Science.gov

Sample records for disposal facility designs

  1. Final Design Report for the RH LLW Disposal Facility (RDF) Project

    SciTech Connect

    Austad, S. L.

    2015-05-01

    The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

  2. Final Design Report for the RH LLW Disposal Facility (RDF) Project

    SciTech Connect

    Austad, Stephanie Lee

    2015-09-01

    The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

  3. Conceptual Design Report for Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect

    Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

    2010-10-01

    This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

  4. Preliminary Safety Design Report for Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect

    Timothy Solack; Carol Mason

    2012-03-01

    A new onsite, remote-handled low-level waste disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled low-level waste disposal for remote-handled low-level waste from the Idaho National Laboratory and for nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled low-level waste in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This preliminary safety design report supports the design of a proposed onsite remote-handled low-level waste disposal facility by providing an initial nuclear facility hazard categorization, by discussing site characteristics that impact accident analysis, by providing the facility and process information necessary to support the hazard analysis, by identifying and evaluating potential hazards for processes associated with onsite handling and disposal of remote-handled low-level waste, and by discussing the need for safety features that will become part of the facility design.

  5. Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect

    Boyd D. Christensen

    2010-05-01

    A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

  6. Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect

    Boyd D. Christensen

    2010-02-01

    A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

  7. 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).

  8. The design and licensing status of the Central Interstate Compact facility: An above-grade LLRW disposal facility

    SciTech Connect

    Gunning, J.E.; Sabbe, M.A.; Schulman, R.F.; DeOld, J.H.

    1997-07-01

    The Central Interstate Compact (CIC) low-level radioactive waste (LLRW) disposal facility being developed near Butte, Nebraska, is scheduled to be the first operational commercial above-grade LLRW disposal facility in the United States. The facility will dispose of LLRW generated by nuclear power plants, industrial facilities, hospitals, and universities from the CIC member states of Nebraska, Kansas, Oklahoma, Arkansas, and Louisiana. The CIC Commission has contracted with US Ecology and its prime subcontractor, Bechtel National Inc., to develop this LLRW disposal facility. The facility is being sited, designed, constructed, operated, closed, and monitored in accordance with Nebraska Department of Environmental Quality Title 194, which is similar to 10 CFR 61 but has some additional requirements that are specific to the State of Nebraska. One of these is that Nebraska regulations specifically exclude the use of traditional shallow-land burial as practiced prior to 1979. The facility will use above-grade earth-mounded concrete structures for disposal of the LLRW. An environmental report (ER) has been prepared that follows the guidance contained in U.S. Nuclear Regulatory Commission Regulatory Guide 4.18. A Safety Analysis Report (SAR) has been prepared that conforms to the guidance contained in NUREG 1199, Both the SAR and the ER were submitted in July 1990. Present plans calls for the facility to be operational approximately 2 years after receipt of the license.

  9. Computer software design description for the Treated Effluent Disposal Facility (TEDF), Project L-045H, Operator Training Station (OTS)

    SciTech Connect

    Carter, R.L. Jr.

    1994-11-07

    The Treated Effluent Disposal Facility (TEDF) Operator Training Station (OTS) is a computer-based training tool designed to aid plant operations and engineering staff in familiarizing themselves with the TEDF Central Control System (CCS).

  10. Durability of a reinforced concrete designed for the construction of an intermediate-level radioactive waste disposal facility

    NASA Astrophysics Data System (ADS)

    Duffó, G. S.; Arva, E. A.; Schulz, F. M.; Vazquez, D. R.

    2012-01-01

    The National Atomic Energy Commission of the Argentine Republic is developing a nuclear waste disposal management programme that contemplates the design and construction of a facility for the final disposal of intermediate-level radioactive wastes. The repository is based on the use of multiple, independent and redundant barriers. The major components are made in reinforced concrete so, the durability of these structures is an important aspect for the facility integrity. This work presents an investigation performed on a reinforced concrete specifically designed for this purpose, to predict the service life of the intermediate level radioactive waste disposal facility from data obtained with several techniques. Results obtained with corrosion sensors embedded in a concrete prototype are also included. The information obtained will be used for the final design of the facility in order to guarantee a service life more or equal than the foreseen durability for this type of facilities.

  11. Cost estimates and economic evaluations for conceptual LLRW disposal facility designs

    SciTech Connect

    Baird, R.D.; Chau, N.; Breeds, C.D.

    1995-12-31

    Total life-cycle costs were estimated in support of the New York LLRW Siting Commission`s project to select a disposal method from four near-surface LLRW disposal methods (namely, uncovered above-grade vaults, covered above-grade vaults, below-grade vaults, and augered holes) and two mined methods (namely, vertical shaft mines and drift mines). Conceptual designs for the disposal methods were prepared and used as the basis for the cost estimates. Typical economic performance of each disposal method was assessed. Life-cycle costs expressed in 1994 dollars ranged from $ 1,100 million (for below-grade vaults and both mined disposal methods) to $2,000 million (for augered holes). Present values ranged from $620 million (for below-grade vaults) to $ 1,100 million (for augered holes).

  12. Design, construction and management of tailings storage facilities for surface disposal in China: case studies of failures.

    PubMed

    Wei, Zuoan; Yin, Guangzhi; Wang, J G; Wan, Ling; Li, Guangzhi

    2013-01-01

    Rapid development of China's economy demands for more mineral resources. At the same time, a vast quantity of mine tailings, as the waste byproduct of mining and mineral processing, is being produced in huge proportions. Tailings impoundments play an important role in the practical surface disposal of these large quantities of mining waste. Historically, tailings were relatively small in quantity and had no commercial value, thus little attention was paid to their disposal. The tailings were preferably discharged near the mines and few tailings storage facilities were constructed in mainland China. This situation has significantly changed since 2000, because the Chinese economy is growing rapidly and Chinese regulations and legislation require that tailings disposal systems must be ready before the mining operation begins. Consequently, data up to 2008 shows that more than 12 000 tailings storage facilities have been built in China. This paper reviews the history of tailings disposal in China, discusses three cases of tailings dam failures and explores failure mechanisms, and the procedures commonly used in China for planning, design, construction and management of tailings impoundments. This paper also discusses the current situation, shortcomings and key weaknesses, as well as future development trends for tailings storage facilities in China. PMID:23064963

  13. Disposal facility data for the interim performance

    SciTech Connect

    Eiholzer, C.R.

    1995-05-15

    The purpose of this report is to identify and provide information on the waste package and disposal facility concepts to be used for the low-level waste tank interim performance assessment. Current concepts for the low-level waste form, canister, and the disposal facility will be used for the interim performance assessment. The concept for the waste form consists of vitrified glass cullet in a sulfur polymer cement matrix material. The waste form will be contained in a 2 {times} 2 {times} 8 meter carbon steel container. Two disposal facility concepts will be used for the interim performance assessment. These facility concepts are based on a preliminary disposal facility concept developed for estimating costs for a disposal options configuration study. These disposal concepts are based on vault type structures. None of the concepts given in this report have been approved by a Tank Waste Remediation Systems (TWRS) decision board. These concepts will only be used in th interim performance assessment. Future performance assessments will be based on approved designs.

  14. Corrosion behaviour of steel rebars embedded in a concrete designed for the construction of an intermediate-level radioactive waste disposal facility

    NASA Astrophysics Data System (ADS)

    Duffó, G. S.; Arva, E. A.; Schulz, F. M.; Vazquez, D. R.

    2013-07-01

    The National Atomic Energy Commission of the Argentine Republic is developing a nuclear waste disposal management programme that contemplates the design and construction of a facility for the final disposal of intermediate-level radioactive wastes. The repository is based on the use of multiple, independent and redundant barriers. The major components are made in reinforced concrete so, the durability of these structures is an important aspect for the facility integrity. This work presents an investigation performed on an instrumented reinforced concrete prototype specifically designed for this purpose, to study the behaviour of an intermediate level radioactive waste disposal facility from the rebar corrosion point of view. The information obtained will be used for the final design of the facility in order to guarantee a service life more or equal than the foreseen durability for this type of facilities.

  15. Design and operational considerations of United States commercial near-surface low-level radioactive waste disposal facilities

    SciTech Connect

    Birk, S.M.

    1997-10-01

    In accordance with the Low-Level Radioactive Waste Policy Amendments Act of 1985, states are responsible for providing for disposal of commercially generated low-level radioactive waste (LLW) within their borders. LLW in the US is defined as all radioactive waste that is not classified as spent nuclear fuel, high-level radioactive waste, transuranic waste, or by-product material resulting from the extraction of uranium from ore. Commercial waste includes LLW generated by hospitals, universities, industry, pharmaceutical companies, and power utilities. LLW generated by the country`s defense operations is the responsibility of the Federal government and its agency, the Department of Energy. The commercial LLRW disposal sites discussed in this report are located near: Sheffield, Illinois (closed); Maxey Flats, Kentucky (closed); Beatty, Nevada (closed); West Valley, New York (closed); Barnwell, South Carolina (operating); Richland, Washington (operating); Ward Valley, California, (proposed); Sierra Blanca, Texas (proposed); Wake County, North Carolina (proposed); and Boyd County, Nebraska (proposed). While some comparisons between the sites described in this report are appropriate, this must be done with caution. In addition to differences in climate and geology between sites, LLW facilities in the past were not designed and operated to today`s standards. This report summarizes each site`s design and operational considerations for near-surface disposal of low-level radioactive waste. The report includes: a description of waste characteristics; design and operational features; post closure measures and plans; cost and duration of site characterization, construction, and operation; recent related R and D activities for LLW treatment and disposal; and the status of the LLW system in the US.

  16. HANDBOOK: GUIDE TO TECHNICAL RESOURCES FOR THE DESIGN OF LAND DISPOSAL FACILITIES

    EPA Science Inventory

    This Handbook facilitates the preparation and processing of land disposal permit applications. It directs the regulated community and the regulators to the appropriate EPA technical resource documents, as they prepare or review permits required under PL 480 (RCRA). Topics discuss...

  17. Undrained shear strength of partially saturated combined coal refuse. First annual report: Strength and consolidation characteristics of coal refuse for design and construction of disposal facilities

    SciTech Connect

    Huang, Y.H.; Li, J.

    1986-09-01

    This report summarizes the results of a study on the undrained shear strength of partially saturated combined refuse. The study is part of a research project entitled 'Strength and Consolidation Characteristics of Coal Refuse for Design and Construction of Disposal Facilities supported by the Office of Surface Mining, Department of the Interior. Information presented in the report will be used for the design and construction of disposal facilities. Coal refuse, the waste product from coal washing, is separated in the coal preparation plant into two fractions (coarse and fine). The fine refuse, in the form of either a slurry or a filter cake, is unstable and difficult to handle.

  18. Project W-049H disposal facility test report

    SciTech Connect

    Buckles, D.I.

    1995-01-01

    The purpose of this Acceptance Test Report (ATR) for the Project W-049H, Treated Effluent Disposal Facility, is to verify that the equipment installed in the Disposal Facility has been installed in accordance with the design documents and function as required by the project criteria.

  19. RH-LLW Disposal Facility Project CD-2/3 to Design/Build Proposal Reconciliation Report

    SciTech Connect

    Annette L. Schafer

    2012-06-01

    A reconciliation plan was developed and implemented to address potential gaps and responses to gaps between the design/build vendor proposals and the Critical Decision-2/3 approval request package for the Remote-Handled Low Level Waste Disposal Facility Project. The plan and results of the plan implementation included development of a reconciliation team comprised of subject matter experts from Battelle Energy Alliance and the Department of Energy Idaho Operations Office, identification of reconciliation questions, reconciliation by the team, identification of unresolved/remaining issues, and identification of follow-up actions and subsequent approvals of responses. The plan addressed the potential for gaps to exist in the following areas: • Department of Energy Order 435.1, “Radioactive Waste Management,” requirements, including the performance assessment, composite analysis, monitoring plan, performance assessment/composite analysis maintenance plan, and closure plan • Environmental assessment supporting the National Environmental Policy Act • Nuclear safety • Safeguards and security • Emplacement operations • Requirements for commissioning • General project implementation. The reconciliation plan and results of the plan implementation are provided in a business-sensitive project file. This report provides the reconciliation plan and non-business sensitive summary responses to identified gaps.

  20. Lessons Learned from Radioactive Waste Storage and Disposal Facilities

    SciTech Connect

    Esh, David W.; Bradford, Anna H.

    2008-01-15

    The safety of radioactive waste disposal facilities and the decommissioning of complex sites may be predicated on the performance of engineered and natural barriers. For assessing the safety of a waste disposal facility or a decommissioned site, a performance assessment or similar analysis is often completed. The analysis is typically based on a site conceptual model that is developed from site characterization information, observations, and, in many cases, expert judgment. Because waste disposal facilities are sited, constructed, monitored, and maintained, a fair amount of data has been generated at a variety of sites in a variety of natural systems. This paper provides select examples of lessons learned from the observations developed from the monitoring of various radioactive waste facilities (storage and disposal), and discusses the implications for modeling of future waste disposal facilities that are yet to be constructed or for the development of dose assessments for the release of decommissioning sites. Monitoring has been and continues to be performed at a variety of different facilities for the disposal of radioactive waste. These include facilities for the disposal of commercial low-level waste (LLW), reprocessing wastes, and uranium mill tailings. Many of the lessons learned and problems encountered provide a unique opportunity to improve future designs of waste disposal facilities, to improve dose modeling for decommissioning sites, and to be proactive in identifying future problems. Typically, an initial conceptual model was developed and the siting and design of the disposal facility was based on the conceptual model. After facility construction and operation, monitoring data was collected and evaluated. In many cases the monitoring data did not comport with the original site conceptual model, leading to additional investigation and changes to the site conceptual model and modifications to the design of the facility. The following cases are discussed

  1. Oil field waste disposal costs at commercial disposal facilities

    SciTech Connect

    Veil, J.A.

    1997-10-01

    The exploration and production segment of the U.S. oil and gas industry generates millions of barrels of nonhazardous oil field wastes annually. In most cases, operators can dispose of their oil fields wastes at a lower cost on-site than off site and, thus, will choose on-site disposal. However, a significant quantity of oil field wastes are still sent to off-site commercial facilities for disposal. This paper provides information on the availability of commercial disposal companies in different states, the treatment and disposal methods they employ, and how much they charge. There appear to be two major off-site disposal trends. Numerous commercial disposal companies that handle oil field wastes exclusively are located in nine oil-and gas-producing states. They use the same disposal methods as those used for on-site disposal. In addition, the Railroad Commission of Texas has issued permits to allow several salt caverns to be used for disposal of oil field wastes. Twenty-two other oil- and gas-producing states contain few or no disposal companies dedicated to oil and gas industry waste. The only off-site commercial disposal companies available handle general industrial wastes or are sanitary landfills. In those states, operators needing to dispose of oil field wastes off-site must send them to a local landfill or out of state. The cost of off-site commercial disposal varies substantially, depending on the disposal method used, the state in which the disposal company is located, and the degree of competition in the area.

  2. Strength and consolidation characteristics of coal refuse for design and construction of disposal facilities: Applications of research findings. Final report

    SciTech Connect

    Huang, Y.H.

    1987-08-01

    The use of coal refuse properties for the short-term stability analysis of disposal facilities is illustrated in the report. Three types of disposal facilities are considered: waste embankments constructed of combined or fine refuse, refuse dams constructed by upstream method, and sandwich construction by placing coarse and fine refuse in alternate layers. Detailed procedures are presented to determine the factor of safety at the end of construction using the REAME computer program developed at the University of Kentucky. The results of analysis show that limiting the maximum moisture content of combined or fine refuse in waste embankments and keeping the construction of refuse dams at a slower pace are very important for short-term stability. Due to the granular nature of coarse and fine refuse, the use of sandwich construction appears to be an efficient and economical disposal method. To compare the properties of coal refuse from the Western Coal Field with those from the Eastern Coal Field reported previously, test results on combined and fine refuse taken from two sites in Colorado are presented.

  3. Definitive design report: Design report project W-025, Radioactive Mixed Waste (RMW) Land Disposal Facility NON-DRAG-OFF. Revision 1, Volume 1 and 2

    SciTech Connect

    Roscha, V.

    1994-11-29

    The purpose of this report is to describe the definitive design of the Radioactive Mixed Waste (RMW) Non-Drag-Off disposal facility, Project W-025. This report presents a n of the major landfill design features and a discussion of how each of the criteria is addressed in the design. The appendices include laboratory test results, design drawings, and individual analyses that were conducted in support of the design. Revision 1 of this document incorporates design changes resulting from an increase in the required operating life of the W-025 landfill from 2 to 20 years. The rationale for these design changes is described in Golder Associates Inc. 1991a. These changes include (1) adding a 1.5-foot-thick layer of compacted admix directory-under the primary FML on the floor of the landfill to mitigate the effects of possible stress cracking in the primary flexible membrane liner (FML), and (2) increasing the operations layer thickness from two to three feet over the entire landfill area, to provide additional protection for the secondary admix layer against mechanical damage and the effects of freezing and desiccation. The design of the W-025 Landfill has also been modified in response to the results of the EPA Method 9090 chemical compatibility testing program (Golder Associates Inc. 1991b and 1991c), which was completed after the original design was prepared. This program consisted of testing geosynthetic materials and soil/bentonite admix with synthetic leachate having the composition expected during the life of the W-025 Landfill., The results of this program indicated that the polyester geotextile originally specified for the landfill might be susceptible to deterioration. On this basis, polypropylene geotextiles were substituted as a more chemically-resistant alternative. In addition, the percentage of bentonite in the admix was increased to provide sufficiently low permeability to the expected leachate.

  4. Developing operating procedures for a low-level radioactive waste disposal facility

    SciTech Connect

    Sutherland, A.A.; Miner, G.L.; Grahn, K.F.; Pollard, C.G.

    1993-10-01

    This document is intended to assist persons who are developing operating and emergency procedures for a low-level radioactive waste disposal facility. It provides 25 procedures that are considered to be relatively independent of the characteristics of a disposal facility site, the facility design, and operations at the facility. These generic procedures should form a good starting point for final procedures on their subjects for the disposal facility. In addition, this document provides 55 annotated outlines of other procedures that are common to disposal facilities. The annotated outlines are meant as checklists to assist the developer of new procedures.

  5. Preliminary design of a biological treatment facility for trench water from a low-level radioactive waste disposal area at West Valley, New York

    SciTech Connect

    Rosten, R.; Malkumus, D.; Sonntag, T.; Sundquist, J.

    1993-03-01

    The New York State Energy Research and Development Authority (NYSERDA) owns and manages a State-Licensed Low-Level Radioactive Waste Disposal Area (SDA) at West Valley, New York. Water has migrated into the burial trenches at the SDA and collected there, becoming contaminated with radionuclides and organic compounds. The US Environmental Protection Agency issued an order to NYSERDA to reduce the levels of water in the trenches. A treatability study of the contaminated trench water (leachate) was performed and determined the best available technology to treat the leachate and discharge the effluent. This paper describes the preliminary design of the treatment facility that incorporates the bases developed in the leachate treatability study.

  6. Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities

    SciTech Connect

    Batandjieva, B.; Torres-Vidal, C.

    2002-02-26

    The International Atomic Energy Agency (IAEA) Coordinated research program ''Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities'' (ISAM) has developed improved safety assessment methodology for near surface disposal facilities. The program has been underway for three years and has included around 75 active participants from 40 countries. It has also provided examples for application to three safety cases--vault, Radon type and borehole radioactive waste disposal facilities. The program has served as an excellent forum for exchange of information and good practices on safety assessment approaches and methodologies used worldwide. It also provided an opportunity for reaching broad consensus on the safety assessment methodologies to be applied to near surface low and intermediate level waste repositories. The methodology has found widespread acceptance and the need for its application on real waste disposal facilities has been clearly identified. The ISAM was finalized by the end of 2000, working material documents are available and an IAEA report will be published in 2002 summarizing the work performed during the three years of the program. The outcome of the ISAM program provides a sound basis for moving forward to a new IAEA program, which will focus on practical application of the safety assessment methodologies to different purposes, such as licensing radioactive waste repositories, development of design concepts, upgrading existing facilities, reassessment of operating repositories, etc. The new program will also provide an opportunity for development of guidance on application of the methodology that will be of assistance to both safety assessors and regulators.

  7. Idaho CERCLA Disposal Facility Complex Compliance Demonstration for DOE Order 435.1

    SciTech Connect

    Simonds, J.

    2007-11-06

    This compliance demonstration document provides an analysis of the Idaho CERCLA Disposal Facility (ICDF) Complex compliance with DOE Order 435.1. The ICDF Complex includes the disposal facility (landfill), evaporation pond, administration facility, weigh scale, and various staging/storage areas. These facilities were designed and constructed to be compliant with DOE Order 435.1, Resource Conservation and Recovery act Subtitle C, and Toxic Substances Control Act polychlorinated biphenyl design and construction standards. The ICDF Complex is designated as the Idaho National Laboratory (INL) facility for the receipt, staging/storage, treatment, and disposal of INL Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) waste streams.

  8. Near-field performance assessment for the Saltstone Disposal Facility

    SciTech Connect

    Seitz, R.R.; Dicke, C.A.; Walton, J.C.

    1993-12-31

    A near-field performance assessment (PA) was conducted for the Saltstone Disposal Facility (SDF) at the Savannah River Site in South Carolina. The analysis was conducted in four parts: general screening calculations, degradation calculations, and flow and transport through the fractured and nonfractured facility. Modeling approaches and example sensitivity analysis results from the simulations of the fractured facility are discussed. Design considerations that may not be apparent without addressing flow and transport through fractures and lessons learned during the process are also presented.

  9. Standardization of DOE Disposal Facilities Waste Acceptance Process

    SciTech Connect

    SHRADER, T.; MACBETH, P.

    2002-01-01

    On February 25, 2000, the US. Department of Energy (DOE) issued the Record of Decision (ROD) for the Waste Management Programmatic Environmental Impact Statement (WM PEIS) for low-level and mixed low-level wastes (LLW/ MLLW) treatment and disposal. The ROD designated the disposal sites at Hanford and the Nevada Test Site (NTS) to dispose of LLWMLLW from sites without their own disposal facilities. DOE's Richland Operations Office (RL) and the National Nuclear Security Administration's Nevada Operations Office (NV) have been charged with effectively implementing the ROD. To accomplish this task NV and RL, assisted by their operating contractors Bechtel Nevada (BN), Fluor Hanford (FH), and Bechtel Hanford (BH) assembled a task team to systematically map out and evaluate the current waste acceptance processes and develop an integrated, standardized process for the acceptance of LLWMLLW. A structured, systematic, analytical process using the Six Sigma system identified disposal process improvements and quantified the associated efficiency gains to guide changes to be implemented. The review concluded that a unified and integrated Hanford/NTS Waste Acceptance Process would be a benefit to the DOE Complex, particularly the waste generators. The Six Sigma review developed quantitative metrics to address waste acceptance process efficiency improvements, and provides an initial look at development of comparable waste disposal cost models between the two disposal sites to allow quantification of the proposed improvements.

  10. Iraq nuclear facility dismantlement and disposal project

    SciTech Connect

    Cochran, J.R.; Danneels, J.; Kenagy, W.D.; Phillips, C.J.; Chesser, R.K.

    2007-07-01

    The Al Tuwaitha nuclear complex near Baghdad contains a significant number of nuclear facilities from Saddam Hussein's dictatorship. Because of past military operations, lack of upkeep and looting there is now an enormous radioactive waste problem at Al Tuwaitha. Al Tuwaitha contains uncharacterised radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals. The current security situation in Iraq hampers all aspects of radioactive waste management. Further, Iraq has never had a radioactive waste disposal facility, which means that ever increasing quantities of radioactive waste and material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS has funded the International Atomic Energy Agency (IAEA) to provide technical assistance to the GOI via a Technical Cooperation Project. Program coordination will be provided by the DOS, consistent with U.S. and GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and for providing waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for the vast majority of the implementation of the NDs Program. (authors)

  11. The Remote Handled Immobilization Low Activity Waste Disposal Facility Environmental Permits & Approval Plan

    SciTech Connect

    DEFFENBAUGH, M.L.

    2000-08-01

    The purpose of this document is to revise Document HNF-SD-ENV-EE-003, ''Permitting Plan for the Immobilized Low-Activity Waste Project, which was submitted on September 4, 1997. That plan accounted for the interim storage and disposal of Immobilized-Low Activity Waste at the existing Grout Treatment Facility Vaults (Project W-465) and within a newly constructed facility (Project W-520). Project W-520 was to have contained a combination of concrete vaults and trenches. This document supersedes that plan because of two subsequent items: (1) A disposal authorization that was received on October 25, 1999, in a U. S. Department of Energy-Headquarters, memorandum, ''Disposal Authorization Statement for the Department of Energy Hanford site Low-Level Waste Disposal facilities'' and (2) ''Breakthrough Initiative Immobilized Low-Activity Waste (ILAW) Disposal Alternative,'' August 1999, from Lucas Incorporated, Richland, Washington. The direction within the U. S. Department of Energy-Headquarters memorandum was given as follows: ''The DOE Radioactive Waste Management Order requires that a Disposal authorization statement be obtained prior to construction of new low-level waste disposal facility. Field elements with the existing low-level waste disposal facilities shall obtain a disposal authorization statement in accordance with the schedule in the complex-wide Low-Level Waste Management Program Plan. The disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate CERCLA documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility based on these reviews. A disposal authorization statement is a part of the required radioactive waste management basis for a disposal facility. Failure to obtain a disposal authorization statement or record of decision shall result in shutdown of an operational

  12. 10 CFR 61.81 - Tests at land disposal facilities.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Tests at land disposal facilities. 61.81 Section 61.81 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Records, Reports, Tests, and Inspections § 61.81 Tests at land disposal facilities. (a)...

  13. Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria

    SciTech Connect

    W. Mahlon Heileson

    2006-10-01

    The Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) has been designed to accept CERCLA waste generated within the Idaho National Laboratory. Hazardous, mixed, low-level, and Toxic Substance Control Act waste will be accepted for disposal at the ICDF. The purpose of this document is to provide criteria for the quantities of radioactive and/or hazardous constituents allowable in waste streams designated for disposal at ICDF. This ICDF Complex Waste Acceptance Criteria is divided into four section: (1) ICDF Complex; (2) Landfill; (3) Evaporation Pond: and (4) Staging, Storage, Sizing, and Treatment Facility (SSSTF). The ICDF Complex section contains the compliance details, which are the same for all areas of the ICDF. Corresponding sections contain details specific to the landfill, evaporation pond, and the SSSTF. This document specifies chemical and radiological constituent acceptance criteria for waste that will be disposed of at ICDF. Compliance with the requirements of this document ensures protection of human health and the environment, including the Snake River Plain Aquifer. Waste placed in the ICDF landfill and evaporation pond must not cause groundwater in the Snake River Plain Aquifer to exceed maximum contaminant levels, a hazard index of 1, or 10-4 cumulative risk levels. The defined waste acceptance criteria concentrations are compared to the design inventory concentrations. The purpose of this comparison is to show that there is an acceptable uncertainty margin based on the actual constituent concentrations anticipated for disposal at the ICDF. Implementation of this Waste Acceptance Criteria document will ensure compliance with the Final Report of Decision for the Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. For waste to be received, it must meet the waste acceptance criteria for the specific disposal/treatment unit (on-Site or off-Site) for which it is destined.

  14. Standardization of DOE Disposal Facilities Waste Acceptance Processes

    SciTech Connect

    Shrader, T. A.; Macbeth, P. J.

    2002-02-26

    On February 25, 2000, the U.S. Department of Energy (DOE) issued the Record of Decision (ROD) for the Waste Management Programmatic Environmental Impact Statement (WM PEIS) for low-level and mixed low-level wastes (LLW/ MLLW) treatment and disposal. The ROD designated the disposal sites at Hanford and the Nevada Test Site (NTS) to dispose of LLW/MLLW from sites without their own disposal facilities. DOE's Richland Operations Office (RL) and the National Nuclear Security Administration's Nevada Operations Office (NV) have been charged with effectively implementing the ROD. To accomplish this task NV and RL, assisted by their operating contractors Bechtel Nevada (BN), Fluor Hanford (FH), and Bechtel Hanford (BH) assembled a task team to systematically map out and evaluate the current waste acceptance processes and develop an integrated, standardized process for the acceptance of LLW/MLLW. A structured, systematic, analytical process using the Six Sigma system identified dispos al process improvements and quantified the associated efficiency gains to guide changes to be implemented. The review concluded that a unified and integrated Hanford/NTS Waste Acceptance Process would be a benefit to the DOE Complex, particularly the waste generators. The Six Sigma review developed quantitative metrics to address waste acceptance process efficiency improvements, and provides an initial look at development of comparable waste disposal cost models between the two disposal sites to allow quantification of the proposed improvements.

  15. Facility design, construction, and operation

    SciTech Connect

    1995-04-01

    France has been disposing of low-level radioactive waste (LLW) at the Centre de Stockage de la Manche (CSM) since 1969 and now at the Centre de Stockage de l`Aube (CSA) since 1992. In France, several agencies and companies are involved in the development and implementation of LLW technology. The Commissariat a l`Energie Atomic (CEA), is responsible for research and development of new technologies. The Agence National pour la Gestion des Dechets Radioactifs is the agency responsible for the construction and operation of disposal facilities and for wastes acceptance for these facilities. Compagnie Generale des Matieres Nucleaires provides fuel services, including uranium enrichment, fuel fabrication, and fuel reprocessing, and is thus one generator of LLW. Societe pour les Techniques Nouvelles is an engineering company responsible for commercializing CEA waste management technology and for engineering and design support for the facilities. Numatec, Inc. is a US company representing these French companies and agencies in the US. In Task 1.1 of Numatec`s contract with Martin Marietta Energy Systems, Numatec provides details on the design, construction and operation of the LLW disposal facilities at CSM and CSA. Lessons learned from operation of CSM and incorporated into the design, construction and operating procedures at CSA are identified and discussed. The process used by the French for identification, selection, and evaluation of disposal technologies is provided. Specifically, the decisionmaking process resulting in the change in disposal facility design for the CSA versus the CSM is discussed. This report provides` all of the basic information in these areas and reflects actual experience to date.

  16. Composite analysis E-area vaults and saltstone disposal facilities

    SciTech Connect

    Cook, J.R.

    1997-09-01

    This report documents the Composite Analysis (CA) performed on the two active Savannah River Site (SRS) low-level radioactive waste (LLW) disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults (EAV) Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of SRS and contains all of the waste disposal facilities, chemical separations facilities and associated high-level waste storage facilities as well as numerous other sources of radioactive material. The analysis considered 114 potential sources of radioactive material containing 115 radionuclides. The results of the CA clearly indicate that continued disposal of low-level waste in the saltstone and EAV facilities, consistent with their respective radiological performance assessments, will have no adverse impact on future members of the public.

  17. Polychlorinated biphenyl levels in the Saginaw Confined Disposal Facility during disposal operations, Fall 1987. Final report

    SciTech Connect

    Myers, T.E.

    1991-01-01

    Pond water samples were collected from the Saginaw confined disposal facility (CDF), Saginaw, MI, during late summer and early fall 1987 and were analyzed for polychlorinated biphenyls (PCBs), suspended sediments and ammonia nitrogen. During this period, sediments from the Saginaw River was dredged and disposed in the Saginaw CDF. The perimeter dikes at the Saginaw CDF have a prepared limestone core that was designed to be permeable, Effluent monitoring is not practical because the discharge through permeable dikes is diffuse and is quickly diluted to background concentrations. This study, therefore, focused on collection of influent and pond water samples during disposal operations, and on the use of PCB concentrations in pond water samples to estimate the amount of PCB entering the dike and possibly being released from the CDF.

  18. Environmental Restoration Disposal Facility (Project W-296) Safety Assessment

    SciTech Connect

    Armstrong, D.L.

    1994-08-01

    This Safety Assessment is based on information derived from the Conceptual Design Report for the Environmental Restoration Disposal Facility (DOE/RL 1994) and ancillary documentation developed during the conceptual design phase of Project W-296. The Safety Assessment has been prepared to support the Solid Waste Burial Ground Interim Safety Basis document. The purpose of the Safety Assessment is to provide an evaluation of the design to determine if the process, as proposed, will comply with US Department of Energy (DOE) Limits for radioactive and hazardous material exposures and be acceptable from an overall health and safety standpoint. The evaluation considered affects on the worker, onsite personnel, the public, and the environment.

  19. Addendum to the composite analysis for the E-Area Vaults and Saltstone Disposal Facilities

    SciTech Connect

    Cook, J.R.

    2000-03-13

    This report documents the composite analysis performed on the two active SRS low-level radioactive waste disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults Disposal Facility.

  20. FY 2006 ANNUAL REVIEW-SALTSTONE DISPOSAL FACILITY PERFORMANCE ASSESSMENT

    SciTech Connect

    Crapse, K; Benjamin Culbertson, B

    2007-03-15

    The Z-Area Saltstone Disposal Facility (SDF) consists of two disposal units, Vaults 1 and 4, described in the Performance Assessment (PA) (WSRC 1992). The FY06 PA Annual Review concludes that both vaults contain much lower levels of radionuclides (curies) than that allowed by the PA. The PA controls established to govern waste operations and monitor disposal facility performance are determined to be adequate.

  1. 10 CFR 61.51 - Disposal site design for land disposal.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Disposal site design for land disposal. 61.51 Section 61.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF... disposal. (a) Disposal site design for near-surface disposal. (1) Site design features must be...

  2. 10 CFR 61.51 - Disposal site design for land disposal.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... disposal. (a) Disposal site design for near-surface disposal. (1) Site design features must be directed... with wastes after disposal. (b) Disposal site design for other than near-surface disposal. ... extent practicable water infiltration, to direct percolating or surface water away from the...

  3. Geology of the Integrated Disposal Facility Trench

    SciTech Connect

    Reidel, Steve P.; Fecht, Karl R.

    2005-07-01

    This report describes the geology of the integrated Disposal Facility (IDF) Trench. The stratigraphy consists of some of the youngest sediments of the Missoula floods (younger than 770 ka). The lithology is dominated sands with minor silts and gravels that are largely unconsolidated. The stratigraphy can be subdivided into five geologic units that can be mapped throughout the trench. Four of the units were deposited by the Missoula floods and the youngest consists of windblown sand and silt. The sediment has little moisture and is consistent with that observed in the characterization boreholes. The sedimentary layers are flat lying and there are no faults or folds present. Two clastic dikes were encountered, one along the west wall and one that can be traced from the north to the southwall. The north-south clastic dike nearly bifurcates the trench but the west wall clastic dike can not be traced very far east into the trench. The classic dikes consist mainly of sand with clay-lined walls. The sediment in the dikes is compacted to partly cemented and are more resistant than the layered sediments.

  4. Probabilistic Modeling of Settlement Risk at Land Disposal Facilities - 12304

    SciTech Connect

    Foye, Kevin C.; Soong, Te-Yang

    2012-07-01

    The long-term reliability of land disposal facility final cover systems - and therefore the overall waste containment - depends on the distortions imposed on these systems by differential settlement/subsidence. The evaluation of differential settlement is challenging because of the heterogeneity of the waste mass (caused by inconsistent compaction, void space distribution, debris-soil mix ratio, waste material stiffness, time-dependent primary compression of the fine-grained soil matrix, long-term creep settlement of the soil matrix and the debris, etc.) at most land disposal facilities. Deterministic approaches to long-term final cover settlement prediction are not able to capture the spatial variability in the waste mass and sub-grade properties which control differential settlement. An alternative, probabilistic solution is to use random fields to model the waste and sub-grade properties. The modeling effort informs the design, construction, operation, and maintenance of land disposal facilities. A probabilistic method to establish design criteria for waste placement and compaction is introduced using the model. Random fields are ideally suited to problems of differential settlement modeling of highly heterogeneous foundations, such as waste. Random fields model the seemingly random spatial distribution of a design parameter, such as compressibility. When used for design, the use of these models prompts the need for probabilistic design criteria. It also allows for a statistical approach to waste placement acceptance criteria. An example design evaluation was performed, illustrating the use of the probabilistic differential settlement simulation methodology to assemble a design guidance chart. The purpose of this design evaluation is to enable the designer to select optimal initial combinations of design slopes and quality control acceptance criteria that yield an acceptable proportion of post-settlement slopes meeting some design minimum. For this specific

  5. Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect

    Lisa Harvego; Mike Lehto

    2010-02-01

    The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

  6. Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect

    Lisa Harvego; Mike Lehto

    2010-05-01

    The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

  7. Low-level radioactive waste disposal facility closure

    SciTech Connect

    White, G.J.; Ferns, T.W.; Otis, M.D.; Marts, S.T.; DeHaan, M.S.; Schwaller, R.G.; White, G.J. )

    1990-11-01

    Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act on long-term predictions are evaluated including biological, chemical, and physical phenomena of both natural and anthropogenic origin. These factors are then applied to six existing, yet very different, low-level radioactive waste sites. A summary and recommendations for future site characterization and monitoring activities is given for application to potential and existing sites. Part II of this report contains guidance on the design and implementation of a performance monitoring program for low-level radioactive waste disposal facilities. A monitoring programs is described that will assess whether engineered barriers surrounding the waste are effectively isolating the waste and will continue to isolate the waste by remaining structurally stable. Monitoring techniques and instruments are discussed relative to their ability to measure (a) parameters directly related to water movement though engineered barriers, (b) parameters directly related to the structural stability of engineered barriers, and (c) parameters that characterize external or internal conditions that may cause physical changes leading to enhanced water movement or compromises in stability. Data interpretation leading to decisions concerning facility closure is discussed. 120 refs., 12 figs., 17 tabs.

  8. 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.

  9. 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.

  10. 300 Area Treated Effluent Disposal Facility (TEDF) Hazards Assessment

    SciTech Connect

    CAMPBELL, L.R.

    1999-01-15

    This document establishes the technical basis in support of emergency planning activities for the 300 Area Treated Effluent Disposal Facility. The technical basis for project-specific Emergency Action Levels and Emergency Planning Zone is demonstrated.

  11. Yucca Mountain Project Surface Facilities Design

    SciTech Connect

    P.W. McDaniel; N.R. Brown; P.G. Harrington; J.T. Gardiner; L.J. Trautner

    2002-11-20

    With the recent designation of the Yucca Mountain site as a proposed repository for the disposal of commercial spent nuclear fuel, DOE spent nuclear fuel and high- level waste, work is proceeding on the design of surface facilities to receive, unload, and package the waste into waste packages for emplacement in the repository. This paper summarizes recent progress in the design of these surface facilities.

  12. Radioactive high level waste insight modelling for geological disposal facilities

    NASA Astrophysics Data System (ADS)

    Carter, Alexander; Kelly, Martin; Bailey, Lucy

    Within this paper we present a simplified analytical model to provide insight into the key performance measures of a generic disposal system for high level waste within a geological disposal facility. The model assumes a low solubility waste matrix within a corrosion resistant disposal container surrounded by a low permeability buffer. Radionuclides migrate from the disposal area through a porous geosphere to the biosphere and give a radiological dose to a receptor. The system of equations describing the migration is transformed into Laplace space and an approximation used to determine peak values for the radionuclide mass transfer rate entering the biosphere. Results from the model are compared with those from more detailed numerical models for key radionuclides in the UK high level waste inventory. Such an insight model can provide a valuable second line of argument to assist in confirming the results of more detailed models and build confidence in the safety case for a geological disposal facility.

  13. Verification of best available technology for the 300 Area Treated Effluent Disposal Facility (310 Facility)

    SciTech Connect

    Wagner, R.N.

    1994-09-26

    This compilation of Project L-045H reference materials documents that the 300 Area Treated Effluent Disposal Facility (TEDF, also designated the 310 Facility) was designed, built, and will be operated in accordance with the best available technology (BAT) identified in the Engineering Summary Report. The facility is intended for treatment of 300 Area process sewer wastewater. The following unit operations for 300 Area process sewer water treatment are specified as: influent receipt; iron co-precipitation and sludge handling for removal of heavy metals and initial suspended solids; ion exchanged for removal of mercury and other heavy metals; ultraviolet (UV)/peroxide treatment for destruction of organic compounds, cyanide, coliforms, sulfide, and nitrite; and effluent discharge to the Columbia River with pH monitoring/control capability.

  14. Construction, Startup and Operation of a New LLRW Disposal Facility in Andrews County, Texas - 12151

    SciTech Connect

    Van Vliet, James A.

    2012-07-01

    During this last year, Waste Control Specialists LLC (WCS) completed construction and achieved start of operations of a new low level radioactive waste (LLRW) disposal facility in Andrews County Texas. Disposal operations are underway for commercial LLRW, and start up evolutions are in progress for disposal of Department of Energy (DOE) LLRW. The overall approach to construction and start up are presented as well as some of the more significant challenges and how they were addressed to achieve initial operations of the first new commercial low level radioactive waste disposal facility in more than 30 years. The WCS disposal facility consists of two LLRW disposal cells, one for Texas Compact waste, and a separate disposal cell for DOE waste. Both disposal cells have very robust and unique designs. The cells themselves are constructed entirely in very low permeability red bed clay. The cell liners include a 0.91 meter thick clay liner meeting unprecedented permeability limits, 0.3 meter thick reinforced concrete barriers, as well as the standard geo-synthetic liners. Actions taken to meet performance criteria and install these liners will be discussed. Consistent with this highly protective landfill design, WCS chose to install a zero discharge site water management system. The considerations behind the design and construction of this system will be presented. Other activities essential to successful start of LLRW disposal operations included process and procedure development and refinement, staffing and staff development, and training. Mock ups were built and used for important evolutions and functions. Consistent with the extensive regulation of LLRW operations, engagement with the Texas Commission on Environmental Quality (TCEQ) was continuous and highly interactive. This included daily activity conference calls, weekly coordination calls and numerous topical conference calls and meetings. TCEQ staff and consultants frequently observed specific construction

  15. Evaluation of a method for designing sealing plugs for HLW geological disposal facilities, taking into account the heterogeneous characteristics of the geological environment

    SciTech Connect

    Suyama, Yasuhiro; Yanagizawa, Koichi; Toida, Masaru

    2007-07-01

    In order to ensure that a repository for the geological disposal of HLW is isolated from the human environment, underground excavations, including pits and tunnels, must be properly sealed. Effective sealing requires that these excavations are backfilled, and that the Excavation Damage or Disturbed Zone (EDZ), which includes preferential flow paths, must be intersected by sealing plugs. Methods for constructing a full-scale sealing plug and their influence on plug performance were evaluated and confirmed by a Tunnel Sealing Experiment (TSX). This experiment was carried out by an international partnership of the Japan Nuclear Cycle Development Institute (JNC) and Atomic Energy of Canada Limited (AECL). However certain specific roles of the scaling plugs at the scale of the whole repository were not studied. There remain issues to be clarified, notably the effectiveness of sealing plugs in a geological environment with heterogeneous characteristics and the resulting influences of the heterogeneities in performance assessment. Focusing on a geological environment with spatially heterogeneous characteristics, the authors have developed a method for designing the sealing plugs, based on a concept of 'primarily design for closure, secondarily design for construction'. Though the proposed method for designing sealing plugs has presently been developed only at a conceptual level, it indicates the possibility of establishing a repository even in a strongly heterogeneous geological environment that may have been considered previously to be inappropriate for a repository. (authors)

  16. Air pollutants emissions from waste treatment and disposal facilities.

    PubMed

    Hamoda, Mohamed F

    2006-01-01

    This study examined the atmospheric pollution created by some waste treatment and disposal facilities in the State of Kuwait. Air monitoring was conducted in a municipal wastewater treatment plant, an industrial wastewater treatment plant established in a petroleum refinery, and at a landfill site used for disposal of solid wastes. Such plants were selected as models for waste treatment and disposal facilities in the Arabian Gulf region and elsewhere. Air measurements were made over a period of 6 months and included levels of gaseous emissions as well as concentrations of volatile organic compounds (VOCs). Samples of gas and bioaerosols were collected from ambient air surrounding the treatment facilities. The results obtained from this study have indicated the presence of VOCs and other gaseous pollutants such as methane, ammonia, and hydrogen sulphide in air surrounding the waste treatment and disposal facilities. In some cases the levels exceeded the concentration limits specified by the air quality standards. Offensive odors were also detected. The study revealed that adverse environmental impact of air pollutants is a major concern in the industrial more than in the municipal waste treatment facilities but sitting of municipal waste treatment and disposal facilities nearby the urban areas poses a threat to the public health. PMID:16401572

  17. Design and operation of a low-level solid-waste disposal site at Los Alamos

    NASA Astrophysics Data System (ADS)

    Balo, K. A.; Wilson, N. E.; Warren, J. L.

    Approximately 185000 cu m of low level and transuranic radioactive solid waste, were disposed of by onsite shallow land burial. Procedures and facilities were designed and evaluated in the areas of waste acceptance, treatment and storage, disposal, traffic control, and support systems. The methodologies assuring the proper management and disposal of radioactive solid waste are summarized.

  18. Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect

    Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

    2011-03-01

    This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

  19. Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect

    David Duncan

    2011-05-01

    This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

  20. 40 CFR 257.3 - Criteria for classification of solid waste disposal facilities and practices.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... PROTECTION AGENCY (CONTINUED) SOLID WASTES CRITERIA FOR CLASSIFICATION OF SOLID WASTE DISPOSAL FACILITIES AND PRACTICES Classification of Solid Waste Disposal Facilities and Practices § 257.3 Criteria for classification of solid waste disposal facilities and practices. Solid waste disposal facilities or...

  1. Contaminant leaching model for dredged material disposal facilities

    SciTech Connect

    Schroeder, P.R.; Aziz, N.M.

    1999-09-01

    This paper describes the hydrologic evaluation of leachate production and quality model, a screening-level tool to simulate contaminant leaching from a confined disposal facility (CDF) for dredged material. The model combines hydraulics, hydrology, and equilibrium partitioning, using site-specific design specifications, weather data, and equilibrium partitioning coefficients from the literature or from sequential batch or column leach tests of dredged material. The hydraulics and hydrology are modeled using Version 3 of the hydrologic evaluation of landfill performance model. The equilibrium partitioning model includes provisions for estuarine sediments that have variable distribution coefficients resulting from saltwater washout. Model output includes contaminant concentrations in the CDF profile, contaminant concentration and mass releases through the bottom of the CDF, and contaminant concentrations and masses captured by leachate collection systems. The purpose of the model is to provide sound information for evaluating the potential leachate impacts on ground water at dredged material CDFs and the effectiveness of leachate control measures.

  2. Idaho CERCLA Disposal Facility Complex Compliance Demonstration for DOE Order 435.1

    SciTech Connect

    J. Simonds

    2006-09-01

    This compliance demonstration document provides an analysis of the Idaho CERCLA Disposal Facility (ICDF) Complex compliance with DOE Order 435.1. The ICDF Complex includes the disposal facility (landfill), evaporation pond, admin facility, weigh scale, decon building, treatment systems, and various staging/storage areas. These facilities were designed and are being constructed to be compliant with DOE Order 435.1, Resource Conservation and Recovery Act Subtitle C, and Toxic Substances Control Act polychlorinated biphenyl design and construction standards. The ICDF Complex is designated as the central Idaho National Laboratory (INL) facilityyy for the receipt, staging/storage, treatment, and disposal of INL Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) waste streams. This compliance demonstration document discusses the conceptual site model for the ICDF Complex area. Within this conceptual site model, the selection of the area for the ICDF Complex is discussed. Also, the subsurface stratigraphy in the ICDF Complex area is discussed along with the existing contamination beneath the ICDF Complex area. The designs for the various ICDF Complex facilities are also included in this compliance demonstration document. These design discussions are a summary of the design as presented in the Remedial Design/Construction Work Plans for the ICDF landfill and evaporation pond and the Staging, Storage, Sizing, and Treatment Facility. Each of the major facilities or systems is described including the design criteria.

  3. CONTAINMENT OF LOW-LEVEL RADIOACTIVE WASTE AT THE DOE SALTSTONE DISPOSAL FACILITY

    SciTech Connect

    Jordan, J.; Flach, G.

    2012-03-29

    As facilities look for permanent storage of toxic materials, they are forced to address the long-term impacts to the environment as well as any individuals living in affected area. As these materials are stored underground, modeling of the contaminant transport through the ground is an essential part of the evaluation. The contaminant transport model must address the long-term degradation of the containment system as well as any movement of the contaminant through the soil and into the groundwater. In order for disposal facilities to meet their performance objectives, engineered and natural barriers are relied upon. Engineered barriers include things like the design of the disposal unit, while natural barriers include things like the depth of soil between the disposal unit and the water table. The Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) in South Carolina is an example of a waste disposal unit that must be evaluated over a timeframe of thousands of years. The engineered and natural barriers for the SDF allow it to meet its performance objective over the long time frame. Some waste disposal facilities are required to meet certain standards to ensure public safety. These type of facilities require an engineered containment system to ensure that these requirements are met. The Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) is an example of this type of facility. The facility is evaluated based on a groundwater pathway analysis which considers long-term changes to material properties due to physical and chemical degradation processes. The facility is able to meet these performance objectives due to the multiple engineered and natural barriers to contaminant migration.

  4. Subproject L-045H 300 Area Treated Effluent Disposal Facility

    SciTech Connect

    Not Available

    1991-06-01

    The study focuses on the project schedule for Project L-045H, 300 Area Treated Effluent Disposal Facility. The 300 Area Treated Effluent Disposal Facility is a Department of Energy subproject of the Hanford Environmental Compliance Project. The study scope is limited to validation of the project schedule only. The primary purpose of the study is to find ways and means to accelerate the completion of the project, thereby hastening environmental compliance of the 300 Area of the Hanford site. The 300 Area'' has been utilized extensively as a laboratory area, with a diverse array of laboratory facilities installed and operational. The 300 Area Process Sewer, located in the 300 Area on the Hanford Site, collects waste water from approximately 62 sources. This waste water is discharged into two 1500 feet long percolation trenches. Current environmental statutes and policies dictate that this practice be discontinued at the earliest possible date in favor of treatment and disposal practices that satisfy applicable regulations.

  5. Integrated Disposal Facility FY2011 Glass Testing Summary Report

    SciTech Connect

    Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Westsik, Joseph H.

    2011-09-29

    Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 x 10{sup 5} m{sup 3} of glass (Certa and Wells 2010). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 8.9 x 10{sup 14} Bq total activity) of long-lived radionuclides, principally {sup 99}Tc (t{sub 1/2} = 2.1 x 10{sup 5}), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2011 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses.

  6. Development of high integrity, maximum durability concrete structures for LLW disposal facilities

    SciTech Connect

    Taylor, W.P.

    1992-05-01

    A number of disposal facilities for Low-Level Radioactive Wastes have been planned for the Savannah River Site. Design has been completed for disposal vaults for several waste classifications and construction is nearly complete or well underway on some facilities. Specific design criteria varies somewhat for each waste classification. All disposal units have been designed as below-grade concrete vaults, although the majority will be above ground for many years before being encapsulated with earth at final closure. Some classes of vaults have a minimum required service life of 100 years. All vaults utilize a unique blend of cement, blast furnace slag and pozzolan. The design synthesizes the properties of the concrete mix with carefully planned design details and construction methodologies to (1) eliminate uncontrolled cracking; (2) minimize leakage potential; and (3) maximize durability. The first of these vaults will become operational in 1992. 9 refs.

  7. Development of high integrity, maximum durability concrete structures for LLW disposal facilities

    SciTech Connect

    Taylor, W.P. , Inc., Charlotte, NC )

    1992-01-01

    A number of disposal facilities for Low-Level Radioactive Wastes have been planned for the Savannah River Site. Design has been completed for disposal vaults for several waste classifications and construction is nearly complete or well underway on some facilities. Specific design criteria varies somewhat for each waste classification. All disposal units have been designed as below-grade concrete vaults, although the majority will be above ground for many years before being encapsulated with earth at final closure. Some classes of vaults have a minimum required service life of 100 years. All vaults utilize a unique blend of cement, blast furnace slag and pozzolan. The design synthesizes the properties of the concrete mix with carefully planned design details and construction methodologies to (1) eliminate uncontrolled cracking; (2) minimize leakage potential; and (3) maximize durability. The first of these vaults will become operational in 1992. 9 refs.

  8. Iodine-129 Dose in LLW Disposal Facility Performance Assessments

    SciTech Connect

    Wilhite, E.L.

    1999-10-15

    Iodine-129 has the lowest Performance Assessment derived inventory limit in SRS disposal facilities. Because iodine is concentrated in the body to one organ, the thyroid, it has been thought that dilution with stable iodine would reduce the dose effects of 129I.Examination of the dose model used to establish the Dose conversion factor for 129I shows that, at the levels considered in performance assessments of low-level waste disposal facilities, the calculated 129I dose already accounts for ingestion of stable iodine. At higher than normal iodine ingestion rates, the uptake of iodine by the thyroid itself decrease, which effectively cancels out the isotopic dilution effect.

  9. Design, construction, and operations experience with the SWSA 6 (Solid Waste Storage Area) Tumulus Disposal Demonstration

    SciTech Connect

    Van Hoesen, S.D.; Van Cleve, J.E.; Wylie, A.N.; Williams, L.C.; Bolinsky, J.

    1988-01-01

    Efforts are underway at the Department of Energy facilities in Oak Ridge to improve the performance of radioactive waste disposal facilities. An engineered disposal concept demonstration involving placement of concrete encased waste on a monitored concrete pad with an earthen cover is being conducted. The design, construction, and operations experience with this project, the SWSA 6 Tumulus Disposal Demonstration, is described. 1 fig., 1 tab.

  10. Support of the Iraq nuclear facility dismantlement and disposal program

    SciTech Connect

    Coates, Roger; Cochran, John; Danneels, Jeff; Chesser, Ronald; Phillips, Carlton; Rogers, Brenda

    2007-07-01

    Available in abstract form only. Full text of publication follows: Iraq's former nuclear facilities contain large quantities of radioactive materials and radioactive waste. The Iraq Nuclear Facility Dismantlement and Disposal Program (the Iraq NDs Program) is a new program to decontaminate and permanently dispose of radioactive wastes in Iraq. The NDs Program is led by the Government of Iraq, under International Atomic Energy Agency (IAEA) auspices, with guidance and assistance from a number of countries. The U.S. participants include Texas Tech University and Sandia National Laboratories. A number of activities are ongoing under the broad umbrella of the Iraq NDs Program: drafting a new nuclear law that will provide the legal basis for the cleanup and disposal activities; assembly and analysis of existing data; characterization of soil contamination; bringing Iraqi scientists to the world's largest symposium on radioactive waste management; touring U.S. government and private sector operating radwaste disposal facilities in the U.S., and hosting a planning workshop on the characterization and cleanup of the Al-Tuwaitha Nuclear Facility. (authors)

  11. GEOTECHNICAL QUALITY ASSURANCE OF CONSTRUCTION OF DISPOSAL FACILITIES

    EPA Science Inventory

    This report presents four major topics related to the permittee's responsibilities during construction,operation, and closure of a hazardous waste disposal facility: (1) geotechnical parameters that should be tested and/or observed, (2) selection of sampling methods and sample si...

  12. INVESTIGATION OF CONTAMINANT TRANSPORT FROM THE SAGINAW CONFINED DISPOSAL FACILITY

    EPA Science Inventory

    Pilot biomonitoring and monitoring studies were conducted at the Saginaw Confined Disposal Facility (CDF), Saginaw Bay, Lake Huron, during 1987 to develop methods to assess the potential for magnitude of 1) contaminant transport from the dike interior to the outside environment, ...

  13. Evaluating Operational Irregularities at Hanford's Environmental Restoration Disposal Facility

    SciTech Connect

    Benson, C.H.; Albright, W.H.; Ray, D.P.; Smegal, J.S.; Robertson, Jr.O.C.; Gupta, D.C.

    2008-07-01

    This paper describes the findings of an independent technical review that investigated operational irregularities at the Environmental Restoration Disposal Facility (ERDF) at Hanford. The ERDF is a large-scale disposal facility authorized by the Environmental Protection Agency and the Washington State Department of Ecology to receive waste from Hanford cleanup activities. The irregularities included (i) failure to recognize that pumps for the leachate collection system were not functioning for an extended period and (ii) falsification of compaction data by a technician responsible for monitoring waste placement in the ERDF. Other issues related to compaction of the waste were also considered during the independent technical review. A number of important lessons were learned as part of this review. These lessons are summarized in the paper. They are relevant to the ERDF as well as other landfill operations at Department of Energy facilities. (authors)

  14. Integrated Disposal Facility FY 2012 Glass Testing Summary Report

    SciTech Connect

    Pierce, Eric M.; Kerisit, Sebastien N.; Krogstad, Eirik J.; Burton, Sarah D.; Bjornstad, Bruce N.; Freedman, Vicky L.; Cantrell, Kirk J.; Snyder, Michelle MV; Crum, Jarrod V.; Westsik, Joseph H.

    2013-03-29

    PNNL is conducting work to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility for Hanford immobilized low-activity waste (ILAW). Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program, PNNL is implementing a strategy, consisting of experimentation and modeling, to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. Key activities in FY12 include upgrading the STOMP/eSTOMP codes to do near-field modeling, geochemical modeling of PCT tests to determine the reaction network to be used in the STOMP codes, conducting PUF tests on selected glasses to simulate and accelerate glass weathering, developing a Monte Carlo simulation tool to predict the characteristics of the weathered glass reaction layer as a function of glass composition, and characterizing glasses and soil samples exhumed from an 8-year lysimeter test. The purpose of this report is to summarize the progress made in fiscal year (FY) 2012 and the first quarter of FY 2013 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of LAW glasses.

  15. 40 CFR 61.220 - Designation of facilities.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... Emissions From the Disposal of Uranium Mill Tailings § 61.220 Designation of facilities. (a) The provisions of this subpart apply to owners and operators of all sites that are used for the disposal of tailings..., commonly referred to as uranium mills and their associated tailings, that are listed in, or designated...

  16. 40 CFR 61.220 - Designation of facilities.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... Emissions From the Disposal of Uranium Mill Tailings § 61.220 Designation of facilities. (a) The provisions of this subpart apply to owners and operators of all sites that are used for the disposal of tailings..., commonly referred to as uranium mills and their associated tailings, that are listed in, or designated...

  17. 40 CFR 61.220 - Designation of facilities.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... Emissions From the Disposal of Uranium Mill Tailings § 61.220 Designation of facilities. (a) The provisions of this subpart apply to owners and operators of all sites that are used for the disposal of tailings..., commonly referred to as uranium mills and their associated tailings, that are listed in, or designated...

  18. 40 CFR 61.220 - Designation of facilities.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... Emissions From the Disposal of Uranium Mill Tailings § 61.220 Designation of facilities. (a) The provisions of this subpart apply to owners and operators of all sites that are used for the disposal of tailings..., commonly referred to as uranium mills and their associated tailings, that are listed in, or designated...

  19. Estimated Particulate Emissions By Wind Erosion From the Indiana Harbor Confined Disposal Facility

    Technology Transfer Automated Retrieval System (TEKTRAN)

    A Confined Disposal Facility (CDF) is being designed for contaminated sediments dredged from the Indiana Harbor Canal at East Chicago, IN. The sediment will be placed in two cells enclosed by earthern berms about 9 m tall and cover about 36 hectares. The purposes of this study were to a) determine...

  20. Iraq nuclear facility dismantlement and disposal project (NDs Project).

    SciTech Connect

    Cochran, John Russell

    2010-06-01

    The Al Tuwaitha nuclear complex near Baghdad contains a number of facilities from Saddam Hussan's nuclear weapons program. Past military operations, lack of upkeep and looting have created an enormous radioactive waste problem at the Al Tuwaitha complex, which contains various, uncharacterized radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals that must be constantly guarded. Iraq has never had a radioactive waste disposal facility and the lack of a disposal facility means that ever increasing quantities of radioactive material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS is funding the IAEA to provide technical assistance via Technical Cooperation projects. Program coordination will be provided by the DOS, consistent with GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for implementation of the NDs Program.

  1. Environmental monitoring of low-level radioactive waste disposal facility

    SciTech Connect

    Shum, E.Y.; Starmer, R.J.; Young, M.H.

    1989-12-01

    This branch technical position (BTP) paper on the environmental monitoring program for a low-level radioactive waste disposal facility provides general guidance on what is required by Section 61.53 of Title 10 of the Code of Federal Regulations (10 CFR) of applicants submitting a license application for such a facility. In general, the environmental monitoring program consists of three phases: preoperational, operational, and postoperational. Each phase of the monitoring program should be designed to fulfill the specific objectives defined in the BTP paper. During the preoperational phase, the objectives of the program are to provide site characterization information, to demonstrate site suitability and acceptability, to obtain background or baseline information, and to provide a record for public information. During the operational phase, the emphasis on measurement shifts. Monitoring data are obtained to provide early warning of releases and to document compliance with regulations, the dose limits of 10 CFR Part 61, or applicable standards of the US Environmental Protection Agency. Data are also used to update important pathway parameters to improve predictions of site performance and to provide a record of performance for public information. The postoperational environmental monitoring program emphasizes measurements to demonstrate compliance with the site-closure requirements and continued compliance with the performance objective in regard to the release of radionuclides to the environment. The data are used to support evaluation of long-term effects on the general public and for public information. Guidance is also provided in the BTP paper on the choice of which constituents to measure, setting action levels, relating measurements to appropriate actions in a corrective action plan, and quality assurance.

  2. Radiological performance assessment for the E-Area Vaults Disposal Facility

    SciTech Connect

    Cook, J.R.; Hunt, P.D.

    1994-04-15

    The E-Area Vaults (EAVs) located on a 200 acre site immediately north of the current LLW burial site at Savannah River Site will provide a new disposal and storage site for solid, low-level, non-hazardous radioactive waste. The EAV Disposal Facility will contain several large concrete vaults divided into cells. Three types of structures will house four designated waste types. The Intermediate Level Non-Tritium Vaults will receive waste radiating greater than 200 mR/h at 5 cm from the outer disposal container. The Intermediate Level Tritium Vaults will receive waste with at least 10 Ci of tritium per package. These two vaults share a similar design, are adjacent, share waste handling equipment, and will be closed as one facility. The second type of structure is the Low Activity Waste Vaults which will receive waste radiating less than 200 mR/h at 5 cm from the outer disposal container and containing less than 10 Ci of tritium per package. The third facility, the Long Lived Waste Storage Building, provides covered, long term storage for waste containing long lived isotopes. Two additional types of disposal are proposed: (1) trench disposal of suspect soil, (2) naval reactor component disposal. To evaluate the long-term performance of the EAVs, site-specific conceptual models were developed to consider: (1) exposure pathways and scenarios of potential importance; (2) potential releases from the facility to the environment; (3) effects of degradation of engineered features; (4) transport in the environment; (5) potential doses received from radionuclides of interest in each vault type.

  3. Environmental management of quarries as waste disposal facilities.

    PubMed

    El-Fadel, M; Sadek, S; Chahine, W

    2001-04-01

    Problems associated with the disposal of municipal solid waste have become a source of public concern worldwide as awareness of potential adverse environmental impacts and health threats from solid waste has increased. Communities are concerned about the generation and management of solid waste to the extent of refusing to allow new disposal facilities near their homes, often after witnessing the legacy of existing facilities. Under these conditions, the development of national policies for the management of solid waste becomes highly political, all while requiring appropriate technical solutions that ensure environmental protection and proper management plans that support an acceptable solution for the disposal of municipal solid waste. In some locations, the conversion of old quarries into well-engineered and controlled landfills appears as a promising solution to a continuously increasing problem, at least for many decades to come. This paper describes the environmental impacts associated with solid waste disposal in a converted quarry site and the mitigation measures that can be adopted to alleviate potential adverse impacts. Environmental management and monitoring plans are also discussed in the context of ensuring adequate environmental protection during and after the conversion process. PMID:11289451

  4. Studies involving proposed waste disposal facilities in Turkey

    SciTech Connect

    Uslu, I.; Fields, D.E.; Yalcintas, M.G.

    1987-01-01

    The Turkish government is in the process of planning two nuclear reactors in Turkey. The Turkish Atomic Energy Authority has been given the task of developing plans for improved control of low-level wastes (LLW) in Turkey. Principal sources of radioactive wastes are hospitals, research institutions, biological research centers, universities, industries, and two research reactors in Turkey. These wastes will be treated in a pilot water treatment facility located in Cekmece Nuclear Research and Training Center, Istanbul. In this temporary waste disposal facility, the wastes will be stored in 200-l concrete containers until the establishment of the permanent waste disposal sites in Turkey in 1990. The PRESTO-II (prediction of radiation effects from shallow trench operations) computer code has been applied for the general probable sites for LLW disposal in Turkey. The model is intended to serve as a non-site-specific screening model for assessing radionuclide transport, ensuring exposure, and health impacts to a static local population for a chosen time period, following the end of the disposal operation. The methodology that this code takes into consideration is versatile and explicitly considers infiltration and percolation of surface water into the trench, leaching of radionuclides, vertical and horizontal transport of radionuclides, and use of this contaminated ground water for farming, irrigation, and ingestion.

  5. Review of systemization of the Tooele Chemical Agent Disposal Facility

    SciTech Connect

    1996-07-01

    In 1993, at Tooele Army Depot, Utah, the Army completed construction of the Tooele Chemical Agent Disposal Facility (TOCDF), the first complete facility for destruction of lethal unitary chemical agents and munitions to be built in the continental United States. The TOCDF will employ the Army`s baseline incineration system to destroy the depot`s increment of the nation`s aging unitary chemical stockpile. This book assesses Army changes and improvements to the TOCDF in response to recommendations contained in earlier reports of the committee. It assesses aspects of the facility`s readiness for safe agent handling and destruction operations, its agent monitoring system, and its site specific risk assessment.

  6. Performance assessment for the class L-II disposal facility

    SciTech Connect

    1997-03-01

    This draft radiological performance assessment (PA) for the proposed Class L-II Disposal Facility (CIIDF) on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the requirements of the US Department of Energy Order 5820.2A. This PA considers the disposal of low-level radioactive wastes (LLW) over the operating life of the facility and the long-term performance of the facility in providing protection to public health and the environment. The performance objectives contained in the order require that the facility be managed to accomplish the following: (1) Protect public health and safety in accordance with standards specified in environmental health orders and other DOE orders. (2) Ensure that external exposure to the waste and concentrations of radioactive material that may be released into surface water, groundwater, soil, plants, and animals results in an effective dose equivalent (EDE) that does not exceed 25 mrem/year to a member of the public. Releases to the atmosphere shall meet the requirements of 40 CFR Pt. 61. Reasonable effort should be made to maintain releases of radioactivity in effluents to the general environment as low as reasonably achievable. (1) Ensure that the committed EDEs received by individual who inadvertently may intrude into the facility after the loss of active institutional control (100 years) will not exceed 100 mrem/year for continuous exposure of 500 mrem for a single acute exposure. (4) Protect groundwater resources, consistent with federal, state, and local requirements.

  7. Bird Mortality in Oil Field Wastewater Disposal Facilities

    NASA Astrophysics Data System (ADS)

    Ramirez, Pedro

    2010-11-01

    Commercial and centralized oilfield wastewater disposal facilities (COWDFs) are used in the Western United States for the disposal of formation water produced from oil and natural gas wells. In Colorado, New Mexico, Utah, and Wyoming, COWDFs use large evaporation ponds to dispose of the wastewater. Birds are attracted to these large evaporation ponds which, if not managed properly, can cause wildlife mortality. The U.S. Fish and Wildlife Service (USFWS) and the U.S. Environmental Protection Agency (EPA) conducted 154 field inspections of 28 COWDFs in Wyoming from March 1998 through September 2008 and documented mortality of birds and other wildlife in 9 COWDFs. Of 269 bird carcasses recovered from COWDFs, grebes (Family Podicipedidae) and waterfowl (Anatidae) were the most frequent casualties. Most mortalities were attributed to oil on evaporation ponds, but sodium toxicity and surfactants were the suspected causes of mortality at three COWDFs. Although the oil industry and state and federal regulators have made much progress in reducing bird mortality in oil and gas production facilities, significant mortality incidents continue in COWDFs, particularly older facilities permitted in the early 1980’s. Inadequate operation and management of these COWDFs generally results in the discharge of oil into the large evaporation ponds which poses a risk for birds and other wildlife.

  8. 76 FR 55256 - Definition of Solid Waste Disposal Facilities for Tax-Exempt Bond Purposes; Correction

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-09-07

    ... Internal Revenue Service 26 CFR Part 1 RIN 1545-BD04 Definition of Solid Waste Disposal Facilities for Tax... published in the Federal Register on Friday, August 19, 2011, on the definition of solid waste disposal... solid waste disposal facilities and to taxpayers that use those facilities. DATES: This correction...

  9. International low level waste disposal practices and facilities

    SciTech Connect

    Nutt, W.M.

    2011-12-19

    The safe management of nuclear waste arising from nuclear activities is an issue of great importance for the protection of human health and the environment now and in the future. The primary goal of this report is to identify the current situation and practices being utilized across the globe to manage and store low and intermediate level radioactive waste. The countries included in this report were selected based on their nuclear power capabilities and involvement in the nuclear fuel cycle. This report highlights the nuclear waste management laws and regulations, current disposal practices, and future plans for facilities of the selected international nuclear countries. For each country presented, background information and the history of nuclear facilities are also summarized to frame the country's nuclear activities and set stage for the management practices employed. The production of nuclear energy, including all the steps in the nuclear fuel cycle, results in the generation of radioactive waste. However, radioactive waste may also be generated by other activities such as medical, laboratory, research institution, or industrial use of radioisotopes and sealed radiation sources, defense and weapons programs, and processing (mostly large scale) of mineral ores or other materials containing naturally occurring radionuclides. Radioactive waste also arises from intervention activities, which are necessary after accidents or to remediate areas affected by past practices. The radioactive waste generated arises in a wide range of physical, chemical, and radiological forms. It may be solid, liquid, or gaseous. Levels of activity concentration can vary from extremely high, such as levels associated with spent fuel and residues from fuel reprocessing, to very low, for instance those associated with radioisotope applications. Equally broad is the spectrum of half-lives of the radionuclides contained in the waste. These differences result in an equally wide variety of

  10. Conceptual design report, Sodium Storage Facility, Fast Flux Test Facility, Project F-031

    SciTech Connect

    Shank, D.R.

    1995-02-14

    The Sodium Storage Facility Conceptual Design Report provides conceptual design for construction of a new facility for storage of the 260,000 gallons of sodium presently in the FFTF plant. The facility will accept the molten sodium transferred from the FFTF sodium systems, and store the sodium in a solid state under an inert cover gas until such time as a Sodium Reaction Facility is available for final disposal of the sodium.

  11. Generator Certification Process for Envirocare's Containerized Class A Disposal Facility

    SciTech Connect

    Rogers, B. C.

    2002-02-25

    On October 19, 2001, the Utah Division of Radiation Control issued Amendment 12 to Radioactive Material License UT2300249 (RML) for Envirocare of Utah, Inc. (Envirocare) disposal operations. The license amendment provides the mechanism for Envirocare to receive and dispose of containerized Class A Low-Level Radioactive Waste (LLRW) at the newly constructed Containerized Waste Facility (CWF). Due to the increased radioactivity and external dose rates of waste that will be shipped to the CWF, a Generator Certification Program has been implemented that eliminates the requirement to sample incoming shipments, thus keeping worker doses to as low as reasonably achievable (ALARA). This paper presents the key elements of the Generator Certification Program and describes the review and approval process for certifying generators to ship waste to the CWF. Each phase of the program will be discussed to assist generators in gaining a better understanding of the certification process. Additionally, the paper will present unique differences between the CWF Waste Acceptance Criteria and the requirements from other commercial disposal facilities.

  12. Integrated Disposal Facility FY2010 Glass Testing Summary Report

    SciTech Connect

    Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Serne, R Jeffrey; Mattigod, Shas V.

    2010-09-30

    Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 × 105 m3 of glass (Puigh 1999). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 0.89 × 1018 Bq total activity) of long-lived radionuclides, principally 99Tc (t1/2 = 2.1 × 105), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessement (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2010 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses. The emphasis in FY2010 was the completing an evaluation of the most sensitive kinetic rate law parameters used to predict glass weathering, documented in Bacon and Pierce (2010), and transitioning from the use of the Subsurface Transport Over Reactive Multi-phases to Subsurface Transport Over Multiple Phases computer code for near-field calculations. The FY2010 activities also consisted of developing a Monte Carlo and Geochemical Modeling framework that links glass composition to alteration phase formation by 1) determining the structure of unreacted and reacted glasses for use as input information into Monte Carlo

  13. Safe design of healthcare facilities

    PubMed Central

    Reiling, J

    2006-01-01

    The physical environment has a significant impact on health and safety; however, hospitals have not been designed with the explicit goal of enhancing patient safety through facility design. In April 2002, St Joseph's Community Hospital of West Bend, a member of SynergyHealth, brought together leaders in healthcare and systems engineering to develop a set of safety‐driven facility design recommendations and principles that would guide the design of a new hospital facility focused on patient safety. By introducing safety‐driven innovations into the facility design process, environmental designers and healthcare leaders will be able to make significant contributions to patient safety. PMID:17142606

  14. Development of an Environmental Safety Case for a Geological Disposal Facility in the UK

    NASA Astrophysics Data System (ADS)

    Bailey, L.; Clark, H.; Wellstead, M.

    2012-04-01

    Geological disposal is the UK policy for the long-term management of higher activity radioactive waste. The Radioactive Waste Management Directorate (RWMD) of the Nuclear Decommissioning Authority (NDA) has been given the responsibility for implementing geological disposal. The implementation process is founded on the principles of voluntarism and partnership and the UK Government has set in place a process that encourages communities to participate in the siting process. Developing an environmental safety case (ESC) that gives confidence that a geological disposal facility (GDF) for higher activity radioactive wastes will remain passively safe for hundreds of thousands of years after the facility has been closed, and is no longer actively maintained, is an important and challenging part of the programme to implement geological disposal. Our approach for building confidence in long-term safety is to use multiple barriers to isolate and contain the wastes and to explain our confidence in the performance of these barriers by developing a multi-factor safety case. We will develop a safety case based on varied and different lines of reasoning, including both quantitative aspects and qualitative arguments. We will use a range of safety arguments to support the ESC, drawing on underpinning science and engineering. We have published a generic ESC (that is not specific to any site or disposal facility design) that considers the long-term safety of illustrative generic disposal facility design examples in stylised geological environments. This generic ESC explains how engineered and natural barriers can work together to isolate and contain the radioactivity in the wastes. The safety arguments in the generic ESC are supported by calculations using a simple model that is illustrative of a broad range of disposal facility designs and geological environments. The generic ESC provides a benchmark enabling us to undertake disposability assessments for waste packages, without

  15. Design and Installation of a Disposal Cell Cover Field Test

    SciTech Connect

    Benson, C.H.; Waugh, W.J.; Albright, W.H.; Smith, G.M.; Bush, R.P.

    2011-02-27

    The U.S. Department of Energy’s Office of Legacy Management (LM) initiated a cover assessment project in September 2007 to evaluate an inexpensive approach to enhancing the hydrological performance of final covers for disposal cells. The objective is to accelerate and enhance natural processes that are transforming existing conventional covers, which rely on low-conductivity earthen barriers, into water balance covers, that store water in soil and release it as soil evaporation and plant transpiration. A low conductivity cover could be modified by deliberately blending the upper layers of the cover profile and planting native shrubs. A test facility was constructed at the Grand Junction, Colorado, Disposal Site to evaluate the proposed methodology. The test cover was constructed in two identical sections, each including a large drainage lysimeter. The test cover was constructed with the same design and using the same materials as the existing disposal cell in order to allow for a direct comparison of performance. One test section will be renovated using the proposed method; the other is a control. LM is using the lysimeters to evaluate the effectiveness of the renovation treatment by monitoring hydrologic conditions within the cover profile as well as all water entering and leaving the system. This paper describes the historical experience of final covers employing earthen barrier layers, the design and operation of the lysimeter test facility, testing conducted to characterize the as-built engineering and edaphic properties of the lysimeter soils, the calibration of instruments installed at the test facility, and monitoring data collected since the lysimeters were constructed.

  16. Disposable Diaper Absorbency: Improvements via Advanced Designs.

    PubMed

    Helmes, C Tucker; O'Connor, Robert; Sawyer, Larry; Young, Sharon

    2014-06-24

    Absorbency effectiveness in diapers has improved significantly in recent years with the advent of new ingredient combinations and advanced design features. With these features, many leading products maintain their dryness performance overnight. Considering the importance of holding liquid away from the skin, ongoing research in diaper construction focuses on strategies to increase the effectiveness to capture liquid and help avoid rewetting of infant skin. The layout and design of a disposable diaper allows for distribution of absorbency features where they can provide the optimal benefit. Clinical evidence indicates materials can keep moisture away from the skin in the diapered area, helping maintain proper skin hydration, minimizing irritation, and contributing to reduced rates of diaper rash. PMID:24961785

  17. Z-Area Saltstone Disposal Facility groundwater monitoring report

    SciTech Connect

    1995-12-01

    Samples from the ZBG wells at the Z-Area Saltstone Disposal Facility are analyzed quarterly for constituents required by South Carolina Department of Health and Environmental Control Industrial Waste Permit IWP-217 and for other constituents as part of the Savannah River Site Groundwater Monitoring Program. During third quarter 1995, no constituents were reported above final Primary Drinking Water Standards or Savannah River Site flagging criteria. In the past, tritium has been detected sporadically in the ZBG wells at levels similar to those detected before Z Area began radioactive operations.

  18. Generation and release of radioactive gases in LLW disposal facilities

    SciTech Connect

    Yim, M.S.; Simonson, S.A.

    1995-02-01

    The atmospheric release of radioactive gases from a generic engineered LLW disposal facility and its radiological impacts were examined. To quantify the generation of radioactive gases, detailed characterization of source inventory for carbon-14, tritium, iodine-129, krypton-85, and radon-222, was performed in terms of their activity concentrations; their distribution within different waste classes, waste forms and containers; and their subsequent availability for release in volatile or gaseous form. The generation of gases was investigated for the processes of microbial activity, radiolysis, and corrosion of waste containers and metallic components in wastes. The release of radionuclides within these gases to the atmosphere was analyzed under the influence of atmospheric pressure changes.

  19. A Change in Envirocare's Disposal Cell Design

    SciTech Connect

    Rogers, T.

    2002-02-25

    Envirocare of Utah, Inc. operates a Low Level Radioactive Waste (LLRW) and 11e. disposal facility in the Utah west dessert. Envirocare disposes of LLRW in above ground cells. A seven-foot excavation lined with two feet of clay comprises the cell floor. Approximately 22 feet of waste is then placed in the cell in one-foot thick compacted lifts. The cover system consists of a nine-foot clay radon barrier and three-foot rock erosion barrier. This is required to prevent radon emissions at the surface of the radon barrier from exceeding 20 pCi/m2s, the radon release standard in Criterion 6 of 10 CFR 40. The required thickness of the current clay radon barrier cover was based on the original radon flux model used to evaluate the safety of Envirocare's proposed LLRW and 11e.(2) license operations. Because of the lack of actual measurements, universally conservative values were used for the long-term moisture content and the radon diffusion coefficients of the waste and radon barrier material. Since receiving its license, Envirocare has collected a number of samples from the radon barrier and waste material to determine their actual radon attenuation characteristics, including the long-term moisture content and the associated radon diffusion coefficient. In addition, radon flux measurements have been performed to compare the model calculations with the calculated results. The results from these analyses indicate that the initial modeling input parameters, specifically the long-term moisture content and the radon diffusion coefficient, are more conservative than that needed to ensure compliance with the applicable regulatory requirements.

  20. Investigation of contaminant transport from the saginaw confined disposal facility

    SciTech Connect

    Velleux, M.L.; Rathbun, J.E.; Kreis, R.G.; Martin, J.L.; Mac, M.J.

    1993-01-01

    Pilot biomonitoring and modeling studies were conducted at the Saginaw Confined Disposal Facility (CDF), Saginaw Bay, Lake Huron, during 1987 to develop methods to assess the potential for or magnitude of (1) contaminant transport from the dike interior to the outside environment, (2) impacts of CDF disposal on the water column and sediments, and (3) impacts of CDF disposal on aquatic biota living in the outdike zone. Polychlorinated biphenyls (PCBs) were selected for study due to their presence in the sediments of the Saginaw River/Bay ecosystem. A mathematical model of near-field contaminant transport through the dike walls was constructed. Model predictions indicate that the rate of contaminant transport through the dike is expected to be small, amounting to less than 0.25 kg of PCBs after 5,000 days of simulation. A mathematical model of the farfield impacts of CDF transport was also constructed. Model predictions indicate that the incremental increase in steady-state, water column PCB concentrations in Saginaw Bay is expected to be approximately 0.05 ng/L per kg of PCB transported from the CDF. A biomonitoring program was developed to assess contaminant transport through dike walls and its impact on contaminant concentrations in biological tissues.

  1. Economics of a small-volume low-level radioactive waste disposal facility

    SciTech Connect

    Not Available

    1993-04-01

    This report was prepared by the US Department of Energy National Low-Level Waste Management Program to present the results of a life-cycle cost analysis of a low-level radioactive waste disposal facility, including all support facilities, beginning in the preoperational phase and continuing through post-closure care. The disposal technology selected for this report is earth-covered concrete vaults, which use reinforced concrete vaults constructed above grade and an earth cover constructed at the end of the operational period for permanent closure. The report develops a design, cost estimate, and schedule for the base case and eight alternative scenarios involving changes in total disposal capacity, operating life, annual disposal rate, source of financing and long-term interest rates. The purpose of this analysis of alternatives is to determine the sensitivity of cost to changes in key analytical or technical parameters, thereby evaluating the influence of a broad range of conditions. The total estimated cost of each alternative is estimated and a unit disposal charge is developed.

  2. 40 CFR 61.90 - Designation of facilities.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... Department of Energy that emits any radionuclide other than radon-222 and radon-220 into the air, except that this subpart does not apply to disposal at facilities subject to 40 CFR part 191, subpart B or 40 CFR... Emissions of Radionuclides Other Than Radon From Department of Energy Facilities § 61.90 Designation...

  3. 40 CFR 61.90 - Designation of facilities.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... Department of Energy that emits any radionuclide other than radon-222 and radon-220 into the air, except that this subpart does not apply to disposal at facilities subject to 40 CFR part 191, subpart B or 40 CFR... Emissions of Radionuclides Other Than Radon From Department of Energy Facilities § 61.90 Designation...

  4. 40 CFR 61.90 - Designation of facilities.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... Department of Energy that emits any radionuclide other than radon-222 and radon-220 into the air, except that this subpart does not apply to disposal at facilities subject to 40 CFR part 191, subpart B or 40 CFR... Emissions of Radionuclides Other Than Radon From Department of Energy Facilities § 61.90 Designation...

  5. 40 CFR 61.90 - Designation of facilities.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... Department of Energy that emits any radionuclide other than radon-222 and radon-220 into the air, except that this subpart does not apply to disposal at facilities subject to 40 CFR part 191, subpart B or 40 CFR... Emissions of Radionuclides Other Than Radon From Department of Energy Facilities § 61.90 Designation...

  6. 40 CFR 61.90 - Designation of facilities.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... Department of Energy that emits any radionuclide other than radon-222 and radon-220 into the air, except that this subpart does not apply to disposal at facilities subject to 40 CFR part 191, subpart B or 40 CFR... Emissions of Radionuclides Other Than Radon From Department of Energy Facilities § 61.90 Designation...

  7. Designing open water disposal for dredged muddy sediments

    NASA Astrophysics Data System (ADS)

    McAnally, William H.; Adamec, Stephen A.

    1987-11-01

    Open water disposal of muddy sediments in the estuarine environment is practiced to minimize dredging costs and to preserve contained disposal site capacity. Open water sites are usually either dispersive or retentive. Dispersive sites are used in the expectation that disposed sediments will not remain there, but will be transported out of the site, leaving room for additional disposal. Retentive sites are designed to ensure that disposed sediments mostly remain within the site. Choice of one of these approaches depends on the site character, sediment character, and disposal quantities. Design of disposal management plans for both site types is accomplished by use of field observations, laboratory tests, and numerical modeling. Three disposal site studies illustrate the methods used. At the Alcatraz site in San Francisco Bay, a dispersive condition is maintained by use of constraints on dredged mud characteristics that were developed from laboratory tests on erosion rates and from numerical modeling of the dump process. Field experiments were designed to evaluate the management procedure. In Corpus Christi Bay a numerical model was used to determine how much disposed sediment returns to the navigation channel, and to devise a location for disposal that will minimize that return. In Puget Sound a model has been used to ensure that most of the disposed material remains in the site. New techniques, including a piped disposal through 60 m of water, were investigated.

  8. USE OF GEOSYNTHETICS IN MUNICIPAL SOLID WASTE DISPOSAL FACILITIES

    EPA Science Inventory

    The use of geosynthetics is increasing in all types of waste management facilities. he use of flexible membranes for containment and geonets and geotextiles for conveyance of liquids and gases will allow the design community to develop innovative designs. owever, the use of geosy...

  9. 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.

  10. EnergySolution's Clive Disposal Facility Operational Research Model - 13475

    SciTech Connect

    Nissley, Paul; Berry, Joanne

    2013-07-01

    EnergySolutions owns and operates a licensed, commercial low-level radioactive waste disposal facility located in Clive, Utah. The Clive site receives low-level radioactive waste from various locations within the United States via bulk truck, containerised truck, enclosed truck, bulk rail-cars, rail boxcars, and rail inter-modals. Waste packages are unloaded, characterized, processed, and disposed of at the Clive site. Examples of low-level radioactive waste arriving at Clive include, but are not limited to, contaminated soil/debris, spent nuclear power plant components, and medical waste. Generators of low-level radioactive waste typically include nuclear power plants, hospitals, national laboratories, and various United States government operated waste sites. Over the past few years, poor economic conditions have significantly reduced the number of shipments to Clive. With less revenue coming in from processing shipments, Clive needed to keep its expenses down if it was going to maintain past levels of profitability. The Operational Research group of EnergySolutions were asked to develop a simulation model to help identify any improvement opportunities that would increase overall operating efficiency and reduce costs at the Clive Facility. The Clive operations research model simulates the receipt, movement, and processing requirements of shipments arriving at the facility. The model includes shipment schedules, processing times of various waste types, labor requirements, shift schedules, and site equipment availability. The Clive operations research model has been developed using the WITNESS{sup TM} process simulation software, which is developed by the Lanner Group. The major goals of this project were to: - identify processing bottlenecks that could reduce the turnaround time from shipment arrival to disposal; - evaluate the use (or idle time) of labor and equipment; - project future operational requirements under different forecasted scenarios. By identifying

  11. Recharge Data Package for the 2005 Integrated Disposal Facility Performance Assessment

    SciTech Connect

    Fayer, Michael J.; Szecsody, Jim E.

    2004-06-30

    Pacific Northwest National Laboratory assisted CH2M Hill Hanford Group, Inc., (CHG) by providing estimates of recharge rates for current conditions and long-term scenarios involving disposal in the Integrated Disposal Facility (IDF). The IDF will be located in the 200 East Area at the Hanford Site and will receive several types of waste including immobilized low-activity waste. The recharge estimates for each scenario were derived from lysimeter and tracer data collected by the IDF PA Project and from modeling studies conducted for the project. Recharge estimates were provided for three specific site features (the surface barrier; possible barrier side slopes; and the surrounding soil) and four specific time periods (pre-Hanford; Hanford operations; surface barrier design life; post-barrier design life). CHG plans to conduct a performance assessment of the latest IDF design and call it the IDF 2005 PA; this recharge data package supports the upcoming IDF 2005 PA.

  12. Near-Field Hydrology Data Package for the Integrated Disposal Facility 2005 Performance Assessment

    SciTech Connect

    Meyer, Philip D.; Saripalli, Prasad; Freedman, Vicky L.

    2004-06-25

    CH2MHill Hanford Group, Inc. (CHG) is designing and assessing the performance of an Integrated Disposal Facility (IDF) to receive immobilized low-activity waste (ILAW), Low-Level and Mixed Low-Level Wastes (LLW/MLLW), and the Waste Treatment Plant (WTP) melters used to vitrify the ILAW. The IDF Performance Assessment (PA) assesses the performance of the disposal facility to provide a reasonable expectation that the disposal of the waste is protective of the general public, groundwater resources, air resources, surface water resources, and inadvertent intruders. The PA requires prediction of contaminant migration from the facilities, which is expected to occur primarily via the movement of water through the facilities and the consequent transport of dissolved contaminants in the pore water of the vadose zone. Pacific Northwest National Laboratory (PNNL) assists CHG in its performance assessment activities. One of PNNL’s tasks is to provide estimates of the physical, hydraulic, and transport properties of the materials comprising the disposal facilities and the disturbed region around them. These materials are referred to as the near-field materials. Their properties are expressed as parameters of constitutive models used in simulations of subsurface flow and transport. In addition to the best-estimate parameter values, information on uncertainty in the parameter values and estimates of the changes in parameter values over time are required to complete the PA. These parameter estimates and information were previously presented in a report prepared for the 2001 ILAW PA. This report updates the parameter estimates for the 2005 IDF PA using additional information and data collected since publication of the earlier report.

  13. Book Processing Facility Design.

    ERIC Educational Resources Information Center

    Sheahan (Drake)-Stewart Dougall, Marketing and Physical Distribution Consultants, New York, NY.

    The Association of New York Libraries for Technical Services (ANYLTS) is established to develop and run a centralized book processing facility for the public library systems in New York State. ANYLTS plans to receive book orders from the 22 library systems, transmit orders to publishers, receive the volumes from the publishers, print and attach…

  14. 10 CFR 61.51 - Disposal site design for land disposal.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... extent practicable water infiltration, to direct percolating or surface water away from the disposed... must direct surface water drainage away from disposal units at velocities and gradients which will not... be designed to minimize to the extent practicable the contact of water with waste during storage,...

  15. 75 FR 19311 - Ocean Dumping; Guam Ocean Dredged Material Disposal Site Designation

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-14

    ...The EPA is proposing to designate the Guam Deep Ocean Disposal Site (G-DODS) as a permanent ocean dredged material disposal site (ODMDS) located offshore of Guam. Dredging is essential for maintaining safe navigation at port and naval facilities in Apra Harbor and other locations around Guam. Not all dredged materials are suitable for beneficial re-use (e.g., construction materials, landfill......

  16. Hydrologic test plan for the Environmental Remediation Disposal Facility

    SciTech Connect

    Swanson, L.C.

    1993-09-30

    Hydrologic tests are planned at seven wells that will be drilled at the proposed Environmental Remediation Disposal Facility (ERDF). These wells are supporting hydrologic, geologic, and hydrochemical characterization at this new facility. Hydrologic testing will consist of instantaneous slug tests, slug interference tests, step-drawdown tests, and constant rate discharge tests (generally single-well). These test results and later groundwater monitoring data will be used to determine groundwater flow directions, flow rates, and the chemical makeup of the groundwater below the proposed ERDF. The seven wells will be drilled in two phases. In Phase I four wells will be drilled and tested: Two to the top of the uppermost aquifer (water table) and two as characterization boreholes to the top of basalt. The Phase I wells are located in the northern portion of the proposed ERDF site (699-32-72, 699-SDF-6, -7 and -8) (Figure 1). If Phase II drilling proceeds, the remaining three wells will be installed and tested (two deep and one shallow). A phased approach to drilling is warranted because of current uncertainty in the land use requirements at the proposed ERDF.

  17. Molycorp Guadalupe Mountain tailings disposal facility. Final report

    SciTech Connect

    Not Available

    1989-11-01

    Molycorp proposes to construct and operate a molybdenum tailings disposal facility on 1,230 acres of public land near Questa, New Mexico and has located mill site claims for this purpose. The project would consist of a 568-acre tailings pond in the saddle of Guadalupe Mountain. The pond would be formed by the construction of two rock-filled dams at either end of the saddle. Other facilities would include a tailings pump station, an extension of the tailings pipeline, tailings distribution lines, access roads and a patrol road, a powerline, a seepage collection pond, surface water diversion channels, and a decant water channel. The project would provide additional storage for approximately 200 million tons of tailings from Molycorp's molybdenum mine located approximately 12 miles east of Guadalupe Mountain. The Bureau of Land Management (BLM) completed an Environmental Assessment (EA) for this project in February 1985. As a result of that EA, the BLM determined that an Environmental Impact Statement (EIS) would be required. The EIS analyzes and documents the environmental impacts of the proposed project through construction, operation, and closure.

  18. 49 CFR 599.201 - Identification of salvage auctions and disposal facilities.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... on the Web site at http://www.cars.gov/disposal; or (3) A facility that disposes of vehicles in Puerto Rico, the Virgin Islands, Guam, American Samoa, or the Commonwealth of the Northern Mariana...) of this section, be currently listed on the Web site at http://www.cars.gov/disposal, as of the...

  19. 49 CFR 599.201 - Identification of salvage auctions and disposal facilities.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... on the Web site at http://www.cars.gov/disposal; or (3) A facility that disposes of vehicles in Puerto Rico, the Virgin Islands, Guam, American Samoa, or the Commonwealth of the Northern Mariana...) of this section, be currently listed on the Web site at http://www.cars.gov/disposal, as of the...

  20. 49 CFR 599.201 - Identification of salvage auctions and disposal facilities.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... on the Web site at http://www.cars.gov/disposal; or (3) A facility that disposes of vehicles in Puerto Rico, the Virgin Islands, Guam, American Samoa, or the Commonwealth of the Northern Mariana...) of this section, be currently listed on the Web site at http://www.cars.gov/disposal, as of the...

  1. 49 CFR 599.201 - Identification of salvage auctions and disposal facilities.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... on the Web site at http://www.cars.gov/disposal; or (3) A facility that disposes of vehicles in Puerto Rico, the Virgin Islands, Guam, American Samoa, or the Commonwealth of the Northern Mariana...) of this section, be currently listed on the Web site at http://www.cars.gov/disposal, as of the...

  2. 49 CFR 599.201 - Identification of salvage auctions and disposal facilities.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... on the Web site at http://www.cars.gov/disposal; or (3) A facility that disposes of vehicles in Puerto Rico, the Virgin Islands, Guam, American Samoa, or the Commonwealth of the Northern Mariana...) of this section, be currently listed on the Web site at http://www.cars.gov/disposal, as of the...

  3. Universal Design for Academic Facilities

    ERIC Educational Resources Information Center

    Salmen, John P. S.

    2011-01-01

    Universal design (UD) can play a role in many aspects of academic life and is often thought of in the context of learning. However, this chapter focuses on the impact of UD on the design of facilities in a university or campus setting. Universal design has the potential for transforming universities into truly egalitarian institutions that…

  4. Production Facility SCADA Design Report

    SciTech Connect

    Dale, Gregory E.; Holloway, Michael Andrew; Baily, Scott A.; Woloshun, Keith Albert; Wheat, Robert Mitchell Jr.

    2015-03-23

    The following report covers FY 14 activities to develop supervisory control and data acquisition (SCADA) system for the Northstar Moly99 production facility. The goal of this effort is to provide Northstar with a baseline system design.

  5. Designing Facilities for Collaborative Operations

    NASA Technical Reports Server (NTRS)

    Norris, Jeffrey; Powell, Mark; Backes, Paul; Steinke, Robert; Tso, Kam; Wales, Roxana

    2003-01-01

    A methodology for designing operational facilities for collaboration by multiple experts has begun to take shape as an outgrowth of a project to design such facilities for scientific operations of the planned 2003 Mars Exploration Rover (MER) mission. The methodology could also be applicable to the design of military "situation rooms" and other facilities for terrestrial missions. It was recognized in this project that modern mission operations depend heavily upon the collaborative use of computers. It was further recognized that tests have shown that layout of a facility exerts a dramatic effect on the efficiency and endurance of the operations staff. The facility designs (for example, see figure) and the methodology developed during the project reflect this recognition. One element of the methodology is a metric, called effective capacity, that was created for use in evaluating proposed MER operational facilities and may also be useful for evaluating other collaboration spaces, including meeting rooms and military situation rooms. The effective capacity of a facility is defined as the number of people in the facility who can be meaningfully engaged in its operations. A person is considered to be meaningfully engaged if the person can (1) see, hear, and communicate with everyone else present; (2) see the material under discussion (typically data on a piece of paper, computer monitor, or projection screen); and (3) provide input to the product under development by the group. The effective capacity of a facility is less than the number of people that can physically fit in the facility. For example, a typical office that contains a desktop computer has an effective capacity of .4, while a small conference room that contains a projection screen has an effective capacity of around 10. Little or no benefit would be derived from allowing the number of persons in an operational facility to exceed its effective capacity: At best, the operations staff would be underutilized

  6. 40 CFR 257.3 - Criteria for classification of solid waste disposal facilities and practices.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 40 Protection of Environment 25 2011-07-01 2011-07-01 false Criteria for classification of solid waste disposal facilities and practices. 257.3 Section 257.3 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES CRITERIA FOR CLASSIFICATION OF SOLID WASTE DISPOSAL FACILITIES AND PRACTICES Classification of Solid...

  7. 40 CFR 257.3 - Criteria for classification of solid waste disposal facilities and practices.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 40 Protection of Environment 26 2012-07-01 2011-07-01 true Criteria for classification of solid... PROTECTION AGENCY (CONTINUED) SOLID WASTES CRITERIA FOR CLASSIFICATION OF SOLID WASTE DISPOSAL FACILITIES AND PRACTICES Classification of Solid Waste Disposal Facilities and Practices § 257.3 Criteria...

  8. 40 CFR 257.3 - Criteria for classification of solid waste disposal facilities and practices.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 40 Protection of Environment 25 2014-07-01 2014-07-01 false Criteria for classification of solid... PROTECTION AGENCY (CONTINUED) SOLID WASTES CRITERIA FOR CLASSIFICATION OF SOLID WASTE DISPOSAL FACILITIES AND PRACTICES Classification of Solid Waste Disposal Facilities and Practices § 257.3 Criteria...

  9. 40 CFR 257.3 - Criteria for classification of solid waste disposal facilities and practices.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 40 Protection of Environment 26 2013-07-01 2013-07-01 false Criteria for classification of solid... PROTECTION AGENCY (CONTINUED) SOLID WASTES CRITERIA FOR CLASSIFICATION OF SOLID WASTE DISPOSAL FACILITIES AND PRACTICES Classification of Solid Waste Disposal Facilities and Practices § 257.3 Criteria...

  10. Preliminary Closure Plan for the Immobilized Low Activity Waste (ILAW) Disposal Facility

    SciTech Connect

    BURBANK, D.A.

    2000-08-31

    This document describes the preliminary plans for closure of the Immobilized Low-Activity Waste (ILAW) disposal facility to be built by the Office of River Protection at the Hanford site in southeastern Washington. The facility will provide near-surface disposal of up to 204,000 cubic meters of ILAW in engineered trenches with modified RCRA Subtitle C closure barriers.

  11. 76 FR 55255 - Definition of Solid Waste Disposal Facilities for Tax-Exempt Bond Purposes; Correction

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-09-07

    ... Internal Revenue Service 26 CFR Part 1 RIN 1545-BD04 Definition of Solid Waste Disposal Facilities for Tax... the Federal Register on Friday, August 19, 2011, on the definition of solid waste disposal facilities... regulations provide guidance to State and local governments that issue tax-exempt bonds to finance solid...

  12. Developing a low-level radioactive waste disposal facility in Connecticut: Update on progress and new directions

    SciTech Connect

    Gingerich, R.E.

    1993-03-01

    Connecticut is a member of the Northeast Interstate Low-Level Radioactive Waste Management Compact (Northeast LLRW Compact). The other member of the Northeast LLRW Compact is New Jersey. The Northeast Interstate Low-Level Radioactive Waste Commission (Northeast Compact Commission), the Northeast LLRW Compact`s governing body, has designated both Connecticut and New Jersey as host states for disposal facilities. The Northeast Compact Commission has recommended that, for purposes of planning for each state`s facility, the siting agency for the state should use projected volumes and characteristics of the LLW generated in its own state. In 1987 Connecticut enacted legislation that assigns major responsibilities for developing a LLW disposal facility in Connecticut to the Connecticut Hazardous Waste Management Service (CHWMS). The CHWMS is required to: prepare and revise, as necessary, a LLW Management Plan for the state; select a site for a LLW disposal facility; select a disposal technology to be used at the site; select a firm to obtain the necessary approvals for the facility and to develop and operate it; and serve as the custodial agency for the facility. This paper discusses progress in developing a facility.

  13. Performance assessment for a hypothetical low-level waste disposal facility

    SciTech Connect

    Smith, C.S.; Rohe, M.J.; Ritter, P.D.

    1997-01-01

    Disposing of low-level waste (LLW) is a concern for many states throughout the United States. A common disposal method is below-grade concrete vaults. Performance assessment analyses make predictions of contaminant release, transport, ingestion, inhalation, or other routes of exposure, and the resulting doses for various disposal methods such as the below-grade concrete vaults. Numerous assumptions are required to simplify the processes associated with the disposal facility to make predictions feasible. In general, these assumptions are made conservatively so as to underestimate the performance of the facility. The objective of this report is to describe the methodology used in conducting a performance assessment for a hypothetical waste facility located in the northeastern United States using real data as much as possible. This report consists of the following: (a) a description of the disposal facility and site, (b) methods used to analyze performance of the facility, (c) the results of the analysis, and (d) the conclusions of this study.

  14. Radiocarbon signal of a low and intermediate level radioactive waste disposal facility in nearby trees.

    PubMed

    Janovics, R; Kelemen, D I; Kern, Z; Kapitány, S; Veres, M; Jull, A J T; Molnár, M

    2016-03-01

    Tree ring series were collected from the vicinity of a Hungarian radioactive waste treatment and disposal facility and from a distant control background site, which is not influenced by the radiocarbon discharge of the disposal facility but it represents the natural regional (14)C level. The (14)C concentration of the cellulose content of tree rings was measured by AMS. Data of the tree ring series from the disposal facility was compared to the control site for each year. The results were also compared to the (14)C data of the atmospheric (14)C monitoring stations at the disposal facility and to international background measurements. On the basis of the results, the excess radiocarbon of the disposal facility can unambiguously be detected in the tree from the repository site. PMID:26704325

  15. 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...

  16. 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...

  17. 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...

  18. 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...

  19. Climate change in safety assessment of a surface disposal facility

    NASA Astrophysics Data System (ADS)

    Leterme, B.

    2012-04-01

    The Belgian Agency for Radioactive Waste and Enriched Fissile Materials (ONDRAF/NIRAS) aims to develop a surface disposal facility for LILW-SL in Dessel (North-East of Belgium). Given the time scale of interest for the safety assessment (several millennia), a number of parameters in the modelling chain near field - geosphere - biosphere may be influenced by climate change. The present study discusses how potential climate change impact was accounted for the following quantities: (i) near field infiltration through the repository earth cover, (ii) partial pressure of CO2 in the water infiltrating the cover and draining the concrete, and (iii) groundwater recharge in the vicinity of the site. For these three parameters, the impact of climate change is assessed using climatic analogue stations, i.e. stations presently under climatic conditions corresponding to a given climate state. Results indicate that : (i) Using Gijon (Spain) as representative analogue station for the next millennia, infiltration at the bottom of the soil layer towards the modules of the facility is expected to increase (from 346 to 413 mm/y) under a subtropical climate. Although no colder climate is foreseen in the next 10 000 years, the approach was also tested with analogue stations for a colder climate state. Using Sisimiut (Greenland) as representative analogue station, infiltration is expected to decrease (109 mm/y). (ii) Due to changes of the partial pressure of CO2 in the soil water, cement degradation is estimated to occur more rapidly under a warmer climate. (iii) A decrease of long-term annual average groundwater recharge by 12% was simulated using Gijon representative analogue (from 314 to 276 mm), although total rainfall was higher (947 mm) in the warmer climate compared to the current temperate climate (899 mm). For a colder climate state, groundwater recharge simulated for the representative analogue Sisimiut showed a decrease by 69% compared to current climate conditions. The

  20. Overview of processes affecting contaminant release from confined disposal facilities. Final report

    SciTech Connect

    Martin, J.L.; McCutcheon, S.C.

    1992-01-01

    Confined disposal facilities (CDFs) are widely used for the disposal of dredged material from Corps of Engineers maintenance dredging projects along the Atlantic and Gulf coasts and waterways and harbors in the Great Lakes. CDFs are a less common disposal alternative along the Pacific coast and inland river systems. When contaminated dredged material is placed in the CDF, there is a potential for contaminant mobilization and release from the CDF by a variety of physical, chemical, and biological processes. This report provides an overview of the processes affecting mobilization and release of contaminants from CDFs and the potential applicability of multimedia models for prediction of contaminant release. Processes affecting release from in-water CDFs are emphasized, although many of the processes discussed are applicable to nearshore and upland CDFs. Processes affecting contaminant release are complex, involving a variety of chemicals and operational and design considerations. Many of the important processes are reasonably well known. Laboratory column settling and elutriate techniques have been developed to estimate solids and contaminant concentration in water directly released during hydraulic disposal operations. Predictive techniques for other processes are not as available.

  1. Approaches to consider covers and liners in a low-level waste disposal facility performance assessment

    SciTech Connect

    Seitz, Roger; Phifer, Mark; Suttora, Linda

    2015-03-17

    On-site disposal cells are in use and being considered at several USDOE sites as the final disposition for large amounts of waste associated with cleanup of contaminated areas and facilities. These disposal cells are typically regulated by States and/or the USEPA in addition to having to comply with requirements in DOE Order 435.1, Radioactive Waste Management. The USDOE-EM Office of Site Restoration formed a working group to foster improved communication and sharing of information for personnel associated with these Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) disposal cells and work towards more consistent assumptions, as appropriate, for technical and policy considerations related to performance and risk assessments in support of a Record of Decision and Disposal Authorization Statement. One task completed by the working group addressed approaches for considering the performance of covers and liners/leachate collection systems in the context of a performance assessment (PA). A document has been prepared which provides recommendations for a general approach to address covers and liners/leachate collection systems in a PA and how to integrate assessments with defense-in-depth considerations such as design, operations and waste acceptance criteria to address uncertainties. Specific information and references are provided for details needed to address the evolution of individual components of cover and liner/leachate collection systems. This information is then synthesized into recommendations for best practices for cover and liner system design and examples of approaches to address the performance of covers and liners as part of a performance assessment of the disposal system.

  2. An Evaluation of Long-Term Performance of Liner Systems for Low-Level Waste Disposal Facilities

    SciTech Connect

    Arthur S. Rood; Annette L. Schafer; A. Jeffrey Sondrup

    2011-03-01

    Traditional liner systems consisting of a geosynthetic membrane underlying a waste disposal facility coupled with a leachate collection system have been proposed as a means of containing releases of low-level radioactive waste within the confines of the disposal facility and thereby eliminating migration of radionuclides into the vadose zone and groundwater. However, this type of hydraulic containment liner system is only effective as long as the leachate collection system remains functional or an overlying cover limits the total infiltration to the volumetric pore space of the disposal system. If either the leachate collection system fails, or the overlying cover becomes less effective during the 1,000’s of years of facility lifetime, the liner may fill with water and release contaminated water in a preferential or focused manner. If the height of the liner extends above the waste, the waste will become submerged which could increase the release rate and concentration of the leachate. If the liner extends near land surface, there is the potential for contamination reaching land surface creating a direct exposure pathway. Alternative protective liner systems can be engineered that eliminate radionuclide releases to the vadose zone during operations and minimizing long term migration of radionuclides from the disposal facility into the vadose zone and aquifer. Non-traditional systems include waste containerization in steel or composite materials. This type of system would promote drainage of clean infiltrating water through the facility without contacting the waste. Other alternatives include geochemical barriers designed to transmit water while adsorbing radionuclides beneath the facility. Facility performance for a hypothetical disposal facility has been compared for the hydraulic and steel containerization liner alternatives. Results were compared in terms of meeting the DOE Order 435.1 low-level waste performance objective of 25 mrem/yr all-pathways dose

  3. Annual Report for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2011

    SciTech Connect

    French, Sean B.; Shuman, Rob

    2012-05-22

    of these activities cannot be used to evaluate the validity of the performance assessment and composite analysis models because the monitoring data collected are specific to operational releases or address receptors that are outside the domain of the performance assessment and composite analysis. In general, applicable monitoring data are supportive of some aspects of the performance assessment and composite analysis. Several research and development (R and D) efforts have been initiated under the performance assessment and composite analysis maintenance program. These investigations are designed to improve the current understanding of the disposal facility and site, thereby reducing the uncertainty associated with the projections of the long-term performance of Area G. The status and results of R and D activities that were undertaken in fiscal year 2011 are discussed in this report. Special analyses have been conducted to determine the feasibility of disposing of specific waste streams, to address proposed changes in disposal operations, and to consider the impacts of changes to the models used to conduct the performance assessment and composite analysis. These analyses are described and the results of the evaluations are summarized in this report. The Area G disposal facility consists of Material Disposal Area (MDA) G and the Zone 4 expansion area. To date, all disposal operations at Area G have been confined to MDA G. Material Disposal Area G is scheduled to undergo final closure in 2015; disposal of waste in the pits and shafts is scheduled to end in 2013. In anticipation of the closure of MDA G, plans are being made to ship the majority of the waste generated at LANL to off-site locations for disposal. It is not clear at this time if waste that will be disposed of at LANL will be placed in Zone 4 or if disposal operations will move to a new location at the Laboratory. Separately, efforts to optimize the final cover used in the closure of MDA G are underway; a

  4. CHARACTERIZATION OF CORE SAMPLE COLLECTED FROM THE SALTSTONE DISPOSAL FACILITY

    SciTech Connect

    Cozzi, A.; Duncan, A.

    2010-01-28

    During the month of September 2008, grout core samples were collected from the Saltstone Disposal Facility, Vault 4, cell E. This grout was placed during processing campaigns in December 2007 from Deliquification, Dissolution and Adjustment Batch 2 salt solution. The 4QCY07 Waste Acceptance Criteria sample collected on 11/16/07 represents the salt solution in the core samples. Core samples were retrieved to initiate the historical database of properties of emplaced Saltstone and to demonstrate the correlation between field collected and laboratory prepared samples. Three samples were collected from three different locations. Samples were collected using a two-inch diameter concrete coring bit. In April 2009, the core samples were removed from the evacuated sample container, inspected, transferred to PVC containers, and backfilled with nitrogen. Samples furthest from the wall were the most intact cylindrically shaped cored samples. The shade of the core samples darkened as the depth of coring increased. Based on the visual inspection, sample 3-3 was selected for all subsequent analysis. The density and porosity of the Vault 4 core sample, 1.90 g/cm{sup 3} and 59.90% respectively, were comparable to values achieved for laboratory prepared samples. X-ray diffraction analysis identified phases consistent with the expectations for hydrated Saltstone. Microscopic analysis revealed morphology features characteristic of cementitious materials with fly ash and calcium silicate hydrate gel. When taken together, the results of the density, porosity, x-ray diffraction analysis and microscopic analysis support the conclusion that the Vault 4, Cell E core sample is representative of the expected waste form.

  5. Program Plan for Revision of the Z-Area Saltstone Disposal Facility Performance Assessment

    SciTech Connect

    Cook, James R.

    2005-12-07

    Savannah River National Laboratory (SRNL) and the Saltstone Project, are embarking on the next revision to the Saltstone Disposal Facility (SDF) performance assessment (PA). This program plan has been prepared to outline the general approach, scope, schedule and resources for the PA revision. The plan briefly describes the task elements of the PA process. It discusses critical PA considerations in the development of conceptual models and interpretation of results. Applicable quality assurance (QA) requirements are identified and the methods for implementing QA for both software and documentation are described. The plan identifies project resources supporting the core team and providing project oversight. Program issues and risks are identified as well as mitigation of those risks. Finally, a preliminary program schedule has been developed and key deliverables identified. A number of significant changes have been implemented since the last PA revision resulting in a new design for future SDF disposal units. This revision will encompass the existing and planned disposal units, PA critical radionuclides and exposure pathways important to SDF performance. An integrated analysis of the overall facility layout, including all disposal units, will be performed to assess the impact of plume overlap on PA results. Finally, a rigorous treatment of uncertainty will be undertaken using probabilistic simulations. This analysis will be reviewed and approved by DOE-SR, DOE-HQ and potentially the Nuclear Regulatory Commission (NRC). This revision will be completed and ready for the start of the DOE review at the end of December 2006. This work supports a Saltstone Vault 2 fee-bearing milestone. This milestone includes completion of the Vault 2 module of the PA revision by the end of FY06.

  6. 40 CFR 761.213 - Use of manifest-Commercial storage and disposal facility requirements.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ..., PROCESSING, DISTRIBUTION IN COMMERCE, AND USE PROHIBITIONS PCB Waste Disposal Records and Reports § 761.213... or disposal facility receives PCB waste accompanied by a manifest, the owner, operator or his/her... the PCB waste covered by the manifest was received, that the PCB waste was received except as noted...

  7. 40 CFR 761.213 - Use of manifest-Commercial storage and disposal facility requirements.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ..., PROCESSING, DISTRIBUTION IN COMMERCE, AND USE PROHIBITIONS PCB Waste Disposal Records and Reports § 761.213... or disposal facility receives PCB waste accompanied by a manifest, the owner, operator or his/her... the PCB waste covered by the manifest was received, that the PCB waste was received except as noted...

  8. Life-Cycle Cost Study for a Low-Level Radioactive Waste Disposal Facility in Texas

    SciTech Connect

    B. C. Rogers; P. L. Walter; R. D. Baird

    1999-08-01

    This report documents the life-cycle cost estimates for a proposed low-level radioactive waste disposal facility near Sierra Blanca, Texas. The work was requested by the Texas Low-Level Radioactive Waste Disposal Authority and performed by the National Low-Level Waste Management Program with the assistance of Rogers and Associates Engineering Corporation.

  9. DREDGED MATERIAL RECLAMATION AT THE JONES ISLAND CONFINED DISPOSAL FACILITY - ITER

    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...

  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. Managing commercial low-level radioactive waste beyond 1992: Transportation planning for a LLW disposal facility

    SciTech Connect

    Quinn, G.J.

    1992-01-01

    This technical bulletin presents information on the many activities and issues related to transportation of low-level radioactive waste (LLW) to allow interested States to investigate further those subjects for which proactive preparation will facilitate the development and operation of a LLW disposal facility. The activities related to transportation for a LLW disposal facility are discussed under the following headings: safety; legislation, regulations, and implementation guidance; operations-related transport (LLW and non-LLW traffic); construction traffic; economics; and public involvement.

  12. 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.

  13. Field Investigation Plan for 1301-N and 1325-N FacilitiesSampling to Support Remedial Design

    SciTech Connect

    S. G. Weiss.

    1998-12-04

    This field investigation plan (FIP) provides for the sampling and analysis activities supporting the remedial design planning for the planned removal action for the 1301-N and 1325-N Liquid Waste Disposal Facilities (LWDFs), which are treatment, storage,and disposal (TSD) units (cribs/trenches). The planned removalaction involves excavation, transportation, and disposal of contaminated material at the Environmental Restoration Disposal Facility (ERDF).An engineering study (BHI 1997) was performed to develop and evaluate various options that are predominately influenced by the volume of high- and low-activity contaminated soil requiring removal. The study recommended that additional sampling be performed to supplement historical data for use in the remedial design.

  14. Idaho Chemical Processing Plant Liquid Effluent Treatment and Disposal Facility hot test report

    SciTech Connect

    Hastings, R.L.

    1993-09-01

    Prior to initial operation with radioactive feed or ``hot`` operation, the Liquid Effluent Treatment and Disposal (LET&D) Facility underwent extensive testing. This report provides a detailed description and analysis of this testing. Testing has determined that LET&D is capable of processing radioactive solutions between the design flowrates of 275 gph to 550 gph. Modifications made to prevent condensation on the off-gas HEPA filters, to the process vacuum control, bottoms cooler rupture disks, and feed control system operation were successful. Unfortunately, two mixers failed prior to ``hot`` testing due to manufacturer`s error which limited operation of the PEW Evaporator System and sampling was not able to prove that design removal efficiencies for Mercury, Cadmium, Plutonium, and Non-Volatile Radionuclides.

  15. Z-Area saltstone disposal facility groundwater monitoring report. First and second quarters 1997

    SciTech Connect

    1997-07-01

    This report presents the results of groundwater sampling during the first and second quarters of 1997 in the Z-Area Saltstone Disposal Facility. This report presents only the data for sampling during the first half of 1997 as required by industrial Solid Waste Permit No. 025500-1603. For a detailed discussion of groundwater monitoring in the Z-Area Saltstone Disposal Facility, consult the 1996 Z-Area Saltstone Disposal Annual Report. Appendix A presents the proposed South Carolina Department of Health and Environmental Control Proposed Groundwater Monitoring Standards. Flagging criteria are described in Appendix B. In May 1997 SCDHEC granted approval for seven hydrocone sampling.

  16. Need to use probabilistic risk approach in performance assessment of waste disposal facilities

    SciTech Connect

    Bonano, E.J.; Gallegos, D.P.

    1991-01-01

    Regulations governing the disposal of radioactive, hazardous, and/or mixed wastes will likely require, either directly or indirectly, that the performance of disposal facilities be assessed quantitatively. Such analyses, commonly called performance assessments,'' rely on the use of predictive models to arrive at a quantitative estimate of the potential impact of disposal on the environment and the safety and health of the public. It has been recognized that a suite of uncertainties affect the results of a performance assessment. These uncertainties are conventionally categorized as (1) uncertainty in the future state of the disposal system (facility and surrounding medium), (2) uncertainty in models (including conceptual models, mathematical models, and computer codes), and (3) uncertainty in data and parameters. Decisions regarding the suitability of a waste disposal facility must be made in light of these uncertainties. Hence, an approach is needed that would allow the explicit consideration of these uncertainties so that their impact on the estimated consequences of disposal can be evaluated. While most regulations for waste disposal do not prescribe the consideration of uncertainties, it is proposed that, even in such cases, a meaningful decision regarding the suitability of a waste disposal facility cannot be made without considering the impact of the attendant uncertainties. A probabilistic risk assessment (PRA) approach provides the formalism for considering the uncertainties and the technical basis that the decision makers can use in discharging their duties. A PRA methodology developed and demonstrated for the disposal of high-level radioactive waste provides a general framework for assessing the disposal of all types of wastes (radioactive, hazardous, and mixed). 15 refs., 1 fig., 1 tab.

  17. Orientation to pollution prevention for facility design

    SciTech Connect

    Raney, E.A.; Whitehead, J.K.; Encke, D.B.; Dorsey, J.A.

    1994-01-01

    This material was developed to assist engineers in incorporating pollution prevention into the design of new or modified facilities within the U.S. Department of Energy (DOE). The material demonstrates how the design of a facility can affect the generation of waste throughout a facility`s entire life and it offers guidance on how to prevent the generation of waste during design. Contents include: Orientation to pollution prevention for facility design training course booklet; Pollution prevention design guideline; Orientation to pollution prevention for facility design lesson plan; Training participant survey and pretest; and Training facilitator`s guide and schedule.

  18. Performance assessment monitoring of low-level radioactive waste disposal facilities

    SciTech Connect

    Garland, S.B. II; Craig, P.M.; Styers, D.R.

    1988-01-01

    To develop a long-range plan for the disposal of the solid low-level radioactive wastes (LLW) generated by these facilities, the Low-Level Waste Disposal Development and Demonstration Program was initiated. A key component of the program is selecting promising disposal technologies to be demonstrated at a scale sufficient to assess performance adequately. One technology selected for demonstration is the aboveground tumulus. The tumulus facility consists of a concrete pad on which the LLW is placed, a synthetic underpad liner, concrete disposal vaults in which the LLW is contained, and a multilayered cap to be constructed after the pad is filled. This paper describes the methodology being used to assess the performance of the tumulus in terms of environmental impacts and worker exposures. This assessment also will assist in determining monitoring needs during routine operations of future full-scale facilities.

  19. Groundwater Flow and Transport Calculations Supporting the Immobilized Low-Activity Waste Disposal Facility Performance Assessment

    SciTech Connect

    Bergeron, Marcel P.; Wurstner, Signe K.

    2000-12-04

    This report summarizes the Hanford Site-Wide Groundwater Model and its application to the Immobilized Low-Activity Waste (ILAW) Disposal Facility Performance Assessment (PA). The site-wide model and supporting local-scale models are used to evaluate impacts from the transport of contaminants at a hypothetical well 100 m downgradient of the disposal facilities and to evaluate regional flow conditions and transport from the ILAW disposal facilities to the Columbia River. These models were used to well-intercept factors (WIFs) or dilution factors from a given areal flux of a hypothetical contaminant released to the unconfined aquifer from the ILAW disposal facilities for two waste-disposal options: 1) a remote-handled trench concept and 2) a concrete-vault concept. The WIF is defined as the ratio of the concentration at a well location in the aquifer to the concentration of infiltrating water entering the aquifer. These WIFs are being used in conjunction with calculations of released contaminant fluxes through the vadose zone to estimate potential impacts from radiological and hazardous chemical contaminants within the ILAW disposal facility at compliance points.

  20. EFFECT OF CAPILLARITY AND SOIL STRUCTURE ON FLOW IN LOW PERMEABILITY SATURATED SOILS AT DISPOSAL FACILITIES

    EPA Science Inventory

    Permit applications may be received which propose to place hazardous waste land disposal facilities in a saturated zone of low permeability (low-K) soils. This report addresses only movement of the leachate after release from the facility and does not consider those factors relat...

  1. Hazard Classification of the Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect

    Boyd D. Christensen

    2012-05-01

    The Battelle Energy Alliance (BEA) at the Idaho National Laboratory (INL) is constructing a new facility to replace remote-handled low-level radioactive waste disposal capability for INL and Naval Reactors Facility operations. Current disposal capability at the Radioactive Waste Management Complex (RWMC) will continue until the facility is full or closed for remediation (estimated at approximately fiscal year 2015). Development of a new onsite disposal facility is the highest ranked alternative and will provide RH-LLW disposal capability and will ensure continuity of operations that generate RH-LLW for the foreseeable future. As a part of establishing a safety basis for facility operations, the facility will be categorized according to DOE-STD-1027-92. This classification is important in determining the scope of analyses performed in the safety basis and will also dictate operational requirements of the completed facility. This paper discusses the issues affecting hazard classification in this nuclear facility and impacts of the final hazard categorization.

  2. Proceedings of the tenth annual DOE low-level waste management conference: Session 3: Disposal technology and facility development

    SciTech Connect

    Not Available

    1988-12-01

    This document contains ten papers on various aspects of low-level radioactive waste management. Topics include: design and construction of a facility; alternatives to shallow land burial; the fate of tritium and carbon 14 released to the environment; defense waste management; engineered sorbent barriers; remedial action status report; and the disposal of mixed waste in Texas. Individual papers were processed separately for the data base. (TEM)

  3. Corrective action management unit application for the Environmental Restoration Disposal Facility

    SciTech Connect

    Evans, G.C.

    1994-06-01

    The Environmental Restoration Disposal Facility (ERDF) is to accept both CERCLA (EPA-regulated) and RCRA (Ecology-regulated) remediation waste. The ERDF is considered part of the overall remediation strategy on the Hanford Site, and as such, determination of ERDF viability has followed both RCRA and CERCLA decision making processes. Typically, determination of the viability of a unit, such as the ERDF, would occur as part of record of decision (ROD) or permit modification for each remediation site before construction of the ERDF. However, because construction of the ERDF may take a significant amount of time, it is necessary to begin design and construction of the ERDF before final RODs/permit modifications for the remediation sites. This will allow movement of waste to occur quickly once the final remediation strategy for the RCRA and CERCLA past-practice units is determined. Construction of the ERDF is a unique situation relative to Hanford Facility cleanup, requiring a Hanford Facility specific process be developed for implementing the ERDF that would satisfy both RCRA and CERCLA requirements. While the ERDF will play a significant role in the remediation process, initiation of the ERDF does not preclude the evaluation of remedial alternatives at each remediation site. To facilitate this, the January 1994 amendment to the Tri-Party Agreement recognizes the necessity for the ERDF, and the Tri-Party Agreement states: ``Ecology, EPA, and DOE agree to proceed with the steps necessary to design, approve, construct, and operate such a ... facility.`` The Tri-Party Agreement requires the DOE-RL to prepare a comprehensive ``package`` for the EPA and Ecology to consider in evaluating the ERDF. The package is to address the criteria listed in 40 CFR 264.552(c) for corrective action management unit (CAMU) designation and a CERCLA ROD. This CAMU application is submitted as part of the Tri-Party Agreement-required information package.

  4. Engineering test facility design definition

    NASA Astrophysics Data System (ADS)

    Bercaw, R. W.; Seikel, G. R.

    1980-06-01

    The Engineering Test Facility (ETF) is the major focus of the Department of Energy (DOE) Magnetohydrodynamics (MHD) Program to facilitate commercialization and to demonstrate the commercial operability of MHD/steam electric power. The ETF will be a fully integrated commercial prototype MHD power plant with a nominal output of 200 MW sub e. Performance of this plant is expected to meet or surpass existing utility standards for fuel, maintenance, and operating costs; plant availability; load following; safety; and durability. It is expected to meet all applicable environmental regulations. The current design concept conforming to the general definition, the basis for its selection, and the process which will be followed in further defining and updating the conceptual design.

  5. New facility shield design criteria

    SciTech Connect

    Howell, W.P.

    1981-07-01

    The purpose of the criteria presented here is to provide standard guidance for the design of nuclear radiation shields thoughout new facilities. These criteria are required to assure a consistent and integrated design that can be operated safely and economically within the DOE standards. The scope of this report is confined to the consideration of radiation shielding for contained sources. The whole body dose limit established by the DOE applies to all doses which are generally distributed throughout the trunk of the body. Therefore, where the whole body is the critical organ for an internally deposited radionuclide, the whole body dose limit applies to the sum of doses received must assure control of the concentration of radionuclides in the building atmosphere and thereby limit the dose from internal sources.

  6. Engineering test facility design definition

    NASA Technical Reports Server (NTRS)

    Bercaw, R. W.; Seikel, G. R.

    1980-01-01

    The Engineering Test Facility (ETF) is the major focus of the Department of Energy (DOE) Magnetohydrodynamics (MHD) Program to facilitate commercialization and to demonstrate the commercial operability of MHD/steam electric power. The ETF will be a fully integrated commercial prototype MHD power plant with a nominal output of 200 MW sub e. Performance of this plant is expected to meet or surpass existing utility standards for fuel, maintenance, and operating costs; plant availability; load following; safety; and durability. It is expected to meet all applicable environmental regulations. The current design concept conforming to the general definition, the basis for its selection, and the process which will be followed in further defining and updating the conceptual design.

  7. Protocol for the E-Area Low Level Waste Facility Disposal Limits Database

    SciTech Connect

    Swingle, R

    2006-01-31

    A database has been developed to contain the disposal limits for the E-Area Low Level Waste Facility (ELLWF). This database originates in the form of an EXCEL{copyright} workbook. The pertinent sheets are translated to PDF format using Adobe ACROBAT{copyright}. The PDF version of the database is accessible from the Solid Waste Division web page on SHRINE. In addition to containing the various disposal unit limits, the database also contains hyperlinks to the original references for all limits. It is anticipated that database will be revised each time there is an addition, deletion or revision of any of the ELLWF radionuclide disposal limits.

  8. Groundwater impact assessment report for the 1325-N Liquid Waste Disposal Facility

    SciTech Connect

    Alexander, D.J.; Johnson, V.G.

    1993-09-01

    In 1943 the Hanford Site was chosen as a location for the Manhattan Project to produce plutonium for use in nuclear weapons. The 100-N Area at Hanford was used from 1963 to 1987 for a dual-purpose, plutonium production and steam generation reactor and related operational support facilities (Diediker and Hall 1987). In November 1989, the reactor was put into dry layup status. During operations, chemical and radioactive wastes were released into the area soil, air, and groundwater. The 1325-N LWDF was constructed in 1983 to replace the 1301-N Liquid Waste Disposal Facility (1301-N LWDF). The two facilities operated simultaneously from 1983 to 1985. The 1301-N LWDF was retired from use in 1985 and the 1325-N LWDF continued operation until April 1991, when active discharges to the facility ceased. Effluent discharge to the piping system has been controlled by administrative means. This report discusses ground water contamination resulting from the 1325-N Liquid Waste Disposal facility.

  9. National Ignition Facility system design requirements conventional facilities SDR001

    SciTech Connect

    Hands, J.

    1996-04-09

    This System Design Requirements (SDR) document specifies the functions to be performed and the minimum design requirements for the National Ignition Facility (NIF) site infrastructure and conventional facilities. These consist of the physical site and buildings necessary to house the laser, target chamber, target preparation areas, optics support and ancillary functions.

  10. {sup 137}Cs sorption into bentonite from Cidadap-Tasikmalaya as buffer material for disposal demonstration plant facility at Serpong

    SciTech Connect

    Setiawan, B. Sriwahyuni, H. Ekaningrum, NE. Sumantry, T.

    2014-03-24

    According to co-location principle, near surface disposal type the disposal demonstration plant facility will be build at Serpong nuclear area. The facility also for anticipation of future needs to provide national facility for the servicing of radwaste management of non-nuclear power plant activity in Serpong Nuclear Area. It is needs to study the material of buffer and backfill for the safety of demonstration plant facility. A local bentonite rock from Cidadap-Tasikmalaya was used as the buffer materials. Objective of experiment is to find out the specific data of sorption characteristic of Cidadap bentonite as buffer material in a radwaste disposal system. Experiments were performed in batch method, where bentonite samples were contacted with CsCl solution labeled with Cs-137 in 100 ml/g liquid:solid ratio. Initial Cs concentration was 10{sup −8} M and to study the effects of ionic strength and Cs concentration in solution, 0.1 and 1.0 M NaCl also CsCl concentration ranging 10{sup −8} - 10{sup −4} M were added in solution. As the indicator of Cs saturated in bentonite samples, Kd value was applied. Affected parameters in the experiment were contact time, effects of ionic strength and concentration of CsCl. Results showed that sorption of Cs by bentonite reached constantly after 16 days contacted, and Kd value was 10.600 ml/g. Effect of CsCl concentration on Kd value may decreased in increased in CsCl concentration. Effect of ionic strength increased according to increased in concentration of background and would effect to Kd value due to competition of Na ions and Cs in solution interacts with bentonite. By obtaining the bentonite character data as buffer material, the results could be used as the basis for making of design and the basic of performance assessment the near surface disposal facility in terms of isolation capacity of radwaste later.

  11. 137Cs sorption into bentonite from Cidadap-Tasikmalaya as buffer material for disposal demonstration plant facility at Serpong

    NASA Astrophysics Data System (ADS)

    Setiawan, B.; Sriwahyuni, H.; Ekaningrum, NE.; Sumantry, T.

    2014-03-01

    According to co-location principle, near surface disposal type the disposal demonstration plant facility will be build at Serpong nuclear area. The facility also for anticipation of future needs to provide national facility for the servicing of radwaste management of non-nuclear power plant activity in Serpong Nuclear Area. It is needs to study the material of buffer and backfill for the safety of demonstration plant facility. A local bentonite rock from Cidadap-Tasikmalaya was used as the buffer materials. Objective of experiment is to find out the specific data of sorption characteristic of Cidadap bentonite as buffer material in a radwaste disposal system. Experiments were performed in batch method, where bentonite samples were contacted with CsCl solution labeled with Cs-137 in 100 ml/g liquid:solid ratio. Initial Cs concentration was 10-8 M and to study the effects of ionic strength and Cs concentration in solution, 0.1 and 1.0 M NaCl also CsCl concentration ranging 10-8 - 10-4 M were added in solution. As the indicator of Cs saturated in bentonite samples, Kd value was applied. Affected parameters in the experiment were contact time, effects of ionic strength and concentration of CsCl. Results showed that sorption of Cs by bentonite reached constantly after 16 days contacted, and Kd value was 10.600 ml/g. Effect of CsCl concentration on Kd value may decreased in increased in CsCl concentration. Effect of ionic strength increased according to increased in concentration of background and would effect to Kd value due to competition of Na ions and Cs in solution interacts with bentonite. By obtaining the bentonite character data as buffer material, the results could be used as the basis for making of design and the basic of performance assessment the near surface disposal facility in terms of isolation capacity of radwaste later.

  12. Radiological performance assessment for the E-Area Vaults Disposal Facility

    SciTech Connect

    Cook, J.R.

    2000-04-11

    This report is the first revision to ``Radiological Performance Assessment for the E-Area Vaults Disposal Facility, Revision 0'', which was issued in April 1994 and received conditional DOE approval in September 1994. The title of this report has been changed to conform to the current name of the facility. The revision incorporates improved groundwater modeling methodology, which includes a large data base of site specific geotechnical data, and special Analyses on disposal of cement-based wasteforms and naval wastes, issued after publication of Revision 0.

  13. Laboratory Animal Facilities. Laboratory Design Notes.

    ERIC Educational Resources Information Center

    Jonas, Albert M.

    1965-01-01

    Design of laboratory animal facilities must be functional. Accordingly, the designer should be aware of the complex nature of animal research and specifically the type of animal research which will be conducted in a new facility. The building of animal-care facilities in research institutions requires special knowledge in laboratory animal…

  14. Elements of uncertainty in a radiological performance assessment of a Saltstone Disposal Facility for low level waste

    SciTech Connect

    McDowell-Boyer, L.M.; Little, C.A.

    1991-01-01

    Oak Ridge National Laboratory is currently conducting a radiological performance assessment for the Saltstone Disposal Facility at the Savannah River Site near Aiken, South Carolina. Saltstone is a solidified, low-level waste form which contains very low levels of radionuclides but considerable levels of nitrate. The preliminary results of the performance assessment indicate that the final outcome will be very sensitive to the degradation scenario for the cover and containment system for this facility. The uncertainty in the results beyond several hundred years, arising from the choice of elements in this scenario, is extremely large due to the limited knowledge of the behavior of the clay and cementitious materials beyond this time frame. Design of low-level waste facilities should address this uncertainty, and policy makers and regulators should decide both what the tolerable level of uncertainty is and the length of time over which a facility's performance should be predictively evaluated. 6 refs., 4 figs.

  15. Waste disposal technology transfer matching requirement clusters for waste disposal facilities in China

    SciTech Connect

    Dorn, Thomas; Nelles, Michael; Flamme, Sabine; Jinming, Cai

    2012-11-15

    Highlights: Black-Right-Pointing-Pointer We outline the differences of Chinese MSW characteristics from Western MSW. Black-Right-Pointing-Pointer We model the requirements of four clusters of plant owner/operators in China. Black-Right-Pointing-Pointer We examine the best technology fit for these requirements via a matrix. Black-Right-Pointing-Pointer Variance in waste input affects result more than training and costs. Black-Right-Pointing-Pointer For China technology adaptation and localisation could become push, not pull factors. - Abstract: Even though technology transfer has been part of development aid programmes for many decades, it has more often than not failed to come to fruition. One reason is the absence of simple guidelines or decision making tools that help operators or plant owners to decide on the most suitable technology to adopt. Practical suggestions for choosing the most suitable technology to combat a specific problem are hard to get and technology drawbacks are not sufficiently highlighted. Western counterparts in technology transfer or development projects often underestimate or don't sufficiently account for the high investment costs for the imported incineration plant; the differing nature of Chinese MSW; the need for trained manpower; and the need to treat flue gas, bunker leakage water, and ash, all of which contain highly toxic elements. This article sets out requirements for municipal solid waste disposal plant owner/operators in China as well as giving an attribute assessment for the prevalent waste disposal plant types in order to assist individual decision makers in their evaluation process for what plant type might be most suitable in a given situation. There is no 'best' plant for all needs and purposes, and requirement constellations rely on generalisations meaning they cannot be blindly applied, but an alignment of a type of plant to a type of owner or operator can realistically be achieved. To this end, a four-step approach is

  16. Waste disposal technology transfer matching requirement clusters for waste disposal facilities in China.

    PubMed

    Dorn, Thomas; Nelles, Michael; Flamme, Sabine; Jinming, Cai

    2012-11-01

    Even though technology transfer has been part of development aid programmes for many decades, it has more often than not failed to come to fruition. One reason is the absence of simple guidelines or decision making tools that help operators or plant owners to decide on the most suitable technology to adopt. Practical suggestions for choosing the most suitable technology to combat a specific problem are hard to get and technology drawbacks are not sufficiently highlighted. Western counterparts in technology transfer or development projects often underestimate or don't sufficiently account for the high investment costs for the imported incineration plant; the differing nature of Chinese MSW; the need for trained manpower; and the need to treat flue gas, bunker leakage water, and ash, all of which contain highly toxic elements. This article sets out requirements for municipal solid waste disposal plant owner/operators in China as well as giving an attribute assessment for the prevalent waste disposal plant types in order to assist individual decision makers in their evaluation process for what plant type might be most suitable in a given situation. There is no 'best' plant for all needs and purposes, and requirement constellations rely on generalisations meaning they cannot be blindly applied, but an alignment of a type of plant to a type of owner or operator can realistically be achieved. To this end, a four-step approach is suggested and a technology matrix is set out to ease the choice of technology to transfer and avoid past errors. The four steps are (1) Identification of plant owner/operator requirement clusters; (2) Determination of different municipal solid waste (MSW) treatment plant attributes; (3) Development of a matrix matching requirement clusters to plant attributes; (4) Application of Quality Function Deployment Method to aid in technology localisation. The technology transfer matrices thus derived show significant performance differences between the

  17. Scoping analysis of toxic metal performance in DOE low-level waste disposal facilities

    SciTech Connect

    Waters, R.D; Bougai, D.A.; Pohl, P.I.

    1996-03-01

    This study provides a scoping safety assessment for disposal of toxic metals contained in Department of Energy (DOE) mixed low-level waste (MLLW) at six DOE sites that currently have low-level waste (LLW) disposal facilities--Savannah River Site, Oak Ridge Reservation, Los Alamos National Laboratory, Hanford Reservation, Nevada Test Site, and Idaho National Engineering Laboratory. The study has focused on the groundwater contaminant pathway, which is considered to be the dominant human exposure pathway from shallow land MLLW disposal. A simple and conservative transport analysis has been performed using site hydrological data to calculate site-specific ``permissible`` concentrations of toxic metals in grout-immobilized waste. These concentrations are calculated such that, when toxic metals are leached from the disposal facility by infiltrating water and attenuated in local ground-water system the toxic metal concentrations in groundwater below the disposal facility do not exceed the Maximum Contaminant Levels as stated in the National Primary Drinking Water Regulation. The analysis shows that and sites allow about I00 times higher toxic metal concentrations in stabilized waste leachate than humid sites. From the limited available data on toxic metal concentrations in DOE MLLW, a margin of protection appears to exist in most cases when stabilized wastes containing toxic metals are disposed of at the DOE sites under analysis. Possible exceptions to this conclusion are arsenic, chromium selenium, and mercury when disposed of at some humid sites such as the Oak Ridge Reservation. This analysis also demonstrates that the US Environmental Protection Agency`s prescriptive regulatory approach that defines rigid waste treatment standards does not inherently account for the variety of disposal environments encountered nationwide and may result in either underprotection of groundwater resources (at humid sites) or an excessive margin of protection (at and sites).

  18. Ageing management program for the Spanish low and intermediate level waste disposal and spent fuel and high-level waste centralised storage facilities

    NASA Astrophysics Data System (ADS)

    Zuloaga, P.; Ordoñez, M.; Andrade, C.; Castellote, M.

    2011-04-01

    The generic design of the centralised spent fuel storage facility was approved by the Spanish Safety Authority in 2006. The planned operational life is 60 years, while the design service life is 100 years. Durability studies and surveillance of the behaviour have been considered from the initial design steps, taking into account the accessibility limitations and temperatures involved. The paper presents an overview of the ageing management program set in support of the Performance Assessment and Safety Review of El Cabril low and intermediate level waste (LILW) disposal facility. Based on the experience gained for LILW, ENRESA has developed a preliminary definition of the Ageing Management Plan for the Centralised Interim Storage Facility of spent Fuel and High Level Waste (HLW), which addresses the behaviour of spent fuel, its retrievability, the confinement system and the reinforced concrete structure. It includes tests plans and surveillance design considerations, based on the El Cabril LILW disposal facility.

  19. Water resources: Legislation needed to extend the life of confined disposal facilities

    SciTech Connect

    Not Available

    1986-01-01

    The U.S. Army Corps of Engineers periodically dredges various harbors in the Great Lakes and elsewhere in the United States. It normally disposes of dredgings by dumping them in open water. Public Law 91-611 authorized the Corps to construct confined disposal facilities for holding contaminated dredgings for a period not to exceed ten years. Concern was raised about whether a disposal facility constructed at Kenosha, Wisconsin, which was less than one-third full but which the Corps was planning to use after the 10-year period, should be closed. GAO believes that P.L. 91-611 does not authorize the Corps to keep such facilities as the one at Kenosha or other locations open beyond the ten years. To continue to use such facilities the Corps should seek, in GAO's opinion, legislation to extend the life of those facilities when local communities are in agreement to an extension. When communities do not agree the Corps should find alternatives for disposing of the contaminated dredgings.

  20. Readiness assessment plan for the Radioactive Mixed Waste Land Disposal Facility (Trench 31)

    SciTech Connect

    Irons, L.G.

    1994-11-22

    This document provides the Readiness Assessment Plan (RAP) for the Project W-025 (Radioactive Mixed Waste Land Disposal Facility) Readiness Assessment (RA). The RAP documents prerequisites to be met by the operating organization prior to the RA. The RAP is to be implemented by the RA Team identified in the RAP. The RA Team is to verify the facility`s compliance with criteria identified in the RAP. The criteria are based upon the {open_quotes}Core Requirements{close_quotes} listed in DOE Order 5480.31, {open_quotes}Startup and Restart of Nuclear Facilities{close_quotes}.

  1. Geochemical Data Package for the 2005 Hanford Integrated Disposal Facility Performance Assessment

    SciTech Connect

    Krupka, Kenneth M.; Serne, R JEFFREY.; Kaplan, D I.

    2004-09-30

    CH2M HILL Hanford Group, Inc. (CH2M HILL) is designing and assessing the performance of an integrated disposal facility (IDF) to receive low-level waste (LLW), mixed low-level waste (MLLW), immobilized low-activity waste (ILAW), and failed or decommissioned melters. The CH2M HILL project to assess the performance of this disposal facility is the Hanford IDF Performance Assessment (PA) activity. The goal of the Hanford IDF PA activity is to provide a reasonable expectation that the disposal of the waste is protective of the general public, groundwater resources, air resources, surface-water resources, and inadvertent intruders. Achieving this goal will require prediction of contaminant migration from the facilities. This migration is expected to occur primarily via the movement of water through the facilities, and the consequent transport of dissolved contaminants in the vadose zone to groundwater where contaminants may be re-introduced to receptors via drinking water wells or mixing in the Columbia River. Pacific Northwest National Laboratory (PNNL) assists CH2M HILL in their performance assessment activities. One of the PNNL tasks is to provide estimates of the geochemical properties of the materials comprising the IDF, the disturbed region around the facility, and the physically undisturbed sediments below the facility (including the vadose zone sediments and the aquifer sediments in the upper unconfined aquifer). The geochemical properties are expressed as parameters that quantify the adsorption of contaminants and the solubility constraints that might apply for those contaminants that may exceed solubility constraints. The common parameters used to quantify adsorption and solubility are the distribution coefficient (Kd) and the thermodynamic solubility product (Ksp), respectively. In this data package, we approximate the solubility of contaminants using a more simplified construct, called the solution concentration limit, a constant value. The Kd values and

  2. Cold vacuum drying facility design requirements

    SciTech Connect

    Irwin, J.J.

    1997-09-24

    This release of the Design Requirements Document is a complete restructuring and rewrite to the document previously prepared and released for project W-441 to record the design basis for the design of the Cold Vacuum Drying Facility.

  3. NOMINATION FOR THE PROJECT MANAGEMENT INSTITUTE (PMI) PROJECT OF THE YEAR AWARD INTEGRATED DISPOSAL FACILITY (IDF)

    SciTech Connect

    MCLELLAN, G.W.

    2007-02-07

    CH2M HILL Hanford Group, Inc. (CH2M HILL) is pleased to nominate the Integrated Disposal Facility (IDF) project for the Project Management Institute's consideration as 2007 Project of the Year, Built for the U.S, Department of Energy's (DOE) Office of River Protection (ORP) at the Hanford Site, the IDF is the site's first Resource Conservation and Recovery Act (RCRA)-compliant disposal facility. The IDF is important to DOE's waste management strategy for the site. Effective management of the IDF project contributed to the project's success. The project was carefully managed to meet three Tri-Party Agreement (TPA) milestones. The completed facility fully satisfied the needs and expectations of the client, regulators and stakeholders. Ultimately, the project, initially estimated to require 48 months and $33.9 million to build, was completed four months ahead of schedule and $11.1 million under budget. DOE directed construction of the IDF to provide additional capacity for disposing of low-level radioactive and mixed (i.e., radioactive and hazardous) solid waste. The facility needed to comply with federal and Washington State environmental laws and meet TPA milestones. The facility had to accommodate over one million cubic yards of the waste material, including immobilized low-activity waste packages from the Waste Treatment Plant (WTP), low-level and mixed low-level waste from WTP failed melters, and alternative immobilized low-activity waste forms, such as bulk-vitrified waste. CH2M HILL designed and constructed a disposal facility with a redundant system of containment barriers and a sophisticated leak-detection system. Built on a 168-area, the facility's construction met all regulatory requirements. The facility's containment system actually exceeds the state's environmental requirements for a hazardous waste landfill. Effective management of the IDF construction project required working through highly political and legal issues as well as challenges with

  4. Aboveground roofed design for the disposal of low-level radioactive waste in Maine

    SciTech Connect

    Alexander, J.A.

    1993-03-01

    The conceptual designs proposed in this report resulted from a study for the Maine Low-level Radioactive Waste Authority to develop conceptual designs for a safe and reliable disposal facility for Maine`s low-level radioactive waste (LLW). Freezing temperatures, heavy rainfall, high groundwater tables, and very complex and shallow glaciated soils found in Maine place severe constraints on the design. The fundamental idea behind the study was to consider Maine`s climatic and geological conditions at the beginning of conceptual design rather than starting with a design for another location and adapting it for Maine`s conditions. The conceptual designs recommended are entirely above ground and consist of an inner vault designed to provide shielding and protection against inadvertent intrusion and an outer building to protect the inner vault from water. The air dry conditions within the outer building should lead to almost indefinite service life for the concrete inner vault and the waste containers. This concept differs sharply from the usual aboveground vault in its reliance on at least two independent, but more or less conventional, roofing systems for primary and secondary protection against leakage of radioisotopes from the facility. Features include disposal of waste in air dry environment, waste loading and visual inspection by remote-controlled overhead cranes, and reliance on engineered soils for tertiary protection against release of radioactive materials.

  5. 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.

  6. Review of the Tritium Extraction Facility Design

    SciTech Connect

    Ronald W. Barton; Farid Bamdad; Joel Blackman

    2000-06-04

    The Defense Nuclear Facilities Safety Board (DNFSB) is an independent executive branch agency responsible for technical safety oversight of the U.S. Department of Energy's (DOE's) defense nuclear facilities. One of DNFSB's responsibilities is the review of design and construction projects for DOE's defense nuclear facilities to ensure that adequate health and safety requirements are identified and implemented. These reviews are performed with the expectation that facility designs are being developed within the framework of a site's Integrated Safety Management (ISM) program. This paper describes the application of ISM principles in DNFSB's ongoing review of the Tritium Extraction Facility (TEF) design/construction project.

  7. 26 CFR 17.1 - Industrial development bonds used to provide solid waste disposal facilities; temporary rules.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... materials or heat are recovered, the waste disposal function includes the processing of such materials or... used in solid waste disposal. The heat can be used by A to produce steam. Company B operates an... solid waste disposal facilities; temporary rules. 17.1 Section 17.1 Internal Revenue INTERNAL...

  8. 26 CFR 17.1 - Industrial development bonds used to provide solid waste disposal facilities; temporary rules.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... materials or heat are recovered, the waste disposal function includes the processing of such materials or... used in solid waste disposal. The heat can be used by A to produce steam. Company B operates an... solid waste disposal facilities; temporary rules. 17.1 Section 17.1 Internal Revenue INTERNAL...

  9. National Environmental Policy Act Compliance Strategy for the Remote-Handled Low-level Waste Disposal Facility

    SciTech Connect

    Peggy Hinman

    2010-10-01

    The U.S. Department of Energy (DOE) needs to have disposal capability for remote-handled low level waste (LLW) generated at the Idaho National Laboratory (INL) at the time the existing disposal facility is full or must be closed in preparation for final remediation of the INL Subsurface Disposal Area in approximately the year 2017.

  10. Information on commercial disposal facilities that may have received offshore drilling wastes.

    SciTech Connect

    Gasper, J. R.; Veil, J. A.; Ayers, R. C., Jr.

    2000-08-25

    The U.S. Environmental Protection Agency (EPA) is developing regulations that would establish requirements for discharging synthetic-based drill cuttings from offshore wells into the ocean. Justification for allowing discharges of these cuttings is that the environmental impacts from discharging drilling wastes into the ocean may be less harmful than the impacts from hauling them to shore for disposal. In the past, some onshore commercial facilities that disposed of these cuttings were improperly managed and operated and left behind environmental problems. This report provides background information on commercial waste disposal facilities in Texas, Louisiana, California, and Alaska that received or may have received offshore drilling wastes in the past and are now undergoing cleanup.

  11. MANAGING AND DISPOSING OF RESIDUES FROM ENVIRONMENTAL CONTROL FACILITIES IN THE STEEL INDUSTRY

    EPA Science Inventory

    The report gives results of a study of the management and disposal of residues from environmental control facilities in the steel industry. Information from 13 integrated U.S. steel mills is compared with that found in the literature and with data collected during visits to Engli...

  12. 300 Area Treated Effluent Disposal Facility computer software release cover sheet and revision record

    SciTech Connect

    McCarthy, R.J.

    1994-11-28

    This supporting document contains the computer software release cover sheet and revision records for the 300 Area Treated Effluent Disposal Facility (TEDF). The previous revision was controlled by CH2M Hill which developed the software. A 7-page listing of the contents of directory C:{backslash}TEDF is contained in this report.

  13. 77 FR 48107 - Workshop on Performance Assessments of Near-Surface Disposal Facilities: FEPs Analysis, Scenario...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-13

    ... Radioactive Waste.'' These regulations were published in the Federal Register on December 27, 1982 (47 FR..., Environmental Protection and Performance Assessment Directorate, Division of Waste Management and Environmental...-Surface Disposal Facilities: FEPs Analysis, Scenario and Conceptual Model Development, and Code...

  14. Z-Area Saltstone Disposal Facility groundwater monitoring report. First and second quarters 1996

    SciTech Connect

    1996-07-01

    This report contains groundwater monitoring results from the Z-Area Saltstone Disposal Facility at the Savannah River Site. Appendix A contains the South Carolina Department of Health and Environmental Control proposed groundwater monitoring standards and final primary drinking water standards. Appendix B contains the Savannah River Site Environmental Protection Department/Environmental Monitoring Section flagging criteria for groundwater constituents.

  15. Z-Area Saltstone Disposal Facility groundwater monitoring report. 1996 annual report

    SciTech Connect

    1996-12-01

    The Z-Area Saltstone Disposal Facility is located in the Separations Area, north of H and S Areas, at the Savannah River Site (SRS). The facility permanently disposes of low-level radioactive waste. The facility blends low-level radioactive salt solution with cement, slag, and flyash to form a nonhazardous cementitious waste that is pumped to aboveground disposal vaults. Z Area began these operations in June 1990. Samples from the ZBG wells at the Z-Area Saltstone Disposal Facility are analyzed for constituents required by South Carolina Department of Health and Environmental Control (SCDHEC) Industrial Solid Waste Permit {number_sign}025500-1603 (formerly IWP-217). During second quarter 1996, lead was reported above the SCDHEC-proposed groundwater monitoring standard in one well. No other constituents were reported above SCDHEC-proposed groundwater monitoring standards for final Primary Drinking Water Standards during first, second, or third quarters 1996. Antimony was detected above SRS flagging criteria during third quarter 1996. In the past, tritium has been detected sporadically in the ZBG wells at levels similar to those detected before Z Area began radioactive operations.

  16. Cold vacuum drying facility design requirements

    SciTech Connect

    IRWIN, J.J.

    1999-07-01

    This document provides the detailed design requirements for the Spent Nuclear Fuel Project Cold Vacuum Drying Facility. Process, safety, and quality assurance requirements and interfaces are specified.

  17. 32 CFR 644.486 - Disposal of buildings and improvements constructed under emergency plant facilities (EPF) or...

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 32 National Defense 4 2011-07-01 2011-07-01 false Disposal of buildings and improvements constructed under emergency plant facilities (EPF) or similar contracts. 644.486 Section 644.486 National... Disposal of buildings and improvements constructed under emergency plant facilities (EPF) or...

  18. Planning and Designing Safe Facilities

    ERIC Educational Resources Information Center

    Seidler, Todd

    2006-01-01

    Those who manage physical education, athletic, and recreation programs have a number of legal duties that they are expected to carry out. Among these are an obligation to take reasonable precautions to ensure safe programs and facilities for all participants, spectators, and staff. Physical education and sports facilities that are poorly planned,…

  19. 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.

  20. Materials and degradation modes in an alternative LLW (low-level waste) disposal facility

    SciTech Connect

    Cowgill, M.G.; MacKenzie, D.R.

    1989-01-01

    The materials used in the construction of alternative low-level waste disposal facilities will be subject to interaction with both the internal and the external environments associated with the facilities and unless precautions are taken, may degrade, leading to structural failure. This paper reviews the characteristics of both environments with respect to three alternative disposal concepts, then assesses how reaction with them might affect the properties of the materials, which include concrete, steel-reinforced concrete, structural steel, and various protective coatings and membranes. It identifies and evaluates the probability of reactions occurring which might lead to degradation of the materials and so compromise the structure. The probability of failure (interpreted relative to the ability of the structure to restrict ingress and egress of water) is assessed for each material and precautionary measures, intended to maximize the durability of the facility, are reviewed. 19 refs., 2 tabs.

  1. 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.

  2. ANNUAL SUMMARY OF THE INTEGRATED DISPOSAL FACILITY PERFORMANCE ASSESSMENT FOR 2004

    SciTech Connect

    MANN, F M

    2005-02-09

    As required by the US. Department of Energy (DOE) order on radioactive waste management (DOE 1999a) and as implemented by the ''Maintenance Plan for the Hanford Immobilized Low-Activity Tank Waste Performance Assessment'' (Mann 2004), an annual summary of the adequacy of the Hanford Immobilized Low-Activity Tank Waste Performance Assessment (ILAW PA) is necessary in each year in which a performance assessment is not issued. A draft version of the 2001 ILAW PA was sent to the DOE Headquarters (DOE/HQ) in April 2001 for review and approval. The DOE approved (DOE 2001) the draft version of the 2001 ILAW PA and issued a new version of the Hanford Site waste disposal authorization statement (DAS). Based on comments raised during the review, the draft version was revised and the 2001 ILAW PA was formally issued (Mann et al. 2001). The DOE (DOE 2003a) has reviewed the final 2001 ILAW PA and concluded that no changes to the DAS were necessary. Also as required by the DOE order, annual summaries have been generated and approved. The previous annual summary (Mann 2003b) noted the change of mission from ILAW disposal to the disposal of a range of solid waste types, including ILAW. DOE approved the annual summary (DOE 2003c), noting the expanded mission. Considering the results of data collection and analysis, the conclusions of the 2001 ILAW PA remain valid as they pertain to ILAW disposal. The new data also suggest that impacts from the disposal of the other solid waste will be lower than initially estimated in the ''Integrated Disposal Facility Risk Assessment'' (Mann 2003a). A performance assessment for the Integrated Disposal Facility (IDF) will be issued in the summer of 2005.

  3. Application of total uncertainty theory in radioactive waste disposal facilities safety assessment

    SciTech Connect

    Lemos, Francisco Luiz de; Ross, Timothy; Sullivan, Terry

    2007-07-01

    Safety assessment requires the interaction of a large number of disciplines to model the environmental phenomena necessary to evaluate the safety of the disposal system. In this complex process, the identification and quantification of both types of uncertainties, random and epistemic, plays a very important role for confidence building. In this work an application of the concept of total uncertainty to radioactive waste disposal facilities safety assessment is proposed. By combining both types of uncertainty, aleatory and epistemic, in the same framework, this approach ultimately aims to assess the confidence one can pose in the safety-assessment decisions. (authors)

  4. EXPERIENCES FROM THE SOURCE-TERM ANALYSIS OF A LOW AND INTERMEDIATE LEVEL RADWASTE DISPOSAL FACILITY

    SciTech Connect

    Park,Jin Beak; Park, Joo-Wan; Lee, Eun-Young; Kim, Chang-Lak

    2003-02-27

    Enhancement of a computer code SAGE for evaluation of the Korean concept for a LILW waste disposal facility is discussed. Several features of source term analysis are embedded into SAGE to analyze: (1) effects of degradation mode of an engineered barrier, (2) effects of dispersion phenomena in the unsaturated zone and (3) effects of time dependent sorption coefficient in the unsaturated zone. IAEA's Vault Safety Case (VSC) approach is used to demonstrate the ability of this assessment code. Results of MASCOT are used for comparison purposes. These enhancements of the safety assessment code, SAGE, can contribute to realistic evaluation of the Korean concept of the LILW disposal project in the near future.

  5. 40 CFR 62.14352 - Designated facilities.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 40 Protection of Environment 9 2014-07-01 2014-07-01 false Designated facilities. 62.14352 Section 62.14352 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) APPROVAL AND PROMULGATION OF STATE PLANS FOR DESIGNATED FACILITIES AND POLLUTANTS Federal Plan Requirements for Municipal Solid Waste...

  6. Z-Area Saltstone Disposal Facility groundwater monitoring report. Second quarter 1995

    SciTech Connect

    1995-09-01

    The three monitoring wells at the Z-Area Saltstone Disposal Facility, ZBG 1, 1A, and 2, are sampled quarterly as part of the Savannah River Site Groundwater Monitoring Program and to comply with conditions of the facility`s Industrial Waste Permit IWP-217, issued by the South Carolina Department of Health and Environmental Control (SCDHEC). During second quarter 1995, samples from wells ZBG 1 and 2 were analyzed for selected inorganic constituents, volatile organic compounds, selected radionuclides, and other constituents. Well ZBG 1A was dry and could not be sampled. Dichloromethane, a common laboratory contaminant, was detected above final Primary Drinking Water Standards (PDWS) in well ZBG 1 and was detected in this well`s associated method blank during second quarter 1995. No other constituents exceeded final PDWS, SCDHEC proposed groundwater monitoring standards, or Savannah River Site flagging criteria in the ZBG wells during second quarter 1995. In previous quarters, wells ZBG 1 and 2 contained slightly elevated levels of tritium, similar to the tritium levels detected before Z Area began radioactive operations. The Z-Area Saltstone Disposal Facility blends low-level salt solutions with cement, slag, and flyash to form a nonhazardous cementitious waste that is pumped to aboveground disposal vaults.

  7. PORFLOW MODELING FOR A PRELIMINARY ASSESSMENT OF THE PERFORMANCE OF NEW SALTSTONE DISPOSAL UNIT DESIGNS

    SciTech Connect

    Smith, F.

    2012-08-06

    At the request of Savannah River Remediation (SRR), SRNL has analyzed the expected performance obtained from using seven 32 million gallon Saltstone Disposal Units (SDUs) in the Z-Area Saltstone Disposal Facility (SDF) to store future saltstone grout. The analysis was based on preliminary SDU final design specifications. The analysis used PORFLOW modeling to calculate the release of 20 radionuclides from an SDU and transport of the radionuclides and daughters through the vadose zone. Results from this vadose zone analysis were combined with previously calculated releases from existing saltstone vaults and FDCs and a second PORFLOW model run to calculate aquifer transport to assessment points located along a boundary 100 m from the nearest edge of the SDF sources. Peak concentrations within 12 sectors spaced along the 100 m boundary were determined over a period of evaluation extending 20,000 years after SDF closure cap placement. These peak concentrations were provided to SRR to use as input for dose calculations.

  8. Overview on backfill materials and permeable reactive barriers for nuclear waste disposal facilities.

    SciTech Connect

    Moore, Robert Charles; Hasan, Ahmed Ali Mohamed; Holt, Kathleen Caroline; Hasan, Mahmoud A. (Egyptian Atomic Energy Authority, Cairo, Egypt)

    2003-10-01

    A great deal of money and effort has been spent on environmental restoration during the past several decades. Significant progress has been made on improving air quality, cleaning up and preventing leaching from dumps and landfills, and improving surface water quality. However, significant challenges still exist in all of these areas. Among the more difficult and expensive environmental problems, and often the primary factor limiting closure of contaminated sites following surface restoration, is contamination of ground water. The most common technology used for remediating ground water is surface treatment where the water is pumped to the surface, treated and pumped back into the ground or released at a nearby river or lake. Although still useful for certain remediation scenarios, the limitations of pump-and-treat technologies have recently been recognized, along with the need for innovative solutions to ground-water contamination. Even with the current challenges we face there is a strong need to create geological repository systems for dispose of radioactive wastes containing long-lived radionuclides. The potential contamination of groundwater is a major factor in selection of a radioactive waste disposal site, design of the facility, future scenarios such as human intrusion into the repository and possible need for retrieving the radioactive material, and the use of backfills designed to keep the radionuclides immobile. One of the most promising technologies for remediation of contaminated sites and design of radioactive waste repositories is the use of permeable reactive barriers (PRBs). PRBs are constructed of reactive material(s) to intercept and remove the radionuclides from the water and decontaminate the plumes in situ. The concept of PRBs is relatively simple. The reactive material(s) is placed in the subsurface between the waste or contaminated area and the groundwater. Reactive materials used thus far in practice and research include zero valent iron

  9. 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.

  10. PROCESS DESIGN MANUAL FOR SLUDGE TREATMENT AND DISPOSAL

    EPA Science Inventory

    The purpose of this manual is to provide the engineering community and related industry with a new source of information to be used in the planning, design, and operation of present and future wastewater pollution control facilities. This manual supplements this existing knowledg...

  11. National Ignition Facility Title II Design Plan

    SciTech Connect

    Kumpan, S

    1997-03-01

    This National Ignition Facility (NIF) Title II Design Plan defines the work to be performed by the NIF Project Team between November 1996, when the U.S. Department of Energy (DOE) reviewed Title I design and authorized the initiation of Title H design and specific long-lead procurements, and September 1998, when Title 11 design will be completed.

  12. ENGINEERED NEAR SURFACE DISPOSAL FACILITY OF THE INDUSTRIAL COMPLEX FOR SOLID RADWASTE MANAGEMENT AT CHERNOBYL NUCLEAR POWER PLANT

    SciTech Connect

    Ziehm, Ronny; Pichurin, Sergey Grigorevich

    2003-02-27

    As a part of the turnkey project ''Industrial Complex for Solid Radwaste Management (ICSRM) at the Chernobyl Nuclear Power Plant (ChNPP)'' an Engineered Near Surface Disposal Facility (ENSDF, LOT 3) will be built on the VEKTOR site within the 30 km Exclusion Zone of the ChNPP. This will be performed by RWE NUKEM GmbH, Germany, and it governs the design, licensing support, fabrication, assembly, testing, inspection, delivery, erection, installation and commissioning of the ENSDF. The ENSDF will receive low to intermediate level, short lived, processed/conditioned wastes from the ICSRM Solid Waste Processing Facility (SWPF, LOT 2), the ChNPP Liquid Radwaste Treatment Plant (LRTP) and the ChNPP Interim Storage Facility for RBMK Fuel Assemblies (ISF). The ENSDF has a capacity of 55,000 m{sup 3}. The primary functions of the ENSDF are: to receive, monitor and record waste packages, to load the waste packages into concrete disposal units, to enable capping and closure of the disposal unit s, to allow monitoring following closure. The ENSDF comprises the turnkey installation of a near surface repository in the form of an engineered facility for the final disposal of LILW-SL conditioned in the ICSRM SWPF and other sources of Chernobyl waste. The project has to deal with the challenges of the Chernobyl environment, the fulfillment of both Western and Ukrainian standards, and the installation and coordination of an international project team. It will be shown that proven technologies and processes can be assembled into a unique Management Concept dealing with all the necessary demands and requirements of a turnkey project. The paper emphasizes the proposed concepts for the ENSDF and their integration into existing infrastructure and installations of the VEKTOR site. Further, the paper will consider the integration of Western and Ukrainian Organizations into a cohesive project team and the requirement to guarantee the fulfillment of both Western standards and Ukrainian

  13. 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

  14. Radiological performance assessment for the Z-Area Saltstone Disposal Facility

    SciTech Connect

    Cook, J.R.; Fowler, J.R.

    1992-12-18

    This radiological performance assessment (RPA) for the Savannah River Site (SRS) Saltstone Disposal Facility (SDF) was prepared in accordance with the requirements of Chapter III of the US Department of Energy Order 5820.2A. The Order specifies that an RPA should provide reasonable assurance that a low-level waste (LLW) disposal facility will comply with the performance objectives of the Order. The performance objectives require that: (1) exposures of the general public to radioactivity in the waste or released from the waste will not result in an effective dose equivalent of 25 mrem per year; (2) releases to the atmosphere will meet the requirements of 40 CFR 61; (3) inadvertent intruders will not be committed to an excess of an effective dose equivalent of 100 mrem per year from chronic exposure, or 500 mrem from a single acute exposure; and (4) groundwater resources will be protected in accordance with Federal, State and local requirements.

  15. Risk assessment associated to possible concrete degradation of a near surface disposal facility

    NASA Astrophysics Data System (ADS)

    Capra, B.; Billard, Y.; Wacquier, W.; Gens, R.

    2013-07-01

    This article outlines a risk analysis of possible concrete degradation performed in the framework of the preparation of the Safety Report of ONDRAF/NIRAS, the Belgian Agency for Radioactive Waste and Enriched Fissile Materials, for the construction and operation of a near surface disposal facility of category A waste - short-lived low and intermediate level waste - in Dessel. The main degradation mechanism considered is the carbonation of different concrete components over different periods (from the building phase up to 2000 years), which induces corrosion of the rebars. A dedicated methodology mixing risk analysis and numerical modeling of concrete carbonation has been developed to assess the critical risks of the disposal facility at different periods. According to the results obtained, risk mapping was used to assess the impact of carbonation of concrete on the different components at the different stages. The most important risk is related to an extreme situation with complete removal of the earth cover and side embankment.

  16. 10 CFR 60.132 - Additional design criteria for surface facilities in the geologic repository operations area.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Additional design criteria for surface facilities in the...) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN GEOLOGIC REPOSITORIES Technical Criteria Design Criteria for the Geologic Repository Operations Area § 60.132 Additional design criteria for surface facilities...

  17. 200 Area Treated Effluent Disposal Facility (TEDF) Effluent Sampling and Analysis Plan

    SciTech Connect

    BROWN, M.J.

    2000-05-18

    This Sampling and Analysis Plan (SAP) has been developed to comply with effluent monitoring requirements at the 200 Area Treated Effluent Disposal Facility (TEDF), as stated in Washington State Waste Discharge Permit No. ST 4502 (Ecology 2000). This permit, issued by the Washington State Department of Ecology (Ecology) under the authority of Chapter 90.48 Revised Code of Washington (RCW) and Washington Administrative Code (WAC) Chapter 173-216, is an April 2000 renewal of the original permit issued on April 1995.

  18. European concepts for shared storage and disposal facilities for radioactive wastes?

    SciTech Connect

    Verhoef, Ewoud; Codee, Hans; Stefula, Vladan; McCombie, Charles

    2007-07-01

    Geological disposal is an essential component of the long-term management of spent fuel and high-level radioactive waste. Implementation of a suitable deep repository may, however, be difficult or impossible in some (especially small) countries because of challenging geological conditions or restricted siting options, or because of the high costs involved. For these countries, shared regional or international storage and disposal facilities are a necessity. The European Parliament and the EC have both expressed support for concepts that could lead to regional shared facilities being implemented in the EU. The EC, therefore, funded two projects that form the first two steps of a staged process towards the implementation of shared regional or international storage and disposal facilities. In the period 2003 to 2005, the EC funded SAPIERR I, a project devoted to pilot studies on the feasibility of shared regional storage facilities and geological repositories, for use by European countries. The studies showed that shared regional repositories are feasible, but also that, if they are to be implemented, even some decades ahead, efforts must already be increased now. The first step would be to establish a structured framework for the work on regional repositories. This is the goal of SAPIERR II (2006-2008): to develop possible practical implementation strategies and organisational structures. These will enable a formalised, structured European Development Organisation (EDO) to be established in 2008 or afterwards for working on shared EU radioactive waste storage and disposal activities. The EDO can work in parallel with national waste programmes. Participating EU Member States will be able to use the structures developed as, when and if needed for the furtherance of their individual national policies. (authors)

  19. Z-Area Saltstone Disposal Facility Groundwater Monitoring Report. 1997 Annual Report

    SciTech Connect

    Roach, J.L. Jr.

    1997-12-01

    Samples from the ZBG wells at the Z-Area Saltstone Disposal Facility are analyzed for constituents required by South Carolina Department of Health and Environmental Control (SCDHEC) Industrial Solid Waste Permit {number_sign}025500-1603 (formerly IWP-217). No constituents were reported above SCDHEC-proposed groundwater monitoring standards or final Primary Drinking Water Standards during first or third quareters 1997. No constituents were detected above SRS flagging criteria during first or third quarters 1997.

  20. Model training curriculum for Low-Level Radioactive Waste Disposal Facility Operations

    SciTech Connect

    Tyner, C.J.; Birk, S.M.

    1995-09-01

    This document is to assist in the development of the training programs required to be in place for the operating license for a low-level radioactive waste disposal facility. It consists of an introductory document and four additional appendixes of individual training program curricula. This information will provide the starting point for the more detailed facility-specific training programs that will be developed as the facility hires and trains new personnel and begins operation. This document is comprehensive and is intended as a guide for the development of a company- or facility-specific program. The individual licensee does not need to use this model training curriculum as written. Instead, this document can be used as a menu for the development, modification, or verification of customized training programs.

  1. Investigation of {sup 14}C release in an engineered low-level waste disposal facility

    SciTech Connect

    Yim, M.S.; Simonson, S.A.; Sullivan, T.M.

    1996-05-01

    Atmospheric releases of {sup 14}C from a generic engineered low-level waste (LLW) disposal facility and its radiological impacts are investigated. A computer model that describes microbial gas generation and the transport has been developed and used to analyze the generation of {sup 14}C contaminated gases and subsequent migration in a facility. Models are based on a chemical kinetic description of aerobic and anaerobic decomposition of organic materials coupled with attending models of oxygen transport and consumption within waste containers in a facility. Effects of radiolysis on gas generation are addressed based on the estimated dose rate for class B and C wastes. Estimates predict that annual atmospheric release of {sup 14}C due to atmospheric pressure variations could range between {approximately}2.6 {times} 10{sup 8} and 5.5 {times} 10{sup 11} Bq as a result of microbial gas generation based on a volume of 48 000 m{sup 3} LLW disposed in a facility. The associated dose to a maximally exposed individual is estimated to be dominated by ingestion pathway and strongly depends on the fraction of the food imported from an uncontaminated outside area. Dose rates are expected to be <0.04 mSv/yr, considering a reasonable distance between the facility and the exposed population. The depletion through airborne releases of {sup 14}C inventory that is available for transport through other pathways is not expected to be a significant issue.

  2. Performance Assessment for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect

    Annette L. Schafer; A. Jeffrey Sondrup; Arthur S. Rood

    2012-05-01

    This performance assessment for the Remote-Handled Low-Level Radioactive Waste Disposal Facility at the Idaho National Laboratory documents the projected radiological dose impacts associated with the disposal of low-level radioactive waste at the facility. This assessment evaluates compliance with the applicable radiological criteria of the U.S. Department of Energy and the U.S. Environmental Protection Agency for protection of the public and the environment. The calculations involve modeling transport of radionuclides from buried waste to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses are calculated for both offsite receptors and individuals who inadvertently intrude into the waste after site closure. The results of the calculations are used to evaluate the future performance of the low-level radioactive waste disposal facility and to provide input for establishment of waste acceptance criteria. In addition, one-factor-at-a-time, Monte Carlo, and rank correlation analyses are included for sensitivity and uncertainty analysis. The comparison of the performance assessment results to the applicable performance objectives provides reasonable expectation that the performance objectives will be met

  3. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect

    Boyd D. Chirstensen

    2015-03-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1C, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  4. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect

    Boyd D. Chirstensen

    2012-08-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  5. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect

    Boyd D. Chirstensen

    2012-04-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  6. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect

    Gary Mecham

    2009-10-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  7. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect

    Gary Mecham

    2010-10-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  8. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect

    Gary Mecham

    2010-05-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  9. STAO Science Laboratory Facilities Design Guide.

    ERIC Educational Resources Information Center

    Mackellar, Ian, Ed.

    This design guide offers guidance to science educators, architects, and others concerned with the provision of science accommodations in Ontario, Canada, either through new construction or the adaptation of existing buildings. The publication is not a blueprint for facilities nor an attempt to standardize all science programs and facilities; it is…

  10. Design considerations of the national transonic facility

    NASA Technical Reports Server (NTRS)

    Baals, D. D.

    1976-01-01

    The inability of existing wind tunnels to provide aerodynamic test data at transonic speeds and flight Reynolds numbers was examined. The proposed transonic facility is a high Reynolds number transonic wind tunnel designed to meet the research and development needs of industry, and the scientific community. The facility employs the cryogenic approach to achieve high transonic Reynolds numbers at acceptable model loads and tunnel power. By using temperature as a test variable, a unique capability to separate scale effects from model aeroelastic effects is provided. The performance envelope of the facility is shown to provide a ten fold increase in transonic Reynolds number capability compared to currently available facilities.

  11. 78 FR 38672 - Ocean Dumping; Sabine-Neches Waterway (SNWW) Ocean Dredged Material Disposal Site Designation

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-27

    ...The EPA is proposing to designate four new Ocean Dredged Material Disposal Site(s) (ODMDS) located offshore of Texas for the disposal of dredged material from the Sabine-Neches Waterway (SNWW), pursuant to the Marine Protection, Research and Sanctuaries Act, as amended (MPRSA). The new sites are needed for the disposal of additional dredged material associated with the SNWW Channel Improvement......

  12. HEU to LEU conversion and blending facility: UNH blending alternative to produce LEU oxide for disposal

    SciTech Connect

    1995-09-01

    The United States Department of Energy (DOE) is examining options for the disposition of surplus weapons-usable fissile materials and storage of all weapons-usable fissile materials. Disposition is a process of use or disposal of material that results in the material being converted to a form that is substantially and inherently more proliferation-resistant than is the original form. Examining options for increasing the proliferation resistance of highly enriched uranium (HEU) is part of this effort. This report provides data to be used in the environmental impact analysis for the uranyl nitrate hexahydrate blending option to produce oxide for disposal. This the Conversion and Blending Facility (CBF) alternative will have two missions (1) convert HEU materials into HEU uranyl nitrate (UNH) and (2) blend the HEU uranyl nitrate with depleted and natural assay uranyl nitrate to produce an oxide that can be stored until an acceptable disposal approach is available. The primary emphasis of this blending operation will be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. The blended LEU will be produced as a waste suitable for storage or disposal.

  13. Iterative performance assessment for the greater confinement disposal facilities: Preliminary results of round two

    SciTech Connect

    Olague, N.E.; Conrad, S.H.; Baer, T.A.

    1993-12-31

    The Department of Energy`s Nevada Operations Office has disposed of a small quantity of transuranic waste at the Greater Confinement Disposal (GCD) facility in Area 5 of the Nevada Test Site. The Environmental Protection Agency standards for disposal of transuranic waste (40 CFR 191) require that a performance assessment be conducted and an iterative approach has been adopted. This approach consists of using performance assessment results to guide the collection of site characterization data, and in turn, new site characterization data is incorporated into each successive iteration of the performance assessment. The results of the first iteration indicated that the GCD site should be able to comply with 40 CFR 191. This paper presents results of the second iteration based on results from site-specific environmental tracer studies. These studies indicate significantly lower recharge values then those used in the first performance assessment iteration. For performance assessment these results imply that the downward ground-water advection pathway may be negligible, and therefore, the upward liquid diffusion pathway becomes more significant. The models and the model parameters that were used to simulate this upward pathway have been refined. The preliminary results from these models still indicate that the GCD facility should be able to comply with the Containment Requirements in 40 CFR 191.

  14. 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.

  15. Z-Area Saltstone Disposal Facility groundwater monitoring report. First quarter 1995

    SciTech Connect

    1995-06-01

    The three monitoring wells at the Z-Area Saltstone Disposal Facility, ZBG 1, 1A, and 2, are sampled quarterly as part of the Savannah River Site Groundwater Monitoring Program and to comply with conditions of the facility`s Industrial Waste Permit IWP-217, issued by the South Carolina Department of Health and Environmental Control (SCDHEC). During first quarter 1995, samples from wells ZBG 1 and 2 were analyzed for selected inorganic constituents, volatile organic compounds, selected radionuclides, and other constituents. Well ZBG 1A was dry and could not be sampled. None of the wells contained constituents above SCDHEC proposed groundwater monitoring standards, final Primary Drinking Water Standards, or flagging criteria. In previous quarters, wells ZBG 1 and 2 contained slightly elevated levels of tritium, similar to the tritium levels detected before Z Area began radioactive operations.

  16. Steam plant ash disposal facility and industrial landfill at the Y-12 Plant, Anderson County, Tennessee

    SciTech Connect

    Not Available

    1992-02-01

    The US Department of Energy (DOE) is proposing to install a wet ash handling system to dewater bottom ash from the coal-fired steam plant at its Y-12 Plant and to construct a new landfill for disposal of industrial wastes, including the dewatered bottom ash. The DOE operates three major facilities on its Oak Ridge Reservation (ORR). Operation of these facilities results in the production of a variety of nonhazardous, nonradioactive solid wastes (approximately 300 m{sup 3} per day, compacted) including sanitary wastes, common industrial wastes and construction debris. At the current rate of use, this existing landfill will be filled within approximately 18 months, and more space is urgently needed. In an effort to alleviate this problem, DOE and WMD management propose to create additional landfill facilities at a nearby site. The potential environmental impacts associated with this proposed action are the subject of this environmental assessment (EA).

  17. Evaluation of Low-Level Waste Disposal Receipt Data for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2011

    SciTech Connect

    French, Sean B.; Shuman, Robert

    2012-04-17

    The Los Alamos National Laboratory (LANL or the Laboratory) generates radioactive waste as a result of various activities. Operational or institutional waste is generated from a wide variety of research and development activities including nuclear weapons development, energy production, and medical research. Environmental restoration (ER), and decontamination and decommissioning (D and D) waste is generated as contaminated sites and facilities at LANL undergo cleanup or remediation. The majority of this waste is low-level radioactive waste (LLW) and is disposed of at the Technical Area 54 (TA-54), Area G disposal facility. U.S. Department of Energy (DOE) Order 435.1 (DOE, 2001) requires that radioactive waste be managed in a manner that protects public health and safety, and the environment. To comply with this order, DOE field sites must prepare and maintain site-specific radiological performance assessments for LLW disposal facilities that accept waste after September 26, 1988. Furthermore, sites are required to conduct composite analyses that account for the cumulative impacts of all waste that has been (or will be) disposed of at the facilities and other sources of radioactive material that may interact with the facilities. Revision 4 of the Area G performance assessment and composite analysis was issued in 2008 (LANL, 2008). These analyses estimate rates of radionuclide release from the waste disposed of at the facility, simulate the movement of radionuclides through the environment, and project potential radiation doses to humans for several on-site and off-site exposure scenarios. The assessments are based on existing site and disposal facility data and on assumptions about future rates and methods of waste disposal. The accuracy of the performance assessment and composite analysis depends upon the validity of the data used and assumptions made in conducting the analyses. If changes in these data and assumptions are significant, they may invalidate or call

  18. Handling and Emplacement Options for Deep Borehole Disposal Conceptual Design.

    SciTech Connect

    Cochran, John R.; Hardin, Ernest

    2015-07-01

    This report presents conceptual design information for a system to handle and emplace packages containing radioactive waste, in boreholes 16,400 ft deep or possibly deeper. Its intended use is for a design selection study that compares the costs and risks associated with two emplacement methods: drill-string and wireline emplacement. The deep borehole disposal (DBD) concept calls for siting a borehole (or array of boreholes) that penetrate crystalline basement rock to a depth below surface of about 16,400 ft (5 km). Waste packages would be emplaced in the lower 6,560 ft (2 km) of the borehole, with sealing of appropriate portions of the upper 9,840 ft (3 km). A deep borehole field test (DBFT) is planned to test and refine the DBD concept. The DBFT is a scientific and engineering experiment, conducted at full-scale, in-situ, without radioactive waste. Waste handling operations are conceptualized to begin with the onsite receipt of a purpose-built Type B shipping cask, that contains a waste package. Emplacement operations begin when the cask is upended over the borehole, locked to a receiving flange or collar. The scope of emplacement includes activities to lower waste packages to total depth, and to retrieve them back to the surface when necessary for any reason. This report describes three concepts for the handling and emplacement of the waste packages: 1) a concept proposed by Woodward-Clyde Consultants in 1983; 2) an updated version of the 1983 concept developed for the DBFT; and 3) a new concept in which individual waste packages would be lowered to depth using a wireline. The systems described here could be adapted to different waste forms, but for design of waste packaging, handling, and emplacement systems the reference waste forms are DOE-owned high- level waste including Cs/Sr capsules and bulk granular HLW from fuel processing. Handling and Emplacement Options for Deep Borehole Disposal Conceptual Design July 23, 2015 iv ACKNOWLEDGEMENTS This report has

  19. LEACHATE MIGRATION FROM A SOLID WASTE DISPOSAL FACILITY NEAR BISCAYNE NATIONAL PARK, SOUTH FLORIDA.

    USGS Publications Warehouse

    Waller, Bradley G.; Labowski, James L.

    1987-01-01

    Leachate from the Dade County Solid Waste Disposal Facility (SWDF) is migrating to the east (seaward) and to the south from the currently active disposal cell. Water levels and ground-water flow directions are strongly influenced by water-management practices. The SWDF is constructed over the salt-intruded part of the highly transmissive Biscayne aquifer and because of this, chloride ion concentrations and specific conductance levels could not be used as indicators of leachate concentrations. Leachate was detected in multi-depth wells located 75 meters to the south and 20 meters to the east of the active cell. Concentrations of water-quality indicators had mean concentrations generally 2 to 10 times higher than baseline conditions. Primary controls over leachate movement in the SWDF are water-management practices in the Black Creek and Gould Canals, configuration and integrity of the liner beneath the active cell, and low hydraulic gradients in the landfill area.

  20. 26 CFR 1.142(a)(6)-1 - Exempt facility bonds: solid waste disposal facilities.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... radioactive material subject to regulation under the Nuclear Regulatory Act (10 CFR 1.1 et seq.), as in effect... that is applied to solid waste to create and capture synthesis gas, heat, hot water, steam, or other... 26 Internal Revenue 2 2014-04-01 2014-04-01 false Exempt facility bonds: solid waste...

  1. 26 CFR 1.142(a)(6)-1 - Exempt facility bonds: solid waste disposal facilities.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... radioactive material subject to regulation under the Nuclear Regulatory Act (10 CFR 1.1 et seq.), as in effect... that is applied to solid waste to create and capture synthesis gas, heat, hot water, steam, or other... 26 Internal Revenue 2 2012-04-01 2012-04-01 false Exempt facility bonds: solid waste...

  2. 26 CFR 1.142(a)(6)-1 - Exempt facility bonds: solid waste disposal facilities.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... radioactive material subject to regulation under the Nuclear Regulatory Act (10 CFR 1.1 et seq.), as in effect... that is applied to solid waste to create and capture synthesis gas, heat, hot water, steam, or other... 26 Internal Revenue 2 2013-04-01 2013-04-01 false Exempt facility bonds: solid waste...

  3. Planning and Design of Outdoor Sports Facilities.

    ERIC Educational Resources Information Center

    Department of the Army, Washington, DC.

    Information required for the planning and design of outdoor sports facilities is provided in the format of an outline text and design criteria placed opposite an accompanying page of definitive drawings. Scope of the manual covers those outdoor sports and games most commonly played for competition and/or recreation by military and civilian…

  4. How to Tackle Tough Facility Design Considerations

    ERIC Educational Resources Information Center

    Kalina, David

    2007-01-01

    This article is part of a series that has offered insight on planning a facilities project, hiring professionals, delivery system options and owner's responsibilities. In this article, the author focuses on some of the planning and design concepts one may be asked to consider in providing direction to his design and construction team. These…

  5. Interior Design Factors in Library Facilities.

    ERIC Educational Resources Information Center

    Jackson, Patricia Ann

    When planning the interior of a library facility, the planning team of librarian, library consultant, architect, and interior design consultant must focus attention on the basic principles of interior design and the psychological needs of the user. Colors for an interior should be selected with careful regard to space, light, and emotional and…

  6. Designing a test facility LEBT for RISP

    NASA Astrophysics Data System (ADS)

    Bodenstein, R. M.; Bahng, J. B.

    2015-10-01

    Raon, the rare isotope accelerator of the Rare Isotope Science Project (RISP) in Daejeon, South Korea, is being designed to accelerate multiple-charge-state beams simultaneously. Using an Electron Cyclotron Resonance (ECR) Ion Source to produce the ions, Raon will transport the beam through two 90-degree bending magnets and a Low Energy Beam Transport (LEBT) system to a Radio Frequency Quadrupole (RFQ). A test facility is under development to test the components of the injector and LEBT system. A new LEBT, based upon the LEBT of the main driver linac, is being designed to fit within the test facility's restrictive space requirements. This work will briefly review the main driver linac LEBT design, and then discuss the current status of the test facility LEBT design.

  7. High efficiency waste to energy facility -- Pilot plant design

    SciTech Connect

    Orita, Norihiko; Kawahara, Yuuzou; Takahashi, Kazuyoshi; Yamauchi, Toru; Hosoda, Takuo

    1998-07-01

    Waste To Energy facilities are commonly acceptable to the environment and give benefits in two main areas: one is a hygienic waste disposal and another is waste heat energy recovery to save fossil fuel consumption. Recovered energy is used for electricity supply, and it is required to increase the efficiency of refuse to electric energy conversion, and to spread the plant construction throughout the country of Japan, by the government. The national project started in 1992, and pilot plant design details were established in 1995. The objective of the project is to get 30% of energy conversion efficiency through the measure by raising the steam temperature and pressure to 500 C and 9.8 MPa respectively. The pilot plant is operating under the design conditions, which verify the success of applied technologies. This paper describes key technologies which were used to design the refuse burning boiler, which generates the highest steam temperature and pressure steam.

  8. SUPPLEMENTAL RISK ANALYSIS FOR POTENTIAL AIR EMISSIONS FROM THE PROPOSED CONFINED DISPOSAL FACILITY FOR THE INDIANA HARBOR AND SHIPPING CANAL SEDIMENT DREDGING AND DISPOSAL PROJECT

    EPA Science Inventory

    In 1995, EPA completed a risk assessment for potential air emissions from the operation of a proposed confined disposal facility (CDF) to be constructed and operated by the U.S. Army Corps of Engineers for dredged sediments from the Indiana Harbor and Shipping Canal in East Chica...

  9. 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.

  10. The contractor`s role in low-level waste disposal facility application review and licensing

    SciTech Connect

    Serie, P.J.; Dressen, A.L.

    1991-12-31

    The California Department of Health Services will soon reach a licensing decision on the proposed Ward Valley low-level radioactive waste disposal facility. As the first regulatory agency in the country to address the 10 CFR Part 61 requirements for a new disposal facility, California`s program has broken new ground in its approach. Throughout the review process, the Department has relied on contractor support to augment its technical and administrative staff. A team consisting of Roy F. Weston, Inc., supported by ERM-Program Management Corp., Environmental Issues Management, Inc., and Rogers and Associates Engineering Corporation, has worked closely with the Department in a staff extension role. The authors have been involved with the project in contractor project management roles since 1987, and continue to support the Department`s program as it proceeds to finalize its licensing process. This paper describes the selection process used to identify a contractor team with the needed skills and experience, and the makeup of team capabilities. It outlines the management, communication, and technical approaches used to assure a smooth agency-contractor function and relationship. It describes the techniques used to ensure that decisions and documents represented the Department credibly in its role as the regulatory and licensing agency under the Nuclear Regulatory Commission (NRC) Agreement State program. The paper outlines the license application review process and activities, through preparation of licensing documentation and responses to public comments. Lessons learned in coordination of an agency-contractor team effort to review and license a low-level waste disposal facility are reviewed and suggestions made for approaching a similar license application review and licensing situation.