at a frequency ideal for EPA regulatory model input. However, an independent analysis and processing of the meteorological data from each tower is required to derive a data set appropriate for use in the CAP88 model. The National Atmospheric Release Advisory Center (NARAC) was contracted by KAPL to process the on-site data for the calendar year 2014.

  10. On-site waste treatment at a fire-damaged electroplating facility

    SciTech Connect

    Vu, H.Q.; Ramsey, W.H.

    1994-12-31

    The Region 7 EPA Emergency Planning and Response Branch conducted a CERCLA removal action at a plating facility in Kansas City, Kansas. A fire at the facility had destroyed three businesses, which were housed in the same building. The local fire department responded and extinguished the blaze, spraying an estimated 280,000 gallons of water into the building. Over two-thirds of the building collapsed and other portions suffered extensive structural damage. Approximately 314 containers of plating chemicals ranging in size from 5-gallon buckets to 1,000-gallon vats were found at the site (2). Most of the containers had either ruptured due to the tremendous heat or had overflowed from the water used to put out the fire. The primary contaminants at the site were corrosive inorganics, heavy metals including chromium, copper, lead, nickel, and cyanide compounds. Hazardous substances released from the containers mingled with the building debris and presented cleanup workers with a complicated mixture of physical and chemical hazards. Subsequent heavy rainfall promoted off-site migration of contaminated free liquids in the areas where the roof had collapsed. On-site treatment of wastewaters contaminated with metals was performed after the damaged structure had been stabilized and wastes characterized. Prior to the treatment, a bench-scale study was conducted to determine feasible techniques for treatment of contaminated wastewater. Treatment techniques evaluated during the study included hexavalent-chromium reduction, and hydroxide precipitation and neutralization.

  11. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text

    SciTech Connect

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

  12. The Methodology of Interactive Parametric Modelling of Construction Site Facilities in BIM Environment

    NASA Astrophysics Data System (ADS)

    Kozlovská, Mária; Čabala, Jozef; Struková, Zuzana

    2014-11-01

    Information technology is becoming a strong tool in different industries, including construction. The recent trend of buildings designing is leading up to creation of the most comprehensive virtual building model (Building Information Model) in order to solve all the problems relating to the project as early as in the designing phase. Building information modelling is a new way of approaching to the design of building projects documentation. Currently, the building site layout as a part of the building design documents has a very little support in the BIM environment. Recently, the research of designing the construction process conditions has centred on improvement of general practice in planning and on new approaches to construction site layout planning. The state of art in field of designing the construction process conditions indicated an unexplored problem related to connection of knowledge system with construction site facilities (CSF) layout through interactive modelling. The goal of the paper is to present the methodology for execution of 3D construction site facility allocation model (3D CSF-IAM), based on principles of parametric and interactive modelling.

  13. CPP-603 Underwater Fuel Storage Facility Site Integrated Stabilization Management Plan (SISMP), Volume I

    SciTech Connect

    Denney, R.D.

    1995-10-01

    The CPP-603 Underwater Fuel Storage Facility (UFSF) Site Integrated Stabilization Management Plan (SISMP) has been constructed to describe the activities required for the relocation of spent nuclear fuel (SNF) from the CPP-603 facility. These activities are the only Idaho National Engineering Laboratory (INEL) actions identified in the Implementation Plan developed to meet the requirements of the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1 to the Secretary of Energy regarding an improved schedule for remediation in the Defense Nuclear Facilities Complex. As described in the DNFSB Recommendation 94-1 Implementation Plan, issued February 28, 1995, an INEL Spent Nuclear Fuel Management Plan is currently under development to direct the placement of SNF currently in existing INEL facilities into interim storage, and to address the coordination of intrasite SNF movements with new receipts and intersite transfers that were identified in the DOE SNF Programmatic and INEL Environmental Restoration and Waste Management Environmental Impact Statement Record, of Decision. This SISMP will be a subset of the INEL Spent Nuclear Fuel Management Plan and the activities described are being coordinated with other INEL SNF management activities. The CPP-603 relocation activities have been assigned a high priority so that established milestones will be meet, but there will be some cases where other activities will take precedence in utilization of available resources. The Draft INEL Site Integrated Stabilization Management Plan (SISMP), INEL-94/0279, Draft Rev. 2, dated March 10, 1995, is being superseded by the INEL Spent Nuclear Fuel Management Plan and this CPP-603 specific SISMP.

  14. Resource Conservation and Recovery Act Industrial Site Environmental Restoration Site Characterization Plan, Area 6 Decontamination Pond Facility, Revision 1

    SciTech Connect

    1996-08-12

    This plan presents the strategy for the characterization of the Area 6 Decontamination Pond Facility (DPF) at the Nevada Test Site (NTS) which will be conducted for the U.S. Department of Energy, Nevada Operations OffIce (DOE/NV), Environmental Restoration Division (ERD). The objectives of the planned activities are to: o Obtain sufficient, ample analytical data from which further assessment, remediation, and/or closure strategies maybe developed for the site. o Obtain sufficient, sample analytical data for management of investigation-derived waste. All references to regulations contained in this plan are to the versions of the regulations that are current at the time of publication of this plan. The scope of the characterization may include surface radiation survey(s), surface soil sampling, subsurface soil boring (i.e., drilling), and sampling of soil in and Mound the pond; in situ sampling of the soil within subsurface soil borings; and sample analysis for both site . . characterization and waste management purposes.

  15. Site selection study for Sandia National Laboratories/New Mexico as an alternative site for the National Ignition Facility

    SciTech Connect

    Miller, D.; Wheeler, T.; McClellan, Y.

    1996-03-01

    The Department of Energy (DOE) proposes to construct and operate the National Ignition Facility (NIF) in support of the Stockpile Stewardship and Management (SSM) Programmatic Environmental impact Statement (PEIS). The National Environmental Policy Act requires the DOE to look at alternative sites for the NIF. The SSM PEIS will evaluate four alternative locations for the NIF. This study documents the process and results of a site selection study for a preferred site for the NIF at SNL/NM. The NIF research objectives are to provide the world`s most powerful laser systems to be used in ignition of fusion fuel and energy gain to perform high energy density and radiation effects experiments in support of the DOE`s national security, energy, and basic science research mission. The most immediate application of the NIF will be to provide nuclear-weapon-related physics data, since many phenomena occurring on the laboratory scale are similar to those that occur in weapons. The NIF may also provide an important capability for weapons effects simulation. The NIF is designed to achieve propagating fusion bum and modest energy gain for development as a source of civilian energy.

  16. Niagara Falls Storage Site, Annual site environmental report, Lewiston, New York, Calendar year 1986: Surplus Facilities Management Program (SFMP)

    SciTech Connect

    Not Available

    1987-06-01

    During 1986, the environmental monitoring program was continued at the Niagara Falls Storage Site (NFSS), a US Department of Energy (DOE) surplus facility located in Niagara County, New York, presently used for the interim storage of radioactive residues and contaminated soils and rubble. The monitoring program is being conducted by Bechtel National, Inc. The monitoring program at the NFSS measures radon gas concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, this individual would receive an annual external exposure approximately equivalent to 6% of the DOE radiation protection standard of 100 mrem/yr. By comparison, the incremental dose received from living in a brick house versus a wooden house is 10 mrem/yr above background. The cumulative dose to the population within an 80-km (50-mi) radius of the NFSS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. Results of the 1986 monitoring show that the NFSS is in compliance with the DOE radiation protection standard. 14 refs., 11 figs., 14 tabs.

  17. Preliminary siting criteria for the proposed mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

    SciTech Connect

    Jorgenson-Waters, M.

    1992-09-01

    The Mixed and Low-Level Waste Treatment Facility project was established in 1991 by the US Department of Energy Idaho Field Office. This facility will provide treatment capabilities for Idaho National Engineering Laboratory (INEL) low-level mixed waste and low-level waste. This report identifies the siting requirements imposed on facilities that treat and store these waste types by Federal and State regulatory agencies and the US Department of Energy. Site selection criteria based on cost, environmental, health and safety, archeological, geological and service, and support requirements are presented. These criteria will be used to recommend alternative sites for the new facility. The National Environmental Policy Act process will then be invoked to evaluate the alternatives and the alternative sites and make a final site determination.

  18. Pre-operational environmental monitoring plan for the Device Assembly Facility at the Nevada Test Site

    SciTech Connect

    Ferate, F.D.

    1995-01-01

    Nuclear explosives operations have been and may continue to be an important component of the DOE mission at the NTS. This mission has been to conduct the nation`s nuclear testing program in a safe, secure, and efficient manner while assuring full compliance with state and federal regulations, and DOE order`s and directives. These operations have generally included assembly, disassembly or modification, staging, transportation, and tesbng of nuclear explosive devices. They may also include maintenance, repair, retrofit, and surveillance. The Device Assembly Facility (DAF) was constructed to provide a dedicated facility in which to prepare nuclear explosives assemblies for their intended disposition. This facility will provide for combined operations (replacing two separate facilities) and incorporates state-of-the-art safety and security features while minimizing the risks of environmental impacts. The facility has been completed but not yet operated, so the impacts to be considered will b e based on normal operations and not on the impacts of construction activities. The impacts will arise from nuclear explosives operations that require the handling of high explosives in combination with special nuclear materials. Wastes from operation of the earlier device assembly facilities have included grams of epoxies, pints of solvents, and small quantities of waste explosives. These are hazardous (includes radioactive) wastes and are disposed of in accordance with state and federal regulations. Assuming similar operations at the DAF, non-hazardous (includes non-radioactive) solid waste would be transported to a permitted landfill. Waste explosives would be sent to the Area 11 Explosive Ordnance Disposal Unit. Other hazardous waste would be sent to the Area 5 Radioactive Waste.Management Site for shipment or burial.

  19. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12. Environmental Restoration Program

    SciTech Connect

    Not Available

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  20. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12

    SciTech Connect

    Owen, P. T.; Webb, J. R.; Knox, N. P.; Goins, L. F.; Harrell, R. E.; Mallory, P. K.; Cravens, C. D.

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  1. Environmental assessment for device assembly facility operations, Nevada Test Site, Nye County, Nevada. Final report

    SciTech Connect

    1995-05-01

    The U.S. Department of Energy, Nevada Operations Office (DOE/NV), has prepared an environmental assessment (EA), (DOE/EA-0971), to evaluate the impacts of consolidating all nuclear explosive operations at the newly constructed Device Assembly Facility (DAF) in Area 6 of the Nevada Test Site. These operations generally include assembly, disassembly or modification, staging, transportation, testing, maintenance, repair, retrofit, and surveillance. Such operations have previously been conducted at the Nevada Test Site in older facilities located in Area 27. The DAF will provide enhanced capabilities in a state-of-the-art facility for the safe, secure, and efficient handling of high explosives in combination with special nuclear materials (plutonium and highly enriched uranium). Based on the information and analyses in the EA, DOE has determined that the proposed action would not constitute a major federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (42 U.S.C. 4321 et seq.). Therefore, an environmental impact statement is not required, and DOE is issuing this finding of no significant impact.

  2. New challenges for the maintenance strategies on large astronomical facilities at remote observing sites

    NASA Astrophysics Data System (ADS)

    Silber, Armin

    2012-09-01

    The Change from a reacting to a proactive maintenance concept represents for large Observatories at remote operational sites a new challenge, considering the increasing numbers of complex subsystems. Conventional operational maintenance models will not cover all the requirements, will lead to more down time and the operational cost cannot be reduced. For the successful astronomical observation with large telescope facilities new strategies have to be applied. In this contribution we will demonstrate on the example of the 78 Cryogenic Sub-systems of ALMA how a proactive maintenance strategy help to increase the efficiency, to reduce the operational cost and the required staff resources. With respect to the growing number of complex subsystems on future telescope facilities the operational staff needs proper diagnostic and monitoring tools to allow a precise prediction respectively synchronization of the service activities. This leads away from a pure scheduling of preventive maintenance and enables a longer availability of the subsystems as tendencies and performance are monitored and controlled. Having this strategy considered during the developing phase of future large astronomical facilities allows the optimization of the required Infrastructure, a proper definition of the LRU1 strategy and to which level maintenance can be cost efficient on site.

  3. Siting new or expanded treatment, storage, or disposal facilities: the pigs in the parlors of the 1980s

    SciTech Connect

    Tarlock, A.D.

    1984-01-01

    There are no signs that the controversy over siting new treatment, storage, or disposal (TSD) facilities for hazardous wastes or expanding existing facilities is abating. Few communities want a TSD facility because of safety concerns. Public fear has moved the siting issue from a technical problem into the institutional bog of risk-benefit analysis. A review of the legal issues, including that of state control and federal preemption, concludes that states face difficult choices in designing statutes because of conflict between technical and political problems. The most positive aspects of siting statutes is the back door they open to the basic problem of waste-stream reduction. 138 references.

  4. Cost estimate for a proposed GDF Suez LNG testing program

    SciTech Connect

    Blanchat, Thomas K.; Brady, Patrick Dennis; Jernigan, Dann A.; Luketa, Anay Josephine; Nissen, Mark R.; Lopez, Carlos; Vermillion, Nancy; Hightower, Marion Michael

    2014-02-01

    At the request of GDF Suez, a Rough Order of Magnitude (ROM) cost estimate was prepared for the design, construction, testing, and data analysis for an experimental series of large-scale (Liquefied Natural Gas) LNG spills on land and water that would result in the largest pool fires and vapor dispersion events ever conducted. Due to the expected cost of this large, multi-year program, the authors utilized Sandia's structured cost estimating methodology. This methodology insures that the efforts identified can be performed for the cost proposed at a plus or minus 30 percent confidence. The scale of the LNG spill, fire, and vapor dispersion tests proposed by GDF could produce hazard distances and testing safety issues that need to be fully explored. Based on our evaluations, Sandia can utilize much of our existing fire testing infrastructure for the large fire tests and some small dispersion tests (with some modifications) in Albuquerque, but we propose to develop a new dispersion testing site at our remote test area in Nevada because of the large hazard distances. While this might impact some testing logistics, the safety aspects warrant this approach. In addition, we have included a proposal to study cryogenic liquid spills on water and subsequent vaporization in the presence of waves. Sandia is working with DOE on applications that provide infrastructure pertinent to wave production. We present an approach to conduct repeatable wave/spill interaction testing that could utilize such infrastructure.

  5. Acid mine drainage risks - A modeling approach to siting mine facilities in Northern Minnesota USA

    NASA Astrophysics Data System (ADS)

    Myers, Tom

    2016-02-01

    Most watershed-scale planning for mine-caused contamination concerns remediation of past problems while future planning relies heavily on engineering controls. As an alternative, a watershed scale groundwater fate and transport model for the Rainy Headwaters, a northeastern Minnesota watershed, has been developed to examine the risks of leaks or spills to a pristine downstream watershed. The model shows that the risk depends on the location and whether the source of the leak is on the surface or from deeper underground facilities. Underground sources cause loads that last longer but arrive at rivers after a longer travel time and have lower concentrations due to dilution and attenuation. Surface contaminant sources could cause much more short-term damage to the resource. Because groundwater dominates baseflow, mine contaminant seepage would cause the most damage during low flow periods. Groundwater flow and transport modeling is a useful tool for decreasing the risk to downgradient sources by aiding in the placement of mine facilities. Although mines are located based on the minerals, advance planning and analysis could avoid siting mine facilities where failure or leaks would cause too much natural resource damage. Watershed scale transport modeling could help locate the facilities or decide in advance that the mine should not be constructed due to the risk to downstream resources.

  6. Facility for Antiproton and Ion Research, FAIR, at the GSI site

    SciTech Connect

    Rosner, Guenther

    2006-11-17

    FAIR is a new large-scale particle accelerator facility to be built at the GSI site in Germany. The research pursued at FAIR will cover a wide range of topics in nuclear and hadron physics, as well as high density plasma physics, atomic and antimatter physics, and applications in condensed matter physics and biology. The working horse of FAIR will be a 1.1km circumference double ring of rapidly cycling 100 and 300Tm synchrotrons, which will be used to produce high intensity secondary beams of short-lived radioactive ions or antiprotons. A subsequent suite of cooler and storage rings will deliver heavy ion and antiproton beams of unprecedented quality. Large experimental facilities are presently being designed by the NUSTAR, PANDA, PAX, CBM, SPARC, FLAIR, HEDgeHOB and BIOMAT collaborations.

  7. Transporter Development for the Tritium Extraction Facility at the Savannah River Site

    SciTech Connect

    Gordon, J.

    1998-12-17

    The Commercial Light Water Reactor-Tritium Extraction Facility (CLWR-TEF) is planned for location at the Savannah River Site (SRS) as part of the US Department of Energy CLWR tritium production alternative. This new facility will rely on processes and equipment that are significantly different from those proven in the past or currently in use at SRS. For instance, the CLWR-TEF reference design employs remote modules to provide an inert processing atmosphere, secondary confinement for tritium and the primary confinement for particulate contamination. The primary component of this modular system is the Transporter. A Transporter mock-up was developed to demonstrate concept feasibility of the required processing functions (sealing, attachment/alignment and materials handling). The module design, the seal door selection, and the planned test program are discussed.

  8. Site inspection health and safety plan. Bennett Army National Guard Facility Bennett, Colorado. Final report

    SciTech Connect

    1995-01-26

    This Health and Safety Plan (HSP) is based on the Remedial Investigation/Feasibility Study (RI/FS) HSP originally developed by R.L. Stollar Associates, Inc. in 1991 for use at the Bennett Army National Guard Facility (BANGF). Subsequent to the initial preparation of the plan, funding to perform the RI/FS at BANGF was not provided. The original RI/FS HSP has been modified to address the potential health and safety hazards associated with conducting a Site Inspection (SI) of this facility. The HSP meets the requirements of Title 29 of the Code of Federal Regulations, Section 1910.120 (29 CFR 1910.120) and 29 CFR 1910.134. Compliance with this HSP for BANGF is required of all field personnel, including subcontractors conducting investigations and waste management identified in the BANGF SI Sampling and Analysis Plan.

  9. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Vol. 18. Part 2. Indexes

    SciTech Connect

    1997-09-01

    This bibliography contains 3638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D&D), uranium mill tailings management, and site remedial actions. This report is the eighteenth in a series of bibliographies prepared annually for the U.S. Department of Energy (DOE) Office of Environmental Restoration. Citations to foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - have been included in Part 1 of the report. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D&D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized Sites Remedial Action Programs; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluations; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues. Within the 16 sections, the citations are sorted by geographic location. If a geographic location is not specified, the citations are sorted according to the document title. In Part 2 of the report, indexes are provided for author, author affiliation, selected title phrase, selected title word, publication description, geographic location, and keyword.

  10. 46 CFR 154.703 - Methane (LNG).

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 46 Shipping 5 2010-10-01 2010-10-01 false Methane (LNG). 154.703 Section 154.703 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) CERTAIN BULK DANGEROUS CARGOES SAFETY STANDARDS FOR... system that meets § 154.702; (b) A waste heat or catalytic furnace that burns boil-off gas, and:...

  11. 46 CFR 154.703 - Methane (LNG).

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 46 Shipping 5 2011-10-01 2011-10-01 false Methane (LNG). 154.703 Section 154.703 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) CERTAIN BULK DANGEROUS CARGOES SAFETY STANDARDS FOR SELF-PROPELLED VESSELS CARRYING BULK LIQUEFIED GASES Design, Construction and Equipment Cargo Pressure and Temperature Control § 154.703 Methane...

  12. Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 4

    SciTech Connect

    Owen, P.T.; Knox, N.P.; Fielden, J.M.; Faust, R.A.

    1983-09-01

    This bibliography of 657 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fourth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic documents of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - have been references in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; and (6) Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author, or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. Appendix A lists 264 bibliographic references to literature identified during this reporting period but not abstracted due to time constraints. Title and publication description indexes are given for this appendix. Appendix B defines frequently used acronyms, and Appendix C lists the recipients of this report according to their corporate affiliation.

  13. Nuclear facility licensing, documentaion, and reviews, and the SP-100 test site experience

    SciTech Connect

    Cornwell, B.C.; Deobald, T.L.; Bitten, E.J.

    1991-06-01

    The required approvals and permits to test a nuclear facility are extensive. Numerous regulatory requirements result in the preparation of documentation to support the approval process. The principal regulations for the SP-100 Ground Engineering System (GES) include the National Environmental Policy Act, Clean Air Act, and Atomic Energy Act. The documentation prepared for the SP-100 Nuclear Assembly Test (NAT) included an Environmental Assessment, state permit applications, and Safety Analysis Reports. This paper discusses the regulation documentation requirements and the SP-100 NAT Test Site experience. 12 refs., 2 figs., 2 tabs.

  14. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes. Environmental Restoration Program

    SciTech Connect

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

  15. 10 CFR 50.83 - Release of part of a power reactor facility or site for unrestricted use.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Release of part of a power reactor facility or site for unrestricted use. 50.83 Section 50.83 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Transfers of Licenses-Creditors' Rights-Surrender of Licenses § 50.83 Release of part of a power reactor facility...

  16. 77 FR 57094 - Draft Guidance for Industry on Self-Identification of Generic Drug Facilities, Sites, and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-17

    ... Generic Drug Facilities, Sites, and Organizations; Availability; Correction AGENCY: Food and Drug... notice that appeared in the Federal Register of Monday, August 27, 2012 (77 FR 51811). The document announced a draft guidance for industry entitled ``Self-Identification of Generic Drug Facilities,...

  17. Facilities for Conferences, Retreats and Outdoor Education. A Directory of Sites Approved by the American Camping Association.

    ERIC Educational Resources Information Center

    American Camping Association, Martinsville, IN.

    Brief descriptions of approximately 750 sites approved by the American Camping Association which lease their facilities to others are listed alphabetically by state. Entries list camp address, contact address, capacity, special facilities, services, whether available year-round, and date of information. A narrative provides general information on…

  18. Facility Closure Report for Tunnel U16a, Area 16, Nevada Test Site, Nevada

    SciTech Connect

    NSTec Environmental Restoration

    2009-07-01

    U16a is not listed in the Federal Facility Agreement and Consent Order. The closure of U16a was sponsored by the Defense Threat Reduction Agency (DTRA) and performed with the cooperation of the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office and the Nevada Division of Environmental Protection. This report documents closure of this site as identified in the DTRA Fiscal Year 2008 Statement of Work, Task 6.3. Closure activities included: · Removing and disposing of a shack and its contents · Disposing of debris from within the shack and in the vicinity of the tunnel entrance · Verifying that the tunnel is empty · Welding screened covers over tunnel vent holes to limit access and allow ventilation · Constructing a full-tunnel cross-section fibercrete bulkhead to prevent access to the tunnel Field activities were conducted from July to August 2008.

  19. Interaction of Sr-90 with site candidate soil for demonstration disposal facility at Serpong

    NASA Astrophysics Data System (ADS)

    Setiawan, Budi; Mila, Oktri; Safni

    2014-03-01

    Interaction of radiostrontium (Sr-90) with site candidate soil for demonstration disposal facility to be constructed in the near future at Serpong has been done. This activity is to anticipate the interim storage facility at Serpong nuclear area becomes full off condition, and show to the public how radioactive waste can be well managed with the existing technology. To ensure that the location is save, a reliability study of site candidate soil becomes very importance to be conducted through some experiments consisted some affected parameters such as contact time, effect of ionic strength, and effect of Sr+ ion in solution. Radiostrontium was used as a tracer on the experiments and has role as radionuclide reference in low-level radioactive waste due to its long half-live and it's easy to associate with organism in nature. So, interaction of radiostrontium and soil samples from site becomes important to be studied. Experiment was performed in batch method, and soil sample-solution containing radionuclide was mixed in a 20 ml of PE vial. Ratio of solid: liquid was 10-2 g/ml. Objective of the experiment is to collect the specific characteristics data of radionuclide sorption onto soil from site candidate. Distribution coefficient value was used as indicator where the amount of initial and final activities of radiostrontium in solution was compared. Result showed that equilibrium condition was reached after contact time 10 days with Kd values ranged from 1600-2350 ml/g. Increased in ionic strength in solution made decreased of Kd value into soil sample due to competition of background salt and radiostrontium into soil samples, and increased in Sr ion in solution caused decreased of Kd value in soil sample due to limitation of sorption capacity in soil samples. Fast condition in saturated of metal ion into soil samples was reached due to a simple reaction was occurred.

  20. Interaction of Sr-90 with site candidate soil for demonstration disposal facility at Serpong

    SciTech Connect

    Setiawan, Budi; Mila, Oktri; Safni

    2014-03-24

    Interaction of radiostrontium (Sr-90) with site candidate soil for demonstration disposal facility to be constructed in the near future at Serpong has been done. This activity is to anticipate the interim storage facility at Serpong nuclear area becomes full off condition, and show to the public how radioactive waste can be well managed with the existing technology. To ensure that the location is save, a reliability study of site candidate soil becomes very importance to be conducted through some experiments consisted some affected parameters such as contact time, effect of ionic strength, and effect of Sr{sup +} ion in solution. Radiostrontium was used as a tracer on the experiments and has role as radionuclide reference in low-level radioactive waste due to its long half-live and it's easy to associate with organism in nature. So, interaction of radiostrontium and soil samples from site becomes important to be studied. Experiment was performed in batch method, and soil sample-solution containing radionuclide was mixed in a 20 ml of PE vial. Ratio of solid: liquid was 10{sup −2} g/ml. Objective of the experiment is to collect the specific characteristics data of radionuclide sorption onto soil from site candidate. Distribution coefficient value was used as indicator where the amount of initial and final activities of radiostrontium in solution was compared. Result showed that equilibrium condition was reached after contact time 10 days with Kd values ranged from 1600-2350 ml/g. Increased in ionic strength in solution made decreased of Kd value into soil sample due to competition of background salt and radiostrontium into soil samples, and increased in Sr ion in solution caused decreased of Kd value in soil sample due to limitation of sorption capacity in soil samples. Fast condition in saturated of metal ion into soil samples was reached due to a simple reaction was occurred.

  1. Off-site movement of pesticide-contaminated fill from agrichemical facilities during the 1993 flooding in Illinois

    USGS Publications Warehouse

    Roy, W.R.; Chou, S.-F.J.; Krapac, I.G.

    1995-01-01

    Twenty retail agrichemical facilities were flooded. There was a concern that pesticide-contaminated road fill at these facilities had been transported into residential areas by the flooding. Forty fill and flood- related sediment samples were collected at six facilities. No significant accumulation of sediments was present at any of the six facilities. At five of the six facilities, it did not appear that road fill had been transported off-site. Pesticides were detected in sediment samples collected off-site adjacent to five of the facilities. Of the 21 samples collected off-site, atrazine (2-chloro-4-ethylamino-6-isopropylamino-1,3,5-triazide) and metolachlor (2-chloro-6'-ethyl-N-(2-methoxy-1-methylethyl)acet-o-toluidine) were detected in 86 and 81% of the samples, respectively. When compared with on-site concentrations, off-site pesticide concentrations were either at similar levels, or were as much as three orders of magnitude less. The interpretation of the pesticide data was difficult and often inconclusive, because there were no background data on the occurrence and distribution of pesticides at each site before flooding.

  2. Pacific Northwest Laboratory FY 1993 Site Maintenance Plan for maintenance of DOE nonnuclear facilities

    SciTech Connect

    Bright, J.D.

    1992-09-28

    This Site Maintenance Plan has been developed for Pacific Northwest Laboratory`s (PNL) Nonnuclear Facilities. It is based on requirements specified by US Department of Energy (DOE) Order 4330.4A, Chapter I, Change No. 4. The objective of this maintenance plan is to provide baseline information for compliance to the DOE Order 4330.4A, to identify needed improvements, and to document the planned maintenance budget for Fiscal Year (FY) 1993 and to estimate maintenance budgets for FY 1994 and FY 1995 for all PNL facilities. Using the results of the self-assessment, PNL has selected 12 of the 36 elements of the Maintenance Program defined by DOE Order 4330.4A, Chapter I, for improvement. The elements selected for improvement are: Facility Condition Inspections; Work Request (Order) System; Formal Job Planning and Estimating; Work Performance (Time) Standards; Priority System; Maintenance Procedures and Other Work-Related Documents; Scheduling System; Post Maintenance Testing; Backlog Work Control; Equipment Repair History and Vendor Information; Work Sampling; and Identification and Control. Based upon a graded approach and current funding, those elements considered most important have been selected as goals for earliest compliance. Commitment dates for these elements have been established for compliance. The remaining elements of noncompliance will be targeted for implementation during later budget periods.

  3. Pacific Northwest Laboratory FY 1993 Site Maintenance Plan for maintenance of DOE nonnuclear facilities

    SciTech Connect

    Bright, J.D.

    1992-09-28

    This Site Maintenance Plan has been developed for Pacific Northwest Laboratory's (PNL) Nonnuclear Facilities. It is based on requirements specified by US Department of Energy (DOE) Order 4330.4A, Chapter I, Change No. 4. The objective of this maintenance plan is to provide baseline information for compliance to the DOE Order 4330.4A, to identify needed improvements, and to document the planned maintenance budget for Fiscal Year (FY) 1993 and to estimate maintenance budgets for FY 1994 and FY 1995 for all PNL facilities. Using the results of the self-assessment, PNL has selected 12 of the 36 elements of the Maintenance Program defined by DOE Order 4330.4A, Chapter I, for improvement. The elements selected for improvement are: Facility Condition Inspections; Work Request (Order) System; Formal Job Planning and Estimating; Work Performance (Time) Standards; Priority System; Maintenance Procedures and Other Work-Related Documents; Scheduling System; Post Maintenance Testing; Backlog Work Control; Equipment Repair History and Vendor Information; Work Sampling; and Identification and Control. Based upon a graded approach and current funding, those elements considered most important have been selected as goals for earliest compliance. Commitment dates for these elements have been established for compliance. The remaining elements of noncompliance will be targeted for implementation during later budget periods.

  4. Social assessment of siting a low-level radioactive waste storage facility in Michigan

    SciTech Connect

    Stoffle, R.W.; Traugott, M.J.; Stone, J.V.; McIntyre, P.D.; Davidson, C.C.; Jensen, F.V.; Coover, G.E. )

    1990-01-01

    This report presents findings from a social assessment of siting a low-level radioactive waste storage facility in Michigan. Social assessments derive from direct interaction between researchers and study participants. The report is organized into five chapters. Chapter One, Summary of Findings, focuses on key findings from the statewide telephone surveys and the in-depth ethnographic study conducted by the SNR/ISR study team. These and additional findings are discussed in greater detail in the three subsequent chapters. Chapter Two, Statewide Telephone Survey Findings, presents the knowledge, attitudes and beliefs statewide residents have regarding the LLRW project. Chapter Three, Statewide Demographic Findings, presents a detailed examination of differences among various demographic groups and includes regional analysis. Chapter Four, Hillsdale-area Ethnographic Study Findings, discusses perceived impacts of the proposed LLRW storage facility on local residents who mistakenly came to believe that their area had been specially selected as the location for the facility. Specifically, the chapter presents the development, spread, shape and persistence of what is termed a risk perception shadow in the greater Hillsdale area. Possible causes of the shadow also are discussed, and comparisons are made between statewide and Hillsdale-area survey populations. Chapter Five, Research Methods, presents a discussion of the social assessment research methods used to derive these findings.

  5. Environmental Assessment for the LGF Spill Test Facility at Frenchman Flat, Nevada Test Site

    SciTech Connect

    Patton, S.E.; Novo, M.G.; Shinn, J.H.

    1986-04-01

    The LGF Spill Test Facility at Frenchman Flat, Nevada Test Site, is being constructed by the United States Department of Energy (DOE). In this Environmental Assessment, environmental consequences of spilling hazardous materials in the Frenchman Flat basin are evaluated and mitigations and recommendations are stated in order to protect natural resources and reduce land-use impacts. Guidelines and restrictions concerning spill-test procedures will be determined by the LGF Test Facility Operations Manager and DOE based on toxicity documentation for the test material, provided by the user, and mitigations imposed by the Environmental Assessment. In addition to Spill Test Facility operational procedures, certain assumptions have been made in preparation of this document: no materials will be considered for testing that have cumulative, long-term persistence in the environment; spill tests will consist of releases of 15 min or less; and sufficient time will be allowed between tests for recovery of natural resources. Geographic limits to downwind concentrations of spill materials were primarily determined from meteorological data, human occupational exposure standards to hazardous materials and previous spill tests. These limits were established using maximum spill scenarios and environmental impacts are discussed as worst case scenarios; however, spill-test series will begin with smaller spills, gradually increasing in size after the impacts of the initial tests have been evaluated.

  6. Human error model adaptation and validation for Savannah River Site nonreactor facilities

    SciTech Connect

    Eide, S.A.; Benhardt, H.C.; Held, J.E.; Olsen, L.M.; Vail, R.E.

    1993-09-01

    As part of an overall effort to improve safety analysis methods for the Savannah River Site (SRS) nonreactor nuclear facilities, a comprehensive human reliability analysis (HRA) methodology has been developed and selectively validated. The HRA methodology covers a wide variety of human errors that may exist in risk analyses of the nonreactor nuclear facilities. Such risk analyses are an integral part of safety analysis reports (SARS) at the SRS, forming the basis for severe accident analysis and assisting in the identification of safety classes for equipment. Nonreactor nuclear facilities at the SRS include nuclear fuel fabrication and reprocessing, nuclear waste processing, and nuclear waste storage and disposal. The SRS HRA methodology improvement included both adaptation of existing human error models and validation of selected model results with SRS-specific data on actual human errors. The data were obtained from three existing SRS data bases: (1) Fuel Processing, (2) Fuel Fabrication, and (3) Waste Management. These three are part of the Risk Analysis Methodology (RAM) Fault Tree data banks. Events in these data banks are obtained from a wide variety of sources, including operator log books, occurrence reports, safety newsletters, and others. Validation of the human error models involved comparison with SRS-specific data and calibration of model results where appropriate.

  7. Closure End States for Facilities, Waste Sites, and Subsurface Contamination - 12543

    SciTech Connect

    Gerdes, Kurt; Chamberlain, Grover; Whitehurst, Latrincy; Marble, Justin; Wellman, Dawn; Deeb, Rula; Hawley, Elisabeth

    2012-07-01

    The United States (U.S.) Department of Energy (DOE) manages the largest groundwater and soil cleanup effort in the world. DOE's Office of Environmental Management (EM) has made significant progress in its restoration efforts at sites such as Fernald and Rocky Flats. However, remaining sites, such as Savannah River Site, Oak Ridge Site, Hanford Site, Los Alamos, Paducah Gaseous Diffusion Plant, Portsmouth Gaseous Diffusion Plant, and West Valley Demonstration Project possess the most complex challenges ever encountered by the technical community and represent a challenge that will face DOE for the next decade. Closure of the remaining 18 sites in the DOE EM Program requires remediation of 75 million cubic yards of contaminated soil and 1.7 trillion gallons of contaminated groundwater, deactivation and decommissioning (D and D) of over 3000 contaminated facilities and thousands of miles of contaminated piping, removal and disposition of millions of cubic yards of legacy materials, treatment of millions of gallons of high level tank waste and disposition of hundreds of contaminated tanks. The financial obligation required to remediate this volume of contaminated environment is estimated to cost more than 7% of the to-go life-cycle cost. Critical in meeting this goal within the current life-cycle cost projections is defining technically achievable end states that formally acknowledge that remedial goals will not be achieved for a long time and that residual contamination will be managed in the interim in ways that are protective of human health and environment. Formally acknowledging the long timeframe needed for remediation can be a basis for establishing common expectations for remedy performance, thereby minimizing the risk of re-evaluating the selected remedy at a later time. Once the expectations for long-term management are in place, remedial efforts can be directed towards near-term objectives (e.g., reducing the risk of exposure to residual contamination

  8. Multiple criteria approach to site selection of radioactive waste disposal facility in the Republic of Croatia

    SciTech Connect

    Schaller, A.; Skanata, D.

    1995-12-31

    Site selection approach to radioactive waste disposal facility, which is under way in Croatia, is presented in the paper. This approach is based on application of certain relevant terrestrial and technical criteria in the site selection process. Basic documentation used for this purpose are regional planning documents prepared by the Regional Planning Institute of Croatia. The basic result of research described in the paper is the proposal of several potential areas which are suitable for siting a radioactive waste repository. All relevant conclusions are based on both data groups -- generic and on-field experienced (measured). Out of a dozen potential areas, four have been chosen as representative by the authors. The presented comparative analysis was made by means of the VISA II computer code, developed by the V. Belton and SPV Software Products. The code was donated to the APO by the IAEA. The main objective of the paper is to initiate and facilitate further discussions on possible ways of evaluation and comparison of potential areas for sitting of radioactive waste repository in this country, as well as to provide additional contributions to the current site selection process in the Republic of Croatia.

  9. Estimating the contribution of industrial facilities to annual PM10 concentrations at industrially influenced sites

    NASA Astrophysics Data System (ADS)

    Gladtke, Dieter; Volkhausen, Wolfgang; Bach, Bastian

    If measures to reduce the industrial discharge of PM10 shall be planned with high accuracy, a first step must be to estimate the contribution of single industrial facilities to the overall PM10 burden as accurately as possible. In northern Duisburg as an example, an area where iron and steel producing industry is concentrated, PM10 was measured at 4 sampling sites very close to an industrial complex of blast furnaces, a sinter plant, oxygen steel works and a coke oven plant for 9 months in 2006. At two sites metals in PM10 were determined. The results, together with analytical data of urban background sites in the region and data of wind direction and wind speed were used for an estimation of the contribution of single plants to the PM10 burden. A careful analysis of the data showed, that the data of PM10, calcium, iron and zinc measured at two sites close to the industrial area and information about the urban background aerosol were sufficient to calculate the PM10 contribution of the main single plants. The data could be compared with those of modelling.

  10. U.S. LNG Imports - The Next Wave

    EIA Publications

    2007-01-01

    U.S. LNG imports - The Next Wave, is now available as a special supplement to the January 2007 issue of the Short-Term Energy Outlook (STEO). Although liquefied natural gas (LNG) imports still account for less than 3% of total U.S. natural gas supplies, the global market is growing and the Energy Information Administration (EIA) foresees another wave of U.S. LNG import growth over the next two years. The supplement focuses on recent trends in global and U.S. LNG trade, and presents factors expected to influence LNG imports through 2008. EIA expects year-over-year increases in LNG imports of 34.5% and 38.5% in 2007 and 2008, respectively.

  11. The Field Lysimeter Test Facility (FLTF) at the Hanford Site: Installation and initial tests

    SciTech Connect

    Gee, G.W.; Kirkham, R.R.; Downs, J.L.; Campbell, M.D.

    1989-02-01

    The objectives of this program are to test barrier design concepts and to demonstrate a barrier design that meets established performance criteria for use in isolating wastes disposed of near-surface at the Hanford Site. Specifically, the program is designed to assess how well the barriers perform in controlling biointrusion, water infiltration, and erosion, as well as evaluating interactions between environmental variables and design factors of the barriers. To assess barrier performance and design with respect to infiltration control, field lysimeters and small- and large-scale field plots are planned to test the performance of specific barrier designs under actual and modified (enhanced precipitation) climatic conditions. The Field Lysimeter Test Facility (FLTF) is located in the 600 Area of the Hanford Site just east of the 200 West Area and adjacent to the Hanford Meteorological Station. The FLTF data will be used to assess the effectiveness of selected protective barrier configurations in controlling water infiltration. The facility consists of 14 drainage lysimeters (2 m dia x 3 m deep) and four precision weighing lysimeters (1.5 m x 1.5 m x 1.7 m deep). The lysimeters are buried at grade and aligned in a parallel configuration, with nine lysimeters on each side of an underground instrument chamber. The lysimeters were filled with materials to simulate a multilayer protective barrier system. Data gathered from the FLTF will be used to compare key barrier components and to calibrate and test models for predicting long-term barrier performance.

  12. Groundwater Monitoring Plan for the Hanford Site 216-B-3 Pond RCRA Facility

    SciTech Connect

    Barnett, D. Brent; Smith, Ronald M.; Chou, Charissa J.

    2000-11-28

    The 216-B-3 Pond was a series of ponds for disposal of liquid effluent from past Hanford production facilities. In 1990, groundwater monitoring at B Pond was elevated from "detection" to assessment status because total organic halides and total organic carbon were found to exceed critical means in two wells. Groundwater quality assessment, which ended in 1996, failed to find any specific hazardous waste contaminant that could have accounted for the isolated occurrences of elevated total organic halides and total organic carbon. Hence, the facility was subsequently returned to detection-level monitoring in 1998. Exhaustive groundwater analyses during the assessment period indicated that only two contaminants, tritium and nitrate, could be positively attributed to the B Pond System, with two others (arsenic and I-129) possibly originating from B Pond. Chemical and radiological analyses of soil at the main pond and 216-B-3-3 ditch has not revealed significant contamination. Based on the observed, minor contamination in groundwater and in the soil column, three parameters were selected for site-specific, semiannual monitoring; gross alpha, gross beta, and specific conductance. Total organic halides and total organic carbon are included as constituents because of regulatory requirements. Nitrate, tritium, arsenic, and iodine-129 will be monitored under the aegis of Hanford site-wide monitoring. Although the B Pond System is not scheduled to advance from RCRA interim status to final status until the year 2003, a contingency plan for an improved monitoring strategy, which will partially emulate final status requirements, will be contemplated before the official change to final status. This modification will allow a more sensible and effective screening of groundwater for the facility.

  13. 2012 Annual Wastewater Reuse Report for the Idaho National Laboratory Site's Central facilities Area Sewage Treatment Plant

    SciTech Connect

    Mike Lewis

    2013-02-01

    This report describes conditions, as required by the state of Idaho Wastewater Reuse Permit (#LA-000141-03), for the wastewater land application site at Idaho National Laboratory Site’s Central Facilities Area Sewage Treatment Plant from November 1, 2011, through October 31, 2012. The report contains the following information: • Site description • Facility and system description • Permit required monitoring data and loading rates • Status of compliance conditions and activities • Discussion of the facility’s environmental impacts. During the 2012 permit year, no wastewater was land-applied to the irrigation area of the Central Facilities Area Sewage Treatment Plant.

  14. 2010 Annual Wastewater Reuse Report for the Idaho National Laboratory Site's Central Facilities Area Sewage Treatment Plant

    SciTech Connect

    Mike lewis

    2011-02-01

    This report describes conditions, as required by the state of Idaho Wastewater Reuse Permit (#LA-000141-03), for the wastewater land application site at Idaho National Laboratory Site’s Central Facilities Area Sewage Treatment Plant from November 1, 2009, through October 31, 2010. The report contains the following information: • Site description • Facility and system description • Permit required monitoring data and loading rates • Status of special compliance conditions • Discussion of the facility’s environmental impacts. During the 2010 permit year, approximately 2.2 million gallons of treated wastewater was land-applied to the irrigation area at Central Facilities Area Sewage Treatment plant.

  15. 78 FR 62344 - Sabine Pass Liquefaction Expansion, LLC, Sabine Pass Liquefaction, LLC, and Sabine Pass LNG, L.P...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-18

    ... Sabine Pass LNG, L.P., Cheniere Creole Trail Pipeline, L.P.; Notice of Application Take notice that on... Commission an application under section 3(a) of the Natural Gas Act (NGA) for authorization to site...) filed, in the same application, a request under section 7(c) of the NGA, for authorization to...

  16. Beauty of Simplicity: Phillips Optimized Cascade LNG Liquefaction Process

    NASA Astrophysics Data System (ADS)

    Andress, D. L.; Watkins, R. J.

    2004-06-01

    Paper describes how use of single component refrigerants yields an LNG liquefaction process that is safe, simple to operate, easy to understand, and robust in reliability. The 34-year operating history of Kenai LNG has proven the inherent advantages of the Phillips Optimized Cascade LNG Process. The paper is written from an operational point of view, and describes basic design parameters and operation of the processes.

  17. Performance Assessment Program for the Savannah River Site Liquid Waste Facilities - 13610

    SciTech Connect

    Rosenberger, Kent H.

    2013-07-01

    The Liquid Waste facilities at the U.S. Department of Energy's (DOE) Savannah River Site (SRS) are operated by Liquid Waste Operations contractor Savannah River Remediation LLC (SRR). A separate Performance Assessment (PA) is prepared to support disposal operations at the Saltstone Disposal Facility and closure evaluations for the two liquid waste tank farm facilities at SRS, F-Tank Farm and H-Tank Farm. A PA provides the technical basis and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements identified in operations and closure regulatory guidance. The Saltstone Disposal Facility is subject to a State of South Carolina industrial solid waste landfill permit and the tank farms are subject to a state industrial waste water permit. The three Liquid Waste facilities are also subject to a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Due to the regulatory structure, a PA is a key technical document reviewed by the DOE, the State of South Carolina and the EPA. As the waste material disposed of in the Saltstone Disposal Facility and the residual material in the closed tank farms is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005, the U.S. Nuclear Regulatory Commission (NRC) is also a reviewing agency for the PAs. Pursuant to the Act, the NRC also has a continuing role to monitor disposal actions to assess compliance with stated performance objectives. The Liquid Waste PA program at SRS represents a continual process over the life of the disposal and closure operations. When the need for a PA or PA revision is identified, the first step is to develop a conceptual model to best represent the facility conditions. The conceptual model will include physical dimensions of the closed system, both the engineered and natural system, and modeling

  18. Interpretation and Modelling of Data from Site Investigations for a Geological Disposal facility located in the UK

    NASA Astrophysics Data System (ADS)

    Clark, H.; Bailey, L.; Parkes, A.

    2012-04-01

    The Radioactive Waste Management Directorate (RWMD) of the Nuclear Decommissioning Authority (NDA) has been given the responsibility for implementing geological disposal in the United Kingdom. The implementation process envisaged is that once a candidate site or sites for a geological disposal facility have been identified, NDA-RWMD will undertake surface-based investigations at the site or sites. The information acquired through these investigations would be used as an input to the development of the safety case, for engineering design of the disposal facility and to demonstrate confidence to the key stakeholders that the potential disposal facility site is adequately understood. NDA-RWMD proposes to develop and present the information derived from site characterisation activities in the form of a single integrated Site Descriptive Model, i.e. a description of the geometry, properties of the bedrock and water, and the associated interacting processes and mechanisms, which will be used to address the information requirements of all the end users (including the safety case). It is anticipated that, in a similar way to the approach adopted by international radioactive waste programmes led by SKB (Sweden) and Posiva (Finland), the integrated Site Descriptive Model will be divided into parts comprising clearly defined disciplines which may form either chapters or discipline-based models such as: • Geology; • Hydrogeology; • Hydrochemistry; • Geotechnical; • Radionuclide Transport Properties; • Thermal Properties; and • Biosphere. The integrated Site Descriptive Model will evolve as understanding of the particular site advances and will describe the current understanding of a specific site and, where relevant, the historical development of conditions at the site where this supports the conceptual understanding. The Site Descriptive Model will not include prediction of the future evolution of the conditions at the site: this will be an important component

  19. The use of long acting subcutaneous levonorgestrel (LNG) gel depot as an effective contraceptive option for cotton-top tamarins (Saguinus oedipus).

    PubMed

    Wheaton, C J; Savage, A; Shukla, A; Neiffer, D; Qu, W; Sun, Y; Lasley, B L

    2011-01-01

    Cotton-top tamarins (Saguinus oedipus) are a critically endangered species that have been bred successfully in captivity for many years. For two decades, the Cotton-top Tamarin SSP(©) has been challenged with a high rate of reproduction combined with a history of contraceptive failures and nonrecommended births using the current Depo Provera(®) (medroxyprogesterone acetate) injection followed by MGA (melengestrol acetate) implant contraception combination. To address these issues we have developed and tested the use of levonorgestrel (LNG) as an effective contraception option for cotton-top tamarins. LNG was delivered in an injectable, gel matrix consisting of polylactic-co-glycolic acid, triethyl citrate and N-methylpyrrolidone. This gel matrix forms a biodegradable depot at the subcutaneous injection site providing slow release of the active ingredient. Gel matrix composition and LNG concentration were adjusted in four gel formulations to maximize the duration of contraceptive efficacy while minimizing immediate post-injection increases in fecal LNG concentration. LNG treatment (68.44 ± 8.61 mg/kg) successfully eliminated ovarian cycles (fecal pregnanediol-3-glucuronide (PdG) and estrone conjugates (E(1) C)) for 198.8 ± 70.3 days (formulation four; range 19-50 weeks). It was demonstrated that subcutaneous LNG depot injection was an effective, reversible contraceptive option for the management of cotton-top tamarins in captivity. PMID:20938969

  20. High efficiency Brayton cycles using LNG

    DOEpatents

    Morrow, Charles W.

    2006-04-18

    A modified, closed-loop Brayton cycle power conversion system that uses liquefied natural gas as the cold heat sink media. When combined with a helium gas cooled nuclear reactor, achievable efficiency can approach 68 76% (as compared to 35% for conventional steam cycle power cooled by air or water). A superheater heat exchanger can be used to exchange heat from a side-stream of hot helium gas split-off from the primary helium coolant loop to post-heat vaporized natural gas exiting from low and high-pressure coolers. The superheater raises the exit temperature of the natural gas to close to room temperature, which makes the gas more attractive to sell on the open market. An additional benefit is significantly reduced costs of a LNG revaporization plant, since the nuclear reactor provides the heat for vaporization instead of burning a portion of the LNG to provide the heat.

  1. West Virginia Geological Survey's role in siting fluidized bed combustion facilities

    USGS Publications Warehouse

    Smith, C.J.; King, Hobart M.; Ashton, K.C.; Kirstein, D.S.; McColloch, G.H.

    1989-01-01

    A project is presented which demonstrates the role of geology in planning and siting a fluidized bed combustion facility. Whenever a project includes natural resource utilization, cooperation between geologists and design engineers will provide an input that could and should save costs, similar to the one stated in our initial premise. Regardless of whether cost reductions stem from a better knowledge of fuel and sorbent availabilities, or a better understanding of the local hydrology, susceptibility to mine-subsidence, or other geologic hazards, the geological survey has a vital role in planning. Input to planning could help the fluidized-bed developer and design-engineer solve some economic questions and stretch the financial resources at their disposal.

  2. Slush hydrogen propellant production, transfer, and expulsion studies at the NASA K-Site Facility

    NASA Technical Reports Server (NTRS)

    Hardy, Terry L.; Whalen, Margaret V.

    1991-01-01

    Slush hydrogen is currently being considered as a fuel for the National AeroSpace Plane (NASP) because it offers the potential for decreased vehicle size and weight. However, no large scale data was available on the production, transfer, and tank pressure control characteristics required to use the fuel for the NASP. Therefore, experiments were conducted at NASA-Lewis K-Site Facility to improve the slush hydrogen data base. Slush hydrogen was produced using the evaporative cooling, or freeze-thaw, technique in batches for approx. 800 gallons. This slush hydrogen was pressure transferred to a 5 ft diameter spherical test tank following production, and flow characteristics were measured during this transfer process. The slush hydrogen in the test tank was pressurized and expelled using a pressurized expulsion technique to obtain information on tank pressure control for the NASP. Results from the production, transfer, pressurization, and pressurized expulsion tests are described.

  3. Slush hydrogen pressurized expulsion studies at the NASA K-Site Facility

    NASA Technical Reports Server (NTRS)

    Whalen, Margaret V.; Hardy, Terry L.

    1992-01-01

    An experiment test series of the slush hydrogen (SLH2) project at the NASA LeRC Plum Brook K-Site Facility was completed. This testing was done as part of the characterization and technology database development on slush hydrogen required for the National Aero-Space Plane (NASP) Program. The primary objective of these experiments was to investigate tank thermodynamic parameters during the pressurized expulsion of slush hydrogen. To accomplish this, maintenance of tank pressure control was investigated during pressurized expulsion of slush hydrogen using gaseous hydrogen and gaseous helium pressurant. In addition, expulsion tests were performed using gaseous helium for initial pressurization, then gaseous hydrogen during expulsion. These tests were conducted with and without mixing of the slush hydrogen. Results from the testing included an evaluation of tank pressure control, pressurant requirements, SLH2 density change, and system mass and energy balances.

  4. Dynamic simulation study of the Consolidated Incineration Facility (CIF) incinerator at the Savannah River Site

    SciTech Connect

    Hang, T.

    1992-01-01

    The Savannah River Site (SRS), operated by Westinghouse Savannah River Company for the US Department of Energy, plans to start up the Consolidated Incineration Facility (CIF) in 1995. The CIF will treat liquid and solid low-level radioactive, mixed, and hazardous wastes generated at SRS. A Fortran computer model was developed to simulate the transient responses of the CIF to fluctuations in solid waste feed. Of particular interest was the performance of two independent pressure control loops in maintaining system pressure. The model is capable of predicting the dynamic behavior of all components (rotary kiln, secondary combustion chamber, quencher, scrubber cyclone, mist eliminator, HEPA filters, and ID fans). This paper summarizes the model development and results of the simulation study.

  5. Slush hydrogen propellant production, transfer, and expulsion studies at the NASA K-Site Facility

    NASA Technical Reports Server (NTRS)

    Hardy, Terry L.; Whalen, Margaret V.

    1991-01-01

    Slush hydrogen is currently being considered as a fuel for the National Aero-Space Plane (NASP) because it offers the potential for decreased vehicle size and weight. However, no large-scale data was available on the production, transfer, and tank pressure control characteristics required to use the fuel for the NASP. Therefore, experiments were conducted at the NASA Lewis Research Center K-Site Facility to improve the slush hydrogen database. Slush hydrogen was produced using the evaporative cooling, or freeze-thaw, technique in batches of about 800 gallons. This slush hydrogen was pressure transferred to a 5 ft diameter spherical test tank following production, and flow characteristics were measured during this transfer process. The slush hydrogen in the test tank was pressurized and expelled using a pressurized expulsion technique to obtain information on tank pressure control for the NASP. Results from the production, transfer, pressurization, and pressurized expulsion tests are described.

  6. Groundwater monitoring plan for the Hanford Site 200 Area Treated Effluent Disposal Facility

    SciTech Connect

    DB Barnett

    2000-05-17

    Seven years of groundwater monitoring at the 200 Area Treated Effluent Disposal Facility (TEDF) have shown that the uppermost aquifer beneath the facility is unaffected by TEDF effluent. Effluent discharges have been well below permitted and expected volumes. Groundwater mounding from TEDF operations predicted by various models has not been observed, and waterlevels in TEDF wells have continued declining with the dissipation of the nearby B Pond System groundwater mound. Analytical results for constituents with enforcement limits indicate that concentrations of all these are below Practical Quantitation Limits, and some have produced no detections. Likewise, other constituents on the permit-required list have produced results that are mostly below sitewide background. Comprehensive geochemical analyses of groundwater from TEDF wells has shown that most constituents are below background levels as calculated by two Hanford Site-wide studies. Additionally, major ion proportions and anomalously low tritium activities suggest that groundwater in the aquifer beneath the TEDF has been sequestered from influences of adjoining portions of the aquifer and any discharge activities. This inference is supported by recent hydrogeologic investigations which indicate an extremely slow rate of groundwater movement beneath the TEDF. Detailed evaluation of TEDF-area hydrogeology and groundwater geochemistry indicate that additional points of compliance for groundwater monitoring would be ineffective for this facility, and would produce ambiguous results. Therefore, the current groundwater monitoring well network is retained for continued monitoring. A quarterly frequency of sampling and analysis is continued for all three TEDF wells. The constituents list is refined to include only those parameters key to discerning subtle changes in groundwater chemistry, those useful in detecting general groundwater quality changes from upgradient sources, or those retained for comparison with end

  7. Department of Energy Arm Facilities on the North Slope of Alaska and Plans for a North Slope "Mega-Site"

    NASA Astrophysics Data System (ADS)

    Ivey, M.; Verlinde, J.

    2014-12-01

    The U.S. Department of Energy (DOE), through its scientific user facility, the Atmospheric Radiation Measurement (ARM) Climate Research Facility, provides scientific infrastructure and data to the international Arctic research community via its research sites located on the North Slope of Alaska. The DOE ARM Program has operated an atmospheric measurement facility in Barrow, Alaska, since 1998. Major upgrades to this facility, including scanning radars, were added in 2010. Facilities and infrastructure to support operations of unmanned aerial systems for science missions in the Arctic and North Slope of Alaska were established at Oliktok Point Alaska in 2013. Tethered instrumented balloons will be used in the near future to make measurements of clouds in the boundary layer including mixed-phase clouds. The Atmospheric Radiation Measurement (ARM) Climate Research Facility is implementing "mega-sites" at the Southern Great Plains and North Slope of Alaska sites. Two workshops were held to gather input from the scientific community on these mega-sites. The NSA workshop was held September 10 and 11 in the Washington DC area. The workshops included discussions of additional profiling remote sensors, detailed measurements of the land-atmosphere interface, aerial operations to link the Barrow and Oliktok sites, unmanned aerial system measurements, and routine large eddy simulation model runs. The "mega-sites" represent a significant new scientific and infrastructure investment by DOE Office of Science, Office of Biological and Environmental Research. This poster will present information on plans for a North Slope "Megasite" as well as new opportunities for members of the arctic research community to make atmospheric measurements using unmanned aerial systems or tethered balloons in conjunction with the DOE ARM facilities on the North Slope of Alaska.

  8. INSTALLATION OF BUBBLERS IN THE SAVANNAH RIVER SITED DEFENSE WASTE PROCESSING FACILITY MELTER

    SciTech Connect

    Smith, M.; Iverson, D.

    2010-12-08

    Savannah River Remediation (SRR) LLC assumed the liquid waste contract at the Savannah River Site (SRS) in the summer of 2009. The main contractual agreement was to close 22 High Level Waste (HLW) tanks in eight years. To achieve this aggressive commitment, faster waste processing throughout the SRS liquid waste facilities will be required. Part of the approach to achieve faster waste processing is to increase the canister production rate of the Defense Waste Processing Facility (DWPF) from approximately 200 canisters filled with radioactive waste glass per year to 400 canisters per year. To reach this rate for melter throughput, four bubblers were installed in the DWPF Melter in the late summer of 2010. This effort required collaboration between SRR, SRR critical subcontractor EnergySolutions, and Savannah River Nuclear Solutions, including the Savannah River National Laboratory (SRNL). The tasks included design and fabrication of the bubblers and related equipment, testing of the bubblers for various technical issues, the actual installation of the bubblers and related equipment, and the initial successful operation of the bubblers in the DWPF Melter.

  9. Technical report for the generic site add-on facility for plutonium polishing

    SciTech Connect

    Collins, E. D.

    1998-06-01

    The purpose of this report is to provide environmental data and reference process information associated with incorporating plutonium polishing steps (dissolution, impurity removal, and conversion to oxide powder) into the genetic-site Mixed-Oxide Fuel Fabrication Facility (MOXFF). The incorporation of the plutonium polishing steps will enable the removal of undesirable impurities, such as gallium and americium, known to be associated with the plutonium. Moreover, unanticipated impurities can be removed, including those that may be contained in (1) poorly characterized feed materials, (2) corrosion products added from processing equipment, and (3) miscellaneous materials contained in scrap recycle streams. These impurities will be removed to the extent necessary to meet plutonium product purity specifications for MOX fuels. Incorporation of the plutonium polishing steps will mean that the Pit Disassembly and Conversion Facility (PDCF) will need to produce a plutonium product that can b e dissolved at the MOXFF in nitric acid at a suitable rate (sufficient to meet overall production requirements) with the minimal usage of hydrofluoric acid, and its complexing agent, aluminum nitrate. This function will require that if the PDCF product is plutonium oxide powder, that powder must be produced, stored, and shipped without exceeding a temperature of 600 C.

  10. SAVANNAH RIVER SITE'S H-CANYON FACILITY: RECOVERY AND DOWN BLEND URANIUM FOR BENEFICIAL USE

    SciTech Connect

    Magoulas, V.

    2013-05-27

    For over fifty years, the H Canyon facility at the Savannah River Site (SRS) has performed remotely operated radiochemical separations of irradiated targets to produce materials for national defense. Although the materials production mission has ended, the facility continues to play an important role in the stabilization and safe disposition of proliferable nuclear materials. As part of the US HEU Disposition Program, SRS has been down blending off-specification (off-spec) HEU to produce LEU since 2003. Off-spec HEU contains fission products not amenable to meeting the American Society for Testing and Material (ASTM) commercial fuel standards prior to purification. This down blended HEU material produced 301 MT of ~5% enriched LEU which has been fabricated into light water reactor fuel being utilized in Tennessee Valley Authority (TVA) reactors in Tennessee and Alabama producing economic power. There is still in excess of ~10 MT of off-spec HEU throughout the DOE complex or future foreign and domestic research reactor returns that could be recovered and down blended for beneficial use as either ~5% enriched LEU, or for use in subsequent LEU reactors requiring ~19.75% enriched LEU fuel.

  11. Geological site characterization for the proposed Mixed Waste Disposal Facility, Los Alamos National Laboratory

    SciTech Connect

    Reneau, S.L.; Raymond, R. Jr.

    1995-12-01

    This report presents the results of geological site characterization studies conducted from 1992 to 1994 on Pajarito Mesa for a proposed Los Alamos National Laboratory Mixed Waste Disposal Facility (MWDF). The MWDF is being designed to receive mixed waste (waste containing both hazardous and radioactive components) generated during Environmental Restoration Project cleanup activities at Los Alamos. As of 1995, there is no Resource Conservation and Recovery Act (RCRA) permitted disposal site for mixed waste at the Laboratory, and construction of the MWDF would provide an alternative to transport of this material to an off-site location. A 2.5 km long part of Pajarito Mesa was originally considered for the MWDF, extending from an elevation of about 2150 to 2225 m (7060 to 7300 ft) in Technical Areas (TAs) 15, 36, and 67 in the central part of the Laboratory, and planning was later concentrated on the western area in TA-67. The mesa top lies about 60 to 75 m (200 to 250 ft) above the floor of Pajarito Canyon on the north, and about 30 m (100 ft) above the floor of Threemile Canyon on the south. The main aquifer used as a water supply for the Laboratory and for Los Alamos County lies at an estimated depth of about 335 m (1100 ft) below the mesa. The chapters of this report focus on surface and near-surface geological studies that provide a basic framework for siting of the MWDF and for conducting future performance assessments, including fulfillment of specific regulatory requirements. This work includes detailed studies of the stratigraphy, mineralogy, and chemistry of the bedrock at Pajarito Mesa by Broxton and others, studies of the geological structure and of mesa-top soils and surficial deposits by Reneau and others, geologic mapping and studies of fracture characteristics by Vaniman and Chipera, and studies of potential landsliding and rockfall along the mesa-edge by Reneau.

  12. Surplus Facilities Management Program. Post-remedial-action survey report for SNAP-8 Experimental Reactor Facility, building 010 site, Santa Susana Field Laboratories, Rockwell International, Ventura County, California

    NASA Astrophysics Data System (ADS)

    Wynveen, R. A.; Smith, W. H.; Sholeem, C. M.; Mayes, C. B.; Justas, A. L.; Flynn, K. F.

    1984-04-01

    Based on the results of the radiological assessment the following conclusions were reached: (1) soil contaminated with the radionuclides Co(60) and Er(152)Eu of undetermined origin was detected in the southwest quadrant of the Building 010 site. Co(60) was also detected in a borehole sample taken from the area that previously held the radioactive gas hold up tanks. Uranium was detected in soil from a hole in the center of the building site and in a second hole southwest of the building site. In all cases, the radionuclide levels encountered in the soil were well below the criteria set by DOE for this site; and (2) the direct instrument readings at the surface of the site were probably the result of natural radiation (terrestrial and celestial), as well as shine from the material being stored at the nearby RMDF facility. There was no evidence that the contaminated soil under the asphalt pad contributed detectable levels to the total background readings.

  13. Environmental Management Waste Management Facility (EMWMF) Site-Specific Health and Safety Plan, Oak Ridge, Tennessee

    SciTech Connect

    Flynn, N.C. Bechtel Jacobs

    2008-04-21

    The Bechtel Jacobs Company LLC (BJC) policy is to provide a safe and healthy workplace for all employees and subcontractors. The implementation of this policy requires that operations of the Environmental Management Waste Management Facility (EMWMF), located one-half mile west of the U.S. Department of Energy (DOE) Y-12 National Security Complex, be guided by an overall plan and consistent proactive approach to environment, safety and health (ES&H) issues. The BJC governing document for worker safety and health, BJC/OR-1745, 'Worker Safety and Health Program', describes the key elements of the BJC Safety and Industrial Hygiene (IH) programs, which includes the requirement for development and implementation of a site-specific Health and Safety Plan (HASP) where required by regulation (refer also to BJC-EH-1012, 'Development and Approval of Safety and Health Plans'). BJC/OR-1745, 'Worker Safety and Health Program', implements the requirements for worker protection contained in Title 10 Code of Federal Regulations (CFR) Part 851. The EMWMF site-specific HASP requirements identifies safe operating procedures, work controls, personal protective equipment, roles and responsibilities, potential site hazards and control measures, site access requirements, frequency and types of monitoring, site work areas, decontamination procedures, and outlines emergency response actions. This HASP will be available on site for use by all workers, management and supervisors, oversight personnel and visitors. All EMWMF assigned personnel will be briefed on the contents of this HASP and will be required to follow the procedures and protocols as specified. The policies and procedures referenced in this HASP apply to all EMWMF operations activities. In addition the HASP establishes ES&H criteria for the day-to-day activities to prevent or minimize any adverse effect on the environment and personnel safety and health and to meet standards that define acceptable waste management practices. The

  14. Inadvertent Intruder Analysis For The Portsmouth On-Site Waste Disposal Facility (OSWDF)

    SciTech Connect

    Smith, Frank G.; Phifer, Mark A.

    2014-01-22

    The inadvertent intruder analysis considers the radiological impacts to hypothetical persons who are assumed to inadvertently intrude on the Portsmouth OSWDF site after institutional control ceases 100 years after site closure. For the purposes of this analysis, we assume that the waste disposal in the OSWDF occurs at time zero, the site is under institutional control for the next 100 years, and inadvertent intrusion can occur over the following 1,000 year time period. Disposal of low-level radioactive waste in the OSWDF must meet a requirement to assess impacts on such individuals, and demonstrate that the effective dose equivalent to an intruder would not likely exceed 100 mrem per year for scenarios involving continuous exposure (i.e. chronic) or 500 mrem for scenarios involving a single acute exposure. The focus in development of exposure scenarios for inadvertent intruders was on selecting reasonable events that may occur, giving consideration to regional customs and construction practices. An important assumption in all scenarios is that an intruder has no prior knowledge of the existence of a waste disposal facility at the site. Results of the analysis show that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, resides on the site and consumes vegetables from a garden established on the site using contaminated soil (chronic agriculture scenario) would receive a maximum chronic dose of approximately 7.0 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE chronic dose limit of 100 mrem/yr. Results of the analysis also showed that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, excavates a basement in the soil that reaches the waste (acute basement construction scenario) would receive a maximum acute dose of approximately 0.25 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE acute dose limit of 500 mrem/yr. Disposal inventory

  15. HOLDUP MEASUREMENTS FOR THREE VISUAL EXAMINATION AND TRU REMEDIATION GLOVEBOX FACILITIES AT THE SAVANNAH RIVER SITE

    SciTech Connect

    Dewberry, R; Donald Pak, D

    2007-05-04

    Visual Examination (VE) gloveboxes are used to remediate transuranic waste (TRU) drums at three separate facilities at the Savannah River Site. Noncompliant items are removed before the drums undergo further characterization in preparation for shipment to the Waste Isolation Pilot Plant (WIPP). Maintaining the flow of drums through the remediation process is critical to the program's seven-days-per-week operation. Conservative assumptions are used to ensure that glovebox contamination from this continual operation is below acceptable limits. Holdup measurements using cooled HPGe spectrometers are performed in order to confirm that these assumptions are conservative. {sup 239}Pu is the main nuclide of interest; however, {sup 241}Pu, equilibrium {sup 237}Np/{sup 233}Pa and {sup 238}Pu (if detected) are typically assayed. At the Savannah River National Laboratory (SRNL) facility {sup 243,244,245}Cm are also generally observed and are always reported at either finite levels or at limits of detection. A complete assay at each of the three facilities includes a measure of TRU content in the gloveboxes and HEPA filters in the glovebox exhaust. This paper includes a description of the {gamma}-PHA acquisitions, of the modeling, and of the calculations of nuclide content. Because each of the remediation facilities is unique and ergonomically unfavorable to {gamma}-ray acquisitions, we have constructed custom detector support devices specific to each set of acquisitions. This paper includes a description and photographs of these custom devices. The description of modeling and calculations include determination and application of container and matrix photon energy dependent absorption factors and also determination and application of geometry factors relative to our detector calibration geometry. The paper also includes a discussion of our measurements accuracy using off-line assays of two SRNL HEPA filters. The comparison includes assay of the filters inside of 55-gallon

  16. Lessons learned from LNG safety research.

    PubMed

    Koopman, Ronald P; Ermak, Donald L

    2007-02-20

    During the period from 1977 to 1989, the Lawrence Livermore National Laboratory (LLNL) conducted a liquefied gaseous fuels spill effects program under the sponsorship of the US Department of Energy, Department of Transportation, Gas Research Institute and others. The goal of this program was to develop and validate tools that could be used to predict the effects of a large liquefied gas spill through the execution of large scale field experiments and the development of computer models to make predictions for conditions under which tests could not be performed. Over the course of the program, three series of LNG spill experiments were performed to study cloud formation, dispersion, combustion and rapid phase transition (RPT) explosions. The purpose of this paper is to provide an overview of this program, the lessons learned from 12 years of research as well as some recommendations for the future. The general conclusion from this program is that cold, dense gas related phenomena can dominate the dispersion of a large volume, high release rate spill of LNG especially under low ambient wind speed and stable atmospheric conditions, and therefore, it is necessary to include a detailed and validated description of these phenomena in computer models to adequately predict the consequences of a release. Specific conclusions include: * LNG vapor clouds are lower and wider than trace gas clouds and tend to follow the downhill slope of terrain due to dampened vertical turbulence and gravity flow within the cloud. Under low wind speed, stable atmospheric conditions, a bifurcated, two lobed structure develops. * Navier-Stokes models provide the most complete description of LNG dispersion, while more highly parameterized Lagrangian models were found to be well suited to emergency response applications. * The measured heat flux from LNG vapor cloud burns exceeded levels necessary for third degree burns and were large enough to ignite most flammable materials. * RPTs are of two

  17. Addendum to environmental monitoring plan Nevada Test Site and support facilities

    SciTech Connect

    1992-11-01

    This 1992 Addendum to the ``Environmental Monitoring Plan Nevada Test Site and Support Facilities -- 1991,`` Report No. DOE/NV/1 0630-28 (EMP) applies to the US Department of Energy`s (DOE`s) operations on the Continental US (including Amchitka Island, Alaska) that are under the purview of the DOE Nevada Field Office (DOE/NV). The primary purpose of these operations is the conduct of the nuclear weapons testing program for the DOE and the Department of Defense. Since 1951, these tests have been conducted principally at the Nevada Test Site (NTS), which is located approximately 100 miles northwest of Las Vegas, Nevada. In accordance with DOE Order 5400.1, this 1992 Addendum to the EMP brings together, in one document, updated information and/or new sections to the description of the environmental activities conducted at the NTS by user organizations, operations support contractors, and the US Environmental Protection Agency (EPA) originally published in the EMP. The EPA conducts both the offsite environmental monitoring program around the NTS and post-operational monitoring efforts at non-NTS test locations used between 1961 and 1973 in other parts of the continental US All of these monitoring activities are conducted under the auspices of the DOE/NV, which has the stated policy of conducting its operations in compliance with both the letter and the spirit of applicable environmental statutes, regulations, and standards.

  18. Addendum to Environmental Monitoring Plan, Nevada Test Site and Support Facilities; Addendum 2

    SciTech Connect

    1993-11-01

    This 1993 Addendum to the ``Environmental Monitoring Plan Nevada Test Site and Support Facilities -- 1991,`` Report No. DOE/NV/10630-28 (EMP) applies to the US Department of Energy`s (DOE`s) operations on the Continental US (including Amchitka Island, Alaska) that are under the purview of the DOE Nevada Operations Office (DOE/NV). The primary purpose of these operations is the conduct of the nuclear weapons testing program for the DOE and the Department of Defense. Since 1951, these tests have been conducted principally at the Nevada Test Site (NTS), which is located approximately 100 miles northwest of Las Vegas, Nevada. In accordance with DOE Order 5400.1, this 1993 Addendum to the EMP brings together, in one document, updated information and/or new sections to the description of the environmental activities conducted at the NTS by user organizations, operations support contractors, and the US Environmental Protection Agency (EPA) originally published in the EMP. The EPA conducts both the offsite environmental monitoring program around the NTS and post-operational monitoring efforts at non-NTS test locations used between 1961 and 1973 in other parts of the continental US. All of these monitoring activities are conducted under the auspices of the DOE/NV, which has the stated policy of conducting its operations in compliance with both the letter and the spirit of applicable environmental statutes, regulations, and standards.

  19. Annual report for RCRA groundwater monitoring projects at Hanford Site facilities for 1993

    SciTech Connect

    Not Available

    1994-02-01

    This report presents the annual hydrogeologic evaluation of 20 Resource Conservation and Recovery Act of 1976 groundwater monitoring projects and 1 nonhazardous waste facility at the US Department of Energy`s Hanford Site. Most of the projects no longer receive dangerous waste; a few projects continue to receive dangerous waste constituents for treatment, storage, or disposal. The 20 RCRA projects comprise 30 waste management units. Ten of the units are monitored under groundwater quality assessment status because of elevated levels of indicator parameters. The impact of those units on groundwater quality, if any, is being investigated. If dangerous waste or waste constituents have entered groundwater, their concentration, distribution, and rate of migration are evaluated. Groundwater is monitored at the other 20 units to detect contamination, should it occur. This report provides an interpretation of groundwater data collected at the waste management units between October 1992 and September 1993. Recent groundwater quality is also described for the 100, 200, 300, and 600 Areas and for the entire Hanford Site. Widespread contaminants include nitrate, chromium, carbon tetrachloride, tritium, and other radionuclides.

  20. Application of GIS in site selection for nuclear waste disposal facility

    SciTech Connect

    Sheng, G.; Luginaah, I.N.; Sorrell, J.

    1996-12-01

    Whether designing a new facility or investigating, potential contaminant migration at an existing site, proper characterization of the subsurface conditions and their interaction with surface features is critical to the process. The Atomic Energy Control Board, states in its regulatory document R-104 that, {open_quotes}For the long-term management of radioactive wastes, the preferred approach is disposal, a permanent method of management in which there is no intention of retrieval and which, ideally uses techniques and designs that do not rely for their success on long-term institutional control beyond a reasonable period of time{close_quotes}. Thus although storage is safe, eventually disposal is necessary to avoid long-term reliance on continuing care and attention, such as monitoring and maintenance. In Canada, the concept being proposed by Atomic Energy of Canada Limited (AECL) involves disposal in deep underground repositories in intrusive igneous rock. The aim of this concept as a disposal method is to build multiple barriers that would protect humans and the natural environment from contaminants in the radioactive waste. The multiple barriers include the geosphere, which consists of the rock, any sediments overlying the rock, and the groundwater. Nevertheless, immediate, as well as long-term, consequences, including, risk involved with technological systems and the inherent uncertainty of any forecast, make the prediction and analysis tasks of increasing importance. This uncertainty in the area of nuclear waste disposal is leading to growing concerns about nuclear waste site selection.

  1. 75 FR 51989 - Southern LNG Company, L.L.C.; Notice of Application

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-08-24

    ... Energy Regulatory Commission Southern LNG Company, L.L.C.; Notice of Application August 16, 2010. Take notice that on August 4, 2010, Southern LNG Company, L.L.C. (Southern LNG), Post Office Box 2563... Regulatory, Southern LNG Company, L.L.C., 569 Brookwood Village, Suite 501, Birmingham, Alabama 35209 at...

  2. 78 FR 20312 - Downeast LNG, Inc., Downeast Pipeline, LLC.; Notice of Availability of the Supplemental Draft...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-04-04

    ... Energy Regulatory Commission Downeast LNG, Inc., Downeast Pipeline, LLC.; Notice of Availability of the Supplemental Draft Environmental Impact Statement for the Proposed Downeast LNG Project The staff of the... Impact Statement (EIS) for the Downeast LNG Project, proposed by Downeast LNG, Inc. and Downeast...

  3. Research on energy efficiency design index for sea-going LNG carriers

    NASA Astrophysics Data System (ADS)

    Lin, Yan; Yu, Yanyun; Guan, Guan

    2014-12-01

    This paper describes the characteristics of liquefied natural gas (LNG) carriers briefly. The LNG carrier includes power plant selection, vapor treatment, liquid cargo tank type, etc. Two parameters—fuel substitution rate and recovery of boil of gas (BOG) volume to energy efficiency design index (EEDI) formula are added, and EEDI formula of LNG carriers is established based on ship EEDI formula. Then, based on steam turbine propulsion device of LNG carriers, mathematical models of LNG carriers' reference line value are established in this paper. By verification, the EEDI formula of LNG carriers described in this paper can provide a reference for LNG carrier EEDI calculation and green shipbuilding.

  4. Exploratory shaft facility: It`s role in the characterization of the Yucca Mountain site for a potential nuclear repository

    SciTech Connect

    Kalia, H.N.; Merson, T.J.

    1990-03-01

    The US Department of Energy is characterizing Yucca Mountain, Nevada, to assess its suitability as a potential site for the permanent disposal of high-level radioactive waste from nuclear power plants and defense related activities. The assessment activities include surface investigations, drill holes from the surface, and an underground facility for in situ characterization tests. This underground exploratory shaft facility is being designed to meet the criteria for characterizing the mountain as described in the Site Characterization Plan. 9 refs., 9 figs., 1 tab.

  5. Calendar year 2007 annual site environmental report for Tonopah Test Range, Nevada and Kauai Test Facility, Hawaii,

    SciTech Connect

    Agogino, Karen; Sanchez, Rebecca

    2008-09-30

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation (Sandia), a wholly owned subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE)/National Nuclear Security Administration (NNSA), through the Sandia Site Offi ce (SSO), in Albuquerque, NM, administers the contract and oversees contractor operations at TTR and KTF. Sandia manages and conducts operations at TTR in support of the DOE/NNSA’s Weapons Ordnance Program and has operated the site since 1957. Washington Group International subcontracts to Sandia in administering most of the environmental programs at TTR. Sandia operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2007. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia is responsible only for those environmental program activities related to its operations. The DOE/NNSA/Nevada Site Offi ce (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 450.1, Environmental Protection Program (DOE 2007a) and DOE Manual 231.1-1A, Environment, Safety, and Health Reporting Manual (DOE 2007).

  6. Calendar year 2003 : annual site enviromental report for Tonopah Test Range, Nevada and Kauai Test Facility, Hawaii.

    SciTech Connect

    Wagner, Katrina; Sanchez, Rebecca V.; Mayeux, Lucie; Koss, Susan I.; Salinas, Stephanie A.

    2004-09-01

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, manages TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2003. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 450.1, Environmental Protection Program (DOE 2003) and DOE Order 231.1 Chg 2., Environment, Safety, and Health Reporting (DOE 1996).

  7. Calendar year 2002 annual site environmental report for Tonopah Test Range, Nevada and Kauai Test Facility, Hawaii.

    SciTech Connect

    Wagner, Katrina; Sanchez, Rebecca V.; Mayeux, Lucie; Koss, Susan I.; Salinas, Stephanie A.

    2003-09-01

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, oversees TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2002. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 5400.1, General Environmental Protection Program (DOE 1990) and DOE Order 231.1, Environment, Safety, and Health Reporting (DOE 1996).

  8. Rough order of magnitude cost estimate for immobilization of 50 MT of plutonium using existing facilities at the Savannah River site: alternative 12B

    SciTech Connect

    DiSabatino, A., LLNL

    1998-06-01

    The purpose of this Cost Estimate Report is to identify preliminary capital and operating costs for a facility to immobilize 50 metric tons of plutonium using ceramic in an existing facility (221-F) at an Savannah River Site (SRS).

  9. Decommissioning an Active Historical Reactor Facility at the Savannah River Site - 13453

    SciTech Connect

    Bergren, Christopher L.; Long, J. Tony; Blankenship, John K.; Adams, Karen M.

    2013-07-01

    The Savannah River Site (SRS) is an 802 square-kilometer United States Department of Energy (US DOE) nuclear facility located along the Savannah River near Aiken, South Carolina, where Management and Operations are performed by Savannah River Nuclear Solutions (SRNS). In 2004, DOE recognized SRS as structure within the Cold War Historic District of national, state and local significance composed of the first generation of facilities constructed and operated from 1950 through 1989 to produce plutonium and tritium for our nation's defense. DOE agreed to manage the SRS 105-C Reactor Facility as a potentially historic property due to its significance in supporting the U.S. Cold War Mission and for potential for future interpretation. This reactor has five primary areas within it, including a Disassembly Basin (DB) that received irradiated materials from the reactor, cooled them and prepared the components for loading and transport to a Separation Canyon for processing. The 6,317 square meter area was divided into numerous work/storage areas. The walls between the individual basin compartments have narrow vertical openings called 'slots' that permit the transfer of material from one section to another. Data indicated there was over 830 curies of radioactivity associated with the basin sediments and approximately 9.1 M liters of contaminated water, not including a large quantity of activated reactor equipment, scrap metal, and debris on the basin floor. The need for an action was identified in 2010 to reduce risks to personnel in the facility and to eliminate the possible release of contaminants into the environment. The release of DB water could potentially migrate to the aquifer and contaminate groundwater. DOE, its regulators [U. S. Environmental Protection Agency (USEPA)-Region 4 and the South Carolina Department of Health and Environmental Control (SCDHEC)] and the SC Historical Preservation Office (SHPO) agreed/concurred to perform a non-time critical removal

  10. GIS analysis of the siting criteria for the Mixed and Low-Level Waste Treatment Facility and the Idaho Waste Processing Facility

    SciTech Connect

    Hoskinson, R.L.

    1994-01-01

    This report summarizes a study conducted using the Arc/Info{reg_sign} geographic information system (GIS) to analyze the criteria used for site selection for the Mixed and Low-Level Waste Treatment Facility (MLLWTF) and the Idaho Waste Processing Facility (IWPF). The purpose of the analyses was to determine, based on predefined criteria, the areas on the INEL that best satisfied the criteria. The coverages used in this study were produced by importing the AutoCAD files that produced the maps for a pre site selection draft report into the GIS. The files were then converted to Arc/Info{reg_sign} GIS format. The initial analysis was made by considering all of the criteria as having equal importance in determining the areas of the INEL that would best satisfy the requirements. Another analysis emphasized four of the criteria as ``must`` criteria which had to be satisfied. Additional analyses considered other criteria that were considered for, but not included in the predefined criteria. This GIS analysis of the siting criteria for the IWPF and MLLWTF provides a logical, repeatable, and defensible approach to the determination of candidate locations for the facilities. The results of the analyses support the location of the Candidate Locations.

  11. Energy infrastructure of the United States and projected siting needs: Scoping ideas, identifying issues and options. Draft report of the Department of Energy Working Group on Energy Facility Siting to the Secretary

    SciTech Connect

    Not Available

    1993-12-01

    A Department of Energy (DOE) Working Group on Energy Facility Siting, chaired by the Policy Office with membership from the major program and staff offices of the Department, reviewed data regarding energy service needs, infrastructure requirements, and constraints to siting. The Working Group found that the expeditious siting of energy facilities has important economic, energy, and environmental implications for key Administration priorities.

  12. Hanford Site Near-Facility Environmental Monitoring Data Report for Calendar Year 2007- Appendix 2

    SciTech Connect

    Perkins, Craig J.; Dorsey, Michael; Mckinney, Stephen M.; Wilde, Justin W.; Duncan, Joanne P.

    2008-10-13

    Near-facility environmental monitoring is defined as monitoring near facilities that have the potential to discharge or have discharged, stored, or disposed of radioactive or hazardous materials. Monitoring locations are associated with nuclear facilities such as the Plutonium Finishing Plant (PFP), Canister Storage Building (CSB), and the K Basins; inactive nuclear facilities such as N Reactor and the Plutonium-Uranium Extraction (PUREX) Facility; and waste storage or disposal facilities such as burial grounds, cribs, ditches, ponds, tank farms, and trenches. Much of the monitoring consists of collecting and analyzing environmental samples and methodically surveying areas near facilities. The program is also designed to evaluate acquired analytical data, determine the effectiveness of facility effluent monitoring and controls, assess the adequacy of containment at waste disposal units, and detect and monitor unusual conditions.

  13. Hanford Site Near-Facility Environmental Monitoring Data Report for Calendar Year 2008

    SciTech Connect

    Perkins, Craig J.; Dorsey, Michael C.; Mckinney, Stephen M.; Wilde, Justin W.; Poston, Ted M.

    2009-09-15

    Near-facility environmental monitoring is defined as monitoring near facilities that have the potential to discharge or have discharged, stored, or disposed of radioactive or hazardous materials. Monitoring locations are associated with nuclear facilities such as the Plutonium Finishing Plant, Canister Storage Building, and the K Basins; inactive nuclear facilities such as N Reactor and the Plutonium-Uranium Extraction (PUREX) Facility; and waste storage or disposal facilities such as burial grounds, cribs, ditches, ponds, tank farms, and trenches. Much of the monitoring consists of collecting and analyzing environmental samples and methodically surveying areas near facilities. The program is also designed to evaluate acquired analytical data, determine the effectiveness of facility effluent monitoring and controls, assess the adequacy of containment at waste disposal units, and detect and monitor unusual conditions.

  14. Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site

    SciTech Connect

    N /A

    2003-11-28

    This document is a site-specific environmental impact statement (EIS) for construction and operation of a proposed depleted uranium hexafluoride (DUF{sub 6}) conversion facility at the U.S. Department of Energy (DOE) Portsmouth site in Ohio (Figure S-1). The proposed facility would convert the DUF{sub 6} stored at Portsmouth to a more stable chemical form suitable for use or disposal. The facility would also convert the DUF{sub 6} from the East Tennessee Technology Park (ETTP) site near Oak Ridge, Tennessee. In a Notice of Intent (NOI) published in the Federal Register on September 18, 2001 (Federal Register, Volume 66, page 48123 [66 FR 48123]), DOE announced its intention to prepare a single EIS for a proposal to construct, operate, maintain, and decontaminate and decommission two DUF{sub 6} conversion facilities at Portsmouth, Ohio, and Paducah, Kentucky, in accordance with the National Environmental Policy Act of 1969 (NEPA) (United States Code, Title 42, Section 4321 et seq. [42 USC 4321 et seq.]) and DOE's NEPA implementing procedures (Code of Federal Regulations, Title 10, Part 1021 [10 CFR Part 1021]). Subsequent to award of a contract to Uranium Disposition Services, LLC (hereafter referred to as UDS), Oak Ridge, Tennessee, on August 29, 2002, for design, construction, and operation of DUF{sub 6} conversion facilities at Portsmouth and Paducah, DOE reevaluated its approach to the NEPA process and decided to prepare separate site-specific EISs. This change was announced in a Federal Register Notice of Change in NEPA Compliance Approach published on April 28, 2003 (68 FR 22368); the Notice is included as Attachment B to Appendix C of this EIS. This EIS addresses the potential environmental impacts from the construction, operation, maintenance, and decontamination and decommissioning (D&D) of the proposed conversion facility at three alternative locations within the Portsmouth site; from the transportation of all ETTP cylinders (DUF{sub 6}, low-enriched UF6

  15. CHARACTERIZING DOE HANFORD SITE WASTE ENCAPSULATION STORAGE FACILITY CELLS USING RADBALL

    SciTech Connect

    Farfan, E.; Coleman, R.

    2011-03-31

    RadBall{trademark} is a novel technology that can locate and quantify unknown radioactive hazards within contaminated areas, hot cells, and gloveboxes. The device consists of a colander-like outer tungsten collimator that houses a radiation-sensitive polymer semi-sphere. The collimator has a number of small holes with tungsten inserts; as a result, specific areas of the polymer are exposed to radiation becoming increasingly more opaque in proportion to the absorbed dose. The polymer semi-sphere is imaged in an optical computed tomography scanner that produces a high resolution 3D map of optical attenuation coefficients. A subsequent analysis of the optical attenuation data using a reverse ray tracing or backprojection technique provides information on the spatial distribution of gamma-ray sources in a given area forming a 3D characterization of the area of interest. RadBall{trademark} was originally designed for dry deployments and several tests, completed at Savannah River National Laboratory and Oak Ridge National Laboratory, substantiate its modeled capabilities. This study involves the investigation of the RadBall{trademark} technology during four submerged deployments in two water filled cells at the DOE Hanford Site's Waste Encapsulation Storage Facility.

  16. Possible explosive compounds in the Savannah River Site waste tank farm facilities

    SciTech Connect

    Hobbs, D.T.

    1992-03-15

    Based on a comparison of the known constituents in high-level nuclear waste stored at the Savannah River Site (SRS) and explosive compounds reported in the literature, only two classes of explosive compounds (metal NO{sub x} compounds and organic compounds) were identified as requiring further work to determine if they exist in the waste, and if so, in what quantities. Of the fourteen classes of explosive compounds identified as conceivably being present in tank farm operations, nine classes (metal fulminates, metal azides, halogen compounds, metal-amine complexes, nitrate/oxalate mixtures, metal oxalates, metal oxohalogenates, metal cyanides/cyanates, and peroxides) are not a hazard because these classes of compounds cannot be formed or accumulated in sufficient quantity, or they are not reactive at the conditions which exist in the tank farm facilities. Three of the classes (flammable gases, metal nitrides, and ammonia compounds and derivatives) are known to have the potential to build up to concentrations at which an observable reaction might occur. Controls have been in place for some time to limit the formation or control the concentration of these classes of compounds. A comprehensive list of conceivable explosive compounds is provided in Appendix 3.

  17. An astronomical site survey at the Barcroft Facility of the White Mountain Research Station

    NASA Astrophysics Data System (ADS)

    Marvil, J.; Ansmann, M.; Childers, J.; Cole, T.; Davis, G. V.; Hadjiyska, E.; Halevi, D.; Heimberg, G.; Kangas, M.; Levy, A.; Leonardi, R.; Lubin, P.; Meinhold, P.; O'Neill, H.; Parendo, S.; Quetin, E.; Stebor, N.; Villela, T.; Williams, B.; Wuensche, C. A.; Yamaguchi, K.

    2006-01-01

    We present a distillation of weather and sky condition data collected from September 2001 to November 2004 at the University of California White Mountain Research Station, Barcroft Facility. Our conclusion is that Barcroft is an excellent site for microwave observation because of a cold microwave zenith temperature, low precipitable water, and a high percentage of clear days. The solar intensity was above 80% of the theoretical maximum 66% of the time. About 71% of the daytime, the cloud cover was acceptable for observing. Median precipitable water vapor was estimated to be 1.75 mm. We measure a median opacity at 225 GHz of 0.11, which corresponds to a transmission of 89.6%. Zenith sky temperatures were determined to be 9.0 ± 0.2 K and 10.0 ± 0.6 K in Q-band (38-46 GHz) and W-band (81-98 GHz), respectively. We also demonstrate a correlation between measurements of precipitable water vapor from a weatherstation and a 225 GHz radiometer.

  18. Near-surface test facility. Phase I. Geologic site characterization report

    SciTech Connect

    Moak, D.J.; Wintczak, T.M.

    1980-08-01

    The report is a description of the geology and characterization of the rock mass of the area in which the Phase I qualification tests at the Near-Surface Test Facility (NSTF) are being performed. The NSTF is located on Gable Mountain within the Hanford Site near Richland, Washington. It is located in the entablature of the Pomona Member, an upper flow in the Columbia River Basalt Group, and is approximately 150 feet (47.5 meters) below the surface. Core logging from the instrument boreholes coupled with joint mapping, statistics, and other test data provided the basis for a detailed characterization of the 16-foot x 20-foot x 28-foot (5-meter x 6-meter x 9-meter) rock masses surrounding Full-Scale Heater Tests No. 1 and No. 2. The Pomona entablature contains three joint sets delineated by their degree of dip, each with apertures averaging 0.25 millimeter and having no preferred strike orientation. Although joint frequencies in the study area exceed 4 joints per foot (13 per meter), the rock-mass classification rating is good.

  19. Get accurate LNG densities with COSTALD

    SciTech Connect

    Hankinson, R.W.; Coker, T.A.; Thomson, G.H.

    1982-04-01

    A fine-tuned version of the COSTALD correlation predicts the densities for 40 LNG-type mixtures at an average absolute error of 0.078%. When tested against 285 points of low-temperature data collected by the US National Bureau of Standards, the average error was 0.199%, compared with a 0.227% error obtained with the NBS's McCarty-Klosek-McKinley technique. The COSTALD correlation relates the saturated molar volume of a liquid to a characteristic volume, the reduced temperature, and, a modified acentric factor for each stream component. The fine-tuning involved adding several interaction parameters dervied from binary density data.

  20. Submarine LNG tanker concept for the Arctic

    SciTech Connect

    Veliotis, P.T.; Reitz, S.

    1981-01-01

    If LNG tankers could travel underwater, they could transport natural gas from Arctic regions year-round. General Dynamics has designed just such a tanker - a 140,000-m/sup 3/ submarine with a methane-fired steam-propulsion system that uses recirculated exhaust gas injected with oxygen to sustain combustion. (Nuclear power would be cheaper but might not be practical if new regulations are imposed.) Developed from parametric variations in cargo capacity, hull material, and ballasting, the design identifies such ship characteristics as length, beam, depth, cargo-system arrangement, speed, and ship control. An economic analysis indicates the concept's competitiveness with both pipelines and icebreaking tankers.

  1. 77 FR 51811 - Draft Guidance for Industry on Self-Identification of Generic Drug Facilities, Sites, and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-27

    ... HUMAN SERVICES Food and Drug Administration Draft Guidance for Industry on Self-Identification of Generic Drug Facilities, Sites, and Organizations; Availability AGENCY: Food and Drug Administration, HHS. ACTION: Notice. SUMMARY: The Food and Drug Administration (FDA) is announcing the availability of a...

  2. Closure Report for Corrective Action Unit 116: Area 25 Test Cell C Facility, Nevada National Security Site, Nevada

    SciTech Connect

    NSTec Environmental Restoration

    2011-09-29

    This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 116, Area 25 Test Cell C Facility. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 [as amended March 2010]). CAU 116 consists of the following two Corrective Action Sites (CASs), located in Area 25 of the Nevada National Security Site: (1) CAS 25-23-20, Nuclear Furnace Piping and (2) CAS 25-41-05, Test Cell C Facility. CAS 25-41-05 consisted of Building 3210 and the attached concrete shield wall. CAS 25-23-20 consisted of the nuclear furnace piping and tanks. Closure activities began in January 2007 and were completed in August 2011. Activities were conducted according to Revision 1 of the Streamlined Approach for Environmental Restoration Plan for CAU 116 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2008). This CR provides documentation supporting the completed corrective actions and provides data confirming that closure objectives for CAU 116 were met. Site characterization data and process knowledge indicated that surface areas were radiologically contaminated above release limits and that regulated and/or hazardous wastes were present in the facility.

  3. Advanced technologies for maintenance of electrical systems and equipment at the Savannah River Site Defense Waste Processing Facility

    SciTech Connect

    Husler, R.O. ); Weir, T.J. )

    1991-01-01

    An enhanced maintenance program is being established to characterize and monitor cables, components, and process response at the Savannah River Site, Defense Waste Processing Facility. This facility was designed and constructed to immobilize the radioactive waste currently stored in underground storage tanks and is expected to begin operation in 1993. The plant is initiating the program to baseline and monitor instrument and control (I C) and electrical equipment, remote process equipment, embedded instrument and control cables, and in-cell jumper cables used in the facility. This program is based on the electronic characterization and diagnostic (ECAD) system which was modified to include process response analysis and to meet rigid Department of Energy equipment requirements. The system consists of computer-automated, state-of-the-art electronics. The data that are gathered are stored in a computerized database for analysis, trending, and troubleshooting. It is anticipated that the data which are gathered and trended will aid in life extension for the facility.

  4. Particle- and Gaseous Emissions from an LNG Powered Ship.

    PubMed

    Anderson, Maria; Salo, Kent; Fridell, Erik

    2015-10-20

    Measurements of particle number and mass concentrations and number size distribution of particles from a ship running on liquefied natural gas (LNG) were made on-board a ship with dual-fuel engines installed. Today there is a large interest in LNG as a marine fuel, as a means to comply with sulfur and NOX regulations. Particles were studied in a wide size range together with measurements of other exhaust gases under different engine loads and different mixtures of LNG and marine gas oil. Results from these measurements show that emissions of particles, NOX, and CO2 are considerably lower for LNG compared to present marine fuel oils. Emitted particles were mainly of volatile character and mainly had diameters below 50 nm. Number size distribution for LNG showed a distinct peak at 9-10 nm and a part of a peak at diameter 6 nm and below. Emissions of total hydrocarbons and carbon monoxide are higher for LNG compared to present marine fuel oils, which points to the importance of considering the methane slip from combustion of LNG. PMID:26422536

  5. Characterization and remediation of soil prior to construction of an on-site disposal facility at Fernald

    SciTech Connect

    Hunt, A.; Jones, G.; Janke, R.; Nelson, K.

    1998-03-01

    During the production years at the Feed Materials Production Center (FMPC), the soil of the site and the surrounding areas was surficially impacted by airborne contamination. The volume of impacted soil is estimated at 2.2 million cubic yards. During site remediation, this contamination will be excavated, characterized, and disposed of. In 1986 the US Environmental Protection Agency (EPA) and the Department of Energy (DOE) entered into a Federal Facility Compliance Agreement (FFCA) covering environmental impacts associated with the FMPC. A site wide Remedial Investigation/Feasibility Study (RI/FS) was initiated pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act, as amended by the Superfund Amendments and Reauthorization Act (CERCLA). The DOE has completed the RI/FS process and has received approval of the final Records of Decision. The name of the facility was changed to the Fernald Environmental Management Project (FEMP) to emphasize the change in mission to environmental restoration. Remedial actions which address similar scopes of work or types of contaminated media have been grouped into remedial projects for the purpose of managing the remediation of the FEMP. The Soil Characterization and Excavation Project (SCEP) will address the remediation of FEMP soils, certain waste units, at- and below-grade material, and will certify attainment of the final remedial limits (FRLs) for the FEMP. The FEMP will be using an on-site facility for low level radioactive waste disposal. The facility will be an above-ground engineered structure constructed of geological material. The area designated for construction of the base of the on-site disposal facility (OSDF) is referred to as the footprint. Contaminated soil within the footprint must be identified and remediated. Excavation of Phase 1, the first of seven remediation areas, is complete.

  6. Summary environmental site assessment report for the U.S. Department of Energy Oxnard Facility, Oxnard, California

    SciTech Connect

    1996-02-01

    This report summarizes the investigations conducted by Rust Geotech at the U.S. Department of Energy (DOE) Oxnard facility, 1235 East Wooley Road, Oxnard, California. These investigations were designed to locate, identify, and characterize any regulated contaminated media on the site. The effort included site visits; research of ownership, historical uses of the Oxnard facility and adjacent properties, incidences of and investigations for contaminants on adjacent properties, and the physical setting of the site; sampling and analysis; and reporting. These investigations identified two friable asbestos gaskets on the site, which were removed, and nonfriable asbestos, which will be managed through the implementation of an asbestos management plan. The California primary drinking water standards were exceeded for aluminum on two groundwater samples and for lead in one sample collected from the shallow aquifer underlying the site; remediation of the groundwater in this aquifer is not warranted because it is not used. Treated water is available from a municipal water system. Three sludge samples indicated elevated heavy metals concentrations; the sludge must be handled as a hazardous waste if disposed. Polychlorinated biphenyls (PCBs) were detected at concentrations below remediation criteria in facility soils at two locations. In accordance with U.S. Environmental Protection Agency (EPA) and State of California guidance, remediation of the PCBs is not required. No other hazardous substances were detected in concentrations exceeding regulatory limits.

  7. Rocketdyne division, environmental monitoring and facility effluent. Annual Report, De Soto and Santa Susana Field Laboratories Sites 1987

    SciTech Connect

    Moore, J. D.

    1988-03-01

    Environmental and facility effluent radioactivity monitoring at the Rocketdyne Division of Rockwell International is performed by the Radiation and Nuclear Safety Group of the Health, Safety, and Environment Department. Soil and surface water are routinely sampled to a distance of 10 miles from Division sites. Ground water from site supply water wells and other test wells is periodically sampled to measure radioactivity in these waters. Continuous ambient air sampling and direct radiation monitoring by thermoluminescent dosimetry are performed at several on-site and off-site locations for measuring airborne radioactivity concentrations and site ambient radiation levels. Radioactivity in effluents discharged to the atmosphere from nuclear facilities is continually sampled and monitored to ensure that amounts released to uncontrolled areas are below appropriate limited and to identify processes that rnay require additional engineering safeguards to minimize radioactivity in such discharges. In addition, selected nonradioactive chemical constituent concentrations in surface water discharged to uncontrolled areas are determined. The environmental radioactivity reported herein is attributed to natural sources and to residual fallout of radioactive material from past atmospheric testing of nuclear devices. Work in nuclear energy research and development in what has become the Rocketdyne Division of Rockwell International Corporation began in 1946. In addition to a broad spectrum of conventional programs in rocket propulsion, utilization of space, and national defense, Rocketdyne is working on the design, development, and testing of components and systems for central station nuclear power plants, the decladding of irradiated nuclear fuel, and the decontamination and decommissioning of facilities.

  8. A dispersion safety factor for LNG vapor clouds.

    PubMed

    Vílchez, Juan A; Villafañe, Diana; Casal, Joaquim

    2013-02-15

    The growing importance of liquefied natural gas (LNG) to global energy demand has increased interest in the possible hazards associated with its storage and transportation. Concerning the event of an LNG spill, a study was performed on the relationship between the distance at which the lower flammability limit (LFL) concentration occurs and that corresponding to the visible contour of LNG vapor clouds. A parameter called the dispersion safety factor (DSF) has been defined as the ratio between these two lengths, and two expressions are proposed to estimate it. During an emergency, the DSF can be a helpful parameter to indicate the danger of cloud ignition and flash fire. PMID:23305750

  9. Four band differential radiometer for monitoring LNG vapors

    NASA Astrophysics Data System (ADS)

    Simmonds, J. J.

    1981-06-01

    The development by JPL of a four band differential radiometer (FBDR) which is capable of providing a fast rate of response, accurate measurements of methane, ethane, and propane concentrations on the periphery of a dispersing LNG cloud. The FBDR is a small, low power, lightweight, portable instrument system that uses differential absorption of near infrared radiation by the LNG cloud as a technique for the determination of concentration of the three gases as the LNG cloud passes the instrument position. Instrument design and data analysis approaches are described. The data obtained from the FBDR prototype instrument system deployed in an instrument array during two 40 cubic meter spill tests are discussed.

  10. Four band differential radiometer for monitoring LNG vapors

    NASA Technical Reports Server (NTRS)

    Simmonds, J. J.

    1981-01-01

    The development by JPL of a four band differential radiometer (FBDR) which is capable of providing a fast rate of response, accurate measurements of methane, ethane, and propane concentrations on the periphery of a dispersing LNG cloud. The FBDR is a small, low power, lightweight, portable instrument system that uses differential absorption of near infrared radiation by the LNG cloud as a technique for the determination of concentration of the three gases as the LNG cloud passes the instrument position. Instrument design and data analysis approaches are described. The data obtained from the FBDR prototype instrument system deployed in an instrument array during two 40 cubic meter spill tests are discussed.

  11. Thermoelectric Power Conversion System Combined with LNG Vaporizer

    NASA Astrophysics Data System (ADS)

    Kambe, Mitsuru; Morita, Ryo; Omoto, Kazuyuki; Koji, Yasuhiro; Yoshida, Tatsuo; Noishiki, Koji

    A conceptual design of the thermoelectric power conversion system combined with open rack type LNG (liquefied natural gas) vaporizer to make use of cold heat of LNG is presented. The system performance analysis has been made based on the thermoelectric module performance data obtained at the cryogenic thermoelectric (CTE) test rig which could realize temperature and fluid dynamic condition of the open rack type LNG vaporizer. Conventional bismuth-telluride thermoelectric modules were tested, however, each module is encapsulated in the stainless steel container to achieve water proof. Electricity production cost evaluation of the system is also discussed.

  12. Siting algae cultivation facilities for biofuel production in the United States: trade-offs between growth rate, site constructability, water availability, and infrastructure

    SciTech Connect

    Venteris, Erik R.; McBride, Robert; Coleman, Andre M.; Skaggs, Richard; Wigmosta, Mark S.

    2014-02-21

    Locating sites for new algae cultivation facilities is a complex task. The climate must support high growth rates, and cultivation ponds require appropriate land and water resources as well as key utility and transportation infrastructure. We employ our spatiotemporal Biomass Assessment Tool (BAT) to select promising locations based on the open-pond cultivation of Arthrospira sp. and a strain of the order Desmidiales. 64,000 potential sites across the southern United States were evaluated. We progressively apply a range of screening criteria and track their impact on the number of selected sites, geographic location, and biomass productivity. Both strains demonstrate maximum productivity along the Gulf of Mexico coast, with the highest values on the Florida peninsula. In contrast, sites meeting all selection criteria for Arthrospira were located along the southern coast of Texas and for Desmidiales were located in Louisiana and southern Arkansas. Site selection was driven mainly by the lack of oil pipeline access in Florida and elevated groundwater salinity in southern Texas. The requirement for low salinity freshwater (<400 mg L-1) constrained Desmidiales locations; siting flexibility is greater for salt-tolerant species such as Arthrospira. Combined siting factors can result in significant departures from regions of maximum productivity but are within the expected range of site-specific process improvements.

  13. The National Criticality Experiments Research Center at the Device Assembly Facility, Nevada National Security Site: Status and Capabilities, Summary Report

    SciTech Connect

    S. Bragg-Sitton; J. Bess; J. Werner

    2011-09-01

    The National Criticality Experiments Research Center (NCERC) was officially opened on August 29, 2011. Located within the Device Assembly Facility (DAF) at the Nevada National Security Site (NNSS), the NCERC has become a consolidation facility within the United States for critical configuration testing, particularly those involving highly enriched uranium (HEU). The DAF is a Department of Energy (DOE) owned facility that is operated by the National Nuclear Security Agency/Nevada Site Office (NNSA/NSO). User laboratories include the Lawrence Livermore National Laboratory (LLNL) and Los Alamos National Laboratory (LANL). Personnel bring their home lab qualifications and procedures with them to the DAF, such that non-site specific training need not be repeated to conduct work at DAF. The NNSS Management and Operating contractor is National Security Technologies, LLC (NSTec) and the NNSS Safeguards and Security contractor is Wackenhut Services. The complete report provides an overview and status of the available laboratories and test bays at NCERC, available test materials and test support configurations, and test requirements and limitations for performing sub-critical and critical tests. The current summary provides a brief summary of the facility status and the method by which experiments may be introduced to NCERC.

  14. Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site

    SciTech Connect

    N /A

    2003-11-28

    This document is a site-specific environmental impact statement (EIS) for construction and operation of a proposed depleted uranium hexafluoride (DUF{sub 6}) conversion facility at the U.S. Department of Energy (DOE) Paducah site in northwestern Kentucky (Figure S-1). The proposed facility would convert the DUF{sub 6} stored at Paducah to a more stable chemical form suitable for use or disposal. In a Notice of Intent (NOI) published in the ''Federal Register'' (FR) on September 18, 2001 (''Federal Register'', Volume 66, page 48123 [66 FR 48123]), DOE announced its intention to prepare a single EIS for a proposal to construct, operate, maintain, and decontaminate and decommission two DUF{sub 6} conversion facilities at Portsmouth, Ohio, and Paducah, Kentucky, in accordance with the National Environmental Policy Act of 1969 (NEPA) (''United States Code'', Title 42, Section 4321 et seq. [42 USC 4321 et seq.]) and DOE's NEPA implementing procedures (''Code of Federal Regulations'', Title 10, Part 1021 [10 CFR Part 1021]). Subsequent to award of a contract to Uranium Disposition Services, LLC (hereafter referred to as UDS), Oak Ridge, Tennessee, on August 29, 2002, for design, construction, and operation of DUF{sub 6} conversion facilities at Portsmouth and Paducah, DOE reevaluated its approach to the NEPA process and decided to prepare separate site-specific EISs. This change was announced in a ''Federal Register'' Notice of Change in NEPA Compliance Approach published on April 28, 2003 (68 FR 22368); the Notice is included as Attachment B to Appendix C of this EIS. This EIS addresses the potential environmental impacts from the construction, operation, maintenance, and decontamination and decommissioning (D&D) of the proposed conversion facility at three alternative locations within the Paducah site; from the transportation of depleted uranium conversion products to a disposal facility; and from the transportation, sale, use, or disposal of the fluoride

  15. FACILITY UPGRADES FOR RECEIPT FROM ACTINIDE REMOVAL AND MODULAR CAUSTIC SIDE SOLVENT EXTRACTION PROCESSES AT THE SAVANNAH RIVER SITE

    SciTech Connect

    Fellinger, T; Stephen Phillips, S; Benjamin Culbertson, B; Beverly02 Davis, B; Aaron Staub, A

    2007-02-13

    The Savannah River Site (SRS) is currently on an aggressive program to empty its High Level Waste (HLW) tanks and immobilize its radioactive waste into a durable borosilicate glass in the Defense Waste Processing Facility (DWPF). As a part of that program, two new processes will be brought on-line to assist in emptying the HLW tanks. These processes are in addition to the current sludge removal process and are called the Actinide Removal Process (ARP) and the Modular Caustic Side Solvent Extraction (MCU) Process. In order to accept and process the streams generated from these two new processes, several facility modifications are required and are broken down into several projects. These projects are handling the facility modifications required for the Tank Farm (241-96H), and DWPF vitrification facility (221-S), and DWPF ancillary facilities (511-S, and 512-S). Additional modifications to the 221-S building were required to address the flammability concern from the solvent carryover from the MCU process. This paper will describe a summary of the modifications impacting the 511-S, 512-S, and the 221-S facilities in order to receive the new streams from the ARP and MCU processes at the DWPF.

  16. Confirmatory radiological survey for the 190-C Main Pumphouse Facility decommissioning at the Hanford Site, Richland, Washington

    SciTech Connect

    Coleman, R.L.; Forbes, G.H.

    1997-06-01

    An independent assessment of remedial action activities at the 190-C Main Pumphouse Facility at the Hanford Site, Richland, Washington has been accomplished by the Oak Ridge National Laboratory Environmental Assessments Group. The purpose of the assessment was to confirm the site`s compliance with DOE applicable guidelines and provide independent measurements of the activity levels in the 190-C trenches and 105-C process water tunnels. The assessment included reviews of the Decontamination and Decommissioning Plan and data provided in the pre- and post-remedial action surveys. An on-site independent verification survey of the facility was conducted during the period of November 19--21, 1996. The independent verification survey included beta and gamma scans, smears for removable contamination, and direct measurements for beta-gamma activity in the trenches and tunnels. The same measurements and scans, with the addition of alpha measurements, were performed on the floor in the filter repair confinement area. The facility was also spot-checked for direct alpha and beta-gamma activity.

  17. Siting algae cultivation facilities for biofuel production in the United States: trade-offs between growth rate, site constructability, water availability, and infrastructure.

    PubMed

    Venteris, Erik R; McBride, Robert C; Coleman, Andre M; Skaggs, Richard L; Wigmosta, Mark S

    2014-03-18

    Locating sites for new algae cultivation facilities is a complex task. The climate must support high growth rates, and cultivation ponds require appropriate land and water resources, as well as transportation and utility infrastructure. We employ our spatiotemporal Biomass Assessment Tool (BAT) to select promising locations based on the open-pond cultivation of Arthrospira sp. and strains of the order Sphaeropleales. A total of 64,000 sites across the southern United States were evaluated. We progressively applied screening criteria and tracked their impact on the number of potential sites, geographic location, and biomass productivity. Both strains demonstrated maximum productivity along the Gulf of Mexico coast, with the highest values on the Florida peninsula. In contrast, sites meeting all selection criteria for Arthrospira were located along the southern coast of Texas and for Sphaeropleales were located in Louisiana and southern Arkansas. Results were driven mainly by the lack of oil pipeline access in Florida and elevated groundwater salinity in southern Texas. The requirement for low-salinity freshwater (<400 mg L(-1)) constrained Sphaeropleales locations; siting flexibility is greater for salt-tolerant species like Arthrospira. Combined siting factors can result in significant departures from regions of maximum productivity but are within the expected range of site-specific process improvements. PMID:24559117

  18. Design wind speeds for high hazard, moderate hazard, important/low hazard and general use facilities at the Savannah River Site

    SciTech Connect

    King, H.H.

    1989-09-11

    The design wind speeds for High Hazard, Moderate Hazard, Important/Low Hazard and General Use facilities at the Savannah River Site are developed below using the procedures and site-specific hazards model required by DOE Order 6430.1A. These are less than the previously required Design Wind Speeds and are: (1) High Hazard (Maximum Resistance) Facility, 185 mph; (2) Moderate Hazard (High Resistance) Facility, 37 mph; (3) Important/Low Hazard (Intermediate) Facility, 83 mph; and, (4) General Use (Standard) Facility, 78 mph.

  19. Removal site evaluation report on the bulk shielding facility at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1996-09-01

    This removal site evaluation report on the Bulk Shielding Facility (BSF) at Oak Ridge National Laboratory was prepared to provide the Environmental Restoration Program with information necessary to evaluate whether hazardous and/or radiological contaminants in and around BSF buildings pose a substantial risk to human health or the environment (i.e., a high probability of adverse effects) and whether remedial site evaluations or removal actions are, therefore, required. A removal site evaluation was conducted at nine areas associated with the BSF. The scope of each evaluation included (1) a search for, and review of, readily available historical records regarding operations and use of the facility (including hazardous substance usage and existing contamination); (2) interviews with facility personnel concerning current and past practices; and (3) a brief walk-through to visually inspect the facility and identify existing hazard areas requiring maintenance actions or remedial evaluation. The results of the removal site evaluation indicate that no substantial risks exist from contaminants present because adequate efforts are being made to contain and control existing contamination and hazardous substances and to protect human health and the environment. At Building 3004, deteriorated and peeling exterior paint has a direct pathway to the storm water drainage system and can potentially impact local surface water during periods of storm water runoff. The paint is assumed to be lead based, thus posing a potential problem. The paint should be sampled and analyzed to determine its lead content and to assess whether a hazard exists. If so, a maintenance action will be necessary to prevent further deterioration and dislodging of the paint. In addition, if the paint contains lead, then a remedial site evaluation should be conducted to determine whether lead from fallen chips has impacted soils in the immediate area of the building.

  20. 10 CFR Appendix F to Part 50 - Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 1 2014-01-01 2014-01-01 false Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities F Appendix F to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Pt. 50, App. F Appendix F to Part 50—Policy Relating to the Siting of Fuel...

  1. 10 CFR Appendix F to Part 50 - Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 1 2012-01-01 2012-01-01 false Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities F Appendix F to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Pt. 50, App. F Appendix F to Part 50—Policy Relating to the Siting of Fuel...

  2. The Pajarito Site operating procedures for the Los Alamos Critical Experiments Facility

    SciTech Connect

    Malenfant, R.E.

    1991-12-01

    Operating procedures consistent with DOE Order 5480.6, and the American National Standard Safety Guide for the Performance of Critical Experiments are defined for the Los Alamos Critical Experiments Facility (LACEF) of the Los Alamos National Laboratory. These operating procedures supersede and update those previously published in 1983 and apply to any criticality experiment performed at the facility. 11 refs.

  3. Topsides equipment, operating flexibility key floating LNG design

    SciTech Connect

    Yost, K.; Lopez, R.; Mok, J.

    1998-03-09

    Use of a large-scale floating liquefied natural gas (LNG) plant is an economical alternative to an onshore plant for producing from an offshore field. Mobil Technology Co., Dallas, has advanced a design for such a plant that is technically feasible, economical, safe, and reliable. Presented were descriptions of the general design basis, hull modeling and testing, topsides and storage layouts, and LNG offloading. But such a design also presents challenges for designing topsides equipment in an offshore environment and for including flexibility and safety. These are covered in this second article. Mobil`s floating LNG plant design calls for a square concrete barge with a moon-pool in the center. It is designed to produce 6 million tons/year of LNG with up to 55,000 b/d of condensate from 1 bcfd of raw feed gas.

  4. Safety analysis--200 Area Savannah River Site: Separations Area operations Building 211-H Outside Facilities. Supplement 11, Revision 1

    SciTech Connect

    Not Available

    1993-01-01

    The H-Area Outside Facilities are located in the 200-H Separations Area and are comprised of a number of processes, utilities, and services that support the separations function. Included are enriched uranium loadout, bulk chemical storage, water handling, acid recovery, general purpose evaporation, and segregated solvent facilities. In addition, services for water, electricity, and steam are provided. This Safety Analysis Report (SAR) documents an analysis of the H-Area Outside Facilities and is one of a series of documents for the Separations Area as specified in the SR Implementation Plan for DOE order 5481.1A. The primary purpose of the analysis was to demonstrate that the facility can be operated without undue risk to onsite or offsite populations, to the environment, and to operating personnel. In this report, risks are defined as the expected frequencies of accidents, multiplied by the resulting radiological consequences in person-rem. Following the summary description of facility and operations is the site evaluation including the unique features of the H-Area Outside Facilities. The facility and process design are described in Chapter 3.0 and a description of operations and their impact is given in Chapter 4.0. The accident analysis in Chapter 5.0 is followed by a list of safety related structures and systems (Chapter 6.0) and a description of the Quality Assurance program (Chapter 7.0). The accident analysis in this report focuses on estimating the risk from accidents as a result of operation of the facilities. The operations were evaluated on the basis of three considerations: potential radiological hazards, potential chemical toxicity hazards, and potential conditions uniquely different from normal industrial practice.

  5. Environmental assessment for the construction, operation, and decommissioning of the Waste Segregation Facility at the Savannah River Site

    SciTech Connect

    1998-01-01

    This Environmental Assessment (EA) has been prepared by the Department of Energy (DOE) to assess the potential environmental impacts associated with the construction, operation and decontamination and decommissioning (D&D) of the Waste Segregation Facility (WSF) for the sorting, shredding, and compaction of low-level radioactive waste (LLW) at the Savannah River Site (SRS) located near Aiken, South Carolina. The LLW to be processed consists of two waste streams: legacy waste which is currently stored in E-Area Vaults of SRS and new waste generated from continuing operations. The proposed action is to construct, operate, and D&D a facility to process low-activity job-control and equipment waste for volume reduction. The LLW would be processed to make more efficient use of low-level waste disposal capacity (E-Area Vaults) or to meet the waste acceptance criteria for treatment at the Consolidated Incineration Facility (CIF) at SRS.

  6. The 1993 baseline biological studies and proposed monitoring plan for the Device Assembly Facility at the Nevada Test Site

    SciTech Connect

    Woodward, B.D.; Hunter, R.B.; Greger, P.D.; Saethre, M.B.

    1995-02-01

    This report contains baseline data and recommendations for future monitoring of plants and animals near the new Device Assembly Facility (DAF) on the Nevada Test Site (NTS). The facility is a large structure designed for safely assembling nuclear weapons. Baseline data was collected in 1993, prior to the scheduled beginning of DAF operations in early 1995. Studies were not performed prior to construction and part of the task of monitoring operational effects will be to distinguish those effects from the extensive disturbance effects resulting from construction. Baseline information on species abundances and distributions was collected on ephemeral and perennial plants, mammals, reptiles, and birds in the desert ecosystems within three kilometers (km) of the DAF. Particular attention was paid to effects of selected disturbances, such as the paved road, sewage pond, and the flood-control dike, associated with the facility. Radiological monitoring of areas surrounding the DAF is not included in this report.

  7. Operation of Bubblers in the Savannah River Site Defense Waste Processing Facility Melter - 12166

    SciTech Connect

    Hodges, Brandon C.; Iverson, Daniel C.; Diener, Glenn

    2012-07-01

    Savannah River Remediation (SRR) LLC acquired the liquid waste contract at the Savannah River Site (SRS) in the summer of 2009. In order to achieve the main goal of the contract, closing of High Level Waste (HLW) tanks, it was necessary to process more waste throughout the SRS liquid waste facilities. The Defense Waste Processing Facility (DWPF) would need to increase its production rate of radioactive waste glass filled canisters as a part of the plan to achieve this commitment. To attain the increased production rate, four bubblers were installed in the DWPF Melter in September 2010 to agitate the DWPF Melter glass pool. The four bubblers were designed to be installed in existing nozzles on the top-head of the DWPF Melter. The design and fabrication of the four (4) bubblers was accomplished through SRR critical subcontractor EnergySolutions LLC. In addition to the existing bubbler design, a new design concept has been approved and is in the process of fabrication. The new design will allow for the lower end (inside melter) of the bubbler to be replaced while the upper end (outside melter) of the bubbler is reused to minimize cost and waste at the DWPF. The bubblers have been operating in the DWPF Melter for approximately 1 year. The originally installed bubbler set was replaced in January 2011. The bubblers were visually examined once removed from the melter and showed minimal signs of wear. Material testing of the Inconel 690 is being performed to determine if the bubblers operational life can be extended. The use of the bubblers has changed the dynamics within the melter glass pool. This is shown through indications that the bubblers have increased the glass pool circulation. Overall, performance of the bubblers has been encouraging and the DWPF Melter has seen a significant improvement in its ability to process waste since the bubbler installation. The installation of the bubblers accomplished the goal of increasing the glass production capability of DWPF

  8. Closure Report for Corrective Action Unit 254: Area 25, R-MAD Decontamination Facility, Nevada Test Site, Nevada

    SciTech Connect

    G. N. Doyle

    2002-02-01

    Corrective Action Unit (CAU) 254 is located in Area 25 of the Nevada Test Site (NTS), approximately 100 kilometers (km) (62 miles) northwest of Las Vegas, Nevada. The site is located within the Reactor Maintenance, Assembly and Disassembly (R-MAD) compound and consists of Building 3126, two outdoor decontamination pads, and surrounding areas within an existing fenced area measuring approximately 50 x 37 meters (160 x 120 feet). The site was used from the early 1960s to the early 1970s as part of the Nuclear Rocket Development Station program to decontaminate test-car hardware and tooling. The site was reactivated in the early 1980s to decontaminate a radiologically contaminated military tank. This Closure Report (CR) describes the closure activities performed to allow un-restricted release of the R-MAD Decontamination Facility.

  9. Corrective Action Plan for Corrective Action Unit 254: Area 25 R-MAD Decontamination Facility Nevada Test Site, Nevada

    SciTech Connect

    C. M. Obi

    2000-12-01

    The Area 25 Reactor Maintenance, Assembly, and Disassembly Decontamination Facility is identified in the Federal Facility Agreement and Consent Order (FFACO) as Corrective Action Unit (CAU) 254. CAU 254 is located in Area 25 of the Nevada Test Site and consists of a single Corrective Action Site CAS 25-23-06. CAU 254 will be closed, in accordance with the FFACO of 1996. CAU 254 was used primarily to perform radiological decontamination and consists of Building 3126, two outdoor decontamination pads, and surrounding soil within an existing perimeter fence. The site was used to decontaminate nuclear rocket test-car hardware and tooling from the early 1960s through the early 1970s, and to decontaminate a military tank in the early 1980s. The site characterization results indicate that, in places, the surficial soil and building materials exceed clean-up criteria for organic compounds, metals, and radionuclides. Closure activities are expected to generate waste streams consisting of nonhazardous construction waste. petroleum hydrocarbon waste, hazardous waste, low-level radioactive waste, and mixed waste. Some of the wastes exceed land disposal restriction limits and will require off-site treatment before disposal. The recommended corrective action was revised to Alternative 3- ''Unrestricted Release Decontamination, Verification Survey, and Dismantle Building 3126,'' in an addendum to the Correction Action Decision Document.

  10. Rocketdyne division, environmental monitoring and facility effluent. Annual report, De Soto and Santa Susana Field Laboratories Sites, 1986

    SciTech Connect

    Moore, J. D.

    1987-03-01

    Environmental and facility effluent radioactivity monitoring at the Rocketdyne Division of Rockwell International is performed by the Radiation and Nuclear Safety Group of the Health, Safety, and Environment Department. Soil and surface water are routinely sampled to a distance of 10 miles from Division sites. Ground water from site supply water wells and other test wells is periodically sampled to measure radioactivity in these waters. Continuous ambient air sampling and direct radiation monitoring by thermoluminescent dosimetry are performed at several on=site and off-site locations for measuring airborne radioactivity concentrations and site ambient radiation levels. Radioactivity in effluents discharged to the atmosphere from nuclear facilities is continuously sampled and monitored to ensure that amounts released to uncontrolled areas are below appropriate limits and to identify processes that may require additional engineering safeguards to minimize radioactivity in such discharges. In addition, selected nonradioactive chemical constituent concentrations in surface water discharged to uncontrolled areas are determined. The environmental radioactivity reported herein is attributed to natural sources, to local fallout of radioactive debris from the Chernobyl reactor accident, and to residual fallout of radioactive material from past atmospheric testing of nuclear devices.

  11. ALL-PATHWAYS DOSE ANALYSIS FOR THE PORTSMOUTH ON-SITE WASTE DISPOSAL FACILITY

    SciTech Connect

    Smith, F.; Phifer, M.

    2014-04-10

    A Portsmouth On-Site Waste Disposal Facility (OSWDF) All-Pathways analysis has been conducted that considers the radiological impacts to a resident farmer. It is assumed that the resident farmer utilizes a farm pond contaminated by the OSWDF to irrigate a garden and pasture and water livestock from which food for the resident farmer is obtained, and that the farmer utilizes groundwater from the Berea sandstone aquifer for domestic purposes (i.e. drinking water and showering). As described by FBP 2014b the Hydrologic Evaluation of Landfill Performance (HELP) model (Schroeder et al. 1994) and the Surface Transport Over Multiple Phases (STOMP) model (White and Oostrom 2000, 2006) were used to model the flow and transport from the OSWDF to the Points of Assessment (POAs) associated with the 680-ft elevation sandstone layer (680 SSL) and the Berea sandstone aquifer. From this modeling the activity concentrations radionuclides were projected over time at the POAs. The activity concentrations were utilized as input to a GoldSimTM (GTG 2010) dose model, described herein, in order to project the dose to a resident farmer over time. A base case and five sensitivity cases were analyzed. The sensitivity cases included an evaluation of the impacts of using a conservative inventory, an uncased well to the Berea sandstone aquifer, a low waste zone uranium distribution coefficient (Kd), different transfer factors, and reference person exposure parameters (i.e. at 95 percentile). The maximum base case dose within the 1,000 year assessment period was projected to be 1.5E-14 mrem/yr, and the maximum base case dose at any time less than 10,000 years was projected to be 0.002 mrem/yr. The maximum projected dose of any sensitivity case was approximately 2.6 mrem/yr associated with the use of an uncased well to the Berea sandstone aquifer. This sensitivity case is considered very unlikely because it assumes leakage from the location of greatest concentration in the 680 SSL in to the

  12. Boise Hydrogeophysical Research Site: Field-Scale Test Facility for Addressing Fundamental Questions of Environmental Science

    NASA Astrophysics Data System (ADS)

    Barrash, W.; Routh, P. S.

    2006-12-01

    The Boise Hydrogeophysical Research Site (BHRS) is a research wellfield or field-scale test facility developed in a shallow, coarse, fluvial aquifer with the objectives of supporting (a) development of cost-effective, non- invasive methods for quantitative characterization and imaging methods in heterogeneous aquifers using hydrologic and geophysical techniques; (b) examination of fundamental relationships and processes at multiple scales; (c) testing theories and models for groundwater flow and solute transport; and (d) educating and training the next generation of professionals in multidisciplinary subsurface science and engineering. The design of the wells and the wellfield provide for a wide range of single-well, cross-hole, multiwell and multilevel hydrologic, geophysical, and combined hydrologic-geophysical experiments. Efforts have been focused largely on (a) establishing the 3D distributions of geologic, hydrologic, and geophysical parameters which can then be used as the basis for testing methods to jointly invert hard and soft data to return the "known" 3D K distribution and (b) developing subsurface measurement and imaging methods including static and time-lapse tomographic imaging methods. From this work we have developed a good understanding of the hydrostratigraphic framework of the BHRS as a hierarchical system which includes layers and lenses; this framework is recognized with geologic, hydrologic, radar, seismic, and EM methods and tracer tests. Work to date has been conducted by Boise State University with some collaboration and exchange with researchers and students from other institutions. At this point the BHRS is functioning well as a field-scale control volume and test cell in a multiscale heterogeneous aquifer so there is an opportunity to increase the range of both collaborative participation and research activities at the BHRS. In this regard, opportunities exist to investigate and monitor process and property variation in time and space

  13. Characterization and reclamation assessment for the Central Shops Diesel Storage Facility, Savannah River Site, Aiken, South Carolina

    SciTech Connect

    Fliermans, C.B.; Hazen, T.C.; Bledsoe, H.

    1993-10-01

    The contamination of subsurface terrestrial environments by organic contaminants is a global phenomenon. The remediation of such environments requires innovative assessment techniques and strategies for successful clean-ups. Central Shops Diesel Storage Facility at Savannah River Site was characterized to determine the extent of subsurface diesel fuel contamination using innovative approaches and effective bioremediation techniques for clean-up of the contaminant plume have been established.

  14. Assessment of Potential Flood Events and Impacts at INL's Proposed Remote-Handled Low-Level Waste Disposal Facility Sites

    SciTech Connect

    A. Jeff Sondrup; Annette L. Schafter

    2010-09-01

    Rates, depths, erosion potential, increased subsurface transport rates, and annual exceedance probability for potential flooding scenarios have been evaluated for the on-site alternatives of Idaho National Laboratory’s proposed remote handled low-level waste disposal facility. The on-site disposal facility is being evaluated in anticipation of the closure of the Radioactive Waste Management Complex at the INL. An assessment of flood impacts are required to meet the Department of Energy’s Low-Level Waste requirements (DOE-O 435.1), its natural phenomena hazards assessment criteria (DOE-STD-1023-95), and the Radioactive Waste Management Manual (DOE M 435.1-1) guidance in addition to being required by the National Environmental Policy Act (NEPA) environmental assessment (EA). Potential sources of water evaluated include those arising from (1) local precipitation events, (2) precipitation events occurring off of the INL (off-site precipitation), and (3) increased flows in the Big Lost River in the event of a Mackay Dam failure. On-site precipitation events include potential snow-melt and rainfall. Extreme rainfall events were evaluated for the potential to create local erosion, particularly of the barrier placed over the disposal facility. Off-site precipitation carried onto the INL by the Big Lost River channel was evaluated for overland migration of water away from the river channel. Off-site precipitation sources evaluated were those occurring in the drainage basin above Mackay Reservoir. In the worst-case scenarios, precipitation occurring above Mackay Dam could exceed the dam’s capacity, leading to overtopping, and eventually complete dam failure. Mackay Dam could also fail during a seismic event or as a result of mechanical piping. Some of the water released during dam failure, and contributing precipitation, has the potential of being carried onto the INL in the Big Lost River channel. Resulting overland flows from these flood sources were evaluated for

  15. Initiating continuing improvement within Greenfield sites: A federal remanufacturing facility case study

    SciTech Connect

    Montgomery, J.C.; Paul, B.K.

    1992-09-01

    The setting for this study was a federal government remanufacturing depot, responsible for the replacement and overhaul of large wheeled vehicles. These vehicles include 2.5 and 5 ton trucks and their major subordinate component items such as engines, axles, and transmissions. At the time of the case study the depot was involved in the design and construction of a 400,000 square foot hard metal subordinate items remanufacturing facility. The purpose of the facility was to consolidate all existing subordinate item remanufacturing under one roof. Commodity items to be remanufactured within the facility included engines, transmissions, transfer cases, axles, differentials, power generators, and other components. From the onset, the concept of consolidating existing processes under one roof had posed a significant material handling problem. Digital simulation was used to analyze material flow patterns within the new facility. As a result it was determined that, without changing the existing flow of material between processes, significant choke points would form in the areas of shared-capacity resources such as cleaning and painting. It was estimated that these choke points, representing piles of work-in-process (WIP) inventory, would clog aisles and prevent forklifts from making essential deliveries. Thus, a strategy was needed for controlling the buildup of WIP inventory within the new facility. To accomplish this objective, a program was begun to certify the WIP inventory levels of each subordinate item commodity line within existing facilities prior to the move into the new facility. This program focused on training workers in new methods of inventory control, production control, and quality control needed to minimize the WIP levels required within the new facility.

  16. Feasibility study: Assess the feasibility of siting a monitored retrievable storage facility. Phase 1

    SciTech Connect

    King, J.W.

    1993-08-01

    The purpose of phase one of this study are: To understand the waste management system and a monitored retrievable storage facility; and to determine whether the applicant has real interest in pursuing the feasibility assessment process. Contents of this report are: Generating electric power; facts about exposure to radiation; handling storage, and transportation techniques; description of a proposed monitored retrievable storage facility; and benefits to be received by host jurisdiction.

  17. Manhattan Project buildings and facilities at the Hanford Site: A construction history

    SciTech Connect

    Gerber, M.S.

    1993-09-01

    This document thoroughly examines the role that the Hanford Engineer Works played in the Manhattan project. The historical aspects of the buildings and facilities are characterized. An in depth look at the facilities, including their functions, methods of fabrication and appearance is given for the 100 AREAS, 200 AREAS, 300 AREAS, 500, 800 and 900 AREAS, 600 AREA, 700 AREA, 1100 AREA and temporary construction structures.

  18. Implementation of Treatment Systems for Low and Intermediate Radioactive Waste at Site Radwaste Treatment Facility (SRTF), PR China - 12556

    SciTech Connect

    Lohmann, Peter; Nasarek, Ralph; Aign, Joerg

    2012-07-01

    The AP1000 reactors being built in the People's Republic of China require a waste treatment facility to process the low and intermediate radioactive waste produced by these nuclear power stations. Westinghouse Electric Germany GmbH was successful in being awarded a contract as to the planning, delivery and commissioning of such a waste treatment facility. The Site Radwaste Treatment Facility (SRTF) is a waste treatment facility that can meet the AP1000 requirements and it will become operational in the near future. The SRTF is situated at the location of Sanmen, People's Republic of China, next to one of the AP1000 and is an adherent building to the AP1000 comprising different waste treatment processes for radioactive spent filter cartridges, ion-exchange resins and radioactive liquid and solid waste. The final product of the SRTF-treatment is a 200 l drum with cemented waste or grouted waste packages for storage in a local storage facility. The systems used in the SRTF are developed for these special requirements, based on experience from similar systems in the German nuclear industry. The main waste treatment systems in the SRTF are: - Filter Cartridge Processing System (FCS); - HVAC-Filter and Solid Waste Treatment Systems (HVS); - Chemical Liquid Treatment Systems (CTS); - Spent Resin Processing Systems (RES); - Mobile Treatment System (MBS). (authors)

  19. Niagara falls storage site: Annual site environmental report, Lewiston, New York, Calendar Year 1988: Surplus Facilities Management Program (SFMP)

    SciTech Connect

    Not Available

    1989-04-01

    The monitoring program at the Niagara Falls Storage Site (NFSS) measures radon concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for a hypothetical maximally exposed individual. Based on the conservative scenario described in this report, this hypothetical individual receives an annual external exposure approximately equivalent to 6 percent of the DOE radiation protection standard of 100 mrem/yr. This exposure is less than a person receives during two round-trip flights from New York to Los Angeles (because of the greater amounts of cosmic radiation at higher altitudes). The cumulative dose to the population within an 80-km (50-mi) radius of the NFSS that results from radioactive materials present at the site is indistinguishable from the dose that the same population receives from naturally occurring radioactive sources. Results of the 1988 monitoring show that the NFSS is in compliance with applicable DOE radiation protection standards. 17 refs., 31 figs., 20 tabs.

  20. LNG pool fire spectral data and calculation of emissive power.

    PubMed

    Raj, Phani K

    2007-04-11

    Spectral description of thermal emission from fires provides a fundamental basis on which the fire thermal radiation hazard assessment models can be developed. Several field experiments were conducted during the 1970s and 1980s to measure the thermal radiation field surrounding LNG fires. Most of these tests involved the measurement of fire thermal radiation to objects outside the fire envelope using either narrow-angle or wide-angle radiometers. Extrapolating the wide-angle radiometer data without understanding the nature of fire emission is prone to errors. Spectral emissions from LNG fires have been recorded in four test series conducted with LNG fires on different substrates and of different diameters. These include the AGA test series of LNG fires on land of diameters 1.8 and 6m, 35 m diameter fire on an insulated concrete dike in the Montoir tests conducted by Gaz de France, a 1976 test with 13 m diameter and the 1980 tests with 10 m diameter LNG fire on water carried out at China Lake, CA. The spectral data from the Montoir test series have not been published in technical journals; only recently has some data from this series have become available. This paper presents the details of the LNG fire spectral data from, primarily, the China Lake test series, their analysis and results. Available data from other test series are also discussed. China Lake data indicate that the thermal radiation emission from 13 m diameter LNG fire is made up of band emissions of about 50% of energy by water vapor (band emission), about 25% by carbon dioxide and the remainder constituting the continuum emission by luminous soot. The emissions from the H2O and CO2 bands are completely absorbed by the intervening atmosphere in less than about 200 m from the fire, even in the relatively dry desert air. The effective soot radiation constitutes only about 23% during the burning period of methane and increases slightly when other higher hydrocarbon species (ethane, propane, etc.) are

  1. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text. Environmental Restoration Program

    SciTech Connect

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

  2. Rocketdyne division, envionmental monitoring and facility effluent. Annual report, De Soto and Santa Susana Field Laboratories Sites, 1988

    SciTech Connect

    Moore, J. D.

    1989-05-01

    Environmental and facility effluent radioactivity monitoring at the Rocketdyne Division of Rockwell International is performed by the Radiation and Nuclear Safety Group of the Health, Safety, and Environment Department. Soil and surface water are routinely sampled to a distance of 16 km from division sites. Groundwater from Santa Susana Field Laboratories (SSFL) supply water wells and other test wells is periodically sampled to measure radioactivity. Continuous ambient air sampling and direct radiation monitoring by thermoluminescent dosimetry are performed at several on-site and off-site locations for measuring airborne radioactivity concentrations and site ambient radiation levels. Radioactivity in effluents discharged to the atmosphere from nuclear facilities is continually sampled and monitored to assure that amounts released to uncontrolled areas are below appropriate limits. These procedures also help identify processes that may require additional engineering safeguards to minimize radioactivity in such discharges. In addition, selected nonradioactive chemical constituent concentrations in surface water discharged to uncontrolled areas are measured. The environmental radioactivity reported herein is attributed to natural sources and to residual fallout of radioactive material from past atmospheric testing of nuclear devices.

  3. Evaluation of the effects of underground water usage and spillage in the Exploratory Studies Facility; Yucca Mountain Site Characterization Project

    SciTech Connect

    Dunn, E.; Sobolik, S.R.

    1993-12-01

    The Yucca Mountain Site Characterization Project is studying Yucca Mountain in southwestern Nevada as a potential site for a high-level radioactive waste repository. Analyses reported herein were performed to support the design of site characterization activities so that these activities will have a minimal impact on the ability of the site to isolate waste and a minimal impact on underground tests performed as part of the characterization process. These analyses examine the effect of water to be used in the underground construction and testing activities for the Exploratory Studies Facility on in situ conditions. Underground activities and events where water will be used include construction, expected but unplanned spills, and fire protection. The models used predict that, if the current requirements in the Exploratory Studies Facility Design Requirements are observed, water that is imbibed into the tunnel wall rock in the Topopah Springs welded tuff can be removed over the preclosure time period by routine or corrective ventilation, and also that water imbibed into the Paintbrush Tuff nonwelded tuff will not reach the potential waste storage area.

  4. Processing capabilties for the elimination of contaminated metal scrapyards at DOE/ORO-managed sites. [Metal smelting facility

    SciTech Connect

    Mack, J.E.; Williams, L.C.

    1982-01-01

    Capabilities exist for reducing all the contaminated nickel, aluminum, and copper scrap to ingot form by smelting. Processing these metals at existing facilities could be completed in about 5 or 6 years. However, these metals represent only about 20% of the total metal inventories currently on hand at the DOE/ORO-managed sites. No provisions have been made for the ferrous scrap. Most of the ferrous scrap is unclassified and does not require secured storage. Also, the potential resale value of the ferrous scrap at about $100 per ton is very low in comparison. Consequently, this scrap has been allowed to accumulate. With several modifications and equipment additions, the induction melter at PGDP could begin processing ferrous scrap after its commitment to nickel and aluminum. The PGDP smelter is a retrofit installation, and annual throughput capabilities are limited. Processing of the existing ferrous scrap inventories would not be completed until the FY 1995-2000 time frame. An alternative proposal has been the installation of induction melters at the other two enrichment facilities. Conceptual design of a generic metal smelting facility is under way. The design study includes capital and operating costs for scrap preparation through ingot storage at an annual throughput of 10,000 tons per year. Facility design includes an induction melter with the capability of melting both ferrous and nonferrous metals. After three years of operation with scrapyard feed, the smelter would have excess capacity to support on-site decontamination and decomissioning projects or upgrading programs. The metal smelting facility has been proposed for FY 1984 line item funding with start-up operations in FY 1986.

  5. State waste discharge permit application for the 200 Area Effluent Treatment Facility and the State-Approved Land Disposal Site

    SciTech Connect

    Not Available

    1993-08-01

    Application is being made for a permit pursuant to Chapter 173--216 of the Washington Administrative Code (WAC), to discharge treated waste water and cooling tower blowdown from the 200 Area Effluent Treatment Facility (ETF) to land at the State-Approved Land Disposal Site (SALDS). The ETF is located in the 200 East Area and the SALDS is located north of the 200 West Area. The ETF is an industrial waste water treatment plant that will initially receive waste water from the following two sources, both located in the 200 Area on the Hanford Site: (1) the Liquid Effluent Retention Facility (LERF) and (2) the 242-A Evaporator. The waste water discharged from these two facilities is process condensate (PC), a by-product of the concentration of waste from DSTs that is performed in the 242-A Evaporator. Because the ETF is designed as a flexible treatment system, other aqueous waste streams generated at the Hanford Site may be considered for treatment at the ETF. The origin of the waste currently contained in the DSTs is explained in Section 2.0. An overview of the concentration of these waste in the 242-A Evaporator is provided in Section 3.0. Section 4.0 describes the LERF, a storage facility for process condensate. Attachment A responds to Section B of the permit application and provides an overview of the processes that generated the wastes, storage of the wastes in double-shell tanks (DST), preliminary treatment in the 242-A Evaporator, and storage at the LERF. Attachment B addresses waste water treatment at the ETF (under construction) and the addition of cooling tower blowdown to the treated waste water prior to disposal at SALDS. Attachment C describes treated waste water disposal at the proposed SALDS.

  6. Groundwater monitoring plan for the Hanford Site 216-B-3 pond RCRA facility

    SciTech Connect

    Barnett, D.B.; Chou, C.J.

    1998-06-01

    The 216-B-3 pond system was a series of ponds for disposal of liquid effluent from past Hanford production facilities. In operation since 1945, the B Pond system has been a RCRA facility since 1986, with Resource Conservation and Recovery Act (RCRA) interim-status groundwater monitoring in place since 1988. In 1994, discharges were diverted from the main pond, where the greatest potential for contamination was thought to reside, to the 3C expansion pond. In 1997, all discharges to the pond system were discontinued. In 1990, the B Pond system was elevated from detection groundwater monitoring to an assessment-level status because total organic halogens and total organic carbon were found to exceed critical means in two wells. Subsequent groundwater quality assessment failed to find any specific hazardous waste contaminant that could have accounted for the exceedances, which were largely isolated in occurrence. Thus, it was recommended that the facility be returned to detection-level monitoring.

  7. Nest site characteristics, nesting movements, and lack of long-term nest site fidelity in Agassiz's desert tortoises at a wind energy facility in southern California

    USGS Publications Warehouse

    Lovich, Jeffrey E.; Agha, Mickey; Yackulic, Charles B.; Meyer-Wilkins, Kathie; Bjurlin, Curtis; Ennen, Joshua R.; Arundel, Terry R.; Austin, Meaghan

    2014-01-01

    Nest site selection has important consequences for maternal and offspring survival and fitness. Females of some species return to the same nesting areas year after year. We studied nest site characteristics, fidelity, and daily pre-nesting movements in a population of Agassiz’s desert tortoises (Gopherus agassizii) at a wind energy facility in southern California during two field seasons separated by over a decade. No females returned to the same exact nest site within or between years but several nested in the same general area. However, distances between first and second clutches within a year (2000) were not significantly different from distances between nests among years (2000 and 2011) for a small sample of females, suggesting some degree of fidelity within their normal activity areas. Environmental attributes of nest sites did not differ significantly among females but did among years due largely to changes in perennial plant structure as a result of multiple fires. Daily pre-nesting distances moved by females decreased consistently from the time shelled eggs were first visible in X-radiographs until oviposition, again suggesting some degree of nest site selection. Tortoises appear to select nest sites that are within their long-term activity areas, inside the climate-moderated confines of one of their self-constructed burrows, and specifically, at a depth in the burrow that minimizes exposure of eggs and embryos to lethal incubation temperatures. Nesting in “climate-controlled” burrows and nest guarding by females relaxes some of the constraints that drive nest site selection in other oviparous species.

  8. Weldon Spring Site Remedial Action Project Federal Facilities Agreement: Quarterly environmental data summary for third quarter 1998

    SciTech Connect

    1998-11-06

    In support of the Weldon Spring Site Remedial Action Project Federal Facilities Agreement, a copy of the Quarterly Environmental Data Summary (QEDS) for the third quarter of 1998 is enclosed. The data presented in this letter and attachment constitute the QEDS. The data, except for air monitoring data and site KPA generated data (uranium analyses), were received from the contract laboratories, verified by the Weldon Spring Site verification group, and merged into the database during the third quarter of 1998. Air monitoring data presented are the most recent complete sets of quarterly data. Significant data, defined as data values that have exceeded defined above normal Level 2 values, are discussed in this letter for Environmental Monitoring Plan (EMP) generated data only. Above normal Level 2 values are based, in ES and H procedures, on historical high values, DOE Derived Concentration Guides (DCGs), NPDES limits, and other guidelines. The procedures also establish actions to be taken in the event that above normal data occur.

  9. LNG cascading damage study. Volume I, fracture testing report.

    SciTech Connect

    Petti, Jason P.; Kalan, Robert J.

    2011-12-01

    As part of the liquefied natural gas (LNG) Cascading Damage Study, a series of structural tests were conducted to investigate the thermal induced fracture of steel plate structures. The thermal stresses were achieved by applying liquid nitrogen (LN{sub 2}) onto sections of each steel plate. In addition to inducing large thermal stresses, the lowering of the steel temperature simultaneously reduced the fracture toughness. Liquid nitrogen was used as a surrogate for LNG due to safety concerns and since the temperature of LN{sub 2} is similar (-190 C) to LNG (-161 C). The use of LN{sub 2} ensured that the tests could achieve cryogenic temperatures in the range an actual vessel would encounter during a LNG spill. There were four phases to this test series. Phase I was the initial exploratory stage, which was used to develop the testing process. In the Phase II series of tests, larger plates were used and tested until fracture. The plate sizes ranged from 4 ft square pieces to 6 ft square sections with thicknesses from 1/4 inches to 3/4 inches. This phase investigated the cooling rates on larger plates and the effect of different notch geometries (stress concentrations used to initiate brittle fracture). Phase II was divided into two sections, Phase II-A and Phase II-B. Phase II-A used standard A36 steel, while Phase II-B used marine grade steels. In Phase III, the test structures were significantly larger, in the range of 12 ft by 12 ft by 3 ft high. These structures were designed with more complex geometries to include features similar to those on LNG vessels. The final test phase, Phase IV, investigated differences in the heat transfer (cooling rates) between LNG and LN{sub 2}. All of the tests conducted in this study are used in subsequent parts of the LNG Cascading Damage Study, specifically the computational analyses.

  10. 76 FR 81925 - Freeport LNG Development, L.P.; Notice of Application

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-29

    ... Energy Regulatory Commission Freeport LNG Development, L.P.; Notice of Application Take notice that on December 9, 2011, Freeport LNG Development, L.P. (Freeport LNG), filed an application pursuant to Section 3..., Fulbright & Jaworski L.L.P., 666 Fifth Avenue, New York, New York 10103. Telephone (212) 318-3009, fax...

  11. 75 FR 74029 - Sabine Pass LNG, L.P.; Notice of Application

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-30

    ... Energy Regulatory Commission Sabine Pass LNG, L.P.; Notice of Application November 22, 2010. Take notice that on November 12, 2010, Sabine Pass LNG, L.P. (Sabine Pass), 700 Milam Street, Suite 800, Houston... directed to Patricia Outtrim, Sabine Pass LNG, L.P., 700 Milam Street, Suite 800, Houston, Texas 77002,...

  12. 75 FR 53688 - Southern LNG Company, L.L.C.; Notice of Technical Conference

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-01

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Southern LNG Company, L.L.C.; Notice of Technical Conference August 25, 2010..., Southern LNG Company, L.L.C. (Southern LNG) filed a tariff sheet to revise its tariff with respect to...

  13. 77 FR 788 - Southern LNG Company, L.L.C.; Notice of Application

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-01-06

    ... Energy Regulatory Commission Southern LNG Company, L.L.C.; Notice of Application Take notice that on December 15, 2011, Southern LNG Company, L.L.C. (SLNG), 569 Brookwood Village, Suite 501, Birmingham... should be directed to Glenn A. Sheffield, Director, Rates & Regulatory Affairs, Southern LNG Company,...

  14. 75 FR 2126 - Calais Pipeline Company, LLC; Calais LNG Project Company, LLC; Notice of Application

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-14

    ... Energy Regulatory Commission Calais Pipeline Company, LLC; Calais LNG Project Company, LLC; Notice of Application January 6, 2010. Take notice that on December 18, 2009, Calais LNG Project Company, LLC (Calais LNG) and Calais Pipeline Company, LLC (Calais Pipeline) 142 ] Main Street, P.O. Box 133, Calais,...

  15. 33 CFR 127.703 - Access to the marine transfer area for LNG.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... area for LNG. 127.703 Section 127.703 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF... Access to the marine transfer area for LNG. The operator shall ensure that— (a) Access to the marine transfer area for LNG from the shoreside and the waterside is limited to— (1) Personnel who work at...

  16. 33 CFR 127.703 - Access to the marine transfer area for LNG.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... area for LNG. 127.703 Section 127.703 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF... Access to the marine transfer area for LNG. The operator shall ensure that— (a) Access to the marine transfer area for LNG from the shoreside and the waterside is limited to— (1) Personnel who work at...

  17. 33 CFR 127.105 - Layout and spacing of marine transfer area for LNG.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... spacing of marine transfer area for LNG. (a) LNG impounding spaces must be located so that the heat flux... 33 Navigation and Navigable Waters 2 2012-07-01 2012-07-01 false Layout and spacing of marine transfer area for LNG. 127.105 Section 127.105 Navigation and Navigable Waters COAST GUARD, DEPARTMENT...

  18. 33 CFR 127.105 - Layout and spacing of marine transfer area for LNG.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... spacing of marine transfer area for LNG. (a) LNG impounding spaces must be located so that the heat flux... 33 Navigation and Navigable Waters 2 2013-07-01 2013-07-01 false Layout and spacing of marine transfer area for LNG. 127.105 Section 127.105 Navigation and Navigable Waters COAST GUARD, DEPARTMENT...

  19. 33 CFR 127.105 - Layout and spacing of marine transfer area for LNG.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... spacing of marine transfer area for LNG. (a) LNG impounding spaces must be located so that the heat flux... 33 Navigation and Navigable Waters 2 2014-07-01 2014-07-01 false Layout and spacing of marine transfer area for LNG. 127.105 Section 127.105 Navigation and Navigable Waters COAST GUARD, DEPARTMENT...

  20. An exposure assessment of radionuclide emissions associated with potential mixed-low level waste disposal facilities at fifteen DOE sites

    SciTech Connect

    Lombardi, D.A.; Socolof, M.L.

    1996-05-01

    A screening method was developed to compare the doses received via the atmospheric pathway at 15 potential DOE MLLW (mixed low-level waste) sites. Permissible waste concentrations were back calculated using the radioactivity NESHAP (National Emissions Standards for Hazardous Air Pollutants) in 40 FR 61 (DOE Order 5820.2A performance objective). Site-specific soil and meteorological data were used to determine permissible waste concentrations (PORK). For a particular radionuclide, perks for each site do not vary by more than one order of magnitude. perks of {sup 14}C are about six orders of magnitude more restrictive than perks of {sup 3}H because of differences in liquid/vapor partitioning, decay, and exposure dose. When comparing results from the atmospheric pathway to the water and intruder pathways, {sup 14}C disposal concentrations were limited by the atmospheric pathway for most arid sites; for {sup 3}H, the atmospheric pathway was not limiting at any of the sites. Results of this performance evaluation process are to be used for planning for siting of disposal facilities.

  1. Tritium monitoring in groundwater and evaluation of model predictions for the Hanford Site 200 Area Effluent Treatment Facility

    SciTech Connect

    Barnett, D.B.; Bergeron, M.P.; Cole, C.R.; Freshley, M.D.; Wurstner, S.K.

    1997-08-01

    The Effluent Treatment Facility (ETF) disposal site, also known as the State-Approved Land Disposal Site (SALDS), receives treated effluent containing tritium, which is allowed to infiltrate through the soil column to the water table. Tritium was first detected in groundwater monitoring wells around the facility in July 1996. The SALDS groundwater monitoring plan requires revision of a predictive groundwater model and reevaluation of the monitoring well network one year from the first detection of tritium in groundwater. This document is written primarily to satisfy these requirements and to report on analytical results for tritium in the SALDS groundwater monitoring network through April 1997. The document also recommends an approach to continued groundwater monitoring for tritium at the SALDS. Comparison of numerical groundwater models applied over the last several years indicate that earlier predictions, which show tritium from the SALDS approaching the Columbia River, were too simplified or overly robust in source assumptions. The most recent modeling indicates that concentrations of tritium above 500 pCi/L will extend, at most, no further than {approximately}1.5 km from the facility, using the most reasonable projections of ETF operation. This extent encompasses only the wells in the current SALDS tritium-tracking network.

  2. Library Off-Site Shelving: Guide for High-Density Facilities.

    ERIC Educational Resources Information Center

    Nitecki, Danuta A., Ed.; Kendrick, Curtis L., Ed.

    This collection of essays addresses the planning, construction, and operating issues relating to high-density library shelving facilities. The volume covers essential topics that address issues relating to the building, its operations, and serving the collections. It begins with an introduction by the volume's editors, "The Paradox and Politics of…

  3. DETERMINATION OF BREEDING SITES OF NEMATODES IN A MUNICIPAL DRINKING WATER FACILITY

    EPA Science Inventory

    The question concerning the source of nematodes in finished water has been answered by clearly demonstrating that these invertebrates do not breed in the sand filter or another part of the water treatment facility but in the raw water source. The benthic layer of the rivers and l...

  4. Advanced technologies for maintenance of electrical systems and equipment at the Savannah River Site Defense Waste Processing Facility

    SciTech Connect

    Husler, R.O.; Weir, T.J.

    1991-12-31

    An enhanced maintenance program is being established to characterize and monitor cables, components, and process response at the Savannah River Site, Defense Waste Processing Facility. This facility was designed and constructed to immobilize the radioactive waste currently stored in underground storage tanks and is expected to begin operation in 1993. The plant is initiating the program to baseline and monitor instrument and control (I&C) and electrical equipment, remote process equipment, embedded instrument and control cables, and in-cell jumper cables used in the facility. This program is based on the electronic characterization and diagnostic (ECAD) system which was modified to include process response analysis and to meet rigid Department of Energy equipment requirements. The system consists of computer-automated, state-of-the-art electronics. The data that are gathered are stored in a computerized database for analysis, trending, and troubleshooting. It is anticipated that the data which are gathered and trended will aid in life extension for the facility.

  5. Decommissioning and Dismantling of Liquid Waste Storage and Liquid Waste Treatment Facility from Paldiski Nuclear Site, Estonia

    SciTech Connect

    Varvas, M.; Putnik, H.; Johnsson, B.

    2006-07-01

    The Paldiski Nuclear Facility in Estonia, with two nuclear reactors was owned by the Soviet Navy and was used for training the navy personnel to operate submarine nuclear reactors. After collapse of Soviet Union the Facility was shut down and handed over to the Estonian government in 1995. In co-operation with the Paldiski International Expert Reference Group (PIERG) decommission strategy was worked out and started to implement. Conditioning of solid and liquid operational waste and dismantling of contaminated installations and buildings were among the key issues of the Strategy. Most of the liquid waste volume, remained at the Facility, was processed in the frames of an Estonian-Finnish co-operation project using a mobile wastewater purification unit NURES (IVO International OY) and water was discharged prior to the site take-over. In 1999-2002 ca 120 m{sup 3} of semi-liquid tank sediments (a mixture of ion exchange resins, sand filters, evaporator and flocculation slurry), remained after treatment of liquid waste were solidified in steel containers and stored into interim storage. The project was carried out under the Swedish - Estonian co-operation program on radiation protection and nuclear safety. Contaminated installations in buildings, used for treatment and storage of liquid waste (Liquid Waste Treatment Facility and Liquid Waste Storage) were then dismantled and the buildings demolished in 2001-2004. (authors)

  6. Rapid on-site air sampling with a needle extraction device for evaluating the indoor air environment in school facilities.

    PubMed

    Inoue, Mitsuru; Mizuguchi, Ayako; Ueta, Ikuo; Takahashi, Kazuya; Saito, Yoshihiro

    2013-01-01

    A rapid on-site air sampling technique was developed with a miniaturized needle-type sample preparation device for a systematic evaluation of the indoor air environments in school facilities. With the in-needle extraction device packed with a polymer particle of divinylbenzene and activated carbon particles, various types of volatile organic compounds (VOCs) were successfully extracted. For evaluating the indoor air qualities in school facilities, air samples in renovated rooms using organic solvent as a thinner of the paint were analyzed along with measurements of several VOCs in indoor air samples taken in newly built primary schools mainly using low-VOCs materials. After periodical renovation/maintenance, the time-variation profile of typical VOCs found in the school facilities has also been monitored. From the results, it could be observed that the VOCs in most of the rooms in these primary schools were at a quite low level; however, a relatively higher concentration of VOCs was found in some specially designed rooms, such as music rooms. In addition, some non-regulated compounds, including benzyl alcohol and branched alkanes, were detected in these primary schools. The results showed a good applicability of the needle device to indoor air analysis in schools, suggesting a wide range of future employment of the needle device, especially for indoor air analysis in other types of facilities and rooms including hospitals and hotels. PMID:23665624

  7. Construction of the Largest Radionuclide Commingled Plume Groundwater Treatment Facility for the Department of Energy at the Hanford Site - 12411

    SciTech Connect

    Pargmann, Delise

    2012-07-01

    CH2M Hill Plateau Remediation Company (CHPRC) has constructed the largest groundwater treatment systems of its kind throughout the DOE Complex at the Hanford Site in an accelerated manner with American Recovery and Reinvestment Act (ARRA) funds. This complex, one of a kind groundwater treatment facility in Washington State has also attained Leadership in Energy and Environmental Design (LEED) Gold certification. The original concept for the 200 West Area groundwater treatment facility was a 6100 liter per minute (1,600 gallon per minute) facility. With additional ARRA funding, the plant design was improved to construct a 9500 liter per minute (2,500 gallon per minute) facility with expansion areas up to 14,000 liter per minute (3,750 gallon per minute). The current design will remove 53 percent more mass per year for faster clean-up. It is also expected to treat extracted groundwater to 25 percent or less than the Record of Decision-specified limit which improves Monitored Natural Attenuation (MNA) effectiveness. (author)

  8. Corrective Action Decision Document for Corrective Action Unit 254: Area 25 R-MAD Decontamination Facility, Nevada Test Site, Nevada

    SciTech Connect

    U.S. Department of Energy, Nevada Operations Office

    2000-06-01

    This Corrective Action Decision Document identifies and rationalizes the US Department of Energy, Nevada Operations Office's selection of a recommended corrective action alternative (CAA) appropriate to facilitate the closure of Corrective Action Unit (CAU) 254, R-MAD Decontamination Facility, under the Federal Facility Agreement and Consent Order. Located in Area 25 at the Nevada Test Site in Nevada, CAU 254 is comprised of Corrective Action Site (CAS) 25-23-06, Decontamination Facility. A corrective action investigation for this CAS as conducted in January 2000 as set forth in the related Corrective Action Investigation Plan. Samples were collected from various media throughout the CAS and sent to an off-site laboratory for analysis. The laboratory results indicated the following: radiation dose rates inside the Decontamination Facility, Building 3126, and in the storage yard exceeded the average general dose rate; scanning and static total surface contamination surveys indicated that portions of the locker and shower room floor, decontamination bay floor, loft floor, east and west decon pads, north and south decontamination bay interior walls, exterior west and south walls, and loft walls were above preliminary action levels (PALs). The investigation-derived contaminants of concern (COCs) included: polychlorinated biphenyls, radionuclides (strontium-90, niobium-94, cesium-137, uranium-234 and -235), total volatile and semivolatile organic compounds, total petroleum hydrocarbons, and total Resource Conservation and Recovery Act (Metals). During the investigation, two corrective action objectives (CAOs) were identified to prevent or mitigate human exposure to COCs. Based on these CAOs, a review of existing data, future use, and current operations at the Nevada Test Site, three CAAs were developed for consideration: Alternative 1 - No Further Action; Alternative 2 - Unrestricted Release Decontamination and Verification Survey; and Alternative 3 - Unrestricted

  9. Technical assistance to Ohio closure sites; Technologies to address leachate from the on-site disposal facility at Fernald Environmental Management Project, Ohio

    SciTech Connect

    Hazen, Terry

    2002-08-26

    On August 6-7, 2002, a Technical Assistance Team (''Team'') from the U.S. Department of Energy (DOE) Subsurface Contaminants Focus Area (SCFA) met with Fernald Environmental Management Project (FEMP) personnel in Ohio to assess approaches to remediating uranium-contaminated leachate from the On-Site Disposal Facility (OSDF). The Team was composed of technical experts from national labs, technology centers, and industry and was assembled in response to a request from the FEMP Aquifer Restoration Project. Dave Brettschneider of Fluor Fernald, Inc., requested that a Team of experts be convened to review technologies for the removal of uranium in both brine ion exchange regeneration solution from the Advanced Wastewater Treatment facility and in the leachate from the OSDF. The Team was asked to identify one or more technologies for bench-scale testing as a cost effective alternative to remove uranium so that the brine regeneration solution from the Advanced Waste Water Treatment facility and the leachate from the OSDF can be discharged without further treatment. The Team was also requested to prepare a recommended development and demonstration plan for the alternative technologies. Finally, the Team was asked to make recommendations on the optimal technical solution for field implementation. The Site's expected outcomes for this effort are schedule acceleration, cost reduction, and better long-term stewardship implementation. To facilitate consideration of the most appropriate technologies, the Team was divided into two groups to consider the brine and the leachate separately, since they represent different sources with different constraints on solutions, e.g., short-term versus very long-term and concentrated versus dilute contaminant matrices. This report focuses on the technologies that are most appropriate for the leachate from the OSDF. Upon arriving at FEMP, project personnel asked the Team to concentrate its efforts on evaluating potential technologies and

  10. Using Geographic Information Systems to Determine Site Suitability for a Low-Level Radioactive Waste Storage Facility.

    PubMed

    Wilson, Charles A; Matthews, Kennith; Pulsipher, Allan; Wang, Wei-Hsung

    2016-02-01

    ) sites. Cells above 90%, 95%, and 99% suitability include respectively 404, 88, and 4 cells suitable for further analysis. With these areas identified, the next step in siting a LLW storage facility would be on-site analysis using additional requirements as specified by relevant regulatory guidelines. The GIS based method provides an easy, economic, efficient and effective means in evaluating potential sites for LLW storage facilities where sufficient GIS data exist. PMID:26710161

  11. 75 FR 20591 - AES Sparrows Point LNG, LLC and Mid-Atlantic Express, LLC; Notice of Final General Conformity...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-20

    ... General Conformity Determination for Pennsylvania for the Proposed Sparrows Point LNG Terminal and... liquefied natural gas (LNG) import terminal and natural gas pipeline proposed by AES Sparrows Point LNG, LLC... quality impacts from the construction and operation of the following LNG terminal and natural gas...

  12. Facility Utilization and Risk Analysis for Remediation of Legacy Transuranic Waste at the Savannah River Site - 13572

    SciTech Connect

    Gilles, Michael L.; Gilmour, John C.

    2013-07-01

    Savannah River Nuclear Solutions (SRNS) completed the Accelerated TRU Project for remediating legacy waste at the Savannah River Site with significant cost and schedule efficiencies due to early identification of resources and utilization of risk matrices. Initial project planning included identification of existing facilities that could be modified to meet the technical requirements needed for repackaging and remediating the waste. The project schedule was then optimized by utilization of risk matrices that identified alternate strategies and parallel processing paths which drove the overall success of the project. Early completion of the Accelerated TRU Project allowed SRNS to pursue stretch goals associated with remediating very difficult TRU waste such as concrete casks from the hot cells in the Savannah River National Laboratory. Project planning for stretch goals also utilized existing facilities and the risk matrices. The Accelerated TRU project and stretch goals were funded under the American Recovery and Reinvestment Act (ARRA). (authors)

  13. Should North America’s first and only supervised injection facility (InSite) be expanded in British Columbia, Canada?

    PubMed Central

    2013-01-01

    Background This article reports qualitative findings from a sample of 31 purposively chosen injection drug users (IDUs) from Vancouver, Surrey and Victoria, British Columbia interviewed to examine the context of safe injection site in transforming their lives. Further, the purpose is to determine whether the first and only Supervised injection facility (SIF) in North America, InSite, needs to be expanded to other cities. Methods Semi-structured qualitative interviews were conducted in a classical anthropological strategy of conversational format as drug users were actively involved in their routine activities. Purposive sampling combined with snowball sampling techniques was employed to recruit the participants. Audio recorded interviews were transcribed verbatim and analyzed thematically using NVivo 9 software. Results Attending InSite has numerous positive effects on the lives of IDUs including: saving lives, reducing HIV and HCV risk behavior, decreasing injection in public, reducing public syringe disposal, reducing use of various medical resources and increasing access to nursing and other primary health services. Conclusions There is an urgent need to expand the current facility to cities where injection drug use is prevalent to reduce overdose deaths, reduce needle sharing, reduce hospital emergency care, and increase safety. In addition, InSite’s positive changes have contributed to a cultural transformation in drug use within the Downtown Eastside and neighboring communities. PMID:23414093

  14. Information needs for siting new, and evaluating current, nuclear facilities: ecology, fate and transport, and human health.

    PubMed

    Burger, Joanna; Clarke, James; Gochfeld, Michael

    2011-01-01

    The USA is entering an era of energy diversity, and increasing nuclear capacity and concerns focus on accidents, security, waste, and pollution. Physical buffers that separate outsiders from nuclear facilities often support important natural ecosystems but may contain contaminants. The US Nuclear Regulatory Commission (NRC) licenses nuclear reactors; the applicant provides environmental assessments that serve as the basis for Environmental Impact Statements developed by NRC. We provide a template for the types of information needed for safe siting of nuclear facilities with buffers in three categories: ecological, fate and transport, and human health information that can be used for risk evaluations. Each item on the lists is an indicator for evaluation, and individual indicators can be selected for specific region. Ecological information needs include biodiversity (species, populations, communities) and structure and functioning of ecosystems, habitats, and landscapes, in addition to common, abundant, and unique species and endangered and rare ones. The key variables of fate and transport are sources of release for radionuclides and other chemicals, nature of releases (atmospheric vapors, subsurface liquids), features, and properties of environmental media (wind speed, direction and atmospheric stability, hydraulic gradient, hydraulic conductivity, groundwater chemistry). Human health aspects include receptor populations (demography, density, dispersion, and distance), potential pathways (drinking water sources, gardening, fishing), and exposure opportunities (lifestyle activities). For each of the three types of information needs, we expect that only a few of the indicators will be applicable to a particular site and that stakeholders should agree on a site-specific suite. PMID:20140506

  15. Floating LNG plant will stress reliability and safety

    SciTech Connect

    Kinney, C.D.; Schulz, H.R.; Spring, W.

    1997-07-01

    Mobil has developed a unique floating LNG plant design after extensive studies that set safety as the highest priority. The result is a production, storage and offloading platform designed to produce 6 million tons per year of LNG and up to 55,000 bpd of condensate from 1 Bcfd of feed gas. All production and off-loading equipment is supported by a square donut-shaped concrete hull, which is spread-moored. The hull contains storage tanks for 250,000 m{sup 3} of LNG, 6540,000 bbl of condensate and ballast water. Both LNG and condensate can be directly offloaded to shuttle tankers. Since the plant may be moved to produce from several different gas fields during its life, the plant and barge were designed to be generic. It can be used at any location in the Pacific Rim, with up to 15% CO{sub 2}, 100 ppm H{sub 2}S, 55 bbl/MMcf condensate and 650 ft water depth. It can be modified to handle other water depths, depending upon the environment. In addition, it is much more economical than an onshore grassroots LNG plant, with potential capital savings of 25% or more. The paper describes the machinery, meteorology and oceanography, and safety engineering.

  16. Groundwater Monitoring Plan for the Hanford Site 216-B-3 Pond RCRA Facility

    SciTech Connect

    Barnett, D BRENT.; Smith, Ronald M.; Chou, Charissa J.; McDonald, John P.

    2005-11-01

    The 216-B-3 Pond system was a series of ponds used for disposal of liquid effluent from past Hanford production facilities. In operation from 1945 to 1997, the B Pond System has been a Resource Conservation and Recovery Act (RCRA) facility since 1986, with RCRA interim-status groundwater monitoring in place since 1988. In 1994 the expansion ponds of the facility were clean closed, leaving only the main pond and a portion of the 216-B-3-3 ditch as the currently regulated facility. In 2001, the Washington State Department of Ecology (Ecology) issued a letter providing guidance for a two-year, trial evaluation of an alternate, intrawell statistical approach to contaminant detection monitoring at the B Pond system. This temporary variance was allowed because the standard indicator-parameters evaluation (pH, specific conductance, total organic carbon, and total organic halides) and accompanying interim status statistical approach is ineffective for detecting potential B-Pond-derived contaminants in groundwater, primarily because this method fails to account for variability in the background data and because B Pond leachate is not expected to affect the indicator parameters. In July 2003, the final samples were collected for the two-year variance period. An evaluation of the results of the alternate statistical approach is currently in progress. While Ecology evaluates the efficacy of the alternate approach (and/or until B Pond is incorporated into the Hanford Facility RCRA Permit), the B Pond system will return to contamination-indicator detection monitoring. Total organic carbon and total organic halides were added to the constituent list beginning with the January 2004 samples. Under this plan, the following wells will be monitored for B Pond: 699-42-42B, 699-43-44, 699-43-45, and 699-44-39B. The wells will be sampled semi-annually for the contamination indicator parameters (pH, specific conductance, total organic carbon, and total organic halides) and annually for

  17. Hanford Site annual dangerous waste report: Volume 3, Part 1, Waste Management Facility report, dangerous waste

    SciTech Connect

    1994-12-31

    This report contains information on hazardous wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling method and containment vessel, waste number, waste designation, and amount of waste.

  18. Hanford Site annual dangerous waste report: Volume 4, Waste Management Facility report, Radioactive mixed waste

    SciTech Connect

    1994-12-31

    This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling method and containment vessel, waste number, waste designation and amount of waste.

  19. 10 CFR 61.52 - Land disposal facility operation and disposal site closure.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... vertical controls as checked against USGS or NGS record files. (8) A buffer zone of land must be maintained between any buried waste and the disposal site boundary and beneath the disposed waste. The buffer...

  20. 10 CFR 61.52 - Land disposal facility operation and disposal site closure.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... vertical controls as checked against USGS or NGS record files. (8) A buffer zone of land must be maintained between any buried waste and the disposal site boundary and beneath the disposed waste. The buffer...

  1. 10 CFR 61.52 - Land disposal facility operation and disposal site closure.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... vertical controls as checked against USGS or NGS record files. (8) A buffer zone of land must be maintained between any buried waste and the disposal site boundary and beneath the disposed waste. The buffer...

  2. 10 CFR 61.52 - Land disposal facility operation and disposal site closure.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... vertical controls as checked against USGS or NGS record files. (8) A buffer zone of land must be maintained between any buried waste and the disposal site boundary and beneath the disposed waste. The buffer...

  3. Alternative energy facility siting policies for urban coastal areas: Executive summary of findings and policy recommendations

    NASA Astrophysics Data System (ADS)

    Morell, D.; Singer, G.

    1980-11-01

    An analysis was made of siting issues in the coastal zone, one of the nation's most critical natural resource areas and one which is often the target for energy development proposals. The analysis addressed the changing perceptions of citizens toward energy development in the coastal zone, emphasizing urban communities where access to the waterfront and revitalization of waterfront property are of interest to the citizen. The case studies demonstrate the significance of local attitudes and regional cooperation in the siting process.

  4. Preclosure radiological safety analysis for the exploratory shaft facilities; Yucca Mountain Site Characterization Project

    SciTech Connect

    Ma, C.W.; Miller, D.D.; Jardine, L.J.

    1992-06-01

    This study assesses which structures, systems, and components of the exploratory shaft facility (ESF) are important to safety when the ESF is converted to become part of the operating waste repository. The assessment follows the methodology required by DOE Procedure AP-6.10Q. Failures of the converted ESF during the preclosure period have been evaluated, along with other underground accidents, to determine the potential offsite radiation doses and associated probabilities. The assessment indicates that failures of the ESF will not result in radiation doses greater than 0.5 rem at the nearest unrestricted area boundary. Furthermore, credible accidents in other underground facilities will not result in radiation doses larger than 0.5 rem, even if any structure, system, or component of the converted ESF fails at the same time. Therefore, no structure, system, or component of the converted ESF is important to safety.

  5. Reactor-pumped laser facility at DOE`s Nevada Test Site

    SciTech Connect

    Lipinski, R.J.

    1994-02-01

    The Nevada Test Site (NTS) is one excellent possibility for a laser power beaming site. It is in the low latitudes of the US, is in an exceptionally cloud-free area of the southwest, is already an area of restricted access (which enhances safety considerations), and possesses a highly-skilled technical team with extensive engineering and research capabilities from underground testing of our nation`s nuclear deterrence. The average availability of cloud-free clear line of site to a given point in space is about 84%. With a beaming angle of {plus_minus}60{degree} from the zenith, about 52 geostationary-orbit (GEO) satellites could be accessed continuously from NTS. In addition, the site would provide an average view factor of about 10% for orbital transfer from low earth orbit to GEO. One of the major candidates for a long-duration, high-power laser is a reactor-pumped laser being developed by DOE. The extensive nuclear expertise at NTS makes this site a prime candidate for utilizing the capabilities of a reactor pumped laser for power beaming. The site then could be used for many dual-use roles such as industrial material processing research, defense testing, and removing space debris.

  6. Reactor-pumped laser facility at DOE`s Nevada Test Site

    SciTech Connect

    Lipinski, R.J.

    1994-12-31

    The Nevada Test Site (NTS) is one excellent possibility for a laser power beaming site. It is in the low latitudes of the US, is in an exceptionally cloud-free area of the southwest, is already an area of restricted access (which enhances safety considerations), and possesses a highly-skilled technical team with extensive engineering and research capabilities from underground testing of their nation`s nuclear deterrence. The average availability of cloud-free clear line of site to a given point in space is about 84%. With a beaming angle of {+-}60{degree} from the zenith, about 52 geostationary-orbit (GEO) satellites could be accessed continuously from NTS. In addition, the site would provide an average view factor of about 10% for orbital transfer from low earth orbit to GEO. One of the major candidates for a long-duration, high-power laser is a reactor-pumped laser being developed by DOE. The extensive nuclear expertise at NTS makes this site a prime candidate for utilizing the capabilities of a reactor pumped laser for power beaming. The site then could be used for many dual-use roles such as industrial material processing research, defense testing, and removing space debris.

  7. DECOMMISSIONING OF THE 247-F FUEL MANUFACTURING FACILITY AT THE SAVANNAH RIVER SITE

    SciTech Connect

    Santos, J; Stephen Chostner, S

    2007-05-22

    Building 247-F at SRS was a roughly 110,000 ft{sup 2} two-story facility designed and constructed during the height of the cold war naval buildup to provide additional naval nuclear fuel manufacturing capacity in early 1980s. The building layout is shown in Fig. 1. A photograph of the facility is shown in Fig. 2. The manufacturing process employed a wide variety of acids, bases, and other hazardous materials. As the cold war wound down, the need for naval fuel declined. Consequently, the facility was shut down and underwent initial deactivation. All process systems were flushed with water and drained using the existing process drain valves. However, since these drains were not always installed at the lowest point in piping and equipment systems, a significant volume of liquid remained after initial deactivation was completed in 1990. At that time, a non-destructive assay of the process area identified approximately 17 (+/- 100%) kg of uranium held up in equipment and piping.

  8. Closure Report for Corrective Action Unit 117: Area 26 Pluto Disassembly Facility, Nevada Test Site, Nevada, Revision 0

    SciTech Connect

    Mark Burmeister

    2009-06-01

    This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 117: Area 26 Pluto Disassembly Facility, Nevada Test Site, Nevada. This CR complies with the requirements of the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. Corrective Action Unit 117 comprises Corrective Action Site (CAS) 26-41-01, Pluto Disassembly Facility, located in Area 26 of the Nevada Test Site. The purpose of this CR is to provide documentation supporting the completed corrective actions and provide data confirming that the closure objectives for CAU 117 were met. To achieve this, the following actions were performed: • Review the current site conditions, including the concentration and extent of contamination. • Implement any corrective actions necessary to protect human health and the environment. • Properly dispose of corrective action and investigation wastes. • Document Notice of Completion and closure of CAU 117 issued by the Nevada Division of Environmental Protection. From May 2008 through February 2009, closure activities were performed as set forth in the Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 117, Area 26 Pluto Disassembly Facility, Nevada Test Site, Nevada. The purpose of the activities as defined during the data quality objectives process were: • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent, implement appropriate corrective actions, and properly dispose of wastes. Analytes detected during the closure activities were evaluated against final action levels to determine COCs for CAU 117. Assessment of the data generated from closure activities indicated that the final action levels were exceeded for polychlorinated biphenyls (PCBs) reported as total Aroclor and

  9. 1993 RCRA Part B permit renewal application, Savannah River Site: Volume 10, Consolidated Incineration Facility, Section C, Revision 1

    SciTech Connect

    Molen, G.

    1993-08-01

    This section describes the chemical and physical nature of the RCRA regulated hazardous wastes to be handled, stored, and incinerated at the Consolidated Incineration Facility (CIF) at the Savannah River Site. It is in accordance with requirements of South Carolina Hazardous Waste Management Regulations R.61-79.264.13(a) and(b), and 270.14(b)(2). This application is for permit to store and teat these hazardous wastes as required for the operation of CIF. The permit is to cover the storage of hazardous waste in containers and of waste in six hazardous waste storage tanks. Treatment processes include incineration, solidification of ash, and neutralization of scrubber blowdown.

  10. Finding of no significant impact for the tritium facility modernization and consolidation project at the Savannah River Site

    SciTech Connect

    1998-01-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-1222) for the proposed modernization and consolidation of the existing tritium facilities at the Savannah River Site (SRS), located near Aiken, South Carolina. Based on the analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (NEPA). Therefore, the preparation of an environmental impact statement (EIS) is not required, and DOE is issueing this Finding of No Significant Impact (FONSI).

  11. Geohydrologic evaluation for the 200 Area Effluent Treatment Facility State-Approved Land Disposal Site: Addendum to WAC 173-240 Engineering Report

    SciTech Connect

    Ballantyne, N.A.

    1993-08-01

    This document provides a geohydrologic evaluation for the disposal of liquid effluent from the 200 Area Effluent Treatment Facility (ETF) at the Hanford Site. This work forms an addendum to the engineering report that supports the completion of the ETF.

  12. The theoretical analysis of the Fog removal in the LNG Ambient Vaporizer

    NASA Astrophysics Data System (ADS)

    Lee, T.; Lee, D.; Jeong, H.; Chung, H.

    2015-09-01

    The fog removal process is one of the important process in LNG Ambient Vaporizer. In this study we carried out theoretical study of the fog removal process in LNG Ambient Vaporizer. The LNG Ambient Vaporizer in Incheon area was used in our study. The fog temperature and the required energy produced from air fan to remove fog in LNG Ambient Vaporizer were calculated using average temperature of Incheon area in 2012 by Psychometruc Chart method. As a result we can be remove fog in LNG Ambient Vaporizer using Enthalpy[kW] energy in summer season and Enthalpy[kW] in winter season respectively.

  13. Decommissioning of the 247-F Fuel Manufacturing Facility at the Savannah River Site (SRS)

    SciTech Connect

    Santos, Joseph K.; Chostner, Stephen M.

    2008-01-15

    Building 247-F at SRS was a roughly 110,000 ft{sup 2} two-story facility designed and constructed during the height of the cold war naval buildup to provide additional naval nuclear fuel manufacturing capacity in early 1980's. The manufacturing process employed a wide variety of acids, bases, and other hazardous materials. As the need for naval fuel declined, the facility was shut down and underwent initial deactivation, which was completed in 1990. All process systems were flushed with water and drained using the existing process drain valves. However, since these drains were not always installed at the lowest point in piping and equipment systems, a significant volume of liquid remained after initial deactivation. After initial deactivation, a non-destructive assay of the process area identified approximately 17 ({+-}100%) kg of uranium held up in equipment and piping. The facility was placed in Surveillance and Maintenance mode until 2003, when the decision was made to perform final deactivation, and then decommission the facility. The following lessons were learned as a result of the D and D of building 247-F. Successful D and D of a major radiochemical process building requires significant up-front planning by a team of knowledgeable personnel led by a strong project manager. The level of uncertainty and resultant risk to timely, cost effective project execution was found to be high. Examples of the types of problems encountered which had high potential to adversely impact cost and schedule performance are described below. Low level and sanitary waste acceptance criteria do not allow free liquids in waste containers. These liquids, which are often corrosive, must be safely removed from the equipment before it is loaded to waste containers. Drained liquids must be properly managed, often as hazardous or mixed waste. Tapping and draining of process lines is a dangerous operation, which must be performed carefully. The temptation to become complacent when

  14. Intensive archaeological survey of the proposed Central Sanitary Wastewater Treatment Facility, Savannah River Site, Aiken and Barnwell Counties, South Carolina

    SciTech Connect

    Stephenson, D.K.; Sassaman, K.E.

    1993-11-01

    The project area for the proposed Central Sanitary Wastewater Treatment Facility on the Savannah River Site includes a six-acre tract along Fourmile Branch and 18 mi of trunk line corridors. Archaeological investigations of the six-acre parcel resulted in the discovery of one small prehistoric site designated 38AK465. This cultural resource does not have the potential to add significantly to archaeological knowledge of human occupation in the region. The Savannah River Archaeological Research Program (SRARP) therefore recommends that 38AK465 is not eligible for nomination to the National Register of Historic Places (NRHP) and further recommends a determination of no effect. Archaeological survey along the trunk line corridors implicated previously recorded sites 38AK92, 38AK145, 38AK415, 38AK417, 38AK419, and 38AK436. Past disturbance from construction had severely disturbed 38AK92 and no archaeological evidence of 38AK145, 38AK419, and 38AK436 was recovered during survey. Lacking further evidence for the existence of these sites, the SRARP recommends that 38AK92, 38AK145, 38AK419, and 38AK436 are not eligible for nomination to the NRHP and thus warrant a determination of no effect. Two of these sites, 38Ak415 and 38AK417, required further investigation to evaluate their archaeological significance. Both of the sites have the potential to yield significant data on the prehistoric period occupation of the Aiken Plateau and the SRARP recommends that they are eligible for nomination to the NRHP. The Savannah River Archaeological Research Program recommends that adverse effects to sites 38AK415 and 38AK417 from proposed construction can be mitigated through avoidance.

  15. Referenced-site environmental document for a Monitored Retrievable Storage facility: backup waste management option for handling 1800 MTU per year

    SciTech Connect

    Silviera, D.J.; Aaberg, R.L.; Cushing, C.E.; Marshall, A.; Scott, M.J.; Sewart, G.H.; Strenge, D.L.

    1985-06-01

    This environmental document includes a discussion of the purpose of a monitored retrievable storage facility, a description of two facility design concepts (sealed storage cask and field drywell), a description of three reference sites (arid, warm-wet, and cold-wet), and a discussion and comparison of the impacts associated with each of the six site/concept combinations. This analysis is based on a 15,000-MTU storage capacity and a throughput rate of up to 1800 MTU per year.

  16. Vegetation communities associated with the 100-Area and 200-Area facilities on the Hanford Site

    SciTech Connect

    Stegen, J.A.

    1994-01-17

    The Hanford Site, Benton County, Washington, lies within the broad semi-arid shrub-steppe vegetation zone of the Columbia Basin. Thirteen different habitat types on the Hanford Site have been mapped in Habitat Types on the Hanford Site: Wildlife and Plant Species of Concern (Downs et al. 1993). In a broad sense, this classification is correct. On a smaller scale, however, finer delineations are possible. This study was conducted to determine the plant communities and estimate vegetation cover in and directly adjacent to the 100 and 200 Areas, primarily in relation to waste sites, as part of a comprehensive ecological study for the Compensation Environmental Response, Compensation, and Liability Act (CERCLA) characterization of the 100 and 200 Areas. During the summer of 1993, field surveys were conducted and a map of vegetation communities in each area, including dominant species associations, was produced. The field surveys consisted of qualitative community delineations. The community delineations described were made by field reconnaissance and are qualitative in nature. The delineations were made by visually determining the dominant plant species or vegetation types and were based on the species most apparent at the time of inspection. Additionally, 38 transects were run in these plant communities to try to obtain a more accurate representation of the community. Because habitat disturbances from construction/operations activities continue to occur in these areas, users of this information should be cautious in applying these maps without a current ground survey. This work will complement large-scale habitat maps of the Hanford Site.

  17. Savannah River Site Mixed Waste Management Facility Southwest Plume Tritium Phytoremediation Evaluating Irrigation Management Strategies Over 25 Years

    SciTech Connect

    Riah, Susan; Rebel, Karin

    2004-02-27

    To minimize movement of tritium into surface waters at the Mixed Waste Management Facility at the Savannah River Site, tritium contaminated seepage water is being retained in a constructed pond and used to irrigate forest acreage that lies above the pond and over the contaminated groundwater. Twenty five-year potential evapotranspiration and average precipitation are 1443 mm/year and 1127 mm/year, respectively, for the region in which the site is located. Management of the application of tritium contaminated irrigation water needs to be evaluated in the context of the large amount of rainfall relative to evapotranspiration, the strong seasonality in evapotranspiration, and intraannual and inter-annual variability in precipitation. A dynamic simulation model of water and tritium fluxes in the soil-plant-atmosphere continuum was developed to assess the efficiency (tritium transpired/tritium applied) of several irrigation management strategies.

  18. Recommended Method To Account For Daughter Ingrowth For The Portsmouth On-Site Waste Disposal Facility Performance Assessment Modeling

    SciTech Connect

    Phifer, Mark A.; Smith, Frank G. III

    2013-06-21

    A 3-D STOMP model has been developed for the Portsmouth On-Site Waste Disposal Facility (OSWDF) at Site D as outlined in Appendix K of FBP 2013. This model projects the flow and transport of the following radionuclides to various points of assessments: Tc-99, U-234, U-235, U-236, U-238, Am-241, Np-237, Pu-238, Pu-239, Pu-240, Th-228, and Th-230. The model includes the radioactive decay of these parents, but does not include the associated daughter ingrowth because the STOMP model does not have the capability to model daughter ingrowth. The Savannah River National Laboratory (SRNL) provides herein a recommended method to account for daughter ingrowth in association with the Portsmouth OSWDF Performance Assessment (PA) modeling.

  19. Geotechnical characterization of the North Ramp of the Exploratory Studies Facility: Yucca Mountain Site Characterization Project. Volume 1, Data summary

    SciTech Connect

    Brechtel, C.E.; Lin, Ming; Martin, E.; Kessel, D.S.

    1995-05-01

    This report presents the results of geological and geotechnical characterization of the Miocene volcanic tuff rocks of the Timber Mountain and Paintbrush groups that the tunnel boring machine will encounter during excavation of the Exploratory Studies Facility (ESF) North Ramp. The is being constructed by the DOE as part of the Yucca Mountain Project site characterization activities. The purpose of these activities is to evaluate the feasibility of locating a potential high-level nuclear waste repository on lands adjacent to the Nevada Test Site, Nye County, Nevada. This report was prepared as part of the Soil and Rock Properties Studies in accordance with the 8.3.1.14.2 Study Plan. This report is volume 1 of the data summary.

  20. Summary of treatment, storage, and disposal facility usage data collected from U.S. Department of Energy sites

    SciTech Connect

    Jacobs, A.; Oswald, K.; Trump, C.

    1995-04-01

    This report presents an analysis for the US Department of Energy (DOE) to determine the level and extent of treatment, storage, and disposal facility (TSDF) assessment duplication. Commercial TSDFs are used as an integral part of the hazardous waste management process for those DOE sites that generate hazardous waste. Data regarding the DOE sites` usage have been extracted from three sets of data and analyzed in this report. The data are presented both qualitatively and quantitatively, as appropriate. This information provides the basis for further analysis of assessment duplication to be documented in issue papers as appropriate. Once the issues have been identified and adequately defined, corrective measures will be proposed and subsequently implemented.

  1. Results of Surveys for Special Status Reptiles at the Site 300 Facilities of Lawrence Livermore National Laboratory

    SciTech Connect

    Woollett, J J

    2008-09-18

    The purpose of this report is to present the results of a live-trapping and visual surveys for special status reptiles at the Site 300 Facilities of Lawrence Livermore National Laboratory (LLNL). The survey was conducted under the authority of the Federal recovery permit of Swaim Biological Consulting (PRT-815537) and a Memorandum of Understanding issued from the California Department of Fish and Game. Site 300 is located between Livermore and Tracy just north of Tesla road (Alameda County) and Corral Hollow Road (San Joaquin County) and straddles the Alameda and San Joaquin County line (Figures 1 and 2). It encompasses portions of the USGS 7.5 minute Midway and Tracy quadrangles (Figure 2). Focused surveys were conducted for four special status reptiles including the Alameda whipsnake (Masticophis lateralis euryxanthus), the San Joaquin Whipsnake (Masticophis Hagellum ruddock), the silvery legless lizard (Anniella pulchra pulchra), and the California horned lizard (Phrynosoma coronanum frontale).

  2. Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 114: Area 25 EMAD Facility Nevada Test Site, Nevada

    SciTech Connect

    Mark Krauss

    2010-06-01

    This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the actions needed to achieve closure for Corrective Action Unit (CAU) 114, Area 25 EMAD Facility, identified in the Federal Facility Agreement and Consent Order (FFACO). Corrective Action Unit 114 comprises the following corrective action site (CAS) located in Area 25 of the Nevada Test Site: • 25-41-03, EMAD Facility This plan provides the methodology for field activities needed to gather the necessary information for closing CAS 25-41-03. There is sufficient information and process knowledge from historical documentation and investigations of similar sites regarding the expected nature and extent of potential contaminants to recommend closure of CAU 114 using the SAFER process. Additional information will be obtained by conducting a field investigation before selecting the appropriate corrective action for CAS 25-41-03. It is anticipated that the results of the field investigation and implementation of corrective actions will support a defensible recommendation that no further corrective action is necessary. If it is determined that complete clean closure cannot be accomplished during the SAFER, then a hold point will have been reached and the Nevada Division of Environmental Protection (NDEP) will be consulted to determine whether the remaining contamination will be closed under the alternative corrective action of closure in place. This will be presented in a closure report that will be prepared and submitted to NDEP for review and approval. The CAS will be investigated based on the data quality objectives (DQOs) developed on April 30, 2009, by representatives of NDEP and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to determine and implement appropriate corrective actions for CAS 25-41-03. The following text summarizes the SAFER

  3. Hawaii energy strategy project 2: Fossil energy review. Task 3 -- Greenfield options: Prospects for LNG use

    SciTech Connect

    Breazeale, K.; Fesharaki, F.; Fridley, D.; Pezeshki, S.; Wu, K.

    1993-12-01

    This paper begins with an overview of the Asia-Pacific LNG market, its major players, and the likely availability of LNG supplies in the region. The discussion then examines the possibilities for the economic supply of LNG to Hawaii, the potential Hawaiian market, and the viability of an LNG project on Oahu. This survey is far from a complete technical assessment or an actual engineering/feasibility study. The economics alone cannot justify LNG`s introduction. The debate may continue as to whether fuel diversification and environmental reasons can outweigh the higher costs. Several points are made. LNG is not a spot commodity. Switching to LNG in Hawaii would require a massive, long-term commitment and substantial investments. LNG supplies are growing very tight in the Asia-Pacific region. Some of the environmental benefits of LNG are not entirely relevant in Hawaii because Hawaii`s air quality is generally excellent. Any air quality benefits may be more than counterbalanced by the environmental hazards connected with large-scale coastal zone construction, and by the safety hazards of LNG carriers, pipelines, etc. Lastly, LNG is not suitable for all energy uses, and is likely to be entirely unsuitable for neighbor island energy needs.

  4. LNG SAFETY RESEARCH: FEM3A MODEL DEVELOPMENT

    SciTech Connect

    Jerry Havens; Iraj A. Salehi

    2005-02-21

    This quarterly report for DE-FG26-04NT42030 covers a period from October 1, 2004 to December 31, 2004. On December 9, 2004 a meeting was held in Morgantown to rescope the LNG safety modeling project such that the work would complement the DOE's efforts relative to the development of the intended LNG-Fluent model. It was noted and discussed at the December 9th meeting that the fundamental research being performed on surface to cloud heat transfer and low wind speed issues will be relevant to the development of the DOE LNG/Fluent Model. In general, it was decided that all research to be performed from December 9th through the remainder of the contract is to be focused on the development of the DOE LNG/Fluent model. In addition, all GTI activities for dissemination and transfer of FEM3A will cease and dissemination activities will focus on the new DOE LNG/Fluent model. The proposed new scope of work is presented in section 4 of this report. The work reported in the present document relates to the original scope of work which was in effect during the reporting period. The future work will be re-scoped to meet the requirements of the new scope of work. During the report period work was underway to address numerical problems present during simulation of low-wind-speed, stable, atmospheric conditions with FEM3A. Steps 1 and 2 in the plan outlined in the first Quarterly report are complete and steps 3 and 4 are in progress. During this quarter, the University of Arkansas has been investigating the effect upon numerical stability of the heat transfer model used to predict the surface-to-cloud heat transfer, which can be important for LNG vapor dispersion. Previously, no consideration has been given to ground cooling as a result of heat transfer to the colder gas cloud in FEM3A.

  5. Site handbook: data acquisition system information, passive solar retrofit Automobile Maintenance Facility, City of Philadelphia

    SciTech Connect

    Not Available

    1985-01-01

    Data were collected at the City of Philadelphia's Auto Maintenance Facility using an Aeoloan Kinetics PDL-24 data acquisition system. Instantaneous data readings were recorded each 15 seconds by the microprocessor. These channel readings were then averaged to produce hourly values which were then stored on an audio cassette. The energy saving strategies include: styrofoam and concrete roof coverings; weatherstripping; replacement of north windows with combination insulation and view glazing; PVC strips between heated and unheated areas; gas fired radiant heaters at individual work stations; reduction of the number of light fixtures; and the installation of retrofit window units for radiant solar heating, daylighting, ventilation, glare control and vandalism protection.

  6. An LNG release, transport, and fate model system for marine spills.

    PubMed

    Spaulding, Malcolm L; Swanson, J Craig; Jayko, Kathy; Whittier, Nicole

    2007-02-20

    LNGMAP, a fully integrated, geographic information based modular system, has been developed to predict the fate and transport of marine spills of LNG. The model is organized as a discrete set of linked algorithms that represent the processes (time dependent release rate, spreading, transport on the water surface, evaporation from the water surface, transport and dispersion in the atmosphere, and, if ignited, burning and associated radiated heat fields) affecting LNG once it is released into the environment. A particle-based approach is employed in which discrete masses of LNG released from the source are modeled as individual masses of LNG or spillets. The model is designed to predict the gas mass balance as a function of time and to display the spatial and temporal evolution of the gas (and radiated energy field). LNGMAP has been validated by comparisons to predictions of models developed by ABS Consulting and Sandia for time dependent point releases from a draining tank, with and without burning. Simulations were in excellent agreement with those performed by ABS Consulting and consistent with Sandia's steady state results. To illustrate the model predictive capability for realistic emergency scenarios, simulations were performed for a tanker entering Block Island Sound. Three hypothetical cases were studied: the first assumes the vessel continues on course after the spill starts, the second that the vessel stops as soon as practical after the release begins (3 min), and the third that the vessel grounds at the closest site practical. The model shows that the areas of the surface pool and the incident thermal radiation field (with burning) are minimized and dispersed vapor cloud area (without burning) maximized if the vessel continues on course. For this case the surface pool area, with burning, is substantially smaller than for the without burning case because of the higher mass loss rate from the surface pool due to burning. Since the vessel speed substantially

  7. Insights Into Contamination Control For The Shuttle Payload Integration Facility (SPIF) At The Eastern Launch Site (ELS)

    NASA Astrophysics Data System (ADS)

    Pugel, Nancy J.

    1982-02-01

    The Shuttle Payload Integration Facility (SPIF) is a payload processing facility at the Eastern Launch Site (ELS), Cape Canaveral Air Force Station (CCAFS) which has been designed to accommodate assembly, test, and checkout operations for a number of Shuttle payloads, many of which are contamination sensitive. In general, the SPIF was designed to meet class 100,000, per Fed. Std. 209B (Reference 1), cleanliness requirements and operate as a class 100,000 clean area. However, due to the expansiveness of the building (which includes several airlocks, a transfer aisle, and integration cells), the variety of hardware to be processed through the facility (payloads, upper states, and support equipment), and the variety of operations to be performed for these hardware, many different contamination control methods must be carefully integrated and implemented to maintain an overall clean environment. In instances where the operation being performed is not generally compatible with the clean environment, uniaue and innovative contamination control methods must be developed with respect to ease of implementation as well as effectiveness of contamination control.

  8. Comparison of CNG and LNG technologies for transportation applications

    SciTech Connect

    Sinor, J.E. Consultants, Inc., Niwot, CO )

    1992-01-01

    This report provides a head-to-head comparison of compressed natural gas (CNG) and liquefied natural gas (LNG) supplied to heavy-duty vehicles. The comparison includes an assessment of the overall efficiency of the fuel delivery system, the cost of the fuel supply system, the efficiency of use in heavy-duty vehicles, and the environmental impact of each technology. The report concludes that there are applications in which CNG will have the advantage, and applications in which LNG will be preferred.

  9. Marsoweb: A Collaborative Web Facility for Mars Landing Site and Global Data Studies

    NASA Technical Reports Server (NTRS)

    Deardorff, D. G.; Gulick, V. C.; Briggs, G. A.

    2002-01-01

    Marsoweb is an evolving collaborative web environment for interactive 2D and 3D graphical analysis of data for Mars landing site studies, as well as for global Mars datasets of general scientific interest. Additional information is contained in the original extended abstract.

  10. 10 CFR 61.52 - Land disposal facility operation and disposal site closure.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... United States Geological Survey (USGS) or National Geodetic Survey (NGS) survey control stations, must be established on the site to facilitate surveys. The USGS or NGS control stations must provide horizontal and vertical controls as checked against USGS or NGS record files. (8) A buffer zone of land must be...

  11. Review of analytical results from the proposed agent disposal facility site, Aberdeen Proving Ground

    SciTech Connect

    Brubaker, K.L.; Reed, L.L.; Myers, S.W.; Shepard, L.T.; Sydelko, T.G.

    1997-09-01

    Argonne National Laboratory reviewed the analytical results from 57 composite soil samples collected in the Bush River area of Aberdeen Proving Ground, Maryland. A suite of 16 analytical tests involving 11 different SW-846 methods was used to detect a wide range of organic and inorganic contaminants. One method (BTEX) was considered redundant, and two {open_quotes}single-number{close_quotes} methods (TPH and TOX) were found to lack the required specificity to yield unambiguous results, especially in a preliminary investigation. Volatile analytes detected at the site include 1, 1,2,2-tetrachloroethane, trichloroethylene, and tetrachloroethylene, all of which probably represent residual site contamination from past activities. Other volatile analytes detected include toluene, tridecane, methylene chloride, and trichlorofluoromethane. These compounds are probably not associated with site contamination but likely represent cross-contamination or, in the case of tridecane, a naturally occurring material. Semivolatile analytes detected include three different phthalates and low part-per-billion amounts of the pesticide DDT and its degradation product DDE. The pesticide could represent residual site contamination from past activities, and the phthalates are likely due, in part, to cross-contamination during sample handling. A number of high-molecular-weight hydrocarbons and hydrocarbon derivatives were detected and were probably naturally occurring compounds. 4 refs., 1 fig., 8 tabs.

  12. THE OHIO RIVER BASIN ENERGY FACILITY SITING MODEL. VOLUME I: METHODOLOGY

    EPA Science Inventory

    This report was prepared as part of the Ohio River Basin Energy Study (ORBES), a multidisciplinary policy research program supported by the Environmental Protection Agency. The siting model developed for ORBES is specifically designed for regional policy analysis. The region incl...

  13. Recent ORNL experience in site performance prediction: the Gas Centrifuge Enrichment Plant and the Oak Ridge Central Waste Disposal Facility

    SciTech Connect

    Pin, F.G.

    1985-01-01

    The suitability of the Portsmouth Gas Centrifuge Enrichment Plant Landfill and the Oak Ridge, Tennessee, Central Waste Disposal Facility for disposal of low-level radioactive waste was evaluated using pathways analyses. For these evaluations, a conservative approach was selected; that is, conservatism was built into the analyses when assumptions concerning future events had to be made or when uncertainties concerning site or waste characteristics existed. Data from comprehensive laboratory and field investigations were used in developing the conceptual and numerical models that served as the basis for the numerical simulations of the long-term transport of contamination to man. However, the analyses relied on conservative scenarios to describe the generation and migration of contamination and the potential human exposure to the waste. Maximum potential doses to man were calculated and compared to the appropriate standards. Even under this conservative framework, the sites were found to provide adequate buffer to persons outside the DOE reservations and conclusions concerning site capacity and site acceptability were drawn. Our experience through these studies has shown that in reaching conclusions in such studies, some consideration must be given to the uncertainties and conservatisms involved in the analyses. Analytical methods to quantitatively assess the probability of future events to occur and to quantitatively determine the sensitivity of the results to data uncertainty may prove useful in relaxing some of the conservatism built into the analyses. The applicability of such methods to pathways analyses is briefly discussed.

  14. Ecological studies related to construction of the Defense Waste Processing Facility on the Savannah River Site. Annual report, FY 1993

    SciTech Connect

    1994-11-01

    Construction of the Defense Waste Processing Facility (DWPF) on the Savannah River Site (SRS) began during FY-1984. The Savannah River Ecology Laboratory (SREL) has completed 15 years of ecological studies related to the construction of the DWPF complex. Prior to construction, the 600-acre site (S-Area) contained a Carolina bay and the headwaters of a stream. Through the long-term census taking of biota at the DWPF site and Rainbow Bay, SREL has been evaluating the impact of construction on the biota and the effectiveness of mitigation efforts. similarly, the effects of erosion from the DWPF site on the water quality of S-Area peripheral streams are being assessed. This research provides supporting data relevant to the National Environmental Policy Act (NEPA) of 1969, the Endangered Species Act of 1973, Executive orders 11988 (Floodplain Management) and 11990 (Protection of Wetlands), and United States Department of Energy (DOE) Guidelines for Compliance with Floodplain/Wetland Environmental Review Requirements (10 CFR 1022).

  15. Ecological survey for the siting of the Mixed and Low-Level Waste Treatment Facility and the Idaho Waste Processing Facility

    SciTech Connect

    Hoskinson, R.L.

    1994-05-01

    This report summarizes the results of field ecological surveys conducted by the Center for Integrated Environmental Technologies (CIET) on the Idaho National Engineering Laboratory (INEL) at four candidate locations for the siting of the Mixed and Low-Level Waste Treatment Facility (MLLWTF) and the Idaho Waste Processing Facility (IWPF). The purpose of these surveys was to comply with all Federal laws and Executive Orders to identify and evaluate any potential environmental impacts because of the project. The boundaries of the candidate location were marked with blaze-orange lath survey marker stakes by the project management. Global Positioning System (GPS) measurements of the marker stakes were made, and input to the Arc/Info{reg_sign} geographic information system (GIS). Field surveys were conducted to assess any potential impact to any important species, important habitats, and to any environmental study areas. The GIS location data was overlayed onto the INEL vegetation map and an analysis of vegetation classes on the locations was done. Results of the field surveys indicate use of Candidate Location {number_sign}1 by pygmy rabbits (Sylvilagus idahoensis) and expected use by them of Candidate Locations {number_sign}3 and {number_sign}9. Pygmy rabbits are categorized as a C2 species by the US Fish and Wildlife Service (USFWS). Two other C2 species, the ferruginous hawk (Buteo regalis) and the loggerhead shrike (Lanius ludovicianus) would also be expected to frequent the candidate locations. Candidate Location {number_sign}5 at the north end of the INEL is in the winter range of a large number of pronghorn antelope (Antilocapra americana).

  16. A facile reflux procedure to increase active surface sites form highly active and durable supported palladium@platinum bimetallic nanodendrites

    NASA Astrophysics Data System (ADS)

    Wang, Qin; Li, Yingjun; Liu, Baocang; Xu, Guangran; Zhang, Geng; Zhao, Qi; Zhang, Jun

    2015-11-01

    A series of well-dispersed bimetallic Pd@Pt nanodendrites uniformly supported on XC-72 carbon black are fabricated by using different capping agents. These capping agents are essential for the branched morphology control. However, the surfactant adsorbed on the nanodendrites surface blocks the access of reactant molecules to the active surface sites, and the catalytic activities of these bimetallic nanodendrites are significantly restricted. Herein, a facile reflux procedure to effectively remove the capping agent molecules without significantly affecting their sizes is reported for activating supported nanocatalysts. More significantly, the structure and morphology of the nanodendrites can also be retained, enhancing the numbers of active surface sites, catalytic activity and stability toward methanol and ethanol electro-oxidation reactions. The as-obtained hot water reflux-treated Pd@Pt/C catalyst manifests superior catalytic activity and stability both in terms of surface and mass specific activities, as compared to the untreated catalysts and the commercial Pt/C and Pd/C catalysts. We anticipate that this effective and facile removal method has more general applicability to highly active nanocatalysts prepared with various surfactants, and should lead to improvements in environmental protection and energy production.

  17. Linde FUSRAP Site Remediation: Engineering Challenges and Solutions of Remedial Activities on an Active Industrial Facility - 13506

    SciTech Connect

    Beres, Christopher M.; Fort, E. Joseph; Boyle, James D.

    2013-07-01

    The Linde FUSRAP Site (Linde) is located in Tonawanda, New York at a major research and development facility for Praxair, Inc. (Praxair). Successful remediation activities at Linde combines meeting cleanup objectives of radiological contamination while minimizing impacts to Praxair business operations. The unique use of Praxair's property coupled with an array of active and abandoned utilities poses many engineering and operational challenges; each of which has been overcome during the remedial action at Linde. The U.S. Army Corps of Engineers - Buffalo District (USACE) and CABRERA SERVICES, INC. (CABRERA) have successfully faced engineering challenges such as relocation of an aboveground structure, structural protection of an active water line, and installation of active mechanical, electrical, and communication utilities to perform remediation. As remediation nears completion, continued success of engineering challenges is critical as remaining activities exist in the vicinity of infrastructure essential to business operations; an electrical substation and duct bank providing power throughout the Praxair facility. Emphasis on engineering and operations through final remediation and into site restoration will allow for the safe and successful completion of the project. (authors)

  18. 1994 Baseline biological studies for the Device Assembly Facility at the Nevada Test Site

    SciTech Connect

    Townsend, Y.E.; Woodward, B.D.; Hunter, R.B.; Greger, P.D.; Saethre, M.B.

    1995-02-01

    This report describes environmental work performed at the Device Assembly Facility (DAF) in 1994 by the Basic Environmental Monitoring and Compliance Program (BECAMP). The DAF is located near the Mojave-Great Basin desert transition zone 27 km north of Mercury. The area immediately around the DAF building complex is a gentle slope cut by 1 to 3 m deep arroyos, and occupied by transitional vegetation. In 1994, construction activities were largely limited to work inside the perimeter fence. The DAF was still in a preoperational mode in 1994, and no nuclear materials were present. The DAF facilities were being occupied so there was water in the sewage settling pond, and the roads and lights were in use. Sampling activities in 1994 represent the first year in the proposed monitoring scheme. The proposed biological monitoring plan gives detailed experimental protocols. Plant, lizard, tortoise, small mammal, and bird surveys were performed in 1994. The authors briefly outline procedures employed in 1994. Studies performed on each taxon are reviewed separately then summarized in a concluding section.

  19. Evaluation of the 183-D Water Filtration Facility for Bat Roosts and Development of a Mitigation Strategy, 100-D Area, Hanford Site

    SciTech Connect

    Lindsey, C. T.; Gano, K. A.; Lucas, J. G.

    2011-03-07

    The 183-D Water Filtration Facility is located in the 100-D Area of the Hanford Site, north of Richland, Washington. It was used to provide filtered water for cooling the 105-D Reactor and supplying fire-protection and drinking water for all facilities in the 100-D Area. The facility has been inactive since the 1980s and is now scheduled for demolition. Therefore, an evaluation was conducted to determine if any part of the facility was being used as roosting habitat by bats.

  20. Process centrifuge operating problems and equipment failures in canyon reprocessing facilities at the Savannah River Site

    SciTech Connect

    Durant, W.S.; Baughman, D.F.

    1990-03-01

    The Savannah River Laboratory (SRL) maintains a compilation of operating problems and equipment failures that have occurred in the fuel reprocessing areas of the Savannah River Site (SRS). At present, the data bank contains more than 230,000 entries ranging from minor equipment malfunctions to incidents with the potential for injury or contamination of personnel, or for economic loss. The data bank has been used extensively for a wide variety of purposes, such as failure analyses, trend analyses, and preparation of safety analyses. Typical of the data are problems associated with the canyon process centrifuges. This report contains a compilation of the centrifuge operating problems and equipment failures primarily as an aid to organizations with related equipment. Publication of these data was prompted by a number of requests for this information by other Department of Energy (DOE) sites. 11 refs., 2 figs., 4 tabs.

  1. Site Studies for the SuperB Collider and Synchrotron Radiation Facility Project

    SciTech Connect

    Tomassini, S.; Biagini, M.E.; Raimondi, P.; Sanelli, C.; Bolzon, B.; Deleglise, G.; Jeremie, A.; Seeman, J.; /SLAC

    2012-04-26

    The SuperB complex project aims at the construction of a very high luminosity (10{sup 36} cm{sup -2}s{sup -1}) asymmetric e{sup +}e{sup -} B-factory and a few X-ray synchrotron beam lines (SR). The project has been recently approved by the Italian Government as part of the National Research Plan. The Tor Vergata University location has been chosen and a Consortium among INFN, University of Rome II Tor Vergata and the Research Ministry is being signed, allowing for the constitution of the 'Cabibbo Laboratory', where the SuperB project will be hosted. This paper presents and describes the status of the preliminary design of the site layout, related issues for the chosen site and the preliminary ground motion (GM) measurement results.

  2. Installation and first operation of the International Fusion Materials Irradiation Facility injector at the Rokkasho site.

    PubMed

    Gobin, Raphael; Bogard, Daniel; Bolzon, Benoit; Bourdelle, Gilles; Chauvin, Nicolas; Chel, Stéphane; Girardot, Patrick; Gomes, Adelino; Guiho, Patrice; Harrault, Francis; Loiseau, Denis; Lussignol, Yves; Misiara, Nicolas; Roger, Arnaud; Senée, Franck; Valette, Matthieu; Cara, Philippe; Duglué, Daniel; Gex, Dominique; Okumura, Yoshikazu; Ayala, Juan Marcos; Knaster, Juan; Marqueta, Alvaro; Kasugai, Atsushi; O'Hira, Shigeru; Shinto, Katsuhiro; Takahashi, Hiroki

    2016-02-01

    The International Fusion Materials Irradiation Facility (IFMIF) linear IFMIF prototype accelerator injector dedicated to high intensity deuteron beam production has been designed, built, and tested at CEA/Saclay between 2008 and 2012. After the completion of the acceptance tests at Saclay, the injector has been fully sent to Japan. The re-assembly of the injector has been performed between March and May 2014. Then after the check-out phase, the production of the first proton beam occurred in November 2014. Hydrogen and deuteron beam commissioning is now in progress after having proceeded with the final tests on the entire injector equipment including high power diagnostics. This article reports the different phases of the injector installation pointing out the safety and security needs, as well as the first beam production results in Japan and chopper tests. Detailed operation and commissioning results (with H(+) and D(+) 100 keV beams) are reported in a second article. PMID:26931944

  3. Installation and first operation of the International Fusion Materials Irradiation Facility injector at the Rokkasho site

    NASA Astrophysics Data System (ADS)

    Gobin, Raphael; Bogard, Daniel; Bolzon, Benoit; Bourdelle, Gilles; Chauvin, Nicolas; Chel, Stéphane; Girardot, Patrick; Gomes, Adelino; Guiho, Patrice; Harrault, Francis; Loiseau, Denis; Lussignol, Yves; Misiara, Nicolas; Roger, Arnaud; Senée, Franck; Valette, Matthieu; Cara, Philippe; Duglué, Daniel; Gex, Dominique; Okumura, Yoshikazu; Marcos Ayala, Juan; Knaster, Juan; Marqueta, Alvaro; Kasugai, Atsushi; O'Hira, Shigeru; Shinto, Katsuhiro; Takahashi, Hiroki

    2016-02-01

    The International Fusion Materials Irradiation Facility (IFMIF) linear IFMIF prototype accelerator injector dedicated to high intensity deuteron beam production has been designed, built, and tested at CEA/Saclay between 2008 and 2012. After the completion of the acceptance tests at Saclay, the injector has been fully sent to Japan. The re-assembly of the injector has been performed between March and May 2014. Then after the check-out phase, the production of the first proton beam occurred in November 2014. Hydrogen and deuteron beam commissioning is now in progress after having proceeded with the final tests on the entire injector equipment including high power diagnostics. This article reports the different phases of the injector installation pointing out the safety and security needs, as well as the first beam production results in Japan and chopper tests. Detailed operation and commissioning results (with H+ and D+ 100 keV beams) are reported in a second article.

  4. LANDFILL GAS CONVERSION TO LNG AND LCO{sub 2}. PHASE 1, FINAL REPORT FOR THE PERIOD MARCH 1998-FEBRUARY 1999

    SciTech Connect

    COOK,W.J.; NEYMAN,M.; SIWAJEK,L.A.; BROWN,W.R.; VAN HAUWAERT,P.M.; CURREN,E.D.

    1998-02-25

    Process designs and economics were developed to produce LNG and liquid carbon dioxide (CO{sub 2}) from landfill gas (LFG) using the Acrion CO{sub 2} wash process. The patented Acrion CO{sub 2} wash process uses liquid CO{sub 2} to absorb contaminants from the LFG. The process steps are compression, drying, CO{sub 2} wash contaminant removal and CO{sub 2} recovery, residual CO{sub 2} removal and methane liquefaction. Three flowsheets were developed using different residual CO{sub 2} removal schemes. These included physical solvent absorption (methanol), membranes and molecular sieves. The capital and operating costs of the flowsheets were very similar. The LNG production cost was around ten cents per gallon. In parallel with process flowsheet development, the business aspects of an eventual commercial project have been explored. The process was found to have significant potential commercial application. The business plan effort investigated the economics of LNG transportation, fueling, vehicle conversion, and markets. The commercial value of liquid CO{sub 2} was also investigated. This Phase 1 work, March 1998 through February 1999, was funded under Brookhaven National laboratory contract 725089 under the research program entitled ``Liquefied Natural Gas as a Heavy Vehicle Fuel.'' The Phase 2 effort will develop flowsheets for the following: (1) CO{sub 2} and pipeline gas production, with the pipeline methane being liquefied at a peak shaving site, (2) sewage digester gas as an alternate feedstock to LFG and (3) the use of mixed refrigerants for process cooling. Phase 2 will also study the modification of Acrion's process demonstration unit for the production of LNG and a market site for LNG production.

  5. The Site Investigation Of Low-Level Radioactive Waste For Sub-Surface Disposal Facility In Japan

    NASA Astrophysics Data System (ADS)

    Hosoya, S.; Sasaki, T.

    2006-12-01

    [1.Concept of the sub-surface disposal facility] In Japan, the facilities of Low-Level Radioactive West (LLW) for near-surface disposal have already been in operation. Japan Nuclear Fuel Limited (JNFL) has a plan of a new facility of LLW for sub-surface disposal with engineered barrier, for short "the sub-surface disposal facility".This facility can accept the relatively higher low-level waste from unclear power plant operation and in core materials from the decommissioning, estimated about 20 thousands cubic meter in total.In addition, this will accept transuranim (TRU) slightly contaminated waste from reprocessing plant operation and decommissioning. It shall be located at a sufficient depth enough to avoid normal human activities in future. [2.Site investigation] From 2001 to 2006,the site investigation on geology and hydrogeology has been performed in order to acquire the basic data for the design and the safety assessment for the sub-surface disposal facility.The candidate area is located at the site of JNFL, where Rokkasho-mura, Aomori Prefecture in the northern area of the Mainland of Japan.To confirm geology hydraulic conditions and geo-chemistry, 22 boring survey including 6 holes in swamp and marsh have been performed. The 1km long access tunnel (the entrance level EL 8.0m, incline of 1/10) to the altitude of EL -86m underground, around 100m depth from surface, has excavated. During excavating the tunnel, observation of geology, permeability tests, pore water pressure measurements and so on has been performed in situ.And the large size test cavern of 18m diameters was constructed at the end of the tunnel to demonstrate stability of the tunnel. Prior to the excavation, 3 measuring tunnels were excavated surrounding the test cavern to examine the excavation. [3.Geological features] The sedimentary rock called Takahoko formation at the Neogene period is distributed upper than EL-500m in the candidate area.The quaternary stratum about 10m in thickness is

  6. An arid zone lysimeter facility for performance assessment and closure investigations at the Nevada Test Site

    SciTech Connect

    Levitt, D.G.; Lohrstorfer, C.F.; Sully, M.J.; Ginanni, J.M.

    1996-07-01

    Two precision weighing lysimeters were installed near the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada Test Site to provide support for investigations of water, solute, and heat fluxes in the near-surface of the soil. The lysimeters consist of soil tanks with a volume of 16 cubic meters mounted on a sensitive scale. One lysimeter was revegetated with native shrubs whereas the other was kept bare to stimulate a non-vegetated waste cover. Data consisting of physical and hydrological properties of the lysimeter soils, thermal and moisture conditions in the lysimeters, and atmospheric boundary conditions are being collected for calibrating and verifying computer models for simulating the flow of water and heat in the near surface alluvium at the Area 5 RWMS. This effort will provide site- specific models for demonstration of ``no migration`` of constituents to the water table. Moisture and thermal conditions in the lysimeters are monitored daily using time domain reflectometry probes and thermocouple psychrometers. Daily evaporation and evapotranspiration are calculated from the lysimeter scales. Meteorological variables are monitored by sensors mounted on a 3 meter tower adjacent to the lysimeters. An array of soil-solution samplers to be installed through the side of the soil tank will allow studies of waste mobility under natural conditions. Conceptual designs for closure at the RWMS are focused on using an upper layer of repacked native alluvium, which can be tested with the lysimeters. In addition, performance of other components such as a capillary barrier can be tested by installing a scaled version in one of the lysimeter tanks.

  7. Closure Strategy for a Waste Disposal Facility with Multiple Waste Types and Regulatory Drivers at the Nevada Test Site

    SciTech Connect

    L. Desotell; D. Wieland; V. Yucel; G. Shott; J. Wrapp

    2008-03-01

    The U.S. Department of Energy, National Security Administration Nevada Site Office (NNSA/NSO) is planning to close the 92-Acre Area of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS), which is about 65 miles northwest of Las Vegas, Nevada. Closure planning for this facility must take into account the regulatory requirements for a diversity of waste streams, disposal and storage configurations, disposal history, and site conditions. This paper provides a brief background of the Area 5 RWMS, identifies key closure issues, and presents the closure strategy. Disposals have been made in 25 shallow excavated pits and trenches and 13 Greater Confinement Disposal (GCD) boreholes at the 92-Acre Area since 1961. The pits and trenches have been used to dispose unclassified low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform waste, and to store classified low-level and low-level mixed materials. The GCD boreholes are intermediate-depth disposal units about 10 feet (ft) in diameter and 120 ft deep. Classified and unclassified high-specific activity LLW, transuranic (TRU), and mixed TRU are disposed in the GCD boreholes. TRU waste was also disposed inadvertently in trench T-04C. Except for three disposal units that are active, all pits and trenches are operationally covered with 8-ft thick alluvium. The 92-Acre Area also includes a Mixed Waste Disposal Unit (MWDU) operating under Resource Conservation and Recovery Act (RCRA) Interim Status, and an asbestiform waste unit operating under a state of Nevada Solid Waste Disposal Site Permit. A single final closure cover is envisioned over the 92-Acre Area. The cover is the evapotranspirative-type cover that has been successfully employed at the NTS. Closure, post-closure care, and monitoring must meet the requirements of the following regulations: U.S. Department of Energy Order 435.1, Title 40 Code of Federal Regulations (CFR) Part 191, Title 40 CFR Part 265, Nevada Administrative

  8. A brief history of the T Plant facility at the Hanford Site. Addendum 1

    SciTech Connect

    Gerber, M.S.

    1994-05-16

    T Plant (221-T) was the first and largest of the early chemical separations plants at the Hanford Engineer Works (HEW) (World War II name for the Hanford Site). Officially designated as a Cell Building by the Manhattan Engineer District (MED) of the Army Corps of Engineers (agency responsible for HEW), T Plant served as the headquarters of chemical processing operations at Hanford from its construction until the opening of the REDOX Plant in January 1952. Because it formed a crucial link in the first full-scale plutonium production operations in world history, it meets criteria established in the National Historic Preservation Act of 1966 as a National Historic Structure.

  9. Study of launch site processing and facilities for future launch vehicles

    NASA Astrophysics Data System (ADS)

    Shaffer, Rex

    1995-03-01

    The purpose of this research is to provide innovative and creative approaches to assess the impact to the Kennedy Space Center and other launch sites for a range of candidate manned and unmanned space transportation systems. The general scope of the research includes the engineering activities, analyses, and evaluations defined in the four tasks below: (1) development of innovative approaches and computer aided tools; (2) operations analyses of launch vehicle concepts and designs; (3) assessment of ground operations impacts; and (4) development of methodologies to identify promising technologies.

  10. Study of launch site processing and facilities for future launch vehicles

    NASA Technical Reports Server (NTRS)

    Shaffer, Rex

    1995-01-01

    The purpose of this research is to provide innovative and creative approaches to assess the impact to the Kennedy Space Center and other launch sites for a range of candidate manned and unmanned space transportation systems. The general scope of the research includes the engineering activities, analyses, and evaluations defined in the four tasks below: (1) development of innovative approaches and computer aided tools; (2) operations analyses of launch vehicle concepts and designs; (3) assessment of ground operations impacts; and (4) development of methodologies to identify promising technologies.

  11. SAVANNAH RIVER SITE'S H-CANYON FACILITY: IMPACTS OF FOREIGN OBLIGATIONS ON SPECIAL NUCLEAR MATERIAL DISPOSITION

    SciTech Connect

    Magoulas, V.

    2013-06-03

    The US has a non-proliferation policy to receive foreign and domestic research reactor returns of spent fuel materials of US origin. These spent fuel materials are returned to the Department of Energy (DOE) and placed in storage in the L-area spent fuel basin at the Savannah River Site (SRS). The foreign research reactor returns fall subject to the 123 agreements for peaceful cooperation. These “123 agreements” are named after section 123 of the Atomic Energy Act of 1954 and govern the conditions of nuclear cooperation with foreign partners. The SRS management of these foreign obligations while planning material disposition paths can be a challenge.

  12. Siting a municipal solid waste disposal facility, part II: the effects of external criteria on the final decision.

    PubMed

    Korucu, M Kemal; Karademir, Aykan

    2014-02-01

    The procedure of a multi-criteria decision analysis supported by the geographic information systems was applied to the site selection process of a planning municipal solid waste management practice based on twelve different scenarios. The scenarios included two different decision tree modes and two different weighting models for three different area requirements. The suitability rankings of the suitable sites obtained from the application of the decision procedure for the scenarios were assessed by a factorial experimental design concerning the effect of some external criteria on the final decision of the site selection process. The external criteria used in the factorial experimental design were defined as "Risk perception and approval of stakeholders" and "Visibility". The effects of the presence of these criteria in the decision trees were evaluated in detail. For a quantitative expression of the differentiations observed in the suitability rankings, the ranking data were subjected to ANOVA test after a normalization process. Then the results of these tests were evaluated by Tukey test to measure the effects of external criteria on the final decision. The results of Tukey tests indicated that the involvement of the external criteria into the decision trees produced statistically meaningful differentiations in the suitability rankings. Since the external criteria could cause considerable external costs during the operation of the disposal facilities, the presence of these criteria in the decision tree in addition to the other criteria related to environmental and legislative requisites could prevent subsequent external costs in the first place. PMID:24654382

  13. Possible explosive compounds in the Savannah River Site Tank Farm facilities. Revision 1

    SciTech Connect

    Hobbs, D.T.

    1995-04-27

    Since 1970, many studies have been conducted concerning the potential for explosive compounds in tank farm operations including ammonium nitrate, metal oxalates, and silver and mercury compounds. The study currently in progress is the most comprehensive to date, encompassing all previous studies and extending the scope to include all compounds that could be formed from the known species in SRS wastes. In addition to waste storage, the study also considers waste removal and waste processing operations. The total number of possible explosive compounds is so large that it would not be useful to list them all here. Instead, only those compounds are listed that are known to be present or could conceivably be formed from material that is known to be present in the waste. The general approach to the problem is: identify all of the constituents that are known to be present in the waste together with those that might be present from possible chemical and radiolytic reactions, determine the compounds that could be formed from these constituents, compare these compounds with those listed in the literature, and assess the formation and stability of these compounds against the conditions existing in the tank farm facilities.

  14. Preclosure radiological safety evaluation: Exploratory Studies Facility; Yucca Mountain Site Characterization Project

    SciTech Connect

    Schelling, F.J.; Smith, J.D.

    1993-07-01

    A radiological safety evaluation is performed to determine the impacts of Exploratory Studies Facility (ESF) design changes on the preclosure public radiological safety for a potential nuclear waste repository at Yucca Mountain, Nevada. Although the ESF design has undergone significant modification, incorporation of the modified design requires only modest changes to the conceptual repository configuration. To the extent feasible, the results of earlier safety evaluations presented in SAND84-2641, SAND88-7061, and SAND89-7024, which were based on the original ESF configuration, are compared with the results for the modified configuration. This comparison provides an estimate of the range of analysis uncertainty. This preliminary analysis indicates that there are no Q-scenarios, which are defined as those scenarios with a net occurrence probability of greater than 10{sup {minus}6}/yr and produce a radiological dose at the 5-km controlled area boundary of greater than 0.5 rem. The analysis yielded estimates for an underground accident of a probability of 3.8 {times} 10{sup {minus}15}/yr and a dose of 1.5 rem. For a surface-initiated accident, a probability of 1.5 {times} 10{sup {minus}12}/yr and a dose of 0.6 rem was estimated.

  15. Recent characterization activities of Midway Valley as a potential repository surface facility site

    SciTech Connect

    Gibson, J.D.; Wesling, J.R.; Swan, F.H.; Bullard, T.F.

    1992-01-31

    Midway Valley, located at the eastern base of Yucca Mountain, Nye County, Nevada, has been identified as a possible location for the surface facilities of a potential high-level nuclear-waste repository. This structural and topographic valley is bounded by two north- trending, down-to-the-west normal faults: the Paintbrush Canyon fault on the east and the Bow Ridge fault on the west. Surface and near-surface geological data have been acquired from Midway Valley during the past three years with particular emphasis on evaluating the existence of Quaternary faults. A detailed (1:6000) surficial geological map has been prepared based on interpretation of new and existing aerial photographs, field mapping, soil pits, and trenches. No evidence was found that would indicate displacement of these surficial deposits along previously unrecognized faults. However, given the low rates of Quaternary faulting and the extensive areas that are covered by late Pleistocene to Holocene deposits south of Sever Wash, Quaternary faulting between known faults cannot be precluded based on surface evidence alone. Middle to late Pleistocene alluvial fan deposits (Unit Q3) exist at or near the surface throughout Midway Valley. Confidence is increased that the potential for surface fault rupture in Midway Valley can be assessed by excavations that expose the deposits and soils associated with Unit Q3 or older units (middle Pleistocene or earlier).

  16. 76 FR 53425 - Pivotal LNG, Inc.; Notice of Application

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-26

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Pivotal LNG, Inc.; Notice of Application Take notice that on August 8, 2011... Federal Energy Regulatory Commission (Commission) an application under section 7(c) of the Natural Gas...

  17. Fire performance of LNG carriers insulated with polystyrene foam.

    PubMed

    Havens, Jerry; Venart, James

    2008-10-30

    Analysis of the response of a liquid-full Moss Sphere LNG tank insulated with polystyrene foam to an engulfing LNG fire indicates that current regulatory requirements for pressure relief capacity sufficient to prevent tank rupture are inadequate. The inadequacy of the current requirements stems primarily from two factors. Firstly, the area of the Moss Sphere protruding above what would be the nominal deck on a conventional carrier, which is protected only by a steel weather cover from exposure to heat from a tank-engulfing fire, is being underestimated. Secondly, aluminum foil-covered polystyrene foam insulation applied to the exterior of the LNG tank is protected above the deck only by the steel weather cover under which the insulation could begin to melt in as little as 1-3 min, and could completely liquefy in as few as 10 min. U.S. and International Regulations require that the insulations on the above-deck portion of tanks have approved fire proofing and stability under fire exposure. Polystyrene foam, as currently installed on LNG carriers, does not appear to meet these criteria. As a result of these findings, but giving no consideration to the significant potential for further damage if the polystyrene should burn, the boil-off rate is predicted to be an order-of-magnitude higher than provided for by current PRV sizing requirements. PMID:18372107

  18. Field experiments on high expansion (HEX) foam application for controlling LNG pool fire.

    PubMed

    Suardin, Jaffee A; Wang, Yanjun; Willson, Mike; Mannan, M Sam

    2009-06-15

    Previous research suggests that high expansion foam with an expansion ratio of 500 to 1 is one of the best options for controlling liquefied natural gas (LNG) pool fire on land. However, its effectiveness heavily depends on the foam application rate, foam generator location, and the design of LNG spill containment dike. Examination of these factors is necessary to achieve the maximum benefit for applying HEX on LNG pool fires. While theoretical study of the effects of foam on LNG fires is important, the complicated phenomena involved in LNG pool fire and foam application increase the need for LNG field experimentation. Therefore, five LNG experiments were conducted at Texas A&M University's Brayton Fire Training Field. ANGUS FIRE provided Expandol solution to form 500 to 1 high expansion foam (HEX) and its latest LNG Turbex Fixed High Expansion Foam Generators. In this paper, data collected during five experiments are presented and analyzed. The effectiveness of high expansion foam for controlling LNG pool fires with various application rates at two different types of containment pits is discussed. LNG fire behaviors and the effects of dike wall height are also presented and discussed. PMID:19056175

  19. Environmentally based siting assessment for synthetic-liquid-fuels facilities. Final report

    SciTech Connect

    1980-01-01

    A detailed assessment of the major environmental constraints to siting a synthetic fuels industry and the results of that assessment are used to determine on a regional basis the potential for development of such an industry with minimal environmental conflicts. Secondly, the ability to mitigate some of the constraining impacts through alternative institutional arrangements, especially in areas that are judged to have a low development potential is also assessed. Limitations of the study are delineated, but specifically, the study is limited geographically to well-defined boundaries that include the prime coal and oil shale resource areas. The critical factors used in developing the framework are air quality, water availability, socioeconomic capacity, ecological sensitivity, environmental health, and the management of Federally owned lands. (MCW)

  20. Underground facility for geoenvironmental and geotechnical research at the SSC Site in Texas

    SciTech Connect

    Wang, H.F.; Myer, L.R.

    1994-10-31

    The subsurface environment is an important national resource that is utilized for construction, waste disposal and groundwater supply. Conflicting and unwise use has led to problems of groundwater contamination. Cleanup is often difficult and expensive, and perhaps not even possible in many cases. Construction projects often encounter unanticipated difficulties that increase expenses. Many of the difficulties of predicting mechanical behavior and fluid flow and transport behavior stem from problems in characterizing what cannot be seen. An underground research laboratory, such as can be developed in the nearly 14 miles of tunnel at the Superconducting Super Collider (SSC) site, will provide a unique opportunity to advance scientific investigations of fluid flow, chemical transport, and mechanical behavior in situ in weak and fractured, porous rock on a scale relevant to civil and environmental engineering applications involving the subsurface down to a depth of 100 m. The unique element provided by underground studies at the SSC site is three-dimensional access to a range of fracture conditions in two rock types, chalk and shale. Detailed experimentation can be carried out in small sections of the SSC tunnel where different types of fractures and faults occur and where different rock types or contacts are exposed. The entire length of the tunnel can serve as an observatory for large scale mechanical and fluid flow testing. The most exciting opportunity is to mine back a volume of rock to conduct a post-experiment audit following injection of a number of reactive and conservative tracers. Flow paths and tracer distributions can be examined directly. The scientific goal is to test conceptual models and numerical predictions. In addition, mechanical and hydrological data may be of significant value in developing safe and effective methods for closing the tunnel itself.