Sample records for meet waste acceptance

  1. Hanford Site Solid Waste Acceptance Criteria

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1993-11-17

    This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities.

  2. TRU waste absorbent addition project at the Idaho National Engineering and Environmental Laboratory.

    PubMed

    Colson, R Griff; Auman, Laurence E

    2003-08-01

    ABSTRACT In order to meet a commitment to ship 3,100 m3 of transuranic waste to the Waste Isolation Pilot Plant (WIPP), the Idaho National Engineering and Environmental Laboratory (INEEL) developed a process to add absorbent to TRU waste drums that did not meet WIPP waste acceptance criteria. The development, implementation, and safe completion of this project contributed to the INEEL's success in meeting the commitment three months early.

  3. USEPA SITE PROGRAM APPROACH TO TECHNOLOGY TRANSFER AND REGULATORY ACCEPTANCE

    EPA Science Inventory

    The SITE Program was created to meet the increased demand for innovative technologies for hazardous waste treatment. To accomplish this mission, the program seeks to advance the development, implementation and commercialization of innovative technologies for hazardous waste chara...

  4. OE-WIPP Event Presentation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Erickson, Randall Mark

    Information is given on waste generation at TA-55 and remediation needed to meet WIPP acceptance criteria, including the role of nitrate salts. Breaching of a particular waste-filled drum is reviewed, along with an accident analysis and steps for corrective actions and improved process management.

  5. Management of radioactive waste in Belgium: ONDRAF/NIRAS and Belgoprocess as major actors of the waste acceptance system

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Zaelen, Gunter van; Verheyen, Annick

    2007-07-01

    The management of radioactive waste in Belgium is undertaken by the national agency for radioactive waste and enriched fissile materials, ONDRAF/NIRAS, and its industrial partner Belgoprocess. ONDRAF/NIRAS has set up a management system designed to guarantee that the general public and the environment are protected against the potential hazards arising from radioactive waste. Belgoprocess is a private company, founded in 1984 and located in Dessel, Belgium. It is a subsidiary of ONDRAF/NIRAS and its activities focus on the safe processing and storage of radioactive waste. The management system of ONDRAF/NIRAS includes two aspects: a) an integrated system and b) anmore » acceptance system. The integrated system covers all aspects of management ranging from the origin of waste to its transport, processing, interim storage and long-term management. The safety of radioactive waste management not only depends on the quality of the design and construction of the processing, temporary storage or disposal infrastructure, but also on the quality of the waste accepted by ONDRAF/NIRAS. In order to be manage d safely, both in the short and the long term, the waste transferred to ONDRAF/NIRAS must meet certain specific requirements. To that end, ONDRAF/NIRAS has developed an acceptance system. (authors)« less

  6. Guidelines for generators to meet HWHF acceptance requirements for hazardous, radioactive, and mixed wastes at Berkeley Lab. Revision 3

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Albert, R.

    1996-06-01

    This document provides performance standards that one, as a generator of hazardous chemical, radioactive, or mixed wastes at the Berkeley Lab, must meet to manage their waste to protect Berkeley Lab staff and the environment, comply with waste regulations and ensure the continued safe operation of the workplace, have the waste transferred to the correct Waste Handling Facility, and enable the Environment, Health and Safety (EH and S) Division to properly pick up, manage, and ultimately send the waste off site for recycling, treatment, or disposal. If one uses and generates any of these wastes, one must establish a Satellitemore » Accumulation Area and follow the guidelines in the appropriate section of this document. Topics include minimization of wastes, characterization of the wastes, containers, segregation, labeling, empty containers, and spill cleanup and reporting.« less

  7. Enhanced LAW Glass Correlation - Phase 1

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Muller, Isabelle S.; Matlack, Keith S.; Pegg, Ian L.

    About 50 million gallons of high-level mixed waste is currently stored in underground tanks at the United States Department of Energy’s (DOE’s) Hanford site in the State of Washington. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) will provide DOE’s Office of River Protection (ORP) with a means of treating this waste by vitrification for subsequent disposal. The tank waste will be separated into low- and high-activity waste fractions, which will then be vitrified respectively into Immobilized Low Activity Waste (ILAW) and Immobilized High Level Waste (IHLW) products. The ILAW product will be disposed in an engineered facility onmore » the Hanford site while the IHLW product is designed for acceptance into a national deep geological disposal facility for high-level nuclear waste. The ILAW and IHLW products must meet a variety of requirements with respect to protection of the environment before they can be accepted for disposal. Acceptable glass formulations for vitrification of Hanford low activity waste (LAW) must meet a variety of product quality, processability, and waste loading requirements. To this end, The Vitreous State Laboratory (VSL) at The Catholic University of America (CUA) developed and tested a number of glass formulations during Part A, Part B1 and Part B2 of the WTP development program. The testing resulted in the selection of target glass compositions for the processing of eight of the Phase I LAW tanks. The selected glass compositions were tested at the crucible scale to confirm their compliance with ILAW performance requirements. Duramelter 100 (DM100) and LAW Pilot Melter tests were then conducted to demonstrate the viability of these glass compositions for LAW vitrification at high processing rates.« less

  8. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Matlack, K. S.; Abramowitz, H.; Miller, I. S.

    About 50 million gallons of high-level mixed waste is currently stored in underground tanks at the United States Department of Energy’s (DOE’s) Hanford site in the State of Washington. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) will provide DOE’s Office of River Protection (ORP) with a means of treating this waste by vitrification for subsequent disposal. The tank waste will be separated into low- and high-activity waste fractions, which will then be vitrified respectively into Immobilized Low Activity Waste (ILAW) and Immobilized High Level Waste (IHLW) products. The ILAW product will be disposed in an engineered facility onmore » the Hanford site while the IHLW product is designed for acceptance into a national deep geological disposal facility for high-level nuclear waste. The ILAW and IHLW products must meet a variety of requirements with respect to protection of the environment before they can be accepted for disposal.« less

  9. Waste certification program plan for Oak Ridge National Laboratory. Revision 2

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1997-09-01

    This document defines the waste certification program (WCP) developed for implementation at Oak Ridge National Laboratory (ORNL). The document describes the program structure, logic, and methodology for certification of ORNL wastes. The purpose of the WCP is to provide assurance that wastes are properly characterized and that the Waste Acceptance Criteria (WAC) for receiving facilities are met. The program meets the waste certification requirements for mixed (both radioactive and hazardous) and hazardous [including polychlorinated biphenyls (PCB)] waste. Program activities will be conducted according to ORNL Level 1 document requirements.

  10. Low-level radioactive waste management: transitioning to off-site disposal at Los Alamos National Laboratory

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Dorries, Alison M

    2010-11-09

    Facing the closure of nearly all on-site management and disposal capability for low-level radioactive waste (LLW), Los Alamos National Laboratory (LANL) is making ready to ship the majority of LLW off-site. In order to ship off-site, waste must meet the Treatment, Storage, and Disposal Facility's (TSDF) Waste Acceptance Criteria (WAC). In preparation, LANL's waste management organization must ensure LANL waste generators characterize and package waste compliantly and waste characterization documentation is complete and accurate. Key challenges that must be addressed to successfully make the shift to off-site disposal of LLW include improving the detail, accuracy, and quality of process knowledgemore » (PK) and acceptable knowledge (AK) documentation, training waste generators and waste management staff on the higher standard of data quality and expectations, improved WAC compliance for off-site facilities, and enhanced quality assurance throughout the process. Certification of LANL generators will allow direct off-site shipping of LLW from their facilities.« less

  11. Data Package for Secondary Waste Form Down-Selection—Cast Stone

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Serne, R. Jeffrey; Westsik, Joseph H.

    2011-09-05

    Available literature on Cast Stone and Saltstone was reviewed with an emphasis on determining how Cast Stone and related grout waste forms performed in relationship to various criteria that will be used to decide whether a specific type of waste form meets acceptance criteria for disposal in the Integrated Disposal Facility (IDF) at Hanford. After the critical review of the Cast Stone/Saltstone literature, we conclude that Cast Stone is a good candidate waste form for further consideration. Cast stone meets the target IDF acceptance criteria for compressive strength, no free liquids, TCLP leachate are below the UTS permissible concentrations andmore » leach rates for Na and Tc-99 are suiteably low. The cost of starting ingredients and equipment necessary to generate Cast Stone waste forms with secondary waste streams are low and the Cast Stone dry blend formulation can be tailored to accommodate variations in liquid waste stream compositions. The database for Cast Stone short-term performance is quite extensive compared to the other three candidate waste solidification processes. The solidification of liquid wastes in Cast Stone is a mature process in comparison to the other three candidates. Successful production of Cast Stone or Saltstone has been demonstrated from lab-scale monoliths with volumes of cm3 through m3 sized blocks to 210-liter sized drums all the way to the large pours into vaults at Savannah River. To date over 9 million gallons of low activity liquid waste has been solidified and disposed in concrete vaults at Savannah River.« less

  12. Special Analysis for the Disposal of the Materials and Energy Corporation Sealed Sources at the Area 5 Radioactive Waste Management Site

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Shott, Gregory

    This special analysis (SA) evaluates whether the Materials and Energy Corporation (M&EC) Sealed Source waste stream (PERM000000036, Revision 0) is suitable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). Disposal of the M&EC Sealed Source waste meets all U.S. Department of Energy (DOE) Manual DOE M 435.1-1, “Radioactive Waste Management Manual,” Chapter IV, Section P performance objectives (DOE 1999). The M&EC Sealed Source waste stream is recommended for acceptance without conditions.

  13. Waste certification program plan for Oak Ridge National Laboratory. Revision 1

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Orrin, R.C.

    1997-05-01

    This document defines the waste certification program developed for implementation at Oak Ridge National Laboratory (ORNL). The document describes the program structure, logic, and methodology for certification of ORNL wastes. The purpose of the waste certification program is to provide assurance that wastes are properly characterized and that the Waste Acceptance Criteria (WAC) for receiving facilities are met. The program meets the waste certification requirements outlined in US Department of Energy (DOE) Order 5820.2A, Radioactive Waste Management, and ensures that 40 CFR documentation requirements for waste characterization are met for mixed (both radioactive and hazardous) and hazardous (including polychlorinated biphenyls)more » waste. Program activities will be conducted according to ORNL Level 1 document requirements.« less

  14. IAEA activities in the area of partitioning and transmutation

    NASA Astrophysics Data System (ADS)

    Stanculescu, Alexander

    2006-06-01

    Four major challenges are facing the long-term development of nuclear energy: improvement of the economic competitiveness, meeting increasingly stringent safety requirements, adhering to the criteria of sustainable development, and public acceptance. Meeting the sustainability criteria is the driving force behind the topic of this paper. In this context, sustainability has two aspects: natural resources and waste management. IAEA's activities in the area of Partitioning and Transmutation (P&T) are mostly in response to the latter. While not involving the large quantities of gaseous products and toxic solid wastes associated with fossil fuels, radioactive waste disposal is today's dominant public acceptance issue. In fact, small waste quantities permit a rigorous confinement strategy, and mined geological disposal is the strategy followed by some countries. Nevertheless, political opposition arguing that this does not yet constitute a safe disposal technology has largely stalled these efforts. One of the primary reasons cited is the long life of many of the radioisotopes generated from fission. This concern has led to increased R&D efforts to develop a technology aimed at reducing the amount and radio-toxicity of long-lived radioactive waste through transmutation in fission reactors or sub-critical systems. In the frame of the Project on Technology Advances in Fast Reactors and Accelerator-Driven Systems (ADS), the IAEA initiated a number of activities on utilization of plutonium and transmutation of long-lived radioactive waste, ADS, and deuterium-tritium plasma-driven sub-critical systems. The paper presents past accomplishments, current status and planned activities of this IAEA project.

  15. Adequacy of a Small Quantity Site RH-TRU Waste Program in Meeting Proposed WIPP Characterization Objectives

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Biedscheid, J.; Stahl, S.; Devarakonda, M.

    2002-02-26

    The first remote-handled transuranic (RH-TRU) waste is expected to be permanently disposed of at the Waste Isolation Pilot Plant (WIPP) during Fiscal Year (FY) 2003. The first RH-TRU waste shipments are scheduled from the Battelle Columbus Laboratories (BCL) to WIPP in order to facilitate compliance with BCL Decommissioning Project (BCLDP) milestones. Milestones requiring RH-TRU waste containerization and removal from the site by 2004 in order to meet a 2006 site closure goal, established by Congress in the Defense Facilities Closure Projects account, necessitated the establishment and implementation of a site-specific program to direct the packaging of BCLDP RH-TRU waste priormore » to the finalization of WIPP RH-TRU waste characterization requirements. The program was designed to collect waste data, including audio and videotape records of waste packaging, such that upon completion of waste packaging, comprehensive data records exist from which compliance with final WIPP RH-TRU waste characterization requirements can be demonstrated. With the BCLDP data records generated to date and the development by the U.S. Department of Energy (DOE)-Carlsbad Field Office (CBFO) of preliminary documents proposing the WIPP RH-TRU waste characterization program, it is possible to evaluate the adequacy of the BCLDP program with respect to meeting proposed characterization objectives. The BCLDP characterization program uses primarily acceptable knowledge (AK) and visual examination (VE) during waste packaging to characterize RH-TRU waste. These methods are used to estimate physical waste parameters, including weight percentages of metals, cellulosics, plastics, and rubber in the waste, and to determine the absence of prohibited items, including free liquids. AK combined with computer modeling is used to estimate radiological waste parameters, including total activity on a waste container basis, for the majority of BCLDP RH-TRU waste. AK combined with direct analysis is used to characterize radiological parameters for the small populations of the RH-TRU waste generated by the BCLDP. All characterization based on AK is verified. Per its design for comprehensive waste data collection, the BCLDP characterization program using AK and waste packaging procedures, including VE during packaging, meets the proposed WIPP RH-TRU waste characterization objectives. The conservative program design implemented generates certification data that will be adequate to meet any additional program requirements that may be imposed by the CBFO.« less

  16. Biopurification of industrial waste gas from rubber regeneration.

    PubMed

    Sun, Peishi; Yang, Xianwan; Huang, Ruohua; Bin, Huang; Zheng, Sunsheng; Wei, Zaishan; Xu, Xiaoyi; Lu, Jilai; Sun, Xing; Chen, Liuxin

    2004-12-01

    By using the biopurifying technology, the organic waste gas in low concentrations emitted from the rubber-regeneration process was purified in this research. The result of the 100-day continuous running test of the industrial test device indicated that the purification efficiency of toluene in the rubber-regeneration waste gas could be maintained at about 90% for a long period of time and the treated waste gas could meet the China National Emission Standard. The cost of waste gas biotreatment was about 0.12-0.14% of rubber-regeneration production value of the factory. The biopurifying technology of waste gas displayed its excellent technical advancement and economic rationale. The following industrialized device was run continuously and passed the examination and acceptance by the local EPA.

  17. Secondary Waste Form Screening Test Results—THOR® Fluidized Bed Steam Reforming Product in a Geopolymer Matrix

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Pires, Richard P.; Westsik, Joseph H.; Serne, R. Jeffrey

    2011-07-14

    Screening tests are being conducted to evaluate waste forms for immobilizing secondary liquid wastes from the Hanford Tank Waste Treatment and Immobilization Plant (WTP). Plans are underway to add a stabilization treatment unit to the Effluent Treatment Facility to provide the needed capacity for treating these wastes from WTP. The current baseline is to use a Cast Stone cementitious waste form to solidify the wastes. Through a literature survey, DuraLith alkali-aluminosilicate geopolymer, fluidized-bed steam reformation (FBSR) granular product encapsulated in a geopolymer matrix, and a Ceramicrete phosphate-bonded ceramic were identified both as candidate waste forms and alternatives to the baseline.more » These waste forms have been shown to meet waste disposal acceptance criteria, including compressive strength and universal treatment standards for Resource Conservation and Recovery Act (RCRA) metals (as measured by the toxicity characteristic leaching procedure [TCLP]). Thus, these non-cementitious waste forms should also be acceptable for land disposal. Information is needed on all four waste forms with respect to their capability to minimize the release of technetium. Technetium is a radionuclide predicted to be in the secondary liquid wastes in small quantities, but the Integrated Disposal Facility (IDF) risk assessment analyses show that technetium, even at low mass, produces the largest contribution to the estimated IDF disposal impacts to groundwater.« less

  18. GY SAMPLING THEORY IN ENVIRONMENTAL STUDIES 2: SUBSAMPLING ERROR MEASUREMENTS

    EPA Science Inventory

    Sampling can be a significant source of error in the measurement process. The characterization and cleanup of hazardous waste sites require data that meet site-specific levels of acceptable quality if scientifically supportable decisions are to be made. In support of this effort,...

  19. Special Analysis for the Disposal of the INL Waste Associated with the Unirradiated Light Water Breeder Reactor (LWBR) Waste Stream at the Area 5 Radioactive Waste Management Site

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Shott, Gregory

    This special analysis (SA) evaluates whether the Idaho National Laboratory (INL) Waste Associated with the Unirradiated Light Water Breeder Reactor (LWBR) waste stream (INEL167203QR1, Revision 0) is suitable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). Disposal of the INL Waste Associated with the Unirradiated LWBR waste meets all U.S. Department of Energy (DOE) Manual DOE M 435.1-1, “Radioactive Waste Management Manual,” Chapter IV, Section P performance objectives (DOE 1999). The INL Waste Associated with the Unirradiated LWBR waste stream is recommended for acceptance with the conditionmore » that the total uranium-233 ( 233U) inventory be limited to 2.7E13 Bq (7.2E2 Ci).« less

  20. HEU Holdup Measurements on 321-M A-Lathe

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Dewberry, R.A.

    The Analytical Development Section of SRTC was requested by the Facilities Disposition Division (FDD) of the Savannah River Site to determine the holdup of enriched uranium in the 321-M facility as part of an overall deactivation project of the facility. The 321-M facility was used to fabricate enriched uranium fuel assemblies, lithium-aluminum target tubes, neptunium assemblies, and miscellaneous components for the production reactors. The results of the holdup assays are essential for determining compliance with the solid waste Waste Acceptance Criteria, Material Control and Accountability, and to meet criticality safety controls. Three measurement systems were used to determine highly enrichedmore » uranium (HEU) holdup. This report covers holdup measurements on the A-Lathe that was used to machine uranium-aluminum-alloy (U-Al). Our results indicated that the lathe contained more than the limits stated in the Waste Acceptance Criteria (WAC) for the solid waste E-Area Vaults. Thus the lathe was decontaminated three times and assayed four times in order to bring the amounts of uranium to an acceptable content. This report will discuss the methodology, Non-Destructive Assay (NDA) measurements, and results of the U-235 holdup on the lathe.« less

  1. Operational Strategies for Low-Level Radioactive Waste Disposal Site in Egypt - 13513

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mohamed, Yasser T.

    The ultimate aims of treatment and conditioning is to prepare waste for disposal by ensuring that the waste will meet the waste acceptance criteria of a disposal facility. Hence the purpose of low-level waste disposal is to isolate the waste from both people and the environment. The radioactive particles in low-level waste emit the same types of radiation that everyone receives from nature. Most low-level waste fades away to natural background levels of radioactivity in months or years. Virtually all of it diminishes to natural levels in less than 300 years. In Egypt, The Hot Laboratories and Waste Management Centermore » has been established since 1983, as a waste management facility for LLW and ILW and the disposal site licensed for preoperational in 2005. The site accepts the low level waste generated on site and off site and unwanted radioactive sealed sources with half-life less than 30 years for disposal and all types of sources for interim storage prior to the final disposal. Operational requirements at the low-level (LLRW) disposal site are listed in the National Center for Nuclear Safety and Radiation Control NCNSRC guidelines. Additional procedures are listed in the Low-Level Radioactive Waste Disposal Facility Standards Manual. The following describes the current operations at the LLRW disposal site. (authors)« less

  2. The highly successful safe remediation of the Fernald waste pits undertaken under the privatization model

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cherry, Mark; Lojek, Dave; Murphy, Con

    2003-02-23

    Remediation of eight waste pits at the Department of Energy (DOE) Fernald site, located northwest of Cincinnati, Ohio, involves excavating approximately one million tonnes in-situ of low-level waste which were placed in pits during Fernald's production era. This unique project, one of the largest in the history of CERCLA/Superfund, includes uranium and thorium contaminated waste, soils and sludges. These wet soils and sludges are thermally dried in a processing facility to meet Department of Transportation (DOT) transportation and disposal facility waste acceptance criteria, loaded into railcars and shipped to the Envirocare waste disposal facility at Clive, Utah. This project ismore » now approximately 60% complete with more than 415,000 tonnes (460,000 tons) of waste material safely shipped in 74 unit trains to Envirocare. Work is scheduled to be completed in early 2005. Success to date demonstrates that a major DOE site remediation project can be safely and successfully executed in partnership with private industry, utilizing proven commercial best practices, existing site labor resources and support of local stakeholders. In 1997 under the DOE's privatization initiative, Fluor Fernald, Inc. (Fluor Fernald) solicited the services of the remediation industry to design, engineer, procure, construct, own and operate a facility that would undertake the remediation of the waste pits. The resulting procurement was awarded to IT Corporation, currently Shaw Environmental and Infrastructure, Inc. (Shaw). The contractor was required to finance the procurement and construction of its facilities and infrastructure. The contract was performance-based and payment would be made on the successful loadout of the waste from the facility on a per-ton basis meeting the Envirocare waste acceptance criteria. This paper details the performance to date, the challenges encountered, and the seamless partnering between DOE, the Environmental Protection Agency (EPA), Fluor Fernald, Shaw, labor un ions, and the local community in creating and executing a successful project.« less

  3. Low-Activity Waste Pretreatment System Additional Engineering-Scale Integrated Test Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Landon, Matt R.; Wilson, Robert A.

    Washington River Protections Solutions, LLC’s (WRPS) Low Activity Waste Pretreatment System (LAWPS) Project provides for the early production of immobilized low-activity waste (ILAW) by feeding LAW directly from Tank Farms to the Waste Treatment and Immobilization Plant (WTP) LAW Facility, bypassing the WTP Pretreatment Facility. Prior to the transfer of feed to the WTP LAW Vitrification Facility, tank supernatant waste will be pretreated in the LAWPS to meet the WTP LAW waste acceptance criteria (WAC). Full-scale and engineering-scale testing of critical technology elements, as part of the technology maturation process, are components of the overall LAWPS Project. WRPS awarded themore » engineering-scale integrated testing scope to AECOM via WRPS Subcontract 58349. This report is deliverable MSR-008 of the subcontract.« less

  4. USEPA SITE PROGRAM APPROACH TO TECHNOLOGY TRANSFER AND REGULATORY ACCEPTANCE

    EPA Science Inventory

    The USEPA's SITE program was created to meet the demand for innovative technologies for hazardous waste treatment. The primary mission of the SITe Program is to expedite the cleanup of sites on the NPL. These sites often have multiple contaminants in soil and groundwater, and few...

  5. Characterization Results For The 2013 HTF 3H Evaporator Overhead Samples

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Washington, A. L. II

    2013-12-04

    This report tabulates the radiochemical analysis of the 3H evaporator overhead sample for {sup 137}Cs, {sup 90}Sr, and {sup 129}I to meet the requirements in the Effluent Treatment Project (ETP) Waste Acceptance Criteria (WAC) (rev. 6). This report identifies the sample receipt date, preparation method, and analysis performed in the accumulation of the listed values. All data was found to be within the ETP WAC (rev. 6) specification for the Waste Water Collection Tanks (WWCT).

  6. Characterization Results for the 2014 HTF 3H & 2H Evaporator Overhead Samples

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Washington, A.

    2015-05-11

    This report tabulates the radiochemical analysis of the 3H and 2H evaporator overhead samples for 137Cs, 90Sr, and 129I to meet the requirements in the Effluent Treatment Project (ETP) Waste Acceptance Criteria (WAC) (rev. 6). This report identifies the sample receipt date, preparation method, and analysis performed in the accumulation of the listed values. All data was found to be within the ETP WAC (rev. 6) specification for the Waste Water Collection Tanks (WWCT).

  7. Waste Generation Overview, Course 23263

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Simpson, Lewis Edward

    This course, Waste Generation Overview Live (COURSE 23263), provides an overview of federal and state waste management regulations, as well as Los Alamos National Laboratory (LANL) policies and procedures for waste management operations. The course covers the activities involved in the cradle-to-grave waste management process and focuses on waste characterization, waste compatibility determinations and classification, and the storage requirements for temporary waste accumulation areas at LANL. When you have completed this course, you will be able to recognize federal, state, and LANL environmental requirements and their impact on waste operations; recognize the importance of the cradle-to-grave waste management process; identifymore » the roles and responsibilities of key LANL waste management personnel (e.g., Waste Generator, Waste Management Coordinator, Waste Stream Profile approver, and Waste Certification Official); characterize a waste stream to determine whether it meets the definition of a hazardous waste, as well as characterize the use and minimum requirements for use of acceptable knowledge (AK) for waste characterization and waste compatibility documentation requirements; and identify the requirements for setting up and managing temporary waste accumulation areas.« less

  8. Waste Isolation Safety Assessment Program. Technical progress report for FY-1978

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Brandstetter, A.; Harwell, M.A.; Howes, B.W.

    1979-07-01

    Associated with commercial nuclear power production in the United States is the generation of potentially hazardous radioactive wastes. The Department of Energy (DOE) is seeking to develop nuclear waste isolation systems in geologic formations that will preclude contact with the biosphere of waste radionuclides in concentrations which are sufficient to cause deleterious impact on humans or their environments. Comprehensive analyses of specific isolation systems are needed to assess the expectations of meeting that objective. The Waste Isolation Safety Assessment Program (WISAP) has been established at the Pacific Northwest Laboratory (operated by Battelle Memorial Institute) for developing the capability of makingmore » those analyses. Progress on the following tasks is reported: release scenario analysis, waste form release rate analysis, release consequence analysis, sorption-desorption analysis, and societal acceptance analysis. (DC)« less

  9. Alkali activated solidification/stabilisation of air pollution control residues and co-fired pulverised fuel ash.

    PubMed

    Shirley, Robin; Black, Leon

    2011-10-30

    This paper examines the potential treatment by solidification/stabilisation (S/S) of air pollution control (APC) residues using only waste materials otherwise bound for disposal, namely a pulverised fuel ash (PFA) from a co-fired power station and a waste caustic solution. The use of waste materials to stabilise hazardous wastes in order to meet waste acceptance criteria (WAC) would offer an economical and efficient method for reducing the environmental impact of the hazardous waste. The potential is examined against leach limits for chlorides, sulphates and total dissolved solids, and compressive strength performance described in the WAC for stable non-reactive (SNR) hazardous waste landfill cells in England and Wales. The work demonstrates some potential for the treatment, including suitable compressive strengths to meet regulatory limits. Monolithic leach results showed good encapsulation compared to previous work using a more traditional cement binder. However, consistent with previous work, SNR WAC for chlorides was not met, suggesting the need for a washing stage. The potential problems of using a non-EN450 PFA for S/S applications were also highlighted, as well as experimental results which demonstrate the effect of ionic interactions on the mobility of phases during regulatory leach testing. Copyright © 2011 Elsevier B.V. All rights reserved.

  10. Environmental, technical and technological aspects of hazardous waste management in Poland

    NASA Astrophysics Data System (ADS)

    Pyssa, Justyna

    2017-10-01

    The issue of recovery and disposal of hazardous waste is not a new concern. The waste comes from various processes and technologies and therefore the bigger emphasis should be placed on reducing quantities of generated hazardous waste (which is often connected with changes in the technology of manufacturing a given product) and limitation of their negative influence on natural environment. Plants specializing in waste processing processes should meet the so-called cardinal triad of conditions deciding on the full success of investment, and namely: economic effectiveness, ecological efficiency and social acceptance. The structure of generation of hazardous waste in EU-28 has been presented in the paper. Methods of hazardous waste disposal in Poland have been discussed. Economic and ecological criteria for the selection of technology of hazardous waste disposal have been analyzed. The influence of the hazardous waste on the environment is also presented. For four groups of waste, which are currently stored, alternative methods of disposal have been proposed.

  11. An Example of an INPRO Assessment of an INS in the Area of Waste Management

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Allan, C.; Busurin, Y.; Depisch, F.

    2006-07-01

    Following a resolution of the General Conference of the IAEA in the year 2000 the International Project on Innovative Nuclear Reactors and Fuel Cycles, referred to as INPRO, was initiated. INPRO has defined requirements organized in a hierarchy of Basic Principles, User Requirements and Criteria (consisting of an indicator and an acceptance limit) to be met by innovative nuclear reactor systems (INS) in six areas, namely: economics, safety, waste management, environment, proliferation resistance, and infrastructure. If an INS meets all requirements in all areas it represents a sustainable system for the supply of energy, capable of making a significant contributionmore » to meeting the energy needs of the 21. century. Draft manuals have been developed, for each INPRO area, to provide guidance for performing an assessment of whether an INS meets the INPRO requirements in a given area. The manuals set out the information that needs to be assembled to perform an assessment and provide guidance on selecting the acceptance limits and, for a given INS, for determining the value of the indicators for comparison with the associated acceptance limits. Each manual also includes an example of a specific assessment to illustrate the guidance. This paper discusses the example presented in the manual for performing an INPRO assessment in the area of waste management. The example, chosen solely for the purpose of illustrating the INPRO methodology, describes an assessment of an INS based on the DUPIC fuel cycle. It is assumed that uranium is mined, milled, converted, enriched, and fabricated into LWR fuel in Canada. The LWR fuel is assumed to be leased to a utility in the USA. The spent LWR fuel is assumed to be returned to Canada where it is processed into CANDU DUPIC fuel, which is then burned in CANDU reactors. The assessment steps and the results are presented in detail in the paper. The example illustrates an assessment performed for an INS at an early stage of development. (authors)« less

  12. Environmental assessment for the construction, operation, and decommissioning of the Waste Segregation Facility at the Savannah River Site

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1998-01-01

    This Environmental Assessment (EA) has been prepared by the Department of Energy (DOE) to assess the potential environmental impacts associated with the construction, operation and decontamination and decommissioning (D&D) of the Waste Segregation Facility (WSF) for the sorting, shredding, and compaction of low-level radioactive waste (LLW) at the Savannah River Site (SRS) located near Aiken, South Carolina. The LLW to be processed consists of two waste streams: legacy waste which is currently stored in E-Area Vaults of SRS and new waste generated from continuing operations. The proposed action is to construct, operate, and D&D a facility to process low-activity job-controlmore » and equipment waste for volume reduction. The LLW would be processed to make more efficient use of low-level waste disposal capacity (E-Area Vaults) or to meet the waste acceptance criteria for treatment at the Consolidated Incineration Facility (CIF) at SRS.« less

  13. Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada National Security Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NSTec Environmental Programs

    2010-10-04

    The Nevada National Security Site (NNSS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NNSS and National Security Technologies, LLC (NSTec) is the Management and Operations contractor. Access on and off the NNSS is tightly controlled, restricted, and guarded on a 24-hour basis. The NNSS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NNSS. The Area 5 Radioactive Waste Management Site (RWMS) ismore » the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NNSS (Figure 1), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. The site will be used for the disposal of regulated Asbestiform Low-Level Waste (ALLW), small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains Polychlorinated Biphenyl (PCB) Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. Waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM) and PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water. The term asbestiform is used throughout this document to describe RACM. The disposal site will be used as a depository of permissible waste generated both on site and off site. All generators designated by NNSA/NSO will be eligible to dispose regulated ALLW at the Asbestiform Low-Level Waste Disposal Site in accordance with the DOE/NV-325, Nevada National Security Site Waste Acceptance Criteria (NNSSWAC, current revision). Approval will be given by NNSA/NSO to generators that have successfully demonstrated through process knowledge (PK) and/or sampling and analysis that the waste is low-level, contains asbestiform material, or contains PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, or small quantities of LLHB demolition and construction waste and does not contain prohibited waste materials. Each waste stream will be approved through the Radioactive Waste Acceptance Program (RWAP), which ensures that the waste meets acceptance requirements outlined in the NNSSWAC.« less

  14. The role of frit in nuclear waste vitrification

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Vienna, J.D.; Smith, P.A.; Dorn, D.A.

    1994-04-01

    Vitrification of nuclear waste requires additives which are often vitrified independently to form a frit. Frit composition is formulated to meet the needs of glass composition and processing. The effects of frit on melter feed and melt processing, glass acceptance, and waste loading is of practical interest in understanding the trade-offs associated with the competing demands placed on frit composition. Melter feed yield stress, viscosity and durability of frits and corresponding waste glasses as well as the kinetics of elementary melting processes have been measured. The results illustrate the competing requirements on frit. Four frits (FY91, FY93, HW39-4, and SR202)more » and simulated neutralized current acid waste (NCAW) were used in this study. The experimental evidence shows that optimization of frit for one processing related property often results in poorer performance for the remaining properties. The difficulties associated with maximum waste loading and durability are elucidated for glasses which could be processed using technology available for the previously proposed Hanford Waste Vitrification Plant.« less

  15. ENGINEERING STUDY FOR THE 200 AREA EFFLUENT TREATMENT FACILITY (ETF) SECONDARY WASTE TREATMENT OF PROJECTED FUTURE WASTE FEEDS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    LUECK, K.J.

    2004-10-18

    This report documents an engineering study conducted to evaluate alternatives for treating secondary waste in the secondary treatment train (STT) of the Hanford Site 200 Area Effluent Treatment Facility (ETF). The study evaluates ETF STT treatment alternatives and recommends preferred alternatives for meeting the projected future missions of the ETF. The preferred alternative(s) will process projected future ETF influents to produce a solid waste acceptable for final disposal on the Hanford Site. The main text of this report summarizes the ETF past and projected operations, lists the assumptions about projected operations that provide the basis for the engineering evaluation, andmore » summarizes the evaluation process. The evaluation process includes identification of available modifications to the current ETF process, screens those modifications for technical viability, evaluates the technically viable alternatives, and provides conclusions and recommendations based on that evaluation.« less

  16. Space augmentation of military high-level waste disposal

    NASA Technical Reports Server (NTRS)

    English, T.; Lees, L.; Divita, E.

    1979-01-01

    Space disposal of selected components of military high-level waste (HLW) is considered. This disposal option offers the promise of eliminating the long-lived radionuclides in military HLW from the earth. A space mission which meets the dual requirements of long-term orbital stability and a maximum of one space shuttle launch per week over a period of 20-40 years, is a heliocentric orbit about halfway between the orbits of earth and Venus. Space disposal of high-level radioactive waste is characterized by long-term predictability and short-term uncertainties which must be reduced to acceptably low levels. For example, failure of either the Orbit Transfer Vehicle after leaving low earth orbit, or the storable propellant stage failure at perihelion would leave the nuclear waste package in an unplanned and potentially unstable orbit. Since potential earth reencounter and subsequent burn-up in the earth's atmosphere is unacceptable, a deep space rendezvous, docking, and retrieval capability must be developed.

  17. DISPOSITION PATHS FOR ROCKY FLATS GLOVEBOXES: EVALUATING OPTIONS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Lobdell, D.; Geimer, R.; Larsen, P.

    2003-02-27

    The Kaiser-Hill Company, LLC has the responsibility for closure activities at the Rocky Flats Environmental Technology Site (RFETS). One of the challenges faced for closure is the disposition of radiologically contaminated gloveboxes. Evaluation of the disposition options for gloveboxes included a detailed analysis of available treatment capabilities, disposal facilities, and lifecycle costs. The Kaiser-Hill Company, LLC followed several processes in determining how the gloveboxes would be managed for disposition. Currently, multiple disposition paths have been chosen to accommodate the needs of the varying styles and conditions of the gloveboxes, meet the needs of the decommissioning team, and to best managemore » lifecycle costs. Several challenges associated with developing a disposition path that addresses both the radiological and RCRA concerns as well as offering the most cost-effective solution were encountered. These challenges included meeting the radiological waste acceptance criteria of available disposal facilities, making a RCRA determination, evaluating treatment options and costs, addressing void requirements associated with disposal, and identifying packaging and transportation options. The varying disposal facility requirements affected disposition choices. Facility conditions that impacted decisions included radiological and chemical waste acceptance criteria, physical requirements, and measurement for payment options. The facility requirements also impacted onsite activities including management strategies, decontamination activities, and life-cycle cost.« less

  18. NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

    This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal.

  19. Multi-discipline Waste Acceptance Process at the Nevada National Security Site - 13573

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Carilli, Jhon T.; Krenzien, Susan K.

    2013-07-01

    The Nevada National Security Site low-level radioactive waste disposal facility acceptance process requires multiple disciplines to ensure the protection of workers, the public, and the environment. These disciplines, which include waste acceptance, nuclear criticality, safety, permitting, operations, and performance assessment, combine into the overall waste acceptance process to assess low-level radioactive waste streams for disposal at the Area 5 Radioactive Waste Management Site. Four waste streams recently highlighted the integration of these disciplines: the Oak Ridge Radioisotope Thermoelectric Generators and Consolidated Edison Uranium Solidification Project material, West Valley Melter, and classified waste. (authors)

  20. Characterization of the Old Hydrofracture Facility (OHF) waste tanks located at ORNL

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Keller, J.M.; Giaquinto, J.M.; Meeks, A.M.

    1997-04-01

    The Old Hydrofracture Facility (OHF) is located in Melton Valley within Waste Area Grouping (WAG) 5 and includes five underground storage tanks (T1, T2, T3, T4, and T9) ranging from 13,000 to 25,000 gal. capacity. During the period of 1996--97 there was a major effort to re-sample and characterize the contents of these inactive waste tanks. The characterization data summarized in this report was needed to address waste processing options, examine concerns dealing with the performance assessment (PA) data for the Waste Isolation Pilot Plant (WIPP), evaluate the waste characteristics with respect to the waste acceptance criteria (WAC) for WIPPmore » and Nevada Test Site (NTS), address criticality concerns, and to provide the data needed to meet DOT requirements for transporting the waste. This report discusses the analytical characterization data collected on both the supernatant and sludge samples taken from three different locations in each of the OHF tanks. The isotopic data presented in this report supports the position that fissile isotopes of uranium ({sup 233}U and {sup 235}U) do not satisfy the denature ratios required by the administrative controls stated in the ORNL LLLW waste acceptance criteria (WAC). The fissile isotope of plutonium ({sup 239}Pu and {sup 241}Pu) are diluted with thorium far above the WAC requirements. In general, the OHF sludge was found to be hazardous (RCRA) based on total metal content and the transuranic alpha activity was well above the 100 nCi/g limit for TRU waste. The characteristics of the OHF sludge relative to the WIPP WAC limits for fissile gram equivalent, plutonium equivalent activity, and thermal power from decay heat were estimated from the data in this report and found to be far below the upper boundary for any of the remote-handled transuranic waste (RH-TRU) requirements for disposal of the waste in WIPP.« less

  1. Letter Report: LAW Simulant Development for Cast Stone Screening Test

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Russell, Renee L.; Westsik, Joseph H.; Swanberg, David J.

    2013-03-27

    More than 56 million gallons of radioactive and hazardous waste are stored in 177 underground storage tanks at the U.S. Department of Energy’s (DOE’s) Hanford Site in southeastern Washington State. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the wastes and immobilize them in a glass waste form. The WTP includes a pretreatment facility to separate the wastes into a small volume of high-level waste (HLW) containing most of the radioactivity and a larger volume of low-activity waste (LAW) containing most of the nonradioactive chemicals. The HLW will be converted to glass in themore » HLW vitrification facility for ultimate disposal at an offsite federal repository. At least a portion (~35%) of the LAW will be converted to glass in the LAW vitrification facility and will be disposed of onsite at the Integrated Disposal Facility (IDF). The pretreatment and HLW vitrification facilities will have the capacity to treat and immobilize the wastes destined for each facility. However, a second facility will be needed for the expected volume of additional LAW requiring immobilization. A cementitious waste form known as Cast Stone is being considered to provide the required additional LAW immobilization capacity. The Cast Stone waste form must be acceptable for disposal in the IDF. The Cast Stone waste form and immobilization process must be tested to demonstrate that the final Cast Stone waste form can comply with waste acceptance criteria for the IDF disposal facility and that the immobilization processes can be controlled to consistently provide an acceptable waste form product. Further, the waste form must be tested to provide the technical basis for understanding the long term performance of the waste form in the IDF disposal environment. These waste form performance data are needed to support risk assessment and performance assessment (PA) analyses of the long-term environmental impact of the waste disposal in the IDF. A testing program was developed in fiscal year (FY) 2012 describing in some detail the work needed to develop and qualify Cast Stone as a waste form for the solidification of Hanford LAW (Westsik et al. 2012). Included within Westsik et al. (2012) is a section on the near-term needs to address Tri-Party Agreement Milestone M-062-40ZZ. The objectives of the testing program to be conducted in FY 2013 and FY 2014 are to: • Determine an acceptable formulation for the LAW Cast Stone waste form. • Evaluate sources of dry materials for preparing the LAW Cast Stone. • Demonstrate the robustness of the Cast Stone waste form for a range of LAW compositions. • Demonstrate the robustness of the formulation for variability in the Cast Stone process. • Provide Cast Stone contaminant release data for PA and risk assessment evaluations. The first step in determining an acceptable formulation for the LAW Cast Stone waste form is to conduct screening tests to examine expected ranges in pretreated LAW composition, waste stream concentrations, dry-materials sources, and mix ratios of waste feed to dry blend. A statistically designed test matrix will be used to evaluate the effects of these key parameters on the properties of the Cast Stone as it is initially prepared and after curing. The second phase of testing will focus on selection of a baseline Cast Stone formulation for LAW and demonstrating that Cast Stone can meet expected waste form requirements for disposal in the IDF. It is expected that this testing will use the results of the screening tests to define a smaller suite of tests to refine the composition of the baseline Cast Stone formulation (e.g. waste concentration, water to dry mix ratio, waste loading).« less

  2. Framing ethical acceptability: a problem with nuclear waste in Canada.

    PubMed

    Wilding, Ethan T

    2012-06-01

    Ethical frameworks are often used in professional fields as a means of providing explicit ethical guidance for individuals and institutions when confronted with ethically important decisions. The notion of an ethical framework has received little critical attention, however, and the concept subsequently lends itself easily to misuse and ambiguous application. This is the case with the 'ethical framework' offered by Canada's Nuclear Waste Management Organization (NWMO), the crown-corporation which owns and is responsible for the long-term management of Canada's high-level nuclear fuel waste. It makes a very specific claim, namely that it is managing Canada's long-lived radioactive nuclear fuel waste in an ethically responsible manner. According to this organization, what it means to behave in an ethically responsible manner is to act and develop policy in accordance with its ethical framework. What, then, is its ethical framework, and can it be satisfied? In this paper I will show that the NWMO's ethical and social framework is deeply flawed in two respects: (a) it fails to meet the minimum requirements of a code of ethic or ethical framework by offering only questions, and no principles or rules of conduct; and (b) if posed as principles or rules of conduct, some of its questions are unsatisfiable. In particular, I will show that one of its claims, namely that it seek informed consent from individuals exposed to risk of harm from nuclear waste, cannot be satisfied as formulated. The result is that the NWMO's ethical framework is not, at present, ethically acceptable.

  3. Nuclear reference materials to meet the changing needs of the global nuclear community

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Martin, H.R.; Gradle, C.G.; Narayanan, U.I.

    New Brunswick Laboratory (NBL) serves as the U.S. Government`s certifying authority for nuclear reference materials and measurement calibration standards. In this role, NBL provides nuclear reference materials certified for chemical and/or isotopic compositions traceable to a nationally accepted, internationally compatible reference base. Emphasis is now changing as to the types of traceable nuclear reference materials needed as operations change within the Department of Energy complex and at nuclear facilities around the world. New challenges include: environmental and waste minimization issues, facilities and materials transitioning from processing to storage modes with corresponding changes in the types of measurements being performed, emphasismore » on requirements for characterization of waste materials, and difficulties in transporting nuclear materials and international factors, including IAEA influences. During these changing times, it is critical that traceable reference materials be provided for calibration or validation of the performance of measurement systems. This paper will describe actions taken and planned to meet the changing reference material needs of the global nuclear community.« less

  4. Idaho National Engineering Laboratory code assessment of the Rocky Flats transuranic waste

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1995-07-01

    This report is an assessment of the content codes associated with transuranic waste shipped from the Rocky Flats Plant in Golden, Colorado, to INEL. The primary objective of this document is to characterize and describe the transuranic wastes shipped to INEL from Rocky Flats by item description code (IDC). This information will aid INEL in determining if the waste meets the waste acceptance criteria (WAC) of the Waste Isolation Pilot Plant (WIPP). The waste covered by this content code assessment was shipped from Rocky Flats between 1985 and 1989. These years coincide with the dates for information available in themore » Rocky Flats Solid Waste Information Management System (SWIMS). The majority of waste shipped during this time was certified to the existing WIPP WAC. This waste is referred to as precertified waste. Reassessment of these precertified waste containers is necessary because of changes in the WIPP WAC. To accomplish this assessment, the analytical and process knowledge available on the various IDCs used at Rocky Flats were evaluated. Rocky Flats sources for this information include employee interviews, SWIMS, Transuranic Waste Certification Program, Transuranic Waste Inspection Procedure, Backlog Waste Baseline Books, WIPP Experimental Waste Characterization Program (headspace analysis), and other related documents, procedures, and programs. Summaries are provided of: (a) certification information, (b) waste description, (c) generation source, (d) recovery method, (e) waste packaging and handling information, (f) container preparation information, (g) assay information, (h) inspection information, (i) analytical data, and (j) RCRA characterization.« less

  5. Mercury leaching from hazardous industrial wastes stabilized by sulfur polymer encapsulation.

    PubMed

    López, Félix A; Alguacil, Francisco J; Rodríguez, Olga; Sierra, María José; Millán, Rocío

    2015-01-01

    European Directive 2013/39/EU records mercury as a priority hazardous substance. Regulation n° 2008/1102/EC banned the exportation of mercury and required the safe storage of any remaining mercury compounds. The present work describes the encapsulation of three wastes containing combinations of HgS, HgSe, HgCl2, HgO2, Hg3Se2Cl2, HgO and Hg(0), according to patent of Spanish National Research Council WO2011/029970A2. The materials obtained were subjected to leaching tests according to standards UNE-EN-12457 and CEN/TS 14405:2004. The results are compared with the criteria established in the Council Decision 2003/33/EC for the acceptance of waste at landfills. The Hg concentrations of all leachates were <0.01mgHg/kg for a liquid/solid ratio of 10l/kg. All three encapsulated materials therefore meet the requirements for storage in inert waste landfills. Copyright © 2014 Elsevier Ltd. All rights reserved.

  6. Acceptance test report, 241-SY-101 Flexible Receiver System, Phase 2 testing

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Ritter, G.A.

    1995-02-06

    This document summarizes the results of the Phase 2 acceptance test of the 241-SY-101 Flexible Receiver System (FRS). The FRS is one of six major components of the Equipment Removal System, which has been designed to retrieve, transport, and store the test mixer pump currently installed in Tank 241-SY-101. The purpose of this acceptance test is to verify the strength of the containment bag and bag bottom cinching mechanism. It is postulated that 68 gallons of waste could be trapped inside the pump internals. The bag must be capable of supporting this waste if it shakes loose and drains tomore » the bottom of the bag after the bag bottom has been cinched closed. This acceptance test was performed at the Maintenance and Storage Facility (MASF) Facility in the 400 area on January 23, 1995. The bag assembly supported the weight of 920 kg (2,020 lbs) of water with no leakage or damage to the bag. This value meets the acceptance criteria of 910 kg of water and therefore the results were found to be acceptable. The maximum volume of liquid expected to be held up in the pump internals is 258 L (68 gallons), which corresponds to 410 kg. This test weight gives just over a safety factor of 2. The bag also supported a small shock load while it was filled with water when the crane hoisted the bag assembly up and down. Based on the strength rating of the bag components, the bag assembly should support 2--3 times the test weight of 910 kg.« less

  7. Acceptable knowledge document for INEEL stored transuranic waste -- Rocky Flats Plant waste. Revision 2

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1998-01-23

    This document and supporting documentation provide a consistent, defensible, and auditable record of acceptable knowledge for waste generated at the Rocky Flats Plant which is currently in the accessible storage inventory at the Idaho National Engineering and Environmental Laboratory. The inventory consists of transuranic (TRU) waste generated from 1972 through 1989. Regulations authorize waste generators and treatment, storage, and disposal facilities to use acceptable knowledge in appropriate circumstances to make hazardous waste determinations. Acceptable knowledge includes information relating to plant history, process operations, and waste management, in addition to waste-specific data generated prior to the effective date of the RCRAmore » regulations. This document is organized to provide the reader a comprehensive presentation of the TRU waste inventory ranging from descriptions of the historical plant operations that generated and managed the waste to specific information about the composition of each waste group. Section 2 lists the requirements that dictate and direct TRU waste characterization and authorize the use of the acceptable knowledge approach. In addition to defining the TRU waste inventory, Section 3 summarizes the historical operations, waste management, characterization, and certification activities associated with the inventory. Sections 5.0 through 26.0 describe the waste groups in the inventory including waste generation, waste packaging, and waste characterization. This document includes an expanded discussion for each waste group of potential radionuclide contaminants, in addition to other physical properties and interferences that could potentially impact radioassay systems.« less

  8. NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA, JUNE 2006

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

  9. Nevada Test Site Waste Acceptance Criteria

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

  10. US/UK Loan Account Project Status PMOD477

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Stevens, Patrice A.

    2012-07-12

    The viewgraphs describe the status of PMOD477 for LANL. The meeting will occur at DOE-HQ with NA-11 and Military Applications personnel in attendance. Serves to repatriate material with a balance to zero by December 2012. Phase 1 -- Establish formality of operations for War Reserve (WR): Complete surrogate taskings to A90 through a Materials Channel and perform US/UK lessons learned; Complete the US/UK agreed Quality Acceptance Plan, Materials Plan, Shipping procedure, and establish the formal UK/US point of contacts. Phase 2 -- Metal Manufacture (WR): Process material and store material as electrorefined metal (ER) rings, with initial assay and isotopicmore » analysis, prior to manufacturing. Material is cast into accepted configuration and appropriate acceptance document for each aliquot will be generated. Phase 3 -- Intermediate Material Manufacture, Packaging and Shipping (WR): Continue processing of the material in accepted configuration with appropriate acceptance documentation for each aliquot. Provide an initial tasking of the material owed to UK including appropriate quality acceptance documentation. Phase 4 -- Complete Tasking (WR). Phase 5 -- Residue Processing (Non-WR): Complete processing of residue material and waste into accepted configuration with appropriate acceptance document for disposal.« less

  11. The Advancement of Public Awareness, Concerning TRU Waste Characterization, Using a Virtual Document

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    West, T. B.; Burns, T. P.; Estill, W. G.

    2002-02-28

    Building public trust and confidence through openness is a goal of the DOE Carlsbad Field Office for the Waste Isolation Pilot Plant (WIPP). The objective of the virtual document described in this paper is to give the public an overview of the waste characterization steps, an understanding of how waste characterization instrumentation works, and the type and amount of data generated from a batch of drums. The document is intended to be published on a web page and/or distributed at public meetings on CDs. Users may gain as much information as they desire regarding the transuranic (TRU) waste characterization program,more » starting at the highest level requirements (drivers) and progressing to more and more detail regarding how the requirements are met. Included are links to: drivers (which include laws, permits and DOE Orders); various characterization steps required for transportation and disposal under WIPP's Hazardous Waste Facility Permit; physical/chemical basis for each characterization method; types of data produced; and quality assurance process that accompanies each measurement. Examples of each type of characterization method in use across the DOE complex are included. The original skeleton of the document was constructed in a PowerPoint presentation and included descriptions of each section of the waste characterization program. This original document had a brief overview of Acceptable Knowledge, Non-Destructive Examination, Non-Destructive Assay, Small Quantity sites, and the National Certification Team. A student intern was assigned the project of converting the document to a virtual format and to discuss each subject in depth. The resulting product is a fully functional virtual document that works in a web browser and functions like a web page. All documents that were referenced, linked to, or associated, are included on the virtual document's CD. WIPP has been engaged in a variety of Hazardous Waste Facility Permit modification activities. During the public meetings, discussion centered on proposed changes to the characterization program. The philosophy behind the virtual document is to show the characterization process as a whole, rather than as isolated parts. In addition to public meetings, other uses for the information might be as a training tool for new employees at the WIPP facility to show them where their activities fit into the overall scheme, as well as an employee review to help prepare for waste certification audits.« less

  12. Characterization of the MVST waste tanks located at ORNL

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Keller, J.M.; Giaquinto, J.M.; Meeks, A.M.

    During the fall of 1996 there was a major effort to sample and analyze the Active Liquid Low-Level Waste (LLLW) tanks at ORNL which include the Melton Valley Storage Tanks (MVST) and the Bethel Valley Evaporator Service Tanks (BVEST). The characterization data summarized in this report was needed to address waste processing options, address concerns of the performance assessment (PA) data for the Waste Isolation Pilot Plant (WIPP), evaluate the characteristics with respect to the waste acceptance criteria (WAC) for WIPP and Nevada Test Site (NTS), address criticality concerns, and meet DOT requirements for transporting the waste. This report onlymore » discusses the analytical characterization data for the MVST waste tanks. The isotopic data presented in this report support the position that fissile isotopes of uranium and plutonium were ``denatured`` as required by administrative controls. In general, MVST sludge was found to be both hazardous by RCRA characteristics and the transuranic alpha activity was well about the limit for TRU waste. The characteristics of the MVST sludge relative to the WIPP WAC limits for fissile gram equivalent, plutonium equivalent activity, and thermal power from decay heat, were estimated from the data in this report and found to be far below the upper boundary for any of the remote-handled transuranic waste requirements for disposal of the waste in WIPP.« less

  13. The mixed low-level waste problem in BE/NWN capsule

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hensley, D.C.

    1999-07-01

    The Boh Environmental, LLC (BE) and Northwest Nuclear, LLC (NWN) program addresses the problem of diminishing capacity in the United States to store mixed waste. A lack of an alternative program has caused the US Department of Energy (DOE) to indefinitely store all of its mixed waste in Resource Conservation and Recovery Act (RCRA) compliant storage facilities. Unfortunately, this capacity is fast approaching the administrative control limit. The combination of unique BE encapsulation and NWN waste characterization technologies provides an effective solution to DOE's mixed-waste dilemma. The BE ARROW-PAK technique encapsulates mixed low-level waste (MLLW) in extra-high molecular weight, high-densitymore » polyethylene, pipe-grade resin cylinders. ARROW-PAK applications include waste treatment, disposal, transportation (per 49 CFR 173), vault encasement, and interim/long-term storage for 100 to 300 yr. One of the first demonstrations of this treatment/storage technique successfully treated 880 mixed-waste debris drums at the DOE Hanford Site in 1997. NWN, deploying the APNea neutron assay technology, provides the screening and characterization capability necessary to ensure that radioactive waste is correctly categorized as either transuranic (TRU) or LLW. MLLW resulting from D and D activities conducted at the Oak Ridge East Tennessee Technology Park will be placed into ARROW-PAK containers following comprehensive characterization of the waste by NWN. The characterized and encapsulated waste will then be shipped to a commercial disposal facility, where the shipments meet all waste acceptance criteria of the disposal facility including treatment criteria.« less

  14. 76 FR 47613 - Board Meeting: September 13-14, 2011-Salt Lake City, UT; the U.S. Nuclear Waste Technical Review...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-05

    ... NUCLEAR WASTE TECHNICAL REVIEW BOARD Board Meeting: September 13-14, 2011--Salt Lake City, UT; the U.S. Nuclear Waste Technical Review Board Will Meet To Discuss DOE Plans for Used Fuel Disposition R... Amendments Act of 1987, the U.S. Nuclear Waste Technical Review Board will hold a public meeting in Salt Lake...

  15. Development of integrated radioactive waste packaging and conditioning solutions in the UK

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sibley, Peter; Butter, Kevin; Zimmerman, Ian

    2013-07-01

    In order to offer a more cost effective, safer and efficient Intermediate Level Waste (ILW) management service, EnergySolutions EU Ltd. and Gesellschaft fur Nuklear-Service mbH (GNS) have been engaged in the development of integrated radioactive waste retrieval, packaging and conditioning solutions in the UK. Recognising the challenges surrounding regulatory endorsement and on-site implementation in particular, this has resulted in an alternative approach to meeting customer, safety regulator and disposability requirements. By working closely with waste producers and the organisation(s) responsible for endorsing radioactive waste management operations in the UK, our proposed solutions are now being implemented. By combining GNS' off-the-shelf,more » proven Ductile Cast Iron Containers (DCICs) and water removal technologies, with EnergySolutions EU Ltd.'s experience and expertise in waste retrieval, safety case development and disposability submissions, a fully integrated service offering has been developed. This has involved significant effort to overcome technical challenges such as onsite equipment deployment, active commissioning, conditioning success criteria and disposability acceptance. Our experience in developing such integrated solutions has highlighted the importance of working in collaboration with all parties to achieve a successful and viable outcome. Ultimately, the goal is to ensure reliable, safe and effective delivery of waste management solutions. (authors)« less

  16. 76 FR 3678 - Board Meeting: February 16, 2011-Las Vegas, NV, the U.S. Nuclear Waste Technical Review Board...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-20

    ... NUCLEAR WASTE TECHNICAL REVIEW BOARD Board Meeting: February 16, 2011--Las Vegas, NV, the U.S. Nuclear Waste Technical Review Board Will Meet To Discuss DOE Activities Related to Managing Spent Nuclear...-203, Nuclear Waste Policy Amendments Act of 1987, the U.S. Nuclear Waste Technical Review Board will...

  17. 40 CFR 63.1935 - Am I subject to this subpart?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... Standards for Hazardous Air Pollutants: Municipal Solid Waste Landfills What This Subpart Covers § 63.1935... that has accepted waste since November 8, 1987 or has additional capacity for waste deposition and... landfill that has accepted waste since November 8, 1987 or has additional capacity for waste deposition...

  18. Nevada Test Site Waste Acceptance Criteria (NTSWAC)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NNSA /NSO Waste Management Project

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal.

  19. Special Analysis for the Disposal of the Consolidated Edison Uranium Solidification Project Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NSTec Environmental Management

    2013-01-31

    The purpose of this Special Analysis (SA) is to determine if the Oak Ridge (OR) Consolidated Edison Uranium Solidification Project (CEUSP) uranium-233 (233U) waste stream (DRTK000000050, Revision 0) is acceptable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). The CEUSP 233U waste stream requires a special analysis because the concentrations of thorium-229 (229Th), 230Th, 232U, 233U, and 234U exceeded their NNSS Waste Acceptance Criteria action levels. The acceptability of the waste stream is evaluated by determining if performance assessment (PA) modeling provides a reasonable expectation that SLBmore » disposal is protective of human health and the environment. The CEUSP 233U waste stream is a long-lived waste with unique radiological hazards. The SA evaluates the long-term acceptability of the CEUSP 233U waste stream for near-surface disposal as a two tier process. The first tier, which is the usual SA process, uses the approved probabilistic PA model to determine if there is a reasonable expectation that disposal of the CEUSP 233U waste stream can meet the performance objectives of U.S. Department of Energy Manual DOE M 435.1-1, “Radioactive Waste Management,” for a period of 1,000 years (y) after closure. The second tier addresses the acceptability of the OR CEUSP 233U waste stream for near-surface disposal by evaluating long-term site stability and security, by performing extended (i.e., 10,000 and 60,000 y) modeling analyses, and by evaluating the effect of containers and the depth of burial on performance. Tier I results indicate that there is a reasonable expectation of compliance with all performance objectives if the OR CEUSP 233U waste stream is disposed in the Area 5 RWMS SLB disposal units. The maximum mean and 95th percentile PA results are all less than the performance objective for 1,000 y. Monte Carlo uncertainty analysis indicates that there is a high likelihood of compliance with all performance objectives. Tier II results indicate that the long-term performance of the OR CEUSP 233U waste stream is protective of human health and the environment. The Area 5 RWMS is located in one of the least populated and most arid regions of the U.S. Site characterization data indicate that infiltration of precipitation below the plant root zone at 2.5 meters (8.2 feet) ceased 10,000 to 15,000 y ago. The site is not expected to have a groundwater pathway as long as the current arid climate persists. The national security mission of the NNSS and the location of the Area 5 RWMS within the Frenchman Flat Corrective Action Unit require that access controls and land use restrictions be maintained indefinitely. PA modeling results for 10,000 to 60,000 y also indicate that the OR CEUSP 233U waste stream is acceptable for near-surface disposal. The mean resident air pathway annual total effective dose (TED), the resident all-pathways annual TED, and the acute drilling TED are less than their performance objectives for 10,000 y after closure. The mean radon-222 (222Rn) flux density exceeds the performance objective at 4,200 y, but this is due to waste already disposed at the Area 5 RWMS and is only slightly affected by disposal of the CEUSP 233U. The peak resident all-pathways annual TED from CEUSP key radionuclides occurs at 48,000 y and is less than the 0.25 millisievert performance objective. Disposal of the OR CEUSP 233U waste stream in a typical SLB trench slightly increases PA results. Increasing the depth was found to eliminate any impacts of the OR CEUSP 233U waste stream. Containers could not be shown to have any significant impact on performance due to the long half-life of the waste stream and a lack of data for pitting corrosion rates of stainless steel in soil. The results of the SA indicate that all performance objectives can be met with disposal of the OR CEUSP 233U waste stream in the SLB units at the Area 5 RWMS. The long-term performance of the OR CEUSP 233U waste stream disposed in the near surface is protective of human health and the environment. The waste stream is recommended for disposal without conditions.« less

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    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 wastemore » 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 example, relative density, which can be determined through field measurements, was selected as the field quality control parameter for waste placement. This technique can be extended to include a rigorous performance-based methodology using other parameters (void space criteria, debris-soil mix ratio, pre-loading, etc.). As shown in this example, each parameter range, or sets of parameter ranges can be selected such that they can result in an acceptable, long-term differential settlement according to the probabilistic model. The methodology can also be used to re-evaluate the long-term differential settlement behavior at closed land disposal facilities to identify, if any, problematic facilities so that remedial action (e.g., reinforcement of upper and intermediate waste layers) can be implemented. Considering the inherent spatial variability in waste and earth materials and the need for engineers to apply sound quantitative practices to engineering analysis, it is important to apply the available probabilistic techniques to problems of differential settlement. One such method to implement probability-based differential settlement analyses for the design of landfill final covers has been presented. The design evaluation technique presented is one tool to bridge the gap from deterministic practice to probabilistic practice. (authors)« less

  1. Nuclear reference materials to meet the changing needs of the global nuclear community

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Martin, H.R.; Gradle, C.G.; Narayanan, U.I.

    New Brunswick Laboratory (NBL) serves as the US Government`s Certifying Authority for nuclear reference materials and measurement calibration standards. In this role, NBL provides nuclear reference materials certified for chemical and/or isotopic compositions traceable to a nationally accepted, internationally compatible reference base. Emphasis is now changing as to the types of traceable nuclear reference materials needed as operations change within the Department of Energy (DOE) complex and at nuclear facilities around the world. Environmental and waste minimization issues, facilities and materials transitioning from processing to storage modes with corresponding changes in the types of measurements being performed, emphasis on requirementsmore » for characterization of waste materials, difficulties in transporting nuclear materials, and International factors, including International Atomic Energy Agency (IAEA) inspection of excess US nuclear materials, are all contributing influences. During these changing times, ft is critical that traceable reference materials be provided for calibration or validation of the performance of measurement systems. This paper will describe actions taken and planned to meet the changing reference material needs of the global nuclear community.« less

  2. Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada Test Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NSTec Environmental Programs

    The NTS solid waste disposal sites must be permitted by the state of Nevada Solid Waste Management Authority (SWMA). The SWMA for the NTS is the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). The U.S. Department of Energy's National Nuclear Security Administration Nevada Site Office (NNSA/NSO) as land manager (owner), and National Security Technologies (NSTec), as operator, will store, collect, process, and dispose all solid waste by means that do not create a health hazard, a public nuisance, or cause impairment of the environment. NTS disposal sites will not be included in the Nye County Solid Wastemore » Management Plan. The NTS is located approximately 105 kilometers (km) (65 miles [mi]) northwest of Las Vegas, Nevada (Figure 1). The U.S. Department of Energy (DOE) is the federal lands management authority for the NTS, and NSTec is the Management and Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS has signs posted along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The Area 5 RWMS is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NTS (Figure 2), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. A Notice of Intent to operate the disposal site as a Class III site was submitted to the state of Nevada on January 28, 1994, and was acknowledged as being received in a letter to the NNSA/NSO on August 30, 1994. Interim approval to operate a Class III SWDS for regulated asbestiform low-level waste (ALLW) was authorized on August 12, 1996 (in letter from Paul Liebendorfer to Runore Wycoff), with operations to be conducted in accordance with the ''Management Plan for the Disposal of Low-Level Waste with Regulated Asbestos Waste.'' A requirement of the authorization was that on or before October 9, 1999, a permit was required to be issued. Because of NDEP and NNSA/NSO review cycles, the final permit was issued on April 5, 2000, for the operation of the Area 5 Low-Level Waste Disposal Site, utilizing Pit 7 (P07) as the designated disposal cell. The original permit applied only to Pit 7, with a total design capacity of 5,831 cubic yards (yd{sup 3}) (157,437 cubic feet [ft{sup 3}]). NNSA/NSO is expanding the SWDS to include the adjacent Upper Cell of Pit 6 (P06), with an additional capacity of 28,037 yd{sup 3} (756,999 ft{sup 3}) (Figure 3). The proposed total capacity of ALLW in Pit 7 and P06 will be approximately 33,870 yd{sup 3} (0.9 million ft{sup 3}). The site will be used for the disposal of regulated ALLW, small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. The only waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM). The term asbestiform is used throughout this document to describe this waste. Other TSCA waste (i.e., polychlorinated biphenyls [PCBs]) will not be accepted for disposal at the SWDS. The disposal site will be used as a depository of permissible waste generated both on site and off site. All generators designated by NNSA/NSO will be eligible to dispose regulated ALLW at the Asbestiform Low-Level Waste Disposal Site in accordance with the U.S. Department of Energy, Nevada Operations Office (DOE/NV) 325, Nevada Test Site Waste Acceptance Criteria (NTSWAC, current revision). Approval will be given by NNSA/NSO to generators that have successfully demonstrated through process knowledge (PK) and/or sampling and analysis that the waste is low-level, contains asbestiform material, and does not contain prohibited waste materials. Each waste stream will be approved through the Radioactive Waste Acceptance Program (RWAP), which ensures that the waste meets acceptance requirements outlined in the NTS Class III Permit and the NTSWAC.« less

  3. 75 FR 61228 - Board Meeting: Technical Lessons Gained From High-Level Nuclear Waste Disposal Efforts

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-10-04

    ... NUCLEAR WASTE TECHNICAL REVIEW BOARD Board Meeting: Technical Lessons Gained From High-Level... Waste Policy Amendments Act of 1987, the U.S. Nuclear Waste Technical Review Board will meet in Dulles... of Energy on technical issues and to review the technical validity of DOE activities related to...

  4. 78 FR 63251 - Board Meeting; November 20, 2013 in Washington, DC

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-23

    ... NUCLEAR WASTE TECHNICAL REVIEW BOARD Board Meeting; November 20, 2013 in Washington, DC The U.S. Nuclear Waste Technical Review Board will meet to discuss DOE SNF and HLW management research and... Policy Amendments Act of 1987, the U.S. Nuclear Waste Technical Review Board will hold a public meeting...

  5. 76 FR 77270 - Board Meeting; January 9, 2012, Arlington, VA

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-12

    ... NUCLEAR WASTE TECHNICAL REVIEW BOARD Board Meeting; January 9, 2012, Arlington, VA The U.S. Nuclear Waste Technical Review Board will meet to discuss integration efforts undertaken by DOE-NE and DOE... Amendments Act of 1987, the U.S. Nuclear Waste Technical Review Board will hold a public meeting in Arlington...

  6. 78 FR 64413 - Proposed Waste Confidence Rule and Draft Generic Environmental Impact Statement

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-29

    ... rescheduled the Waste Confidence public meetings it initially planned to hold in San Luis Obispo and Carlsbad... Confidence public meeting in San Luis Obispo will now be held on November 20, 2013. The rescheduled meetings... rescheduled Waste Confidence public meeting in San Luis Obispo, California, on November 20, 2013. This...

  7. 40 CFR 240.200 - Solid wastes accepted.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Solid wastes accepted. 240.200 Section 240.200 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES GUIDELINES FOR THE THERMAL PROCESSING OF SOLID WASTES Requirements and Recommended Procedures § 240.200 Solid...

  8. 40 CFR 240.200 - Solid wastes accepted.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 40 Protection of Environment 25 2011-07-01 2011-07-01 false Solid wastes accepted. 240.200 Section 240.200 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES GUIDELINES FOR THE THERMAL PROCESSING OF SOLID WASTES Requirements and Recommended Procedures § 240.200 Solid...

  9. Gaseous emissions during concurrent combustion of biomass and non-recyclable municipal solid waste

    PubMed Central

    2011-01-01

    Background Biomass and municipal solid waste offer sustainable sources of energy; for example to meet heat and electricity demand in the form of combined cooling, heat and power. Combustion of biomass has a lesser impact than solid fossil fuels (e.g. coal) upon gas pollutant emissions, whilst energy recovery from municipal solid waste is a beneficial component of an integrated, sustainable waste management programme. Concurrent combustion of these fuels using a fluidised bed combustor may be a successful method of overcoming some of the disadvantages of biomass (high fuel supply and distribution costs, combustion characteristics) and characteristics of municipal solid waste (heterogeneous content, conflict with materials recycling). It should be considered that combustion of municipal solid waste may be a financially attractive disposal route if a 'gate fee' value exists for accepting waste for combustion, which will reduce the net cost of utilising relatively more expensive biomass fuels. Results Emissions of nitrogen monoxide and sulphur dioxide for combustion of biomass are suppressed after substitution of biomass for municipal solid waste materials as the input fuel mixture. Interactions between these and other pollutants such as hydrogen chloride, nitrous oxide and carbon monoxide indicate complex, competing reactions occur between intermediates of these compounds to determine final resultant emissions. Conclusions Fluidised bed concurrent combustion is an appropriate technique to exploit biomass and municipal solid waste resources, without the use of fossil fuels. The addition of municipal solid waste to biomass combustion has the effect of reducing emissions of some gaseous pollutants. PMID:21284885

  10. The role of public communication in decision making for waste management infrastructure.

    PubMed

    Kirkman, Richard; Voulvoulis, Nikolaos

    2017-12-01

    Modern waste management provision seeks to meet challenging objectives and strategies while reflecting community aspirations and ensuring cost-effective compliance with statutory obligations. Its social acceptability, which affects both what systems (infrastructure) can be put in place and to what extent their implementation will be successful, is a multi-dimensional phenomenon, often not well understood. In light of the growing evidence that decisions to build new infrastructure are often contested by the public, there is a clear need to understand the role of scientific evidence in public perception, particularly as environmental infrastructure delivery is often objected to by the public on environmental grounds. In this paper the need for waste management infrastructure is reviewed, and the way its delivery in the UK has evolved is used as an example of the role of public perception in the planning and delivery of waste facilities. Findings demonstrate the vital role of public communication in waste management infrastructure delivery. Public perception must be taken into account early in the decision making process, with the public informed and engaged from the start. There is a pressing need for people not simply to accept but to understand and appreciate the need for infrastructure, the nature of infrastructure investments and development, the costs and the benefits involved, and the technological aspects. Scientific evidence and literacy have a critical role to play, facilitating public engagement in a process that empowers people, allowing them to define and handle challenges and influence decisions that will impact their lives. Problem ownership, and an increased probability of any solutions proposed being selected and implemented successfully are potential benefits of such approach. Copyright © 2016 Elsevier Ltd. All rights reserved.

  11. Risk perception and public acceptance toward a highly protested Waste-to-Energy facility.

    PubMed

    Ren, Xiangyu; Che, Yue; Yang, Kai; Tao, Yun

    2016-02-01

    The application of Waste-to-Energy treatment in Municipal Solid Waste faces strong protest by local communities, especially in cities with high population densities. This study introduces insight into the public awareness, acceptance and risk perception toward Waste-to-Energy through a structured questionnaire survey around a Waste-to-Energy facility in Shanghai, China. The Dichotomous-Choice contingent valuation method was applied to study the willingness to accept of residents as an indicator of risk perception and tolerance. The factors influencing risk perception and the protest response choice were analyzed. The geographical distributions of the acceptance of Waste-to-Energy facility and protest response were explored using geographical information systems. The findings of the research indicated an encouraging vision of promoting Waste-to-Energy, considering its benefits of renewable energy and the conservation of land. A high percentage of protest willingness to accept (50.94%) was highlighted with the effect of income, opinion about Waste-to-Energy, gender and perceived impact. The fuzzy classification among people with different opinions on compensation (valid 0, positive or protest willingness to accept) revealed the existing yet rejected demand of compensation among protesters. Geographical distribution in the public attitude can also be observed. Finally significant statistical relation between knowledge and risk perception indicates the need of risk communication, as well as involving public into whole management process. Copyright © 2015 Elsevier Ltd. All rights reserved.

  12. Assessment of Options for the Treatment of Nitrate Salt Wastes at Los Alamos National Laboratory

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Robinson, Bruce Alan; Funk, David John; Stevens, Patrice Ann

    2016-03-17

    This paper summarizes the methodology used to evaluate options for treatment of the remediated nitrate salt waste containers at Los Alamos National Laboratory. The method selected must enable treatment of the waste drums, which consist of a mixture of complex nitrate salts (oxidizer) improperly mixed with sWheat Scoop®1, an organic kitty litter and absorbent (fuel), in a manner that renders the waste safe, meets the specifications of waste acceptance criteria, and is suitable for transport and final disposal in the Waste Isolation Pilot Plant located in Carlsbad, New Mexico. A Core Remediation Team was responsible for comprehensively reviewing the options,more » ensuring a robust, defensible treatment recommendation. The evaluation process consisted of two steps. First, a prescreening process was conducted to cull the list on the basis for a decision of feasibility of certain potential options with respect to the criteria. Then, the remaining potential options were evaluated and ranked against each of the criteria in a consistent methodology. Numerical scores were established by consensus of the review team. Finally, recommendations were developed based on current information and understanding of the scientific, technical, and regulatory situation. A discussion of the preferred options and documentation of the process used to reach the recommended treatment options are presented.« less

  13. Secondary Waste Cast Stone Waste Form Qualification Testing Plan

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Westsik, Joseph H.; Serne, R. Jeffrey

    2012-09-26

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). Cast Stone – a cementitious waste form, has been selected for solidification of this secondary waste stream after treatment in the ETF. The secondary-waste Cast Stone waste form must be acceptablemore » for disposal in the IDF. This secondary waste Cast Stone waste form qualification testing plan outlines the testing of the waste form and immobilization process to demonstrate that the Cast Stone waste form can comply with the disposal requirements. Specifications for the secondary-waste Cast Stone waste form have not been established. For this testing plan, Cast Stone specifications are derived from specifications for the immobilized LAW glass in the WTP contract, the waste acceptance criteria for the IDF, and the waste acceptance criteria in the IDF Permit issued by the State of Washington. This testing plan outlines the testing needed to demonstrate that the waste form can comply with these waste form specifications and acceptance criteria. The testing program must also demonstrate that the immobilization process can be controlled to consistently provide an acceptable waste form product. This testing plan also outlines the testing needed to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support performance assessment analyses of the long-term environmental impact of the secondary-waste Cast Stone waste form in the IDF« less

  14. Performance assessment for continuing and future operations at Solid Waste Storage Area 6

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1994-02-01

    This radiological performance assessment for the continued disposal operations at Solid Waste Storage Area 6 (SWSA 6) on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the requirements of the US DOE. The analysis of SWSA 6 required the use of assumptions to supplement the available site data when the available data were incomplete for the purpose of analysis. Results indicate that SWSA 6 does not presently meet the performance objectives of DOE Order 5820.2A. Changes in operations and continued work on the performance assessment are expected to demonstrate compliance with the performance objectives for continuingmore » operations at the Interim Waste Management Facility (IWMF). All other disposal operations in SWSA 6 are to be discontinued as of January 1, 1994. The disposal units at which disposal operations are discontinued will be subject to CERCLA remediation, which will result in acceptable protection of the public health and safety.« less

  15. 40 CFR 761.202 - EPA identification numbers.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... PROHIBITIONS PCB Waste Disposal Records and Reports § 761.202 EPA identification numbers. (a) General. Any... identification number from EPA. (4) A disposer of PCB waste shall not accept any PCB waste for disposal without... disposal facility or mobile treatment unit shall not accept waste unless the disposer has received an EPA...

  16. Secondary Waste Form Down Selection Data Package – Ceramicrete

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cantrell, Kirk J.; Westsik, Joseph H.

    2011-08-31

    As part of high-level waste pretreatment and immobilized low activity waste processing, liquid secondary wastes will be generated that will be transferred to the Effluent Treatment Facility on the Hanford Site for further treatment. These liquid secondary wastes will be converted to stable solid waste forms that will be disposed in the Integrated Disposal Facility. Currently, four waste forms are being considered for stabilization and solidification of the liquid secondary wastes. These waste forms are Cast Stone, Ceramicrete, DuraLith, and Fluidized Bed Steam Reformer. The preferred alternative will be down selected from these four waste forms. Pacific Northwest National Laboratorymore » is developing data packages to support the down selection process. The objective of the data packages is to identify, evaluate, and summarize the existing information on the four waste forms being considered for stabilization and solidification of the liquid secondary wastes. The information included will be based on information available in the open literature and from data obtained from testing currently underway. This data package is for the Ceramicrete waste form. Ceramicrete is a relatively new engineering material developed at Argonne National Laboratory to treat radioactive and hazardous waste streams (e.g., Wagh 2004; Wagh et al. 1999a, 2003; Singh et al. 2000). This cement-like waste form can be used to treat solids, liquids, and sludges by chemical immobilization, microencapsulation, and/or macroencapsulation. The Ceramicrete technology is based on chemical reaction between phosphate anions and metal cations to form a strong, dense, durable, low porosity matrix that immobilizes hazardous and radioactive contaminants as insoluble phosphates and microencapsulates insoluble radioactive components and other constituents that do not form phosphates. Ceramicrete is a type of phosphate-bonded ceramic, which are also known as chemically bonded phosphate ceramics. The Ceramicrete binder is formed through an acid-base reaction between calcined magnesium oxide (MgO; a base) and potassium hydrogen phosphate (KH{sub 2}PO{sub 4}; an acid) in aqueous solution. The reaction product sets at room temperature to form a highly crystalline material. During the reaction, the hazardous and radioactive contaminants also react with KH{sub 2}PO{sub 4} to form highly insoluble phosphates. In this data package, physical property and waste acceptance data for Ceramicrete waste forms fabricated with wastes having compositions that were similar to those expected for secondary waste effluents, as well as secondary waste effluent simulants from the Hanford Tank Waste Treatment and Immobilization Plant were reviewed. With the exception of one secondary waste form formulation (25FA+25 W+1B.A. fabricated with the mixed simulant did not meet the compressive strength requirement), all the Ceramicrete waste forms that were reviewed met or exceeded Integrated Disposal Facility waste acceptance criteria.« less

  17. DOE Office of Scientific and Technical Information (OSTI.GOV)

    NSTec Environmental Management

    The proposed Mixed Waste Storage Unit (MWSU) will be located within the Area 5 Radioactive Waste Management Complex (RWMC). Existing facilities at the RWMC will be used to store low-level mixed waste (LLMW). Storage is required to accommodate offsite-generated LLMW shipped to the Nevada Test Site (NTS) for disposal in the new Mixed Waste Disposal Unit (MWDU) currently in the design/build stage. LLMW generated at the NTS (onsite) is currently stored on the Transuranic (TRU) Pad (TP) in Area 5 under a Mutual Consent Agreement (MCA) with the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). When themore » proposed MWSU is permitted, the U.S. Department of Energy (DOE) will ask that NDEP revoke the MCA and onsite-generated LLMW will fall under the MWSU permit terms and conditions. The unit will also store polychlorinated biphenyl (PCB) waste and friable and non-friable asbestos waste that meets the acceptance criteria in the Waste Analysis Plan (Exhibit 2) for disposal in the MWDU. In addition to Resource Conservation and Recovery Act (RCRA) requirements, the proposed MWSU will also be subject to Department of Energy (DOE) orders and other applicable state and federal regulations. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational RCRA units at the NTS and their respective regulatory status.« less

  18. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hayes, Timothy; Nelson, Roger

    The Department of Energy (DOE) and the National Nuclear Security Administration (NNSA) manages defense nuclear material that has been determined to be excess to programmatic needs and declared waste. When these wastes contain plutonium, they almost always meet the definition of defense transuranic (TRU) waste and are thus eligible for disposal at the Waste Isolation Pilot Plant (WIPP). The DOE operates the WIPP in a manner that physical protections for attractiveness level D or higher special nuclear material (SNM) are not the normal operating condition. Therefore, there is currently a requirement to terminate safeguards before disposal of these wastes atmore » the WIPP. Presented are the processes used to terminate safeguards, lessons learned during the termination process, and how these approaches might be useful for future defense TRU waste needing safeguards termination prior to shipment and disposal at the WIPP. Also described is a new criticality control container, which will increase the amount of fissile material that can be loaded per container, and how it will save significant taxpayer dollars. Retrieval, compliant packaging and shipment of retrievably stored legacy TRU waste has dominated disposal operations at WIPP since it began operations 12 years ago. But because most of this legacy waste has successfully been emplaced in WIPP, the TRU waste clean-up focus is turning to newly-generated TRU materials. A major component will be transuranic SNM, currently managed in safeguards-protected vaults around the weapons complex. As DOE and NNSA continue to consolidate and shrink the weapons complex footprint, it is expected that significant quantities of transuranic SNM will be declared surplus to the nation's needs. Safeguards termination of SNM varies due to the wide range of attractiveness level of the potential material that may be directly discarded as waste. To enhance the efficiency of shipping waste with high TRU fissile content to WIPP, DOE designed an over-pack container, similar to the pipe component, called the criticality control over-pack, which will significantly enhance the efficiency of disposal. Hundreds of shipments of transuranic SNM, suitably packaged to meet WIPP waste acceptance criteria and with safeguards terminated have been successfully emplaced at WIPP (primarily from the Rocky Flats site clean-up) since WIPP opened. DOE expects that thousands more may eventually result from SNM consolidation efforts throughout the weapons complex. (authors)« less

  19. Public acceptance for centralized storage and repositories of low-level waste session (Panel)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Lutz, H.R.

    1995-12-31

    Participants from various parts of the world will provide a summary of their particular country`s approach to low-level waste management and the cost of public acceptance for low-level waste management facilities. Participants will discuss the number, geographic location, and type of low-level waste repositories and centralized storage facilities located in their countries. Each will discuss the amount, distribution, and duration of funds to gain public acceptance of these facilities. Participants will provide an estimated $/meter for centralized storage facilities and repositories. The panel will include a brief discussion about the ethical aspects of public acceptance costs, approaches for negotiating acceptance,more » and lessons learned in each country. The audience is invited to participate in the discussion.« less

  20. Use of acceptable knowledge to demonstrate TRAMPAC compliance

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Whitworth, J.; Becker, B.; Guerin, D.

    2004-01-01

    Recently, Los Alamos National Laboratory-Carlsbad Operations (LANL-CO) has supported the Central Characterization Project (CCP) managed by the U.S. Department of Energy (DOE) in the shipment of transuranic (TRU) waste from various small-quantity TRU waste generators to hub sites or other DOE sites in TRUPACT-II shipping containers. This support has involved using acceptable knowledge (AK) to demonstrate compliance with various requirements of Revision 19 of the TRUPACT-II Authorized Methods of Payload Compliance (TRAMPAC). LANL-CO has worked to facilitate TRUPACT-II shipments from the University of Missouri Research Reactor (MURR) and Lovelace Respiratory Research Institute (LRRI) to Argonne National Laboratory-East (ANL-E) and Losmore » Alamos National Laboratory (LANL), respectively. The latter two sites have TRU waste certification programs approved to ship waste to the Waste Isolation Pilot Plant (WIPP) for disposal. In each case, AK was used to satisfy the necessary information to ship the waste to other DOE facilities. For the purposes of intersite shipment, AK provided data to WIPP Waste Information System (WWIS) transportation modules to ensure that required information was obtained prior to TRUPACT-II shipments. The WWIS modules were used for the intersite shipments, not to enter certification data into WWIS, but rather to take advantage of a validated system to ensure that the containers to be shipped were compliant with TRAMPAC requirements, particularly in the evaluation of quantitative criteria. LANL-CO also assisted with a TRAMPAC compliance demonstration for homogeneous waste containers shipped in TRUPACT-II containers from ANL-E to Idaho National Engineering and Environmental Laboratory (INEEL) for the purpose of core sampling. The basis for the TRAMPAC compliance determinations was AK regarding radiological composition, chemical composition, TRU waste container packaging, and absence of prohibited items. Also, even in the case where AK is not used to fully demonstrate TRAMPAC compliance, it may be used to identify problem areas for shippability of different waste streams. An example is the case of Pu-238-contaminated waste from the Savannah River Site that had a low probability of meeting decay heat limits and aspiration times due to several factors including large numbers of confinement layers. This paper will outline 17 TRAMPAC compliance criteria assessed and the types of information used to show compliance with all criteria other than dose rate and container weight, which are normally easily measured at load preparation.« less

  1. The role of acceptable knowledge in transuranic waste disposal operations - 11117

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Chancellor, Christopher John; Nelson, Roger

    2010-11-08

    The Acceptable Knowledge (AK) process plays a key role in the delineation of waste streams destined for the Waste Isolation Pilot Plant (WIPP). General Electric's Vallecitos Nuclear Center (GEVNC) provides for an ideal case study of the application of AK in a multiple steward environment. In this review we will elucidate the pivotal role Acceptable Knowledge played in segregating Department of Energy (DOE) responsibilities from a commercial facility. The Acceptable Knowledge process is a necessary component of waste characterization that determines whether or not a waste stream may be considered for disposal at the WIPP site. This process may bemore » thought of as an effort to gain a thorough understanding of the waste origin, chemical content, and physical form gleaned by the collection of documentation that concerns generator/storage site history, mission, and operations; in addition to waste stream specific information which includes the waste generation process, the waste matrix, the quantity of waste concerned, and the radiological and chemical make up of the waste. The collection and dissemination of relevant documentation is the fundamental requirement for the AK process to work. Acceptable Knowledge is the predominant process of characterization and, therefore, a crucial part of WIPP's transuranic waste characterization program. This characterization process, when conducted to the standards set forth in WIPP's operating permit, requires confirmation/verification by physical techniques such as Non-Destructive Examination (NDE), Visual Examination (VE), and Non-Destructive Assay (NDA). These physical characterization techniques may vary in their appropriateness for a given waste stream; however, nothing will allow the substitution or exclusion of AK. Beyond the normal scope of operations, AK may be considered, when appropriate, a surrogate for the physical characterization techniques in a procedure that appeals to concepts such As Low As Reasonably Achievable (ALARA) and budgetary savings. This substitution is referred to as an Acceptable Knowledge Sufficiency Determination. With a Sufficiency Determination Request, AK may supplant the need for one or all of the physical analysis methods. This powerful procedure may be used on a scale as small as a single container to that of a vast waste stream. Only under the most stringent requirements will an AK Sufficiency Determination be approved by the regulators and, to date, only six such Sufficiency Determinations have been approved. Although Acceptable Knowledge is legislated into the operational procedures of the WIPP facility there is more to it than compliance. AK is not merely one of a long list of requirements in the characterization and verification of transuranic (TRU) waste destined for the WIPP. Acceptable Knowledge goes beyond the regulatory threshold by offering a way to reduce risk, cost, time, and uncertainty on its own laurels. Therefore, AK alone can be argued superior to any other waste characterization technique.« less

  2. Sustainable water management in rural and peri-urban areas: what technology do we need to meet the UN millennium development goals?

    PubMed

    Wilderer, P A

    2005-01-01

    Installation of advanced urban water management systems is one of the most important first steps in the attempt to overcome poverty on earth, outbreak of diseases, crime and even terrorism. Because world wide application of traditional water supply, sewerage and wastewater treatment technology requires financial resources which are basically not available within a reasonable short time frame novel solutions must be found, developed and implemented. The combination of high-tech on-site treatment of the various waste streams generated in households, enterprises and industrial sites, and reuse of the valuable materials obtained from the treatment plants, including the purified water, is one of the options which is investigated by various groups of researchers and technology developers, nowadays. This concept may help meeting the UN Millennium Development Goals, provided people are ready to accept this new way of dealing with household wastes. Education is necessary to build up the foundation which modern water technology can be based upon. In parallel, tailored modifications are to be considered to satisfy the specific demands of local communities. In this context, female participation appears to be extremely important in the decision making process.

  3. CONCEPTUAL BASIS FOR NATURAL ATTENUATION (NA) ...

    EPA Pesticide Factsheets

    As used in enforcement actions at hazardous waste sites by U.S. EPA, monitored natural attenuation is a remedy fully equivalent to any other remedy. The acceptance of MNA is based on three lines of evidence: historical ground water and/or soil chemistry data that demonstrates a trend of declining contaminant concentration, 2. hydrogeologic and geochemical data that demonstrate NA processes and rates, and 3. Field or microcosm studies. MNA is appropriate as remedial approach only where it can be demonstrated to achieve remedial objectives within reasonable time frame, and meets the applicable remedy selection criteria for the particular regulatory program. To inform the public.

  4. Closure Plan for the Area 5 Radioactive Waste Management Site at the Nevada Test Site

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NSTec Environmental Management

    The Area 5 Radioactive Waste Management Site (RMWS) at the Nevada Test Site (NTS) is managed and operated by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the preliminary closure plan for the Area 5 RWMS at the NTS that was presented in the Integrated Closure and Monitoring Plan (DOE, 2005a). The major updates to the plan include a new closure schedule, updated closure inventory, updated site and facility characterization data, the Title II engineering cover design, and the closure processmore » for the 92-Acre Area of the RWMS. The format and content of this site-specific plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). This interim closure plan meets closure and post-closure monitoring requirements of the order DOE O 435.1, manual DOE M 435.1-1, Title 40 Code of Federal Regulations (CFR) Part 191, 40 CFR 265, Nevada Administrative Code (NAC) 444.743, and Resource Conservation and Recovery Act (RCRA) requirements as incorporated into NAC 444.8632. The Area 5 RWMS accepts primarily packaged low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform low-level waste (ALLW) for disposal in excavated disposal cells.« less

  5. Special Analysis of Transuranic Waste in Trench T04C at the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nye County, Nevada, Revision 1

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Greg Shott, Vefa Yucel, Lloyd Desotell

    2008-05-01

    This Special Analysis (SA) was prepared to assess the potential impact of inadvertent disposal of a limited quantity of transuranic (TRU) waste in classified Trench 4 (T04C) within the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS). The Area 5 RWMS is a low-level radioactive waste disposal site in northern Frenchman Flat on the Nevada Test Site (NTS). The Area 5 RWMS is regulated by the U.S. Department of Energy (DOE) under DOE Order 435.1 and DOE Manual (DOE M) 435.1-1. The primary objective of the SA is to evaluate if inadvertent disposal of limitedmore » quantities of TRU waste in a shallow land burial trench at the Area 5 RWMS is in compliance with the existing, approved Disposal Authorization Statement (DAS) issued under DOE M 435.1-1. In addition, supplemental analyses are performed to determine if there is reasonable assurance that the requirements of Title 40, Code of Federal Regulations (CFR), Part 191, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes, can be met. The 40 CFR 191 analyses provide supplemental information regarding the risk to human health and the environment of leaving the TRU waste in T04C. In 1989, waste management personnel reviewing classified materials records discovered that classified materials buried in trench T04C at the Area 5 RWMS contained TRU waste. Subsequent investigations determined that a total of 102 55-gallon drums of TRU waste from Rocky Flats were buried in trench T04C in 1986. The disposal was inadvertent because unclassified records accompanying the shipment indicated that the waste was low-level. The exact location of the TRU waste in T04C was not recorded and is currently unknown. Under DOE M 435.1-1, Chapter IV, Section P.5, low-level waste disposal facilities must obtain a DAS. The DAS specifies conditions that must be met to operate within the radioactive waste management basis, consisting of a performance assessment (PA), composite analysis (CA), closure plan, monitoring plan, waste acceptance criteria, and a PA/CA maintenance plan. The DOE issued a DAS for the Area 5 RWMS in 2000. The Area 5 RWMS DAS was, in part, based on review of a CA as required under DOE M 435.1-1, Chapter IV, Section P.(3). A CA is a radiological assessment required for DOE waste disposed before 26 September 1988 and includes the radiological dose from all sources of radioactive material interacting with all radioactive waste disposed at the Area 5 RWMS. The approved Area 5 RWMS CA, which includes the inventory of TRU waste in T04C, indicates that the Area 5 RWMS waste inventory and all interacting sources of radioactive material can meet the 0.3 mSv dose constraint. The composite analysis maximum annual dose for a future resident at the Area 5 RWMS was estimated to be 0.01 mSv at 1,000 years. Therefore, the inadvertent disposal of TRU in T04C is protective of the public and the environment, and compliant with all the applicable requirements in DOE M 435.1-1 and the DAS. The U.S. Environmental Protection Agency promulgated 40 CFR 191 to establish standards for the planned disposal of spent nuclear fuel, high level, and transuranic wastes in geologic repositories. Although not required, the National Nuclear Security Administration Nevada Site Office requested a supplemental analysis to evaluate the likelihood that the inadvertent disposal of TRU waste in T04C meets the requirements of 40 CFR 191. The SA evaluates the likelihood of meeting the 40 CFR 191 containment requirements (CRs), assurance requirements, individual protection requirements (IPRs), and groundwater protection standards. The results of the SA indicate that there is a reasonable expectation of meeting all the requirements of 40 CFR 191. The conclusion of the SA is that the Area 5 RWMS with the TRU waste buried in T04C is in compliance with all requirements in DOE M 435.1-1 and the DAS. Compliance with the DAS is demonstrated by the results of the Area 5 RWMS CA. Supplemental analyses in the SA indicate there is a reasonable expectation that the TRU in T04C can meet all the requirements of 40 CFR 191. Therefore, inadvertent disposal of a limited quantity of TRU in a shallow land burial trench at the Area 5 RWMS does not pose a significant risk to the public and the environment.« less

  6. Infectious waste feed system

    DOEpatents

    Coulthard, E. James

    1994-01-01

    An infectious waste feed system for comminuting infectious waste and feeding the comminuted waste to a combustor automatically without the need for human intervention. The system includes a receptacle for accepting waste materials. Preferably, the receptacle includes a first and second compartment and a means for sealing the first and second compartments from the atmosphere. A shredder is disposed to comminute waste materials accepted in the receptacle to a predetermined size. A trough is disposed to receive the comminuted waste materials from the shredder. A feeding means is disposed within the trough and is movable in a first and second direction for feeding the comminuted waste materials to a combustor.

  7. Biodiesel production from Jatropha oil by catalytic and non-catalytic approaches: an overview.

    PubMed

    Juan, Joon Ching; Kartika, Damayani Agung; Wu, Ta Yeong; Hin, Taufiq-Yap Yun

    2011-01-01

    Biodiesel (fatty acids alkyl esters) is a promising alternative fuel to replace petroleum-based diesel that is obtained from renewable sources such as vegetable oil, animal fat and waste cooking oil. Vegetable oils are more suitable source for biodiesel production compared to animal fats and waste cooking since they are renewable in nature. However, there is a concern that biodiesel production from vegetable oil would disturb the food market. Oil from Jatropha curcas is an acceptable choice for biodiesel production because it is non-edible and can be easily grown in a harsh environment. Moreover, alkyl esters of jatropha oil meet the standard of biodiesel in many countries. Thus, the present paper provides a review on the transesterification methods for biodiesel production using jatropha oil as feedstock. Crown Copyright © 2010. Published by Elsevier Ltd. All rights reserved.

  8. The Department of Energy`s Remedial Action Assessment System (RAAS): Decision support tools for performing streamlined feasibility studies

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    White, M.K.

    1994-06-01

    The United States Department of Energy (DOE) faces the major task of cleaning up hundreds of waste sites across the nation, which will require completion of a large number of remedial investigation/feasibility studies (RI/FSs). The intent of each RI/FS is to characterize the waste problems and environmental conditions at the operable unit level, segment the remediation problem into manageable medium-specific and contaminant-specific pieces, define corresponding remediation objectives, and identify remedial response actions to satisfy those objectives. The RI/FS team can then identify combinations of remediation technologies that will meet the remediation objectives. Finally, the team must evaluate these remedial alternativesmore » in terms of effectiveness, implementability, cost, and acceptability. The Remedial Action Assessment System (RAAS) is being developed by Pacific Northwest Laboratory (PNL) to support DOE in this effort.« less

  9. Effective dialogue: enhanced public engagement as a legitimising tool for municipal waste management decision-making.

    PubMed

    Garnett, Kenisha; Cooper, Tim

    2014-12-01

    The complexity of municipal waste management decision-making has increased in recent years, accompanied by growing scrutiny from stakeholders, including local communities. This complexity reflects a socio-technical framing of the risks and social impacts associated with selecting technologies and sites for waste treatment and disposal facilities. Consequently there is growing pressure on local authorities for stakeholders (including communities) to be given an early opportunity to shape local waste policy in order to encourage swift planning, development and acceptance of the technologies needed to meet statutory targets to divert waste from landfill. This paper presents findings from a research project that explored the use of analytical-deliberative processes as a legitimising tool for waste management decision-making. Adopting a mixed methods approach, the study revealed that communicating the practical benefits of more inclusive forms of engagement is proving difficult even though planning and policy delays are hindering development and implementation of waste management infrastructure. Adopting analytical-deliberative processes at a more strategic level will require local authorities and practitioners to demonstrate how expert-citizen deliberations may foster progress in resolving controversial issues, through change in individuals, communities and institutions. The findings suggest that a significant shift in culture will be necessary for local authorities to realise the potential of more inclusive decision processes. This calls for political actors and civic society to collaborate in institutionalising public involvement in both strategic and local planning structures. Copyright © 2014 Elsevier Ltd. All rights reserved.

  10. (Low-level waste disposal facility siting and site characterization)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mezga, L.J.; Ketelle, R.H.; Pin, F.G.

    A US team consisting of representatives of Oak Ridge National Laboratory (ORNL), Savannah River Plant (SRP), Savannah river Laboratory (SRL), and the Department of Energy Office of Defense Waste and Byproducts Management participated in the fourth meeting held under the US/French Radioactive Waste Management Agreement between the US Department of Energy and the Commissariat a l'Energie Atomique. This meeting, held at Agence Nationale pour les Gestion des Dechets Radioactifs' (ANDRA's) Headquarters in Paris, was a detailed, technical topical workshop focusing on Low-Level Waste Disposal Facility Siting and Site Characterization.'' The meeting also included a visit to the Centre de lamore » Manche waste management facility operated by ANDRA to discuss and observe the French approach to low-level waste management. The final day of the meeting was spent at the offices of Societe Generale pour les Techniques Nouvelles (SGN) discussing potential areas of future cooperation and exchange. 20 figs.« less

  11. Environmental assessment: Davis Canyon site, Utah

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    none,

    1986-05-01

    In February 1983, the US Department of Energy (DOE) identified the Davis Canyon site in Utah as one of the nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Davis Canyon site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories. These evaluations were reported in draft environmental assessments (EAs), which were issued for public review and comment. After considering the comments received on the draft EAs, the DOEmore » prepared the final EA. The Davis Canyon site is in the Paradox Basin, which is one of five distinct geohydrologic settings considering for the first repository. This setting contains one other potentially acceptable site -- the Lavender Canyon site. Although the Lavender Canyon site is suitable for site characterization, the DOE has concluded that the Davis Canyon site is the preferred site in the Paradox Basin. On the basis of the evaluations reported in this EA, the DOE has found that the Davis Canyon site is not disqualified under the guidelines. Furthermore, the DOE has found that the site is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is nominating the Davis Canyon site as one of five sites suitable for characterization.« less

  12. Development of iron phosphate ceramic waste form to immobilize radioactive waste solution

    NASA Astrophysics Data System (ADS)

    Choi, Jongkwon; Um, Wooyong; Choung, Sungwook

    2014-09-01

    The objective of this research was to develop an iron phosphate ceramic (IPC) waste form using converter slag obtained as a by-product of the steel industry as a source of iron instead of conventional iron oxide. Both synthetic off-gas scrubber solution containing technetium-99 (or Re as a surrogate) and LiCl-KCl eutectic salt, a final waste solution from pyrochemical processing of spent nuclear fuel, were used as radioactive waste streams. The IPC waste form was characterized for compressive strength, reduction capacity, chemical durability, and contaminant leachability. Compressive strengths of the IPC waste form prepared with different types of waste solutions were 16 MPa and 19 MPa for LiCl-KCl eutectic salt and the off-gas scrubber simulant, respectively, which meet the minimum compressive strength of 3.45 MPa (500 psi) for waste forms to be accepted into the radioactive waste repository. The reduction capacity of converter slag, a main dry ingredient used to prepare the IPC waste form, was 4136 meq/kg by the Ce(IV) method, which is much higher than those of the conventional Fe oxides used for the IPC waste form and the blast furnace slag materials. Average leachability indexes of Tc, Li, and K for the IPC waste form were higher than 6.0, and the IPC waste form demonstrated stable durability even after 63-day leaching. In addition, the Toxicity Characteristic Leach Procedure measurements of converter slag and the IPC waste form with LiCl-KCl eutectic salt met the universal treatment standard of the leachability limit for metals regulated by the Resource Conservation and Recovery Act. This study confirms the possibility of development of the IPC waste form using converter slag, showing its immobilization capability for radionuclides in both LiCl-KCl eutectic salt and off-gas scrubber solutions with significant cost savings.

  13. Development of iron phosphate ceramic waste form to immobilize radioactive waste solution

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Choi, Jongkwon; Um, Wooyong; Choung, Sungwook

    The objective of this research was to develop an iron phosphate ceramic (IPC) waste form using converter slag obtained as a by-product of the steel industry as a source of iron instead of conventional iron oxide. Both synthetic off-gas scrubber solution containing technetium-99 (or Re as a surrogate) and LiCl-KCl eutectic salt, a final waste solution from pyrochemical processing of spent nuclear fuel, were used as radioactive waste streams. The IPC waste form was characterized for compressive strength, reduction capacity, chemical durability, and contaminant leachability. Compressive strengths of the IPC waste form prepared with different types of waste solutions weremore » 16 MPa and 19 MPa for LiCl-KCl eutectic salt and the off-gas scrubber simulant, respectively, which meet the minimum compressive strength of 3.45 MPa (500 psi) for waste forms to be accepted into the radioactive waste repository. The reduction capacity of converter slag, a main dry ingredient used to prepare the IPC waste form, was 4,136 meq/kg by the Ce(IV) method, which is much higher than those of the conventional Fe oxides used for the IPC waste form and the blast furnace slag materials. Average leachability indexes of Tc, Li, and K for the IPC waste form were higher than 6.0, and the IPC waste form demonstrated stable durability even after 63-day leaching. In addition, the Toxicity Characteristic Leach Procedure measurements of converter slag and the IPC waste form with LiCl-KCl eutectic salt met the universal treatment standard of the leachability limit for metals regulated by the Resource Conservation and Recovery Act. This study confirms the possibility of development of the IPC waste form using converter slag, showing its immobilization capability for radionuclides in both LiCl-KCl eutectic salt and off-gas scrubber solutions with significant cost savings.« less

  14. Definition of an Acceptable Glass composition Region (AGCR) via an Index System and a Partitioning Function

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Peeler, D. K.; Taylor, A. S.; Edwards, T.B.

    2005-06-26

    The objective of this investigation was to appeal to the available ComPro{trademark} database of glass compositions and measured PCTs that have been generated in the study of High Level Waste (HLW)/Low Activity Waste (LAW) glasses to define an Acceptable Glass Composition Region (AGCR). The term AGCR refers to a glass composition region in which the durability response (as defined by the Product Consistency Test (PCT)) is less than some pre-defined, acceptable value that satisfies the Waste Acceptance Product Specifications (WAPS)--a value of 10 g/L was selected for this study. To assess the effectiveness of a specific classification or index systemmore » to differentiate between acceptable and unacceptable glasses, two types of errors (Type I and Type II errors) were monitored. A Type I error reflects that a glass with an acceptable durability response (i.e., a measured NL [B] < 10 g/L) is classified as unacceptable by the system of composition-based constraints. A Type II error occurs when a glass with an unacceptable durability response is classified as acceptable by the system of constraints. Over the course of the efforts to meet this objective, two approaches were assessed. The first (referred to as the ''Index System'') was based on the use of an evolving system of compositional constraints which were used to explore the possibility of defining an AGCR. This approach was primarily based on ''glass science'' insight to establish the compositional constraints. Assessments of the Brewer and Taylor Index Systems did not result in the definition of an AGCR. Although the Taylor Index System minimized Type I errors which allowed access to composition regions of interest to improve melt rate or increase waste loadings for DWPF as compared to the current durability model, Type II errors were also committed. In the context of the application of a particular classification system in the process control system, Type II errors are much more serious than Type I errors. A Type I error only reflects that the particular constraint system being used is overly conservative (i.e., its application restricts access to glasses that have an acceptable measured durability response). A Type II error results in a more serious misclassification that could result in allowing the transfer of a Slurry Mix Evaporator (SME) batch to the melter, which is predicted to produce a durable product based on the specific system applied but in reality does not meet the defined ''acceptability'' criteria. More specifically, a nondurable product could be produced in DWPF. Given the presence of Type II errors, the Index System approach was deemed inadequate for further implementation consideration at the DWPF. The second approach (the JMP partitioning process) was purely data driven and empirically derived--glass science was not a factor. In this approach, the collection of composition--durability data in ComPro was sequentially partitioned or split based on the best available specific criteria and variables. More specifically, the JMP software chose the oxide (Al{sub 2}O{sub 3} for this dataset) that most effectively partitions the PCT responses (NL [B]'s)--perhaps not 100% effective based on a single oxide. Based on this initial split, a second request was made to split a particular set of the ''Y'' values (good or bad PCTs based on the 10 g/L limit) based on the next most critical ''X'' variable. This ''splitting'' or ''partitioning'' process was repeated until an AGCR was defined based on the use of only 3 oxides (Al{sub 2}O{sub 3}, CaO, and MgO) and critical values of > 3.75 wt% Al{sub 2}O{sub 3}, {ge} 0.616 wt% CaO, and < 3.521 wt% MgO. Using this set of criteria, the ComPro database was partitioned in which no Type II errors were committed. The automated partitioning function screened or removed 978 of the 2406 ComPro glasses which did cause some initial concerns regarding excessive conservatism regardless of its ability to identify an AGCR. However, a preliminary review of glasses within the 1428 ''acceptable'' glasses defining the ACGR includes glass systems of interest to support the accelerated mission.« less

  15. EM-31 RETRIEVAL KNOWLEDGE CENTER MEETING REPORT: MOBILIZE AND DISLODGE TANK WASTE HEELS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Fellinger, A.

    2010-02-16

    The Retrieval Knowledge Center sponsored a meeting in June 2009 to review challenges and gaps to retrieval of tank waste heels. The facilitated meeting was held at the Savannah River Research Campus with personnel broadly representing tank waste retrieval knowledge at Hanford, Savannah River, Idaho, and Oak Ridge. This document captures the results of this meeting. In summary, it was agreed that the challenges to retrieval of tank waste heels fell into two broad categories: (1) mechanical heel waste retrieval methodologies and equipment and (2) understanding and manipulating the heel waste (physical, radiological, and chemical characteristics) to support retrieval optionsmore » and subsequent processing. Recent successes and lessons from deployments of the Sand and Salt Mantis vehicles as well as retrieval of C-Area tanks at Hanford were reviewed. Suggestions to address existing retrieval approaches that utilize a limited set of tools and techniques are included in this report. The meeting found that there had been very little effort to improve or integrate the multiple proven or new techniques and tools available into a menu of available methods for rapid insertion into baselines. It is recommended that focused developmental efforts continue in the two areas underway (low-level mixing evaluation and pumping slurries with large solid materials) and that projects to demonstrate new/improved tools be launched to outfit tank farm operators with the needed tools to complete tank heel retrievals effectively and efficiently. This document describes the results of a meeting held on June 3, 2009 at the Savannah River Site in South Carolina to identify technology gaps and potential technology solutions to retrieving high-level waste (HLW) heels from waste tanks within the complex of sites run by the U. S. Department of Energy (DOE). The meeting brought together personnel with extensive tank waste retrieval knowledge from DOE's four major waste sites - Hanford, Savannah River, Idaho, and Oak Ridge. The meeting was arranged by the Retrieval Knowledge Center (RKC), which is a technology development project sponsored by the Office of Technology Innovation & Development - formerly the Office of Engineering and Technology - within the DOE Office of Environmental Management (EM).« less

  16. Final waste forms project: Performance criteria for phase I treatability studies

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Gilliam, T.M.; Hutchins, D.A.; Chodak, P. III

    1994-06-01

    This document defines the product performance criteria to be used in Phase I of the Final Waste Forms Project. In Phase I, treatability studies will be performed to provide {open_quotes}proof-of-principle{close_quotes} data to establish the viability of stabilization/solidification (S/S) technologies. This information is required by March 1995. In Phase II, further treatability studies, some at the pilot scale, will be performed to provide sufficient data to allow treatment alternatives identified in Phase I to be more fully developed and evaluated, as well as to reduce performance uncertainties for those methods chosen to treat a specific waste. Three main factors influence themore » development and selection of an optimum waste form formulation and hence affect selection of performance criteria. These factors are regulatory, process-specific, and site-specific waste form standards or requirements. Clearly, the optimum waste form formulation will require consideration of performance criteria constraints from each of the three categories. Phase I will focus only on the regulatory criteria. These criteria may be considered the minimum criteria for an acceptable waste form. In other words, a S/S technology is considered viable only if it meet applicable regulatory criteria. The criteria to be utilized in the Phase I treatability studies were primarily taken from Environmental Protection Agency regulations addressed in 40 CFR 260 through 265 and 268; and Nuclear Regulatory Commission regulations addressed in 10 CFR 61. Thus the majority of the identified criteria are independent of waste form matrix composition (i.e., applicable to cement, glass, organic binders etc.).« less

  17. 40 CFR 267.202 - What special requirements must I meet for ignitable or reactive wastes?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... material no longer meets the definition of ignitable or reactive waste under § 261.21 or § 261.23 of this... requirements for the maintenance of protective distances between the waste management area and any public ways... for ignitable or reactive wastes? 267.202 Section 267.202 Protection of Environment ENVIRONMENTAL...

  18. 40 CFR 60.758 - Recordkeeping requirements.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... Waste Landfills § 60.758 Recordkeeping requirements. (a) Except as provided in § 60.752(b)(2)(i)(B... triggered § 60.752(b), the current amount of solid waste in-place, and the year-by-year waste acceptance... electronic formats are acceptable. (b) Except as provided in § 60.752(b)(2)(i)(B), each owner or operator of...

  19. 40 CFR 60.758 - Recordkeeping requirements.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... Waste Landfills § 60.758 Recordkeeping requirements. (a) Except as provided in § 60.752(b)(2)(i)(B... triggered § 60.752(b), the current amount of solid waste in-place, and the year-by-year waste acceptance... electronic formats are acceptable. (b) Except as provided in § 60.752(b)(2)(i)(B), each owner or operator of...

  20. 40 CFR 60.758 - Recordkeeping requirements.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... Waste Landfills § 60.758 Recordkeeping requirements. (a) Except as provided in § 60.752(b)(2)(i)(B... triggered § 60.752(b), the current amount of solid waste in-place, and the year-by-year waste acceptance... electronic formats are acceptable. (b) Except as provided in § 60.752(b)(2)(i)(B), each owner or operator of...

  1. Environmental assessment: Reference repository location, Hanford site, Washington

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    none,

    1986-05-01

    In February 1983, the US Department of Energy (DOE) identified a reference repository location at the Hanford Site in Washington as one of the nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. The site is in the Columbia Plateau, which is one of five distinct geohydrologic settings considered for the first repository. To determine their suitability, the Hanford Site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories. These evaluations were reported inmore » draft environmental assessments (EAs), which were issued for public review and comment. After considering the comments received on the draft EAs, the DOE prepared the final EAs. On the basis of the evaluations reported in this EA, the DOE has found that the Hanford site is not disqualified under the guidelines. The DOE has also found that it is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is nominating the Hanford site as one of five sites suitable for characterization.« less

  2. Environmental assessment: Yucca Mountain site, Nevada research and development area, Nevada; Volume 1

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1986-05-01

    In February 1983, the US Department of Energy (DOE) identified the Yucca Mountain site in Nevada as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high- level radioactive waste. The site is in the Great Basin, which is one of five distinct geohydrologic settings considered for the first repository. To determine their suitability, the Yucca Mountain site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE`s General Guideline for the Recommendation of Sites for the Nuclear Waste Repositories. These evaluations were reported in draft environmental assessmentsmore » (EA), which were issued for public review and comment. After considering the comments received on the draft EAs, the DOE prepared the final EAs. On the basis of the evaluations reported in this EA, the DOE found that the Yucca Mountain site is not disqualified under the guidelines. The DOE has also found that it is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is nominating the Yucca Mountain site as of five sites suitable for characterization.« less

  3. Environmental assessment: Yucca Mountain site, Nevada research and development area, Nevada; Volume 3

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1986-05-01

    In February 1983, the US Department of Energy (DOE) identified the Yucca Mountain site in Nevada as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. The site is in the Great Basin, which is one of five distinct geohydrologic settings considered for the first repository. To determine their suitability, the Yucca Mountain site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE`s General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories. These evaluations were reported in draft environmental assessments (EAs),more » which were issued for public review and comment. After considering the comments received on the draft EAs, the DOE prepared the final EAs. On the basis of the evaluations reported in this EA, the DOE has found that the Yucca Mountain site is not disqualified under the guidelines. The DOE has also found that it is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is nominating the Yucca Mountain site as one of five sites suitable for characterization.« less

  4. Development of Urine Receptacle Assembly for the Crew Exploration Vehicle

    NASA Technical Reports Server (NTRS)

    Cibuzar, Branelle Rae; Thomas, Evan; Peterson, Laurie; Goforth, Johanna

    2008-01-01

    The Urine Receptacle Assembly (URA) initially was developed for Apollo as a primary means of urine collection. The aluminum housing with stainless steel honeycomb insert provided all male crewmembers with a non-invasive means of micturating into a urine capturing device and then venting to space. The performance of the URA was a substantial improvement over previous devices but its performance was not well understood. The Crew Exploration Vehicle (CEV) program is exploring the URA as a contingency liquid waste management system for the vehicle. URA improvements are required to meet CEV requirements, including: consumables minimization, flow performance, acceptable hygiene standards, crew comfort, and female crewmember capability. This paper presents the results of a historical review of URA performance during the Apollo program, recent URA performance tests on the reduced gravity aircraft flight under varying flow conditions, and a proposed development plan for the URA to meet CEV needs.

  5. Nasreya: a treatment and disposal facility for industrial hazardous waste in Alexandria, Egypt: phase I.

    PubMed

    Ramadan, Adham R; Kock, Per; Nadim, Amani

    2005-04-01

    A facility for the treatment and disposal of industrial hazardous waste has been established in Alexandria, Egypt. Phase I of the facility encompassing a secure landfill and solar evaporation ponds is ready to receive waste, and Phase II encompassing physico-chemical treatment, solidification, and interim storage is underway. The facility, the Nasreya Centre, is the first of its kind in Egypt, and represents the nucleus for the integration, improvement and further expansion of different hazardous waste management practices and services in Alexandria. It has been developed within the overall legal framework of the Egyptian Law for the Environment, and is expected to improve prospects for enforcement of the regulatory requirements specified in this law. It has been developed with the overall aim of promoting the establishment of an integrated industrial hazardous waste management system in Alexandria, serving as a demonstration to be replicated elsewhere in Egypt. For Phase I, the Centre only accepts inorganic industrial wastes. In this respect, a waste acceptance policy has been developed, which is expected to be reviewed during Phase II, with an expansion of the waste types accepted.

  6. 75 FR 7934 - Airworthiness Directives; McCauley Propeller Systems 1A103/TCM Series Propellers

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-23

    ... with cracks that do not meet acceptable limits, and rework of propellers with cracks that meet..., replacement of propellers with cracks that do not meet acceptable limits, and rework of propellers with cracks... propeller hub, removal from service of propellers with cracks that do not meet acceptable limits, and rework...

  7. INPRO Assessment of an INS in the Area of Safety of Fuel Cycle Installations

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Raj, B.; Busurin, Y.; Depisch, F.

    2006-07-01

    INPRO has defined requirements organized in a hierarchy of Basic Principles, User Requirements and Criteria (consisting of an indicator and an acceptance limit) to be met by innovative nuclear reactor systems (INS) in six areas, namely: economics, safety, waste management, environment, proliferation resistance, and infrastructure. If an INS meets all requirements in all areas it represents a sustainable system for the supply of energy, capable of making a significant contribution to meeting the energy needs of the 21. century. Draft manuals have been developed, for each INPRO area, to provide guidance for performing an assessment of whether an INS meetsmore » the INPRO requirements in a given area. The manuals set out the information that needs to be assembled to perform an assessment and provide guidance on selecting the acceptance limits and, for a given INS, for determining the value of the indicators for comparison with the associated acceptance limits. Each manual also includes an example of a specific assessment to illustrate the guidance. This paper discusses the manual for performing an INPRO assessment in the area of safety of fuel cycle installations. The example, chosen solely for the purpose of illustrating the INPRO methodology, describes an assessment of an MOX fuel fabrication plant based on sol-gel technology and illustrates an assessment performed for an INS at an early stage of development. The safety issues and the assessment steps are presented in detail in the paper. (authors)« less

  8. An industry perspective on commercial radioactive waste disposal conditions and trends.

    PubMed

    Romano, Stephen A

    2006-11-01

    The United States is presently served by Class-A, -B and -C low-level radioactive waste and naturally-occurring and accelerator-produced radioactive material disposal sites in Washington and South Carolina; a Class-A and mixed waste disposal site in Utah that also accepts naturally-occurring radioactive material; and hazardous and solid waste facilities and uranium mill tailings sites that accept certain radioactive materials on a site-specific basis. The Washington site only accepts low-level radioactive waste from 11 western states due to interstate Compact restrictions on waste importation. The South Carolina site will be subject to geographic service area restrictions beginning 1 July 2008, after which only three states will have continued access. The Utah site dominates the commercial Class-A and mixed waste disposal market due to generally lower state fees than apply in South Carolina. To expand existing commercial services, an existing hazardous waste site in western Texas is seeking a Class-A, -B and -C and mixed waste disposal license. With that exception, no new Compact facilities are proposed. This fluid, uncertain situation has inspired national level rulemaking initiatives and policy studies, as well as alternative disposal practices for certain low-activity materials.

  9. Draft environmental assessment: Davis Canyon site, Utah. Nuclear Waste Policy Act (Section 112). [Contains glossary

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified the Davis Canyon site in Utah, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Davis Canyon site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluationsmore » are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations reported in this draft EA, the DOE has found that the Davis Canyon site is not disqualified under the guidelines. The site is in the Paradox Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site - the Lavender Canyon site. Although the Lavender Canyon site appears to be suitable for site characterization, the DOE has concluded that the Davis Canyon site is the preferred site in the Paradox Basin. Furthermore, the DOE finds that the site is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the Davis Canyon site as one of five sites suitable for characterization. Having compared the Davis Canyon site with the other four sites proposed for nomination, the DOE has determined that the Davis Canyon site is not one of the three preferred sites for recommendation to the President as candidates for characterization.« less

  10. 30 CFR 7.44 - Technical requirements.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... nonmetallic materials shall meet the acceptable performance criteria for the impact test in § 7.46... material under part 18 of this chapter; and (ii) Meet the acceptable performance criteria for the...) Battery box and cover insulating material shall meet the acceptable performance criteria for the acid...

  11. 30 CFR 7.44 - Technical requirements.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... nonmetallic materials shall meet the acceptable performance criteria for the impact test in § 7.46... material under part 18 of this chapter; and (ii) Meet the acceptable performance criteria for the...) Battery box and cover insulating material shall meet the acceptable performance criteria for the acid...

  12. Environmental assessment: Davis Canyon site, Utah

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    none,

    1986-05-01

    In February 1983, the US Department of Energy (DOE) identified the Davis Canyon site in Utah as one of the nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Davis Canyon site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories. These evaluations were reported in draft environmental assessments (EAs), which were issued for public review and comment. After considering the comments received on the draft EAs, the DOEmore » prepared the final EA. The Davis Canyon site is in the Paradox Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site -- the Lavender Canyon site. Although the Lavender Canyon site is suitable for site characterization, the DOE has concluded that the Davis Canyon site is the preferred site in the Paradox Basin. On the basis of the evaluations reported in this EA, the DOE has found that the Davis Canyon site is not disqualified under the guidelines. Furthermore, the DOE has fond that the site is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is nominating the Davis Canyon site as one of five sites suitable for characterization. 181 figs., 175 tabs.« less

  13. Environmental assessment: Davis Canyon site, Utah

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    none,

    1986-05-01

    In February 1983, the US Department of Energy (DOE) identified the Davis Canyon site in Utah as one of the nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high- level radioactive waste. To determine their suitability, the Davis Canyon site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories. These evaluations were reported in draft environmental assessments (EAs), which were issued for public review and comment. After considering the comments received on the draft EAs, themore » DOE prepared the final EA. The Davis Canyon site is in the Paradox Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site -- the Lavender Canyon site. Although the Lavender Canyon site is suitable for site characterization, the DOE has concluded that the Davis Canyon site is the preferred site in the Paradox Basin. On the basis of the evaluations reported in this EA, the DOE has found that the Davis Canyon site is not disqualified under the guidelines. Furthermore, the DOE has found that the site is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is nominating the Davis Canyon site as one of the five sites suitable for characterization.« less

  14. 40 CFR 60.1040 - Do all five components of these new source performance standards apply at the same time?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... SOURCES Standards of Performance for Small Municipal Waste Combustion Units for Which Construction is...? No, you must meet the preconstruction requirements before you commence construction of the municipal waste combustion unit. After the municipal waste combustion unit begins operation, you must meet all of...

  15. 40 CFR 60.1040 - Do all five components of these new source performance standards apply at the same time?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... SOURCES Standards of Performance for Small Municipal Waste Combustion Units for Which Construction is...? No, you must meet the preconstruction requirements before you commence construction of the municipal waste combustion unit. After the municipal waste combustion unit begins operation, you must meet all of...

  16. A pilot survey of the U.S. medical waste industry to determine training needs for safely handling highly infectious waste.

    PubMed

    Le, Aurora B; Hoboy, Selin; Germain, Anne; Miller, Hal; Thompson, Richard; Herstein, Jocelyn J; Jelden, Katelyn C; Beam, Elizabeth L; Gibbs, Shawn G; Lowe, John J

    2018-02-01

    The recent Ebola outbreak led to the development of Ebola virus disease (EVD) best practices in clinical settings. However, after the care of EVD patients, proper medical waste management and disposal was identified as a crucial component to containing the virus. Category A waste-contaminated with EVD and other highly infectious pathogens-is strictly regulated by governmental agencies, and led to only several facilities willing to accept the waste. A pilot survey was administered to determine if U.S. medical waste facilities are prepared to handle or transport category A waste, and to determine waste workers' current extent of training to handle highly infectious waste. Sixty-eight percent of survey respondents indicated they had not determined if their facility would accept category A waste. Of those that had acquired a special permit, 67% had yet to modify their permit since the EVD outbreak. This pilot survey underscores gaps in the medical waste industry to handle and respond to category A waste. Furthermore, this study affirms reports a limited number of processing facilities are capable or willing to accept category A waste. Developing the proper management of infectious disease materials is essential to close the gaps identified so that states and governmental entities can act accordingly based on the regulations and guidance developed, and to ensure public safety. Copyright © 2018 Association for Professionals in Infection Control and Epidemiology, Inc. Published by Elsevier Inc. All rights reserved.

  17. Radioactive waste management: review on clearance levels and acceptance criteria legislation, requirements and standards.

    PubMed

    Maringer, F J; Suráň, J; Kovář, P; Chauvenet, B; Peyres, V; García-Toraño, E; Cozzella, M L; De Felice, P; Vodenik, B; Hult, M; Rosengård, U; Merimaa, M; Szücs, L; Jeffery, C; Dean, J C J; Tymiński, Z; Arnold, D; Hinca, R; Mirescu, G

    2013-11-01

    In 2011 the joint research project Metrology for Radioactive Waste Management (MetroRWM)(1) of the European Metrology Research Programme (EMRP) started with a total duration of three years. Within this project, new metrological resources for the assessment of radioactive waste, including their calibration with new reference materials traceable to national standards will be developed. This paper gives a review on national, European and international strategies as basis for science-based metrological requirements in clearance and acceptance of radioactive waste. © 2013 Elsevier Ltd. All rights reserved.

  18. 40 CFR 240.200-3 - Recommended procedures: Operations.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ...) SOLID WASTES GUIDELINES FOR THE THERMAL PROCESSING OF SOLID WASTES Requirements and Recommended Procedures § 240.200-3 Recommended procedures: Operations. (a) Storage areas for special wastes should be... acceptance of Special Wastes. ...

  19. 40 CFR 240.200-3 - Recommended procedures: Operations.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ...) SOLID WASTES GUIDELINES FOR THE THERMAL PROCESSING OF SOLID WASTES Requirements and Recommended Procedures § 240.200-3 Recommended procedures: Operations. (a) Storage areas for special wastes should be... acceptance of Special Wastes. ...

  20. WRAP low level waste restricted waste management (LLW RWM) glovebox acceptance test report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Leist, K.J.

    1997-11-24

    On April 22, 1997, the Low Level Waste Restricted Waste Management (LLW RWM) glovebox was tested using acceptance test procedure 13027A-87. Mr. Robert L. Warmenhoven served as test director, Mr. Kendrick Leist acted as test operator and test witness, and Michael Lane provided miscellaneous software support. The primary focus of the glovebox acceptance test was to examine glovebox control system interlocks, operator Interface Unit (OIU) menus, alarms, and messages. Basic drum port and lift table control sequences were demonstrated. OIU menus, messages, and alarm sequences were examined, with few exceptions noted. Barcode testing was bypassed, due to the lack ofmore » installed equipment as well as the switch from basic reliance on fixed bar code readers to the enhanced use of portable bar code readers. Bar code testing was completed during performance of the LLW RWM OTP. Mechanical and control deficiencies were documented as Test Exceptions during performance of this Acceptance Test. These items are attached as Appendix A to this report.« less

  1. EU landfill waste acceptance criteria and EU Hazardous Waste Directive compliance testing of incinerated sewage sludge ash.

    PubMed

    Donatello, S; Tyrer, M; Cheeseman, C R

    2010-01-01

    A hazardous waste assessment has been completed on ash samples obtained from seven sewage sludge incinerators operating in the UK, using the methods recommended in the EU Hazardous Waste Directive. Using these methods, the assumed speciation of zinc (Zn) ultimately determines if the samples are hazardous due to ecotoxicity hazard. Leaching test results showed that two of the seven sewage sludge ash samples would require disposal in a hazardous waste landfill because they exceed EU landfill waste acceptance criteria for stabilised non-reactive hazardous waste cells for soluble selenium (Se). Because Zn cannot be proven to exist predominantly as a phosphate or oxide in the ashes, it is recommended they be considered as non-hazardous waste. However leaching test results demonstrate that these ashes cannot be considered as inert waste, and this has significant implications for the management, disposal and re-use of sewage sludge ash.

  2. Data Quality Objectives Process for Designation of K Basins Debris

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    WESTCOTT, J.L.

    2000-05-22

    The U.S. Department of Energy has developed a schedule and approach for the removal of spent fuels, sludge, and debris from the K East (KE) and K West (KW) Basins, located in the 100 Area at the Hanford Site. The project that is the subject of this data quality objective (DQO) process is focused on the removal of debris from the K Basins and onsite disposal of the debris at the Environmental Restoration Disposal Facility (ERDF). This material previously has been dispositioned at the Hanford Low-Level Burial Grounds (LLBGs) or Central Waste Complex (CWC). The goal of this DQO processmore » and the resulting Sampling and Analysis Plan (SAP) is to provide the strategy for characterizing and designating the K-Basin debris to determine if it meets the Environmental Restoration Disposal Facility Waste Acceptance Criteria (WAC), Revision 3 (BHI 1998). A critical part of the DQO process is to agree on regulatory and WAC interpretation, to support preparation of the DQO workbook and SAP.« less

  3. Solid Waste Assurance Program Implementation Plan

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Irons, L.G.

    1995-06-19

    On June 6, 1995, a waiver to Hanford Site Solid Waste Acceptance Criteria, was approved by the US Department of Energy Richland Operations Office (RL) to replace the low-level, mixed, and transuranic (TRU) generator assessment programs with the Solid Waste Assurance Program (SWAP). This is associated with a waiver that was approved on March 16, 1995 to replace the Storage/Disposal Approval Record (SDAR) requirements with the Waste Specification System (WSS). This implementation plan and the SWAP applies to Solid Waste Disposal (SWD) functions, facilities, and personnel who perform waste acceptance, verification, receipt, and management functions of dangerous, radioactive, and mixedmore » waste from on- and off-site generators who ship to or within the Hanford Site for treatment, storage, and/or disposal (TSD) at SWD TSD facilities.« less

  4. Disposal of LLW and ILW in Germany - Characterisation and Documentation of Waste Packages with Respect to the Change of Requirements

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bandt, G.; Spicher, G.; Steyer, St.

    2008-07-01

    Since the 1998 termination of LLW and ILW emplacement in the Morsleben repository (ERAM), Germany, the treatment, conditioning and documentation of radioactive waste products and packages have been continued on the basis of the waste acceptance requirements as of 1995, prepared for the Konrad repository near Salzgitter in Lower Saxony, Germany. The resulting waste products and packages are stored in interim storage facilities. Due to the Konrad license issued in 2002 the waste acceptance requirements have to be completed by additional requirements imposed by the licensing authority, e. g. for the declaration of chemical waste package constituents. Therefore, documentation ofmore » waste products and packages which are checked by independent experts and are in parts approved by the responsible authority (Office for Radiation Protection, BfS) up to now will have to be checked again for fulfilling the final waste acceptance requirements prior to disposal. In order to simplify these additional checks, databases are used to ensure an easy access to all known facts about the waste packages. A short balance of the existing waste products and packages which are already checked and partly approved by BfS as well as an overview on the established databases ensuring a fast access to the known facts about the conditioning processes is presented. (authors)« less

  5. 40 CFR Table A-6 to Subpart A of... - Data Elements That Are Inputs to Emission Equations and for Which the Reporting Deadline Is...

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... to calculate recycling correction factor). Y 98.256(i)(5) Only annual mass of green coke fed, carbon...) All. GG 98.336(b)(7) All. GG 98.336(b)(10) All. HH 98.346(a) Only year in which landfill first accepted waste, last year the landfill accepted waste, capacity of the landfill, and waste disposal...

  6. 241-AZ-101 Waste Tank Color Video Camera System Shop Acceptance Test Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    WERRY, S.M.

    2000-03-23

    This report includes shop acceptance test results. The test was performed prior to installation at tank AZ-101. Both the camera system and camera purge system were originally sought and procured as a part of initial waste retrieval project W-151.

  7. Conditioning and Repackaging of Spent Radioactive Cs-137 and Co-60 Sealed Sources in Egypt - 13490

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hasan, M.A.; Selim, Y.T.; El-Zakla, T.

    2013-07-01

    Radioactive Sealed sources (RSSs) are widely use all over the world in medicine, agriculture, industry, research, etc. The accidental misuse and exposure to RSSs has caused significant environmental contamination, serious injuries and many deaths. The high specific activity of the materials in many RSSs means that the spread of as little as microgram quantities can generate significant risk to human health and inhibit the use of buildings and land. Conditioning of such sources is a must to protect humans and environment from the hazard of ionizing radiation and contamination. Conditioning is also increase the security of these sources by decreasingmore » the probability of stolen and/or use in terrorist attacks. According to the law No.7/2010, Egyptian atomic energy authority represented in the hot laboratories and waste management center (centralized waste facility, HLWMC) has the responsibility of collecting, conditioning, storing and management of all types of radioactive waste from all Egyptian territory including spent radioactive sealed sources (SRSSs). This paper explains the conditioning procedures for two of the most common SRSSs, Cs{sup 137} and Co{sup 60} sources which make up more than 90% of the total spent radioactive sealed sources stored in our centralized waste facility as one of the major activities of hot laboratories and waste management center. Conditioning has to meet three main objectives, be acceptable for storage, enable their safe transport, and comply with disposal requirements. (authors)« less

  8. Radiological Characterization Methodology of INEEL Stored RH-TRU Waste from ANL-E

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rajiv N. Bhatt

    2003-02-01

    An Acceptable Knowledge (AK)-based radiological characterization methodology is being developed for RH TRU waste generated from ANL-E hot cell operations performed on fuel elements irradiated in the EBR-II reactor. The methodology relies on AK for composition of the fresh fuel elements, their irradiation history, and the waste generation and collection processes. Radiological characterization of the waste involves the estimates of the quantities of significant fission products and transuranic isotopes in the waste. Methods based on reactor and physics principles are used to achieve these estimates. Because of the availability of AK and the robustness of the calculation methods, the AK-basedmore » characterization methodology offers a superior alternative to traditional waste assay techniques. Using this methodology, it is shown that the radiological parameters of a test batch of ANL-E waste is well within the proposed WIPP Waste Acceptance Criteria limits.« less

  9. Radiological Characterization Methodology for INEEL-Stored Remote-Handled Transuranic (RH TRU) Waste from Argonne National Laboratory-East

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kuan, P.; Bhatt, R.N.

    2003-01-14

    An Acceptable Knowledge (AK)-based radiological characterization methodology is being developed for RH TRU waste generated from ANL-E hot cell operations performed on fuel elements irradiated in the EBR-II reactor. The methodology relies on AK for composition of the fresh fuel elements, their irradiation history, and the waste generation and collection processes. Radiological characterization of the waste involves the estimates of the quantities of significant fission products and transuranic isotopes in the waste. Methods based on reactor and physics principles are used to achieve these estimates. Because of the availability of AK and the robustness of the calculation methods, the AK-basedmore » characterization methodology offers a superior alternative to traditional waste assay techniques. Using the methodology, it is shown that the radiological parameters of a test batch of ANL-E waste is well within the proposed WIPP Waste Acceptance Criteria limits.« less

  10. 49 CFR 173.197 - Regulated medical waste.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... (bio) medical waste must be rigid containers meeting the provisions of subpart B of this part. (b) Non... medical waste or clinical waste or (bio) medical waste must be UN standard packagings conforming to the... filled. (2) Liquids. Liquid regulated medical waste or clinical waste or (bio) medical waste transported...

  11. Alternative Radiological Characterization of Sealed Source TRU Waste for WIPP Disposal (LAUR-05-8776)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Whitworth, J.; Pearson, M.; Feldman, A.

    2006-07-01

    The Offsite Source Recovery (OSR) Project at Los Alamos National Laboratory is now shipping transuranic (TRU) waste containers to the Waste Isolation Pilot Plant (WIPP) in New Mexico for disposal. Sealed source waste disposal has become possible in part because OSR personnel were able to obtain Environmental Protection Agency (EPA) and DOE-CBFO approval for an alternative radiological characterization procedure relying on acceptable knowledge (AK) and modeling, rather than on non-destructive assay (NDA) of each container. This is the first successful qualification of an 'alternate methodology' under the radiological characterization requirements of the WIPP Waste Acceptance Criteria (WAC) by any TRUmore » waste generator site. This paper describes the approach OSR uses to radiologically characterize its sealed source waste and the process by which it obtained certification of this approach. (authors)« less

  12. EPA's Review of DOE's Inventory Tracking for TRU Wastes at Waste Control Specialists

    EPA Pesticide Factsheets

    On April 9, 2014, EPA's Waste Isolation Pilot Plant (WIPP) waste characterization team visited Waste Control Specialists (WCS) to determine whether DOE was meeting EPA's waste inventory tracking requirements at 40 CFR 194.24(c)(4).

  13. Dietary and Food Processing for a 90-day Bioregenerative Life Support Experiment in the Lunar Palace 1

    NASA Astrophysics Data System (ADS)

    Zhao, Zhiruo; Fu, Yuming; Dong, Chen; Liu, Guanghui

    A 4-day cycle dietary menu was developed to meet the requirements of balanced diet of the crew within the 90-day closed experiment of bioregenerative life support in the Lunar Palace 1. The menu consisted of items prepared from crops and insect grown inside the system, as well as prestored food. Dairy recipe was composed of breads, vegetables, meats and soups, which provided about 2900 kcal per crew member per day. During food processing, to maximize nutrient recovery and minimize waste production, the whole wheat grains and chufa nuts were milled. Further, the carrot leaves and yellow mealworms were used as salad materials and bread ingredients, respectively. The sensory acceptability of the dishes in the menu was evaluated by flavor, texture, and appearance. Our results show that all dishes in the 4-day cycle menu were highly acceptable, which satisfies nutritional requirement of the crew members in the closed habitation.

  14. When Spreadsheets Become Software - Quality Control Challenges and Approaches - 13360

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Fountain, Stefanie A.; Chen, Emmie G.; Beech, John F.

    2013-07-01

    As part of a preliminary waste acceptance criteria (PWAC) development, several commercial models were employed, including the Hydrologic Evaluation of Landfill Performance model (HELP) [1], the Disposal Unit Source Term - Multiple Species model (DUSTMS) [2], and the Analytical Transient One, Two, and Three-Dimensional model (AT123D) [3]. The results of these models were post-processed in MS Excel spreadsheets to convert the model results to alternate units, compare the groundwater concentrations to the groundwater concentration thresholds, and then to adjust the waste contaminant masses (based on average concentration over the waste volume) as needed in an attempt to achieve groundwater concentrationsmore » at the limiting point of assessment that would meet the compliance concentrations while maximizing the potential use of the landfill (i.e., maximizing the volume of projected waste being generated that could be placed in the landfill). During the course of the PWAC calculation development, one of the Microsoft (MS) Excel spreadsheets used to post-process the results of the commercial model packages grew to include more than 575,000 formulas across 18 worksheets. This spreadsheet was used to assess six base scenarios as well as nine uncertainty/sensitivity scenarios. The complexity of the spreadsheet resulted in the need for a rigorous quality control (QC) procedure to verify data entry and confirm the accuracy of formulas. (authors)« less

  15. Error-free pathology: applying lean production methods to anatomic pathology.

    PubMed

    Condel, Jennifer L; Sharbaugh, David T; Raab, Stephen S

    2004-12-01

    The current state of our health care system calls for dramatic changes. In their pathology department, the authors believe these changes may be accomplished by accepting the long-term commitment of applying a lean production system. The ideal state of zero pathology errors is one that should be pursued by consistently asking, "Why can't we?" The philosophy of lean production systems began in the manufacturing industry: "All we are doing is looking at the time from the moment the customer gives us an order to the point when we collect the cash. And we are reducing that time line by removing non-value added wastes". The ultimate goals in pathology and overall health care are not so different. The authors' intention is to provide the patient (customer) with the most accurate diagnostic information in a timely and efficient manner. Their lead histotechnologist recently summarized this philosophy: she indicated that she felt she could sleep better at night knowing she truly did the best job she could. Her chances of making an error (in cutting or labeling) were dramatically decreased in the one-by-one continuous flow work process compared with previous practices. By designing a system that enables employees to be successful in meeting customer demand, and by empowering the frontline staff in the development and problem solving processes, one can meet the challenges of eliminating waste and build an improved, efficient system.

  16. 40 CFR 60.1140 - Where and when must I hold a public meeting on the siting analysis?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... of Performance for Small Municipal Waste Combustion Units for Which Construction is Commenced After... will construct your municipal waste combustion unit. (c) You must schedule the public meeting to occur...

  17. 36 CFR 13.1008 - Solid waste disposal.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 36 Parks, Forests, and Public Property 1 2011-07-01 2011-07-01 false Solid waste disposal. 13.1008... § 13.1008 Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may be...

  18. 36 CFR 13.1604 - Solid waste disposal.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 36 Parks, Forests, and Public Property 1 2011-07-01 2011-07-01 false Solid waste disposal. 13.1604... Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may be located within one...

  19. 36 CFR 13.1118 - Solid waste disposal.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal. 13.1118... Provisions § 13.1118 Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may...

  20. 36 CFR 13.1604 - Solid waste disposal.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal. 13.1604... Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may be located within one...

  1. 36 CFR 13.1912 - Solid waste disposal.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 36 Parks, Forests, and Public Property 1 2011-07-01 2011-07-01 false Solid waste disposal. 13.1912....1912 Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may be located...

  2. 36 CFR 13.1008 - Solid waste disposal.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal. 13.1008... § 13.1008 Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may be...

  3. 36 CFR 13.1118 - Solid waste disposal.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 36 Parks, Forests, and Public Property 1 2011-07-01 2011-07-01 false Solid waste disposal. 13.1118... Provisions § 13.1118 Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may...

  4. INNOVATIVE PRACTICES FOR TREATING WASTE STREAMS CONTAINING HEAVY METALS: A WASTE MINIMIZATION APPROACH

    EPA Science Inventory

    Innovative practices for treating waste streams containing heavy metals often involve technologies or systems that either reduce the amount of waste generated or recover reusable resources. With the land disposal of metal treatment residuals becoming less of an accepted waste man...

  5. Treatability Variance for Containerised Liquids in Mixed Debris Waste - 12101

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Alstatt, Catherine M.

    2012-07-01

    The TRU Waste Processing Center (TWPC) is a Department of Energy facility whose mission is to receive and process for appropriate disposal legacy Contact Handled (CH) and Remote Handled (RH) waste, including debris waste stored at various DOE Oak Ridge facilities. Acceptable Knowledge (AK) prepared for the waste characterizes the waste as mixed waste, meaning it is both radioactive and regulated under the Resource Conservation and Recovery Act (RCRA). The AK also indicates that a number of the debris waste packages contain small amounts of containerised liquids. The documentation indicates liquid wastes generated in routine lab operations were typically collectedmore » for potential recovery of valuable isotopes. However, during activities associated with decontamination and decommissioning (D and D), some containers with small amounts of liquids were placed into the waste containers with debris waste. Many of these containers now hold from 2.5 milliliters (ml) to 237 ml of liquid; a few contain larger volumes. At least some of these containers were likely empty at the time of generation, but documentation of this condition is lacking. Since WIPP compliant AK is developed on a waste stream basis, rather than an individual container basis, and includes every potential RCRA hazardous constituent within the waste stream, it is insufficient for the purpose of characterizing individual containers of liquid. Debris waste is defined in 40 CFR 268.2(g) as 'solid material exceeding a 60 mm particle size that is intended for disposal and that is: a manufactured object; or plant or animal matter; or natural geologic material'. The definition further states that intact containers of hazardous waste that are not ruptured and that retain at least 75% of their original volume are not debris. The prescribed treatment is removal of intact containers from the debris waste, and treatment of their contents to meet specific Land Disposal Restrictions (LDR) standards. This is true for containers with incidental amounts of liquids, even if the liquid is less than 50% of the total waste volume. Under the proposed variance, all free or containerised liquids (up to 3.8 liters(L)) found in the debris would be treated and returned in solid form to the debris waste stream from which they originated. The waste would then be macro-encapsulated. (author)« less

  6. 40 CFR 761.216 - Unmanifested waste report.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 40 Protection of Environment 32 2013-07-01 2013-07-01 false Unmanifested waste report. 761.216... PROHIBITIONS PCB Waste Disposal Records and Reports § 761.216 Unmanifested waste report. (a) If a facility accepts for storage or disposal any PCB waste from an off-site source without an accompanying manifest, or...

  7. 40 CFR 761.216 - Unmanifested waste report.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 40 Protection of Environment 31 2014-07-01 2014-07-01 false Unmanifested waste report. 761.216... PROHIBITIONS PCB Waste Disposal Records and Reports § 761.216 Unmanifested waste report. (a) If a facility accepts for storage or disposal any PCB waste from an off-site source without an accompanying manifest, or...

  8. Effective dialogue: Enhanced public engagement as a legitimising tool for municipal waste management decision-making

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Garnett, Kenisha, E-mail: k.garnett@cranfield.ac.uk; Cooper, Tim, E-mail: t.h.cooper@ntu.ac.uk

    2014-12-15

    Highlights: • A review of public engagement in waste management decision-making is undertaken. • Enhanced public engagement is explored as a means to legitimise waste decisions. • Analytical–deliberative processes are explored as a tool for effective dialogue. • Considerations for integrating public values with technical analysis are outlined. • Insights into the design of appropriate public engagement processes are provided. - Abstract: The complexity of municipal waste management decision-making has increased in recent years, accompanied by growing scrutiny from stakeholders, including local communities. This complexity reflects a socio-technical framing of the risks and social impacts associated with selecting technologies andmore » sites for waste treatment and disposal facilities. Consequently there is growing pressure on local authorities for stakeholders (including communities) to be given an early opportunity to shape local waste policy in order to encourage swift planning, development and acceptance of the technologies needed to meet statutory targets to divert waste from landfill. This paper presents findings from a research project that explored the use of analytical–deliberative processes as a legitimising tool for waste management decision-making. Adopting a mixed methods approach, the study revealed that communicating the practical benefits of more inclusive forms of engagement is proving difficult even though planning and policy delays are hindering development and implementation of waste management infrastructure. Adopting analytical–deliberative processes at a more strategic level will require local authorities and practitioners to demonstrate how expert-citizen deliberations may foster progress in resolving controversial issues, through change in individuals, communities and institutions. The findings suggest that a significant shift in culture will be necessary for local authorities to realise the potential of more inclusive decision processes. This calls for political actors and civic society to collaborate in institutionalising public involvement in both strategic and local planning structures.« less

  9. 40 CFR 262.57 - Recordkeeping.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) STANDARDS APPLICABLE TO GENERATORS OF HAZARDOUS WASTE Exports of Hazardous Waste § 262.57 Recordkeeping. (a) For all... at least three years from the date the hazardous waste was accepted by the initial transporter; (2...

  10. 40 CFR 257.13 - Deadline for making demonstrations.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ...-Hazardous Waste Disposal Units Location Restrictions § 257.13 Deadline for making demonstrations. Existing..., 1998, must not accept CESQG hazardous waste for disposal. Ground-Water Monitoring and Corrective Action ... WASTES CRITERIA FOR CLASSIFICATION OF SOLID WASTE DISPOSAL FACILITIES AND PRACTICES Disposal Standards...

  11. Recent developments - US spent fuel disposition

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    One of a US utility's major risk factors in continuing to operate a nuclear plant is managing discharged spent fuel. The US Department of Energy (DOE) signed contracts with utilities guaranteeing government acceptance of spent fuel by 1988. However, on December 17, 1992, DOE Secretary Watkins wrote to Sen. J. Bennett Johnston (D-LA), Chairman of the Senate Energy Committee, indicating a reassessment of DOE's programs, the results of which will be presented to Congress in January 1993. He indicated the Department may not be able to meet the 1988 date, because of difficulty in finding a site for the Monitoredmore » Retrievable Storage facility. Watkins indicated that DOE has investigated an interim solution and decided to expedite a program to certify a multi-purpose standardized cask system for spent fuel receipt, storage, transport, and disposal. To meet the expectations of US utilities, DOE is considering a plan to use federal sites for interim storage of the casks. Secretary Watkins recommended the waste program be taken off-budget and put in a revolving fund established to ensure that money already collected from utilities will be available to meet the schedule for completion of the repository.« less

  12. Standard High Solids Vessel Design De-inventory Simulant Qualification

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Fiskum, Sandra K.; Burns, Carolyn A.M.; Gauglitz, Phillip A.

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is working to develop a Standard High Solids Vessel Design (SHSVD) process vessel. To support testing of this new design, WTP engineering staff requested that a Newtonian simulant be developed that would represent the de-inventory (residual high-density tank solids cleanout) process. Its basis and target characteristics are defined in 24590-WTP-ES-ENG-16-021 and implemented through PNNL Test Plan TP-WTPSP-132 Rev. 1.0. This document describes the de-inventory Newtonian carrier fluid (DNCF) simulant composition that will satisfy the basis requirement to mimic the density (1.18 g/mL ± 0.1 g/mL) and viscosity (2.8 cP ± 0.5more » cP) of 5 M NaOH at 25 °C.1 The simulant viscosity changes significantly with temperature. Therefore, various solution compositions may be required, dependent on the test stand process temperature range, to meet these requirements. Table ES.1 provides DNCF compositions at selected temperatures that will meet the density and viscosity specifications as well as the temperature range at which the solution will meet the acceptable viscosity tolerance.« less

  13. Nuclear energy: Where do we go from here?

    NASA Astrophysics Data System (ADS)

    Muslim, Dato'Noramly, Dr

    2015-04-01

    As Malaysia progresses towards 2020, the depleting resource of oil and gas has forced a re-look at alternatives to replace fossil fuels as energy sources. Among the viable options is nuclear energy, enabling us to meet energy needs and sustain national development in the twenty-first century. Three essential steps Malaysia must take to introduce nuclear power into its energy mix are: energy planning, infrastructure development, and deployment. Malaysia has to face a series of challenges, including public acceptance, waste management, minimizing proliferation risk, and ensuring the security of nuclear plants and materials. Timely development of qualified and competent manpower is a key limiting factor in the development and transfer of nuclear technologies — and education and training take time, effort and money. There is a need for political will. Within the Asian region, China, Korea and Japan are in the forefront in utilizing nuclear power to meet electricity demands. Countries such as UAE, Bangladesh, Vietnam and Turkey are moving ahead with the nuclear option for electricity generation and they have begun planning and construction of nuclear power plants. Against this backdrop, what are Malaysia's moves? This paper discusses various options and challenges, obstacles and repercussions in meeting future energy demands.

  14. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Muslim, Dato’ Dr Noramly, E-mail: noramlymuslim@yahoo.com

    As Malaysia progresses towards 2020, the depleting resource of oil and gas has forced a re-look at alternatives to replace fossil fuels as energy sources. Among the viable options is nuclear energy, enabling us to meet energy needs and sustain national development in the twenty-first century. Three essential steps Malaysia must take to introduce nuclear power into its energy mix are: energy planning, infrastructure development, and deployment. Malaysia has to face a series of challenges, including public acceptance, waste management, minimizing proliferation risk, and ensuring the security of nuclear plants and materials. Timely development of qualified and competent manpower ismore » a key limiting factor in the development and transfer of nuclear technologies — and education and training take time, effort and money. There is a need for political will. Within the Asian region, China, Korea and Japan are in the forefront in utilizing nuclear power to meet electricity demands. Countries such as UAE, Bangladesh, Vietnam and Turkey are moving ahead with the nuclear option for electricity generation and they have begun planning and construction of nuclear power plants. Against this backdrop, what are Malaysia’s moves? This paper discusses various options and challenges, obstacles and repercussions in meeting future energy demands.« less

  15. Liquid secondary waste: Waste form formulation and qualification

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cozzi, A. D.; Dixon, K. L.; Hill, K. A.

    The Hanford Site Effluent Treatment Facility (ETF) currently treats aqueous waste streams generated during site cleanup activities. When the Hanford Tank Waste Treatment and Immobilization Plant (WTP) begins operations, including Direct Feed Low Activity Waste (DFLAW) vitrification, a liquid secondary waste (LSW) stream from the WTP will need to be treated. The volume of effluent for treatment at the ETF will increase significantly. The powdered salt waste form produced by the ETF will be replaced by a stabilized solidified waste form for disposal in Hanford’s Integrated Disposal Facility (IDF). Washington River Protection Solutions is implementing a Secondary Liquid Waste Immobilizationmore » Technology Development Plan to address the technology needs for a waste form and solidification process to treat the increased volume of waste planned for disposal at the IDF. Waste form testing to support this plan is composed of work in the near term to provide data as input to a performance assessment (PA) for Hanford’s IDF. In 2015, three Hanford Liquid Secondary Waste simulants were developed based on existing and projected waste streams. Using these waste simulants, fourteen mixes of Hanford Liquid Secondary Waste were prepared and tested varying the waste simulant, the water-to-dry materials ratio, and the dry materials blend composition.1 In FY16, testing was performed using a simulant of the EMF process condensate blended with the caustic scrubber—from the Low Activity Waste (LAW) melter—, processed through the ETF. The initial EMF-16 simulant will be based on modeling efforts performed to determine the mass balance of the ETF for the DFLAW.2 The compressive strength of all of the mixes exceeded the target of 3.4 MPa (500 psi) to meet the requirements identified as potential IDF Waste Acceptance Criteria in Table 1 of the Secondary Liquid Waste Immobilization Technology Development Plan.3 The hydraulic properties of the waste forms tested (hydraulic conductivity and water characteristic curves) were comparable to the properties measured on the Savannah River Site (SRS) Saltstone waste form. Future testing should include efforts to first; 1) determine the rate and amount of ammonia released during each unit operation of the treatment process to determine if additional ammonia management is required, then; 2) reduce the ammonia content of the ETF concentrated brine prior to solidification, making the waste more amenable to grouting, or 3) manage the release of ammonia during production and ongoing release during storage of the waste form, or 4) develop a lower pH process/waste form thereby precluding ammonia release.« less

  16. 75 FR 65297 - Annual Meeting

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-10-22

    ... APPALACHIAN STATES LOW-LEVEL RADIOACTIVE WASTE COMMISSION Annual Meeting Time And Date: 10 a.m.-12:30 p.m., November 5, 2010. Place: Harrisburg Hilton and Towers, One North Second Street, Harrisburg... Commission's financial statements for fiscal year 2009-2010; (2) Review the Low- Level Radioactive Waste...

  17. 78 FR 64472 - Annual Meeting

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-29

    ... APPALACHIAN STATES LOW-LEVEL RADIOACTIVE WASTE COMMISSION Annual Meeting Time and Date: 10 a.m.-12 p.m. October 31, 2013. Place: Harrisburg Hilton and Towers, One North Second Street, Harrisburg, PA... Commission's financial statements for fiscal year 2012-2013; (2) Review the Low- Level Radioactive Waste...

  18. 77 FR 61737 - Annual Meeting

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-11

    ... APPALACHIAN STATES LOW-LEVEL RADIOACTIVE WASTE COMMISSION Annual Meeting Time and Date: 10 a.m.-12 p.m. November 2, 2012. Place: Harrisburg Hilton and Towers, One North Second Street, Harrisburg, PA... Commission's financial statements for fiscal year 2011-2012; (2) Review the Low- Level Radioactive Waste...

  19. 76 FR 64071 - Annual Meeting

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-17

    ... APPALACHIAN STATES LOW-LEVEL RADIOACTIVE WASTE COMMISSION Annual Meeting Time and Date: 10 a.m.-12:30 p.m. November 4, 2011. Place: Harrisburg Hilton and Towers, One North Second Street, Harrisburg... Commission's financial statements for fiscal year 2010-2011; (2) Review the Low- Level Radioactive Waste...

  20. 41 CFR 304-5.1 - When may we accept payment from a non-Federal source for travel to a meeting or authorize an...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... payment from a non-Federal source for travel to a meeting or authorize an employee to accept payment on... System PAYMENT OF TRAVEL EXPENSES FROM A NON-FEDERAL SOURCE AGENCY REQUIREMENTS 5-AGENCY RESPONSIBILITIES § 304-5.1 When may we accept payment from a non-Federal source for travel to a meeting or authorize an...

  1. 77 FR 72997 - Low-Level Waste Disposal

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-07

    ...-2011-0012] RIN 3150-AI92 Low-Level Waste Disposal AGENCY: Nuclear Regulatory Commission. ACTION... Regulatory Commission (NRC) is proposing to amend its regulations that govern low-level radioactive waste... development of criteria for waste acceptance based on the results of these analyses. These amendments will...

  2. 50 CFR 600.1004 - Accepting a request for, and determinations about initiating, a financed program.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 50 Wildlife and Fisheries 8 2010-10-01 2010-10-01 false Accepting a request for, and... meets, or will meet after an appropriate reduction amendment, the requirements in § 600.1002(a); (2) The CFMP meets, or will meet after an appropriate reduction amendment, the requirements in § 600.1002(b...

  3. Waste Acceptance Testing of Secondary Waste Forms: Cast Stone, Ceramicrete and DuraLith

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mattigod, Shas V.; Westsik, Joseph H.; Chung, Chul-Woo

    2011-08-12

    To support the selection of a waste form for the liquid secondary wastes from WTP, Washington River Protection Solutions has initiated secondary-waste-form testing work at Pacific Northwest National Laboratory (PNNL). In anticipation of a down-selection process for a waste form for the Solidification Treatment Unit to be added to the ETF, PNNL is conducting tests on four candidate waste forms to evaluate their ability to meet potential waste acceptance criteria for immobilized secondary wastes that would be placed in the IDF. All three waste forms demonstrated compressive strengths above the minimum 3.45 MPa (500 psi) set as a target formore » cement-based waste forms. Further, none of the waste forms showed any significant degradation in compressive strength after undergoing thermal cycling (30 cycles in a 10 day period) between -40 C and 60 C or water immersion for 90 days. The three leach test methods are intended to measure the diffusion rates of contaminants from the waste forms. Results are reported in terms of diffusion coefficients and a leachability index (LI) calculated based on the diffusion coefficients. A smaller diffusion coefficient and a larger LI are desired. The NRC, in its Waste Form Technical Position (NRC 1991), provides recommendations and guidance regarding methods to demonstrate waste stability for land disposal of radioactive waste. Included is a recommendation to conduct leach tests using the ANS 16.1 method. The resulting leachability index (LI) should be greater than 6.0. For Hanford secondary wastes, the LI > 6.0 criterion applies to sodium leached from the waste form. For technetium and iodine, higher targets of LI > 9 for Tc and LI > 11 for iodine have been set based on early waste-disposal risk and performance assessment analyses. The results of these three leach tests conducted for a total time between 11days (ASTM C1308) to 90 days (ANS 16.1) showed: (1) Technetium diffusivity: ANSI/ANS 16.1, ASTM C1308, and EPA 1315 tests indicated that all the waste forms had leachability indices better than the target LI > 9 for technetium; (2) Rhenium diffusivity: Cast Stone 2M specimens, when tested using EPA 1315 protocol, had leachability indices better than the target LI > 9 for technetium based on rhenium as a surrogate for technetium. All other waste forms tested by ANSI/ANS 16.1, ASTM C1308, and EPA 1315 test methods had leachability indices that were below the target LI > 9 for Tc based on rhenium release. These studies indicated that use of Re(VII) as a surrogate for 99Tc(VII) in low temperature secondary waste forms containing reductants will provide overestimated diffusivity values for 99Tc. Therefore, it is not appropriate to use Re as a surrogate 99Tc in future low temperature waste form studies. (3) Iodine diffusivity: ANSI/ANS 16.1, ASTM C1308, and EPA 1315 tests indicated that the three waste forms had leachability indices that were below the target LI > 11 for iodine. Therefore, it may be necessary to use a more effective sequestering material than silver zeolite used in two of the waste forms (Ceramicrete and DuraLith); (4) Sodium diffusivity: All the waste form specimens tested by the three leach methods (ANSI/ANS 16.1, ASTM C1308, and EPA 1315) exceeded the target LI value of 6; (5) All three leach methods (ANS 16.1, ASTM C1308 and EPA 1315) provided similar 99Tc diffusivity values for both short-time transient diffusivity effects as well as long-term ({approx}90 days) steady diffusivity from each of the three tested waste forms (Cast Stone 2M, Ceramicrete and DuraLith). Therefore, any one of the three methods can be used to determine the contaminant diffusivities from a selected waste form.« less

  4. U-235 Holdup Measurements in the 321-M Lathe HEPA Banks

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Salaymeh, S.R.

    The Analytical Development Section of Savannah River Technology Center (SRTC) was requested by the Facilities Decommissioning Division (FDD) to determine the holdup of enriched uranium in the 321-M facility as part of an overall deactivation project of the facility. The results of the holdup assays are essential for determining compliance with the Waste Acceptance Criteria, Material Control and Accountability, and to meet criticality safety controls. This report covers holdup measurements of uranium residue in six high efficiency particulate air (HEPA) filter banks of the A-lathe and B-lathe exhaust systems of the 321-M facility. This report discusses the non-destructive assay measurements,more » assumptions, calculations, and results of the uranium holdup in these six items.« less

  5. 40 CFR 264.198 - Special requirements for ignitable or reactive wastes.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... waste, mixture, or dissolved material no longer meets the definition of ignitable or reactive waste... comply with the requirements for the maintenance of protective distances between the waste management... reactive wastes. 264.198 Section 264.198 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY...

  6. 40 CFR 265.198 - Special requirements for ignitable or reactive wastes.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ...) The resulting waste, mixture, or dissolved material no longer meets the definition of ignitable or... reactive wastes. 265.198 Section 265.198 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) INTERIM STATUS STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE...

  7. 40 CFR 98.348 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... GREENHOUSE GAS REPORTING Municipal Solid Waste Landfills § 98.348 Definitions. Except as specified in this... contained in landfill gas. Industrial waste landfill means any landfill other than a municipal solid waste... capacity means the maximum amount of solid waste a landfill can accept. For the purposes of this subpart...

  8. Waste Characterization Methods

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Vigil-Holterman, Luciana R.; Naranjo, Felicia Danielle

    2016-02-02

    This report discusses ways to classify waste as outlined by LANL. Waste Generators must make a waste determination and characterize regulated waste by appropriate analytical testing or use of acceptable knowledge (AK). Use of AK for characterization requires several source documents. Waste characterization documentation must be accurate, sufficient, and current (i.e., updated); relevant and traceable to the waste stream’s generation, characterization, and management; and not merely a list of information sources.

  9. 40 CFR 262.87 - Reporting and recordkeeping.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... movements subject to this subpart, persons (e.g., exporters, recognized traders) who meet the definition of...(s) and applicable waste code(s) from the appropriate OECD waste list incorporated by reference in... imprisonment. (b) Exception reports. Any person who meets the definition of primary exporter in § 262.51 or who...

  10. 40 CFR 262.87 - Reporting and recordkeeping.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... movements subject to this subpart, persons (e.g., exporters, recognized traders) who meet the definition of...(s) and applicable waste code(s) from the appropriate OECD waste list incorporated by reference in... imprisonment. (b) Exception reports. Any person who meets the definition of primary exporter in § 262.51 or who...

  11. 40 CFR 262.87 - Reporting and recordkeeping.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... movements subject to this subpart, persons (e.g., exporters, recognized traders) who meet the definition of...(s) and applicable waste code(s) from the appropriate OECD waste list incorporated by reference in... imprisonment. (b) Exception reports. Any person who meets the definition of primary exporter in § 262.51 or who...

  12. 40 CFR 262.87 - Reporting and recordkeeping.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... movements subject to this subpart, persons (e.g., exporters, recognized traders) who meet the definition of...(s) and applicable waste code(s) from the appropriate OECD waste list incorporated by reference in... imprisonment. (b) Exception reports. Any person who meets the definition of primary exporter in § 262.51 or who...

  13. 77 FR 56241 - Board Meeting; October 17, 2012; Idaho Falls, ID

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-12

    .... Nuclear Waste Technical Review Board will meet to discuss DOE work on packaging, transporting, and...) plans for the packaging, transportation, and disposition of spent nuclear fuel (SNF) and high-level radioactive waste (HLW). Among the topics that will be discussed are current activities being undertaken by...

  14. Draft environmental assessment: Lavender Canyon site, Utah. Nuclear Waste Policy Act (Section 112). [Contains glossary

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified the Lavender Canyon site in Utah, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Lavender Canyon site and the eight other potentially acceptable sites h

  15. [Current status on storage, processing and risk communication of medical radioactive waste in Japan].

    PubMed

    Watanabe, Hiroshi; Yamaguchi, Ichiro; Kida, Tetsuo; Hiraki, Hitoshi; Fujibuchi, Toshioh; Maehara, Yoshiaki; Tsukamoto, Atsuko; Koizumi, Mitsue; Kimura, Yumi; Horitsugi, Genki

    2013-03-01

    Decay-in-storage for radioactive waste including that of nuclear medicine has not been implemented in Japan. Therefore, all medical radioactive waste is collected and stored at the Japan Radioisotope Association Takizawa laboratory, even if the radioactivity has already decayed out. To clarify the current situation between Takizawa village and Takizawa laboratory, we investigated the radiation management status and risk communication activities at the laboratory via a questionnaire and site visiting survey in June 2010. Takizawa laboratory continues to maintain an interactive relationship with local residents. As a result, Takizawa village permitted the acceptance of new medical radioactive waste containing Sr-89 and Y-90. However, the village did not accept any non-medical radioactive waste such as waste from research laboratories. To implement decay-in-storage in Japan, it is important to obtain agreement with all stakeholders. We must continue to exert sincere efforts to acquire the trust of all stakeholders.

  16. DOSE ASSESSMENTS FROM THE DISPOSAL OF LOW ...

    EPA Pesticide Factsheets

    Modeling the long-term performance of the RCRA-C disposal cell and potential doses to off-site receptors is used to derive maximum radionuclide specific concentrations in the wastes that would enable these wastes to be disposed of safely using the RCRA-C disposal cell technology. Modeling potential exposures to derive these waste acceptance concentrations involves modeling exposures to workers during storage, treatment and disposal of the wastes, as well as exposures to individuals after disposal operations have ceased. Post facility closure exposures can result from the slow expected degradation of the disposal cell over long time periods (one thousand years after disposal) and in advertent human intrusion. Provide a means of determining waste acceptance radionuclide concentrations for disposal of debris from radiological dispersal device incidents as well as low-activity wastes generated in commercial, medical and research activities, potentially serve as the technical basis for guidance on disposal of these materials.

  17. Participatory approach, acceptability and transparency of waste management LCAs: case studies of Torino and Cuneo.

    PubMed

    Blengini, Gian Andrea; Fantoni, Moris; Busto, Mirko; Genon, Giuseppe; Zanetti, Maria Chiara

    2012-09-01

    The paper summarises the main results obtained from two extensive applications of Life Cycle Assessment (LCA) to the integrated municipal solid waste management systems of Torino and Cuneo Districts in northern Italy. Scenarios with substantial differences in terms of amount of waste, percentage of separate collection and options for the disposal of residual waste are used to discuss the credibility and acceptability of the LCA results, which are adversely affected by the large influence of methodological assumptions and the local socio-economic constraints. The use of site-specific data on full scale waste treatment facilities and the adoption of a participatory approach for the definition of the most sensible LCA assumptions are used to assist local public administrators and stakeholders showing them that LCA can be operational to waste management at local scale. Copyright © 2012 Elsevier Ltd. All rights reserved.

  18. 40 CFR 273.55 - Off-site shipments.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ....55 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) STANDARDS FOR UNIVERSAL WASTE MANAGEMENT Standards for Universal Waste Transporters § 273.55 Off-site... universal waste being shipped off-site meets the Department of Transportation's definition of hazardous...

  19. 40 CFR 35.928-1 - Approval of the industrial cost recovery system.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... treatment works or (2) the charges to be collected by the grantee in providing waste water treatment... accepting waste-waters from other municipalities, the subscribers receiving waste treatment services from... municipalities contributing wastes to the treatment works. The public shall be consulted prior to adoption of the...

  20. 40 CFR 35.928-1 - Approval of the industrial cost recovery system.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... treatment works or (2) the charges to be collected by the grantee in providing waste water treatment... accepting waste-waters from other municipalities, the subscribers receiving waste treatment services from... municipalities contributing wastes to the treatment works. The public shall be consulted prior to adoption of the...

  1. 40 CFR 60.757 - Reporting requirements.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... current amount of solid waste-in-place and the estimated waste acceptance rate for each year of the 5...) STANDARDS OF PERFORMANCE FOR NEW STATIONARY SOURCES Standards of Performance for Municipal Solid Waste... areas where solid waste may be landfilled according to the permit issued by the State, local, or tribal...

  2. 40 CFR 60.757 - Reporting requirements.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... current amount of solid waste-in-place and the estimated waste acceptance rate for each year of the 5...) STANDARDS OF PERFORMANCE FOR NEW STATIONARY SOURCES Standards of Performance for Municipal Solid Waste... areas where solid waste may be landfilled according to the permit issued by the State, local, or tribal...

  3. 40 CFR 60.757 - Reporting requirements.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... current amount of solid waste-in-place and the estimated waste acceptance rate for each year of the 5...) STANDARDS OF PERFORMANCE FOR NEW STATIONARY SOURCES Standards of Performance for Municipal Solid Waste... areas where solid waste may be landfilled according to the permit issued by the State, local, or tribal...

  4. 40 CFR 60.757 - Reporting requirements.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... current amount of solid waste-in-place and the estimated waste acceptance rate for each year of the 5...) STANDARDS OF PERFORMANCE FOR NEW STATIONARY SOURCES Standards of Performance for Municipal Solid Waste... areas where solid waste may be landfilled according to the permit issued by the State, local, or tribal...

  5. 40 CFR 60.757 - Reporting requirements.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... current amount of solid waste-in-place and the estimated waste acceptance rate for each year of the 5...) STANDARDS OF PERFORMANCE FOR NEW STATIONARY SOURCES Standards of Performance for Municipal Solid Waste... areas where solid waste may be landfilled according to the permit issued by the State, local, or tribal...

  6. Supplemental Immobilization of Hanford Low-Activity Waste: Cast Stone Screening Tests

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Westsik, Joseph H.; Piepel, Gregory F.; Lindberg, Michael J.

    2013-09-30

    More than 56 million gallons of radioactive and hazardous waste are stored in 177 underground storage tanks at the U.S. Department of Energy’s (DOE’s) Hanford Site in southeastern Washington State. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the wastes and immobilize them in a glass waste form. The WTP includes a pretreatment facility to separate the wastes into a small volume of high-level waste (HLW) containing most of the radioactivity and a larger volume of low-activity waste (LAW) containing most of the nonradioactive chemicals. The HLW will be converted to glass in themore » HLW vitrification facility for ultimate disposal at an offsite federal repository. At least a portion (~35%) of the LAW will be converted to glass in the LAW vitrification facility and will be disposed of onsite at the Integrated Disposal Facility (IDF). The pretreatment and HLW vitrification facilities will have the capacity to treat and immobilize the wastes destined for each facility. However, a second LAW immobilization facility will be needed for the expected volume of LAW requiring immobilization. A cementitious waste form known as Cast Stone is being considered to provide the required additional LAW immobilization capacity. The Cast Stone waste form must be acceptable for disposal in the IDF. The Cast Stone waste form and immobilization process must be tested to demonstrate that the final Cast Stone waste form can comply with the waste acceptance criteria for the disposal facility and that the immobilization processes can be controlled to consistently provide an acceptable waste form product. Further, the waste form must be tested to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support risk assessment and performance assessment (PA) analyses of the long-term environmental impact of the waste disposal in the IDF. The PA is needed to satisfy both Washington State IDF Permit and DOE Order requirements. Cast Stone has been selected for solidification of radioactive wastes including WTP aqueous secondary wastes treated at the Effluent Treatment Facility (ETF) at Hanford. A similar waste form called Saltstone is used at the Savannah River Site (SRS) to solidify its LAW tank wastes.« less

  7. 33 CFR 159.305 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... in 40 CFR 401.15. Sewage—means human body wastes and the wastes from toilets and other receptacles intended to receive or retain body waste. Treated Sewage—means sewage meeting all applicable effluent...

  8. 33 CFR 159.305 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... in 40 CFR 401.15. Sewage—means human body wastes and the wastes from toilets and other receptacles intended to receive or retain body waste. Treated Sewage—means sewage meeting all applicable effluent...

  9. 78 FR 57538 - Proposed Waste Confidence Rule and Draft Generic Environmental Impact Statement

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-19

    ....nrc.gov/public-involve/public-meetings/index.cfm no later than 10 days prior to the meetings. Dated at... storage of spent nuclear fuel beyond a reactor's licensed life for operation and prior to ultimate... the proposed Waste Confidence rule and DGEIS in order to maximize public participation at these...

  10. 78 FR 56621 - Draft Waste Confidence Generic Environmental Impact Statement

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-13

    .../public-involve/public-meetings/index.cfm no later than 10 days prior to the meetings. Dated at Rockville... licensed life for operation and prior to ultimate disposal (proposed Waste Confidence rule). The NRC staff... confirming receipt, then contact us at 301-415-1677. Fax comments to: Secretary, U.S. Nuclear Regulatory...

  11. 40 CFR 63.1096 - What requirements must I comply with if I transfer waste off-site?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... or transport of each waste stream. The notice shall state that the waste stream contains organic HAP... written certification that the transferee will manage and treat any waste stream received from a source... providing this written certification to the Administrator, the certifying entity accepts responsibility for...

  12. 40 CFR 227.8 - Limitations on the disposal rates of toxic wastes.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ...) OCEAN DUMPING CRITERIA FOR THE EVALUATION OF PERMIT APPLICATIONS FOR OCEAN DUMPING OF MATERIALS Environmental Impact § 227.8 Limitations on the disposal rates of toxic wastes. No wastes will be deemed acceptable for ocean dumping unless such wastes can be dumped so as not to exceed the limiting permissible...

  13. 40 CFR 227.8 - Limitations on the disposal rates of toxic wastes.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ...) OCEAN DUMPING CRITERIA FOR THE EVALUATION OF PERMIT APPLICATIONS FOR OCEAN DUMPING OF MATERIALS Environmental Impact § 227.8 Limitations on the disposal rates of toxic wastes. No wastes will be deemed acceptable for ocean dumping unless such wastes can be dumped so as not to exceed the limiting permissible...

  14. 40 CFR 227.8 - Limitations on the disposal rates of toxic wastes.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ...) OCEAN DUMPING CRITERIA FOR THE EVALUATION OF PERMIT APPLICATIONS FOR OCEAN DUMPING OF MATERIALS Environmental Impact § 227.8 Limitations on the disposal rates of toxic wastes. No wastes will be deemed acceptable for ocean dumping unless such wastes can be dumped so as not to exceed the limiting permissible...

  15. 40 CFR 227.8 - Limitations on the disposal rates of toxic wastes.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ...) OCEAN DUMPING CRITERIA FOR THE EVALUATION OF PERMIT APPLICATIONS FOR OCEAN DUMPING OF MATERIALS Environmental Impact § 227.8 Limitations on the disposal rates of toxic wastes. No wastes will be deemed acceptable for ocean dumping unless such wastes can be dumped so as not to exceed the limiting permissible...

  16. 40 CFR 227.8 - Limitations on the disposal rates of toxic wastes.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ...) OCEAN DUMPING CRITERIA FOR THE EVALUATION OF PERMIT APPLICATIONS FOR OCEAN DUMPING OF MATERIALS Environmental Impact § 227.8 Limitations on the disposal rates of toxic wastes. No wastes will be deemed acceptable for ocean dumping unless such wastes can be dumped so as not to exceed the limiting permissible...

  17. HANFORD FACILITY ANNUAL DANGEROUS WASTE REPORT CY2005

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    SKOLRUD, J.O.

    2006-02-15

    The Hanford Facility Annual Dangerous Waste Report (ADWR) is prepared to meet the requirements of Washington Administrative Code Sections 173-303-220, Generator Reporting, and 173-303-390, Facility Reporting. In addition, the ADWR is required to meet Hanford Facility RCR4 Permit Condition I.E.22, Annual Reporting. The ADWR provides summary information on dangerous waste generation and management activities for the Calendar Year for the Hanford Facility EPA ID number assigned to the Department of Energy for RCRA regulated waste, as well as Washington State only designated waste and radioactive mixed waste. An electronic database is utilized to collect and compile the large array ofmore » data needed for preparation of this report. Information includes details of waste generated on the Hanford Facility, waste generated offsite and sent to Hanford for management, and other waste management activities conducted at Hanford, including treatment, storage, and disposal. Report details consist of waste descriptions and weights, waste codes and designations, and waste handling codes, In addition, for waste shipped to Hanford for treatment and/or disposal, information on manifest numbers, the waste transporter, the waste receiving facility, and the original waste generators are included. In addition to paper copies, the report is also transmitted electronically to a web site maintained by the Washington State Department of Ecology.« less

  18. Publication Rates of Podium Versus Poster Presentations at the Arthroscopy Association of North America Meetings 2008-2012.

    PubMed

    Frank, Rachel M; Cvetanovich, Gregory L; Collins, Michael J; Arns, Thomas A; Black, Austin; Verma, Nikhil N; Cole, Brian J; Forsythe, Brian

    2017-01-01

    To analyze the publication rate of poster and podium presentations at Arthroscopy Association of North America (AANA) annual meetings from 2008 to 2012. An online search using PubMed and Google Scholar for all published manuscripts associated with abstracts presented from 2008 to 2012 AANA annual meetings was performed. Abstracts were classified by presentation type (poster vs podium), and the journal and publication date were recorded for all published abstracts. Descriptive statistics, logistic regression, and Fisher's exact tests were performed, with P < .05 considered significant. A total of 1,508 abstracts were submitted to AANA annual meetings from 2008 to 2012, with 976 abstracts accepted for presentation (65% overall acceptance rate). There were 328 podium (22% acceptance rate) and 648 poster (43% acceptance rate) presentations. Of the 976 accepted abstracts, 479 (49%) were published within 3 years in peer-reviewed journals. The overall publication rates for podium and poster presentations were 59% (n = 193) and 44% (n = 286), respectively. Podium presentations were significantly more likely to be published within 3 years compared with poster presentations (P < .0001; odds ratio 1.8095, confidence interval 1.3826-2.3682). There were no differences in time to publication between podium and poster presentations (1.3 ± 1.2 vs 1.1 ± 1.3 years, P = .0633). Over the 5-year study period, the overall abstract acceptance rate (P < .0001) and the rate of abstracts accepted for poster presentation (P < .0001) increased significantly over time, whereas there was no increase in the rate of abstracts accepted for podium presentation (P = .5638). The most common journals of publication were Arthroscopy (n = 157, 32.7%) followed by American Journal of Sports Medicine (n = 93, 19.4%). The overall publication rate of abstracts presented at AANA annual meetings is 49%, with podium presentations 1.8 times more likely to be published than poster presentations. The overall abstract acceptance rate and the rate of abstracts accepted for poster presentation increased significantly over time, whereas there was no significant increase in the rate of abstracts accepted for podium presentation. The publication rates of abstracts presented at the AANA annual meetings demonstrate the meetings' impact and importance to the advancement of the scientific literature. Copyright © 2016 Arthroscopy Association of North America. Published by Elsevier Inc. All rights reserved.

  19. 40 CFR 265.1 - Purpose, scope, and applicability.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ....1 Section 265.1 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) INTERIM STATUS STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE TREATMENT, STORAGE, AND... establish minimum national standards that define the acceptable management of hazardous waste during the...

  20. Summary of the study of disposal of nuclear waste into space

    NASA Technical Reports Server (NTRS)

    Rom, F. E.

    1973-01-01

    The space shuttle together with expendable and nonexpendable orbital stages such as the space tug or Centaur can safely dispose of waste material by ejecting it from the solar system. The safety problems associated with all phases of launching and operation (normal, emergency, and accident) of such a system are being examined. It appears that solutions can be found that should make the risks acceptable when compared to the benefits to be obtained from the disposal of the nuclear waste. The techniques proposed to make such a system acceptable need to be carefully verified by further study and experiment.

  1. 30 CFR 817.84 - Coal mine waste: Impounding structures.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 3 2014-07-01 2014-07-01 false Coal mine waste: Impounding structures. 817.84... ACTIVITIES § 817.84 Coal mine waste: Impounding structures. New and existing impounding structures constructed of coal mine waste or intended to impound coal mine waste shall meet the requirements of § 817.81...

  2. 30 CFR 816.84 - Coal mine waste: Impounding structures.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Coal mine waste: Impounding structures. 816.84... ACTIVITIES § 816.84 Coal mine waste: Impounding structures. New and existing impounding structures constructed of coal mine waste or intended to impound coal mine waste shall meet the requirements of § 816.81...

  3. 30 CFR 816.84 - Coal mine waste: Impounding structures.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 3 2011-07-01 2011-07-01 false Coal mine waste: Impounding structures. 816.84... ACTIVITIES § 816.84 Coal mine waste: Impounding structures. New and existing impounding structures constructed of coal mine waste or intended to impound coal mine waste shall meet the requirements of § 816.81...

  4. 30 CFR 817.84 - Coal mine waste: Impounding structures.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Coal mine waste: Impounding structures. 817.84... ACTIVITIES § 817.84 Coal mine waste: Impounding structures. New and existing impounding structures constructed of coal mine waste or intended to impound coal mine waste shall meet the requirements of § 817.81...

  5. 30 CFR 816.84 - Coal mine waste: Impounding structures.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 3 2012-07-01 2012-07-01 false Coal mine waste: Impounding structures. 816.84... ACTIVITIES § 816.84 Coal mine waste: Impounding structures. New and existing impounding structures constructed of coal mine waste or intended to impound coal mine waste shall meet the requirements of § 816.81...

  6. 30 CFR 817.84 - Coal mine waste: Impounding structures.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 3 2011-07-01 2011-07-01 false Coal mine waste: Impounding structures. 817.84... ACTIVITIES § 817.84 Coal mine waste: Impounding structures. New and existing impounding structures constructed of coal mine waste or intended to impound coal mine waste shall meet the requirements of § 817.81...

  7. 30 CFR 817.84 - Coal mine waste: Impounding structures.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 3 2013-07-01 2013-07-01 false Coal mine waste: Impounding structures. 817.84... ACTIVITIES § 817.84 Coal mine waste: Impounding structures. New and existing impounding structures constructed of coal mine waste or intended to impound coal mine waste shall meet the requirements of § 817.81...

  8. 30 CFR 816.84 - Coal mine waste: Impounding structures.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 3 2014-07-01 2014-07-01 false Coal mine waste: Impounding structures. 816.84... ACTIVITIES § 816.84 Coal mine waste: Impounding structures. New and existing impounding structures constructed of coal mine waste or intended to impound coal mine waste shall meet the requirements of § 816.81...

  9. 30 CFR 817.84 - Coal mine waste: Impounding structures.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 3 2012-07-01 2012-07-01 false Coal mine waste: Impounding structures. 817.84... ACTIVITIES § 817.84 Coal mine waste: Impounding structures. New and existing impounding structures constructed of coal mine waste or intended to impound coal mine waste shall meet the requirements of § 817.81...

  10. 30 CFR 816.84 - Coal mine waste: Impounding structures.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 3 2013-07-01 2013-07-01 false Coal mine waste: Impounding structures. 816.84... ACTIVITIES § 816.84 Coal mine waste: Impounding structures. New and existing impounding structures constructed of coal mine waste or intended to impound coal mine waste shall meet the requirements of § 816.81...

  11. Implementation of SAP Waste Management System

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Frost, M.L.; LaBorde, C.M.; Nichols, C.D.

    2008-07-01

    The Y-12 National Security Complex (Y-12) assumed responsibility for newly generated waste on October 1, 2005. To ensure effective management and accountability of newly generated waste, Y-12 has opted to utilize SAP, Y-12's Enterprise Resource Planning (ERP) tool, to track low-level radioactive waste (LLW), mixed waste (MW), hazardous waste, and non-regulated waste from generation through acceptance and disposal. SAP Waste will include the functionality of the current waste tracking system and integrate with the applicable modules of SAP already in use. The functionality of two legacy systems, the Generator Entry System (GES) and the Waste Information Tracking System (WITS), andmore » peripheral spreadsheets, databases, and e-mail/fax communications will be replaced by SAP Waste. Fundamentally, SAP Waste will promote waste acceptance for certification and disposal, not storage. SAP Waste will provide a one-time data entry location where waste generators can enter waste container information, track the status of their waste, and maintain documentation. A benefit of the new system is that it will provide a single data repository where Y-12's Waste Management organization can establish waste profiles, verify and validate data, maintain inventory control utilizing hand-held data transfer devices, schedule and ship waste, manage project accounting, and report on waste handling activities. This single data repository will facilitate the production of detailed waste generation reports for use in forecasting and budgeting, provide the data for required regulatory reports, and generate metrics to evaluate the performance of the Waste Management organization and its subcontractors. SAP Waste will replace the outdated and expensive legacy system, establish tools the site needs to manage newly generated waste, and optimize the use of the site's ERP tool for integration with related business processes while promoting disposition of waste. (authors)« less

  12. Maximizing Meetings: Plan to Be Productive

    ERIC Educational Resources Information Center

    Hughes, Michelle

    2008-01-01

    Responsible for calling meetings? Dread the thought of attending another meeting that misses the mark and wastes everyone's time? This article offers tips to improve the effectiveness of meetings by planning their structure. (Contains 2 tables.)

  13. Interpretation of standard leaching test BS EN 12457-2: is your sample hazardous or inert?

    PubMed

    Zandi, Mohammad; Russell, Nigel V; Edyvean, Robert G J; Hand, Russell J; Ward, Philip

    2007-12-01

    A slag sample from a lead refiner has been obtained and given to two analytical laboratories to determine the release of trace elements from the sample according to BS EN 12457-2. Samples analysed by one laboratory passed waste acceptance criteria, leading it to be classified as an inert material; samples of the same material analysed by the other laboratory failed waste acceptance criteria and were classified as hazardous. It was found that the sample preparation procedure is the critical step in the leaching analysis and that the effects of particle size on leachability should be taken into account when using this standard. The purpose of this paper is to open a debate on designing a better defined standard leaching test and making current waste acceptance criteria more flexible.

  14. Process for treating waste water having low concentrations of metallic contaminants

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Looney, Brian B; Millings, Margaret R; Nichols, Ralph L

    A process for treating waste water having a low level of metallic contaminants by reducing the toxicity level of metallic contaminants to an acceptable level and subsequently discharging the treated waste water into the environment without removing the treated contaminants.

  15. Hazardous Waste Handling Should be Defined

    ERIC Educational Resources Information Center

    Steigman, Harry

    1972-01-01

    An examination of the handling, storage and disposition of hazardous wastes from municipal and industrial sources, with a plea for the development of a uniform national hazardous waste code or listing that would be acceptable and useful to all state and federal agencies. (LK)

  16. Hanford Facility Annual Dangerous Waste Report Calendar Year 2002

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    FREEMAN, D.A.

    2003-02-01

    Hanford CY 2002 dangerous waste generation and management forms. The Hanford Facility Annual Dangerous Waste Report (ADWR) is prepared to meet the requirements of Washington Administrative Code Sections 173-303-220, Generator Reporting, and 173-303-390, Facility Reporting. In addition, the ADWR is required to meet Hanford Facility RCRA Permit Condition I.E.22, Annual Reporting. The ADWR provides summary information on dangerous waste generation and management activities for the Calendar Year for the Hanford Facility EPA ID number assigned to the Department of Energy for RCRA regulated waste, as well as Washington State only designated waste and radioactive mixed waste. The Solid Waste Informationmore » and Tracking System (SWITS) database is utilized to collect and compile the large array of data needed for preparation of this report. Information includes details of waste generated on the Hanford Facility, waste generated offsite and sent to Hanford for management, and other waste management activities conducted at Hanford, including treatment, storage, and disposal. Report details consist of waste descriptions and weights, waste codes and designations, and waste handling codes. In addition, for waste shipped to Hanford for treatment and/or disposal, information on manifest numbers, the waste transporter, the waste receiving facility, and the original waste generators are included. In addition to paper copies, electronic copies of the report are also transmitted to the regulatory agency.« less

  17. Chemical and radiological risk factors associated with waste from energy production.

    PubMed

    Christensen, T; Fuglestvedt, J; Benestad, C; Ehdwall, H; Hansen, H; Mustonen, R; Stranden, E

    1992-04-01

    We have tried to estimate the toxic potential of waste from nuclear power plants and from power plants burning fossil fuels. The potential risks have been expressed as 'risk potentials' or 'person equivalents.' These are purely theoretical units and represent only an attempt to quantify the potential impact of different sources and substances on human health. Existing concentration limits for effects on human health are used. The philosophy behind establishing limits for several carcinogenic chemicals is based on a linear dose-effect curve. That is, no lower concentration of no effect exists and one has to accept a certain small risk by accepting the concentration limit. This is in line with the establishment of limits for radiation. Waste products from coal combustion have the highest potential risk among the fossil fuel alternatives. The highest risk is caused by metals, and the fly ash represents the effluent stream giving the largest contribution to the potential risk. The waste from nuclear power production has a lower potential risk than coal if today's limit values re used. If one adjusts the limits for radiation dose and the concentration limit values so that a similar risk is accepted by the limits, nuclear waste seems to have a much higher potential risk than waste from fossil fuel. The possibility that such risk estimates may be used as arguments for safe storage of the different types of waste is discussed. In order to obtain the actual risk from the potential risk, the dispersion of the waste in the environment and its uptake and effects in man have to be taken into account.

  18. RCRA Summary Document for the David Witherspoon 1630 Site, Knoxville, Tennessee

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Pfeffer, J.

    2008-06-10

    The 48-acre David Witherspoon, Inc. (DWI) 1630 Site operated as an unregulated industrial landfill and scrap yard. The Tennessee Division of Superfund (TDSF) closed the landfill in 1974. During the period of operation, the site received solid and liquid wastes from salvage and industrial operations. The site consists of five separate tracts of land including a small portion located across the Norfolk Southern Railroad track. The landfill occupies approximately 5 acres of the site, and roughly 20 acres of the 48 acres contains surface and buried debris associated with the DWI dismantling business operation. Beginning in 1968, the state ofmore » Tennessee licensed DWI to receive scrap metal at the DWI 1630 Site, contaminated with natural uranium and enriched uranium (235U) not exceeding 0.1 percent by weight (TDSF 1990). The U.S. Department of Energy (DOE) has agreed to undertake remedial actions at the DWI 1630 Site as specified under a Consent Order with the Tennessee Department of Environment and Conservation (TDEC) (Consent Order No. 90-3443, April 4, 1991), and as further delineated by a Memorandum of Understanding (MOU) between DOE and the State of Tennessee (MOU Regarding Implementation of Consent Orders, October 6, 1994). The soil and debris removal at the DWI 1630 Site is being performed by Bechtel Jacobs Company LLC (BJC) on behalf of the DOE. Remediation consists of removing contaminated soil and debris from the DWI 1630 site except for the landfill area and repairing the landfill cap. The DWI 1630 remediation waste that is being disposed at the Environmental Management Waste Management Facility (EMWMF) as defined as waste lot (WL) 146.1 and consists primarily of soils and soil like material, incidental debris and secondary waste generated from the excavation of debris and soil from the DWI 1630 site. The WL 146.1 includes soil, soil like material (e.g., shredded or chipped vegetation, ash), discrete debris items (e.g., equipment, drums, large scrap metal, cylinders, and cable) and populations of debris type items (e.g., piles of bricks, small scrap metal, roofing material, scaffolding, and shelving) that are located throughout the DWI 1630 site. The project also generates an additional small volume of secondary waste [e.g., personal protective equipment (PPE), and miscellaneous construction waste] that is bagged and included in bulk soil shipments to the EMWMF. The Waste Acceptance Criteria (WAC) for the EMWMF does not allow for material that does not meet the Resource Conservation and Recovery Act (RCRA) Land Disposal Restrictions (LDRs). The waste being excavated in certain areas of the DWI 1630 site contained soil that did not meet RCRA LDR criteria; therefore this waste had to be segregated for treatment or alternate disposal offsite. This document identifies the approach taken by the DWI 1630 project to further characterize the areas identified during the Phase II Remedial Investigation (RI) as potentially containing RCRA-characteristic waste. This document also describes the methodology used to determine excavation limits for areas determined to be RCRA waste, post excavation sampling, and the treatment and disposal of this material.« less

  19. 78 FR 65903 - Proposed Waste Confidence Rule and Draft Generic Environmental Impact Statement

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-04

    .../public-involve/public-meetings/index.cfm no later than 10 days prior to each meeting. Dated at Rockville... reactor's licensed life for operation and prior to ultimate disposal (the proposed Waste Confidence rule... documents online in the NRC Library at http://www.nrc.gov/reading-rm/adams.html . To begin the search...

  20. DOE's Notification of Planned Change to the EPA 40 CFR Part 194 Certification of the Waste Isolation Pilot Plant: Remote-Handled Transuranic Waste Characterization Plan

    EPA Pesticide Factsheets

    The U.S. Department of Energy's Carlsbad Field Office (DOE/CBFO) provided the U.S. Environmental Protection Agency (EPA) this Notification of Planned Change to accept remote-handled (RH) transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP).

  1. 40 CFR 262.104 - What are the minimum performance criteria?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ...) SOLID WASTES (CONTINUED) STANDARDS APPLICABLE TO GENERATORS OF HAZARDOUS WASTE University Laboratories... criteria? The Minimum Performance Criteria that each University must meet in managing its Laboratory Waste are: (a) Each University must label all laboratory waste with the general hazard class and either the...

  2. 40 CFR 262.104 - What are the minimum performance criteria?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ...) SOLID WASTES (CONTINUED) STANDARDS APPLICABLE TO GENERATORS OF HAZARDOUS WASTE University Laboratories... criteria? The Minimum Performance Criteria that each University must meet in managing its Laboratory Waste are: (a) Each University must label all laboratory waste with the general hazard class and either the...

  3. 40 CFR 262.104 - What are the minimum performance criteria?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ...) SOLID WASTES (CONTINUED) STANDARDS APPLICABLE TO GENERATORS OF HAZARDOUS WASTE University Laboratories... criteria? The Minimum Performance Criteria that each University must meet in managing its Laboratory Waste are: (a) Each University must label all laboratory waste with the general hazard class and either the...

  4. Energy and nutrient intake and acceptability of nutritionally balanced school meals in Filipino students.

    PubMed

    Angeles-Agdeppa, Imelda; Neufingerl, Nicole; Magsadia, Clarita; Hiemstra, Harry; Patalen, Chona; Eilander, Ans

    2014-09-01

    School meals provide an excellent opportunity to improve children's diet. To investigate dietary intakes and acceptance of nutritionally balanced school meals ("nutrimeals") as compared with regular ("baseline") school meals among Filipino students. The study employed a before-after intervention design with one group. Students 13 to 16 years of age from a public school in Metro Manila (n = 112) consumed baseline school meals for 2 weeks followed by consumption of nutri-meals for 7 weeks. Served meals and plate waste were weighed to calculate food and nutrient intakes. Acceptability of meals was assessed daily in a random subsample using a seven-point hedonic scale. Analysis of covariance corrected for age and sex was conducted to test for differences in nutrient intakes and acceptability between nutri-meals and baseline meals. Feeding nutri-meals resulted in a higher intake of vegetables (95.3 ± 13.8 g), fruit (76.5 ± 6.3 g), and fish (19.1 ± 3.3 g) than baseline meals. Energy and protein intakes significantly increased by 140.7 ± 2.8 kcal and 3.2 ± 0.1 g, respectively. The quality of fat intake improved compared with baseline meals (p < .001). Micronutrient intake from nutri-meals was significantly higher than that from baseline meals (except for zinc), contributing 6% to 79% of recommended daily intakes. Most students (> 90%) liked both baseline and nutrimeals; however, the mean acceptability score for baseline meals was slightly higher (0.2 ± 0.07 points, p = .004). Nutritionally balanced nutri-meals may be a healthier and acceptable alternative to regular Filipino school meals. Further optimization of nutri-meals is required to meet the nutritional needs of adolescents and reduce sodium content.

  5. Application of the Evacuated Canister System for Removing Residual Molten Glass From the West Valley Demonstration Project High-Level Waste Melter

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    May, Joseph J.; Dombrowski, David J.; Valenti, Paul J.

    The principal mission of the West Valley Demonstration Project (WVDP) is to meet a series of objectives defined in the West Valley Demonstration Project Act (Public Law 96-368). Chief among these is the objective to solidify liquid high-level waste (HLW) at the WVDP site into a form suitable for disposal in a federal geologic repository. In 1982, the Secretary of Energy formally selected vitrification as the technology to be used to solidify HLW at the WVDP. One of the first steps in meeting the HLW solidification objective involved designing, constructing and operating the Vitrification (Vit) Facility, the WVDP facility thatmore » houses the systems and subsystems used to process HLW into stainless steel canisters of borosilicate waste-glass that satisfy waste acceptance criteria (WAC) for disposal in a federal geologic repository. HLW processing and canister production began in 1996. The final step in meeting the HLW solidification objective involved ending Vit system operations and shut ting down the Vit Facility. This was accomplished by conducting a discrete series of activities to remove as much residual material as practical from the primary process vessels, components, and associated piping used in HLW canister production before declaring a formal end to Vit system operations. Flushing was the primary method used to remove residual radioactive material from the vitrification system. The inventory of radioactivity contained within the entire primary processing system diminished by conducting the flushing activities. At the completion of flushing activities, the composition of residual molten material remaining in the melter (the primary system component used in glass production) consisted of a small quantity of radioactive material and large quantities of glass former materials needed to produce borosilicate waste-glass. A special system developed during the pre-operational and testing phase of Vit Facility operation, the Evacuated Canister System (ECS), was deployed at the West Valley Demonstration Project to remove this radioactively dilute, residual molten material from the melter before Vit system operations were brought to a formal end. The ECS consists of a stainless steel canister of the same size and dimensions as a standard HLW canister that is equipped with a special L-shaped snorkel assembly made of 304L stainless steel. Both the canister and snorkel assembly fit into a stainless steel cage that allows the entire canister assembly to be positioned over the melter as molten glass is drawn out by a vacuum applied to the canister. This paper describes the process used to prepare and apply the ECS to complete molten glass removal before declaring a formal end to Vit system operations and placing the Vit Facility into a safe standby mode awaiting potential deactivation.« less

  6. Impact of community engagement on public acceptance towards waste-to-energy incineration projects: Empirical evidence from China.

    PubMed

    Liu, Yong; Sun, Chenjunyan; Xia, Bo; Cui, Caiyun; Coffey, Vaughan

    2018-06-01

    As one of the most popular methods for the treatment of municipal solid waste (MSW), waste-to-energy (WTE) incineration offers effective solutions to deal with the MSW surge and globe energy issues. Nevertheless, the construction of WTE facilities faces considerable and strong opposition from local communities due to the perceived potential risks. The present study aims to understand whether, and how, community engagement improves local residents' public acceptance towards waste-to-energy (WTE) incineration facilities using a questionnaire survey conducted with nearby residents of two selected WTE incineration plants located in Zhejiang province, China. The results of data analysis using Structural Equation Modeling (SEM) reveal that firstly, a lower level of public acceptance exists among local residents of over the age of 35, of lower education levels, living within 3 km from the WTE Plant and from WTE incineration Plants which are under construction. Secondly, the public trust of local government and other authorities was positively associated with the public acceptance of the WTE incineration project, both directly and indirectly based on perceived risk. Thirdly, community engagement can effectively enhance public trust in local government and other authorities related to the WTE incineration project. The findings contribute to the literature on MSW treatment policy-making and potentially hazardous facility siting, by exploring the determinants of public acceptance towards WTE incineration projects. Copyright © 2018 Elsevier Ltd. All rights reserved.

  7. HANFORD FACILITY ANNUAL DANGEROUS WASTE REPORT CY2003 [SEC 1 & 2

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    FREEMAN, D.A.

    2004-02-17

    The Hanford Facility Annual Dangerous Waste Report (ADWR) is prepared to meet the requirements of Washington Administrative Code Sections 173-303-220, Generator Reporting, and 173-303-390, Facility Reporting. In addition, the ADWR is required to meet Hanford Facility RCRA Permit Condition I.E.22, Annual Reporting. The ADWR provides summary information on dangerous waste generation and management activities for the Calendar Year for the Hanford Facility EPA ID number assigned to the Department of Energy for RCRA regulated waste, as well as Washington State only designated waste and radioactive mixed waste. The Solid Waste Information and Tracking System (SWITS) database is utilized to collectmore » and compile the large array of data needed for preparation of this report. Information includes details of waste generated on the Hanford Facility, waste generated offsite and sent to Hanford for management, and other waste management activities conducted at Hanford, including treatment, storage, and disposal. Report details consist of waste descriptions and weights, waste codes and designations, and waste handling codes. In addition, for waste shipped to Hanford for treatment and or disposal, information on manifest numbers, the waste transporter, the waste receiving facility, and the original waste generators are included. In addition to paper copies, the report is also transmitted electronically to a web site maintained by the Washington State Department of Ecology.« less

  8. MOBILITY AND DEGRADATION OF RESIDUES AT HAZARDOUS WASTE LAND TREATMENT SITES AT CLOSURE

    EPA Science Inventory

    Soil treatment systems that are designed and managed based on a knowledge of soil-waste interactions may represent a significant technology for simultaneous treatment and ultimate disposal of selected hazardous wastes in an environmentally acceptable manner. hese soil treatment s...

  9. 40 CFR 270.60 - Permits by rule.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) EPA ADMINISTERED PERMIT PROGRAMS: THE HAZARDOUS WASTE PERMIT PROGRAM Special Forms of Permits § 270.60 Permits by... operator of a barge or other vessel which accepts hazardous waste for ocean disposal, if the owner or...

  10. 40 CFR 270.60 - Permits by rule.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) EPA ADMINISTERED PERMIT PROGRAMS: THE HAZARDOUS WASTE PERMIT PROGRAM Special Forms of Permits § 270.60 Permits by... operator of a barge or other vessel which accepts hazardous waste for ocean disposal, if the owner or...

  11. 40 CFR 98.340 - Definition of the source category.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... (CONTINUED) MANDATORY GREENHOUSE GAS REPORTING Municipal Solid Waste Landfills § 98.340 Definition of the source category. (a) This source category applies to municipal solid waste (MSW) landfills that accepted... of the following sources at municipal solid waste (MSW) landfills: Landfills, landfill gas collection...

  12. 40 CFR 62.1351 - Identification of sources.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... Landfill Gas Emissions from Existing Municipal Solid Waste Landfills § 62.1351 Identification of sources. The plan applies to all existing municipal solid waste landfills for which construction, reconstruction, or modification was commenced before May 30, 1991 that accepted waste at any time since November...

  13. 40 CFR 240.205-3 - Recommended procedures: Operations.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ...) SOLID WASTES GUIDELINES FOR THE THERMAL PROCESSING OF SOLID WASTES Requirements and Recommended... excessive emissions, appropriate adjustments should be made to lower the emission to acceptable levels. ...

  14. 40 CFR 267.111 - What general standards must I meet when I stop operating the unit?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... to protect human health and the environment, post-closure escape of hazardous waste, hazardous constituents, leachate, contaminated run-off, or hazardous waste decomposition products to the ground or... PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE...

  15. 40 CFR 267.111 - What general standards must I meet when I stop operating the unit?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... to protect human health and the environment, post-closure escape of hazardous waste, hazardous constituents, leachate, contaminated run-off, or hazardous waste decomposition products to the ground or... PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE...

  16. 40 CFR 148.21 - Information to be submitted in support of petitions.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... will lead to waste transformation; and (2) Results of laboratory experiments verifying the waste... (CONTINUED) WATER PROGRAMS (CONTINUED) HAZARDOUS WASTE INJECTION RESTRICTIONS Petition Standards and... of § 148.20 must meet the following criteria: (1) All waste analysis and any new testing performed by...

  17. Analysis of alternatives for immobilized low activity waste disposal

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Burbank, D.A.

    This report presents a study of alternative disposal system architectures and implementation strategies to provide onsite near-surface disposal capacity to receive the immobilized low-activity waste produced by the private vendors. The analysis shows that a flexible unit strategy that provides a suite of design solutions tailored to the characteristics of the immobilized low-activity waste will provide a disposal system that best meets the program goals of reducing the environmental, health, and safety impacts; meeting the schedule milestones; and minimizing the life-cycle cost of the program.

  18. Opportunities for Cost Effective Disposal of Radioactively Contaminated Solid Waste on the Oak Ridge Reservation, Oak Ridge, TN - 13045

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    DeMonia, Brian; Dunning, Don; Hampshire John

    2013-07-01

    Department of Energy (DOE) requirements for the release of non-real property, including solid waste, containing low levels of residual radioactive materials are specified in DOE Order 458.1 and associated guidance. Authorized limits have been approved under the requirements of DOE Order 5400.5, predecessor to DOE Order 458.1, to permit disposal of solid waste containing low levels of residual radioactive materials at solid waste landfills located within the DOE Oak Ridge Reservation (ORR). Specifically, volumetric concentration limits for disposal of solid waste at Industrial Landfill V and at Construction/Demolition Landfill VII were established in 2003 and 2007, respectively, based on themore » requirements in effect at that time, which included: an evaluation to ensure that radiation doses to the public would not exceed 25 mrem/year and would be as low as reasonably achievable (ALARA), with a goal of a few mrem/year or less (in fact, these authorized limits actually were derived to meet a dose constraint of 1 mrem/year); an evaluation of compliance with groundwater protection requirements; and reasonable assurance that the proposed disposal is not likely to result in a future requirement for remediation of the landfill. Prior to approval as DOE authorized limits, these volumetric concentration limits were coordinated with the Tennessee Department of Environment and Conservation (TDEC) and documented in a Memorandum of Understanding (MOU) between the TDEC Division of Radiological Health and the TDEC Division of Solid Waste Management. These limits apply to the disposal of soil and debris waste generated from construction, maintenance, environmental restoration, and decontamination and decommissioning (D and D) activities on the DOE Oak Ridge Reservation. The approved site-specific authorized limits were incorporated in the URS/CH2M Oak Ridge LLC (UCOR) waste profile system that authorizes disposal of special wastes at either of the RCRA Subtitle D landfills. However, a recent DOE assessment found that implementation of the site-specific authorized limits for volumetrically contaminated waste was potentially limited due in part to confusion regarding the applicability of volumetric concentration limits and/or surface activity limits to specific wastes. This paper describes recent efforts to update the authorized limits for Industrial Landfill V and Construction/Demolition Landfill VII and to improve the procedures for implementation of these criteria. The approved authorized limits have been evaluated and confirmed to meet the current requirements of DOE Order 458.1, which superseded DOE Order 5400.5 in February 2011. In addition, volumetric concentration limits have been developed for additional radionuclides, and site-specific authorized limits for wastes with surface contamination have been developed. Implementing procedures have been revised to clarify the applicability of volumetric concentration limits and surface activity limits, and to allow the use of non-destructive waste characterization methods. These changes have been designed to promote improved utilization of available disposal capacity of the onsite disposal facilities within the DOE Oak Ridge Reservation. In addition, these changes serve to bring the waste acceptance requirements at these DOE onsite landfills into greater consistency with the requirements for commercial/ public landfills under the TDEC Bulk Survey for Release (BSFR) program, including two public RCRA Subtitle D landfills in close proximity to the DOE Oak Ridge Reservation. (authors)« less

  19. Cement waste-form development for ion-exchange resins at the Rocky Flats Plant

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Veazey, G.W.; Ames, R.L.

    1997-03-01

    This report describes the development of a cement waste form to stabilize ion-exchange resins at Rocky Flats Environmental Technology Site (RFETS). These resins have an elevated potential for ignition due to inadequate wetness and contact with nitrates. The work focused on the preparation and performance evaluation of several Portland cement/resin formulations. The performance standards were chosen to address Waste Isolation Pilot Plant and Environmental Protection Agency Resource Conservation and Recovery Act requirements, compatibility with Rocky Flats equipment, and throughput efficiency. The work was performed with surrogate gel-type Dowex cation- and anion-exchange resins chosen to be representative of the resin inventorymore » at RFETS. Work was initiated with nonactinide resins to establish formulation ranges that would meet performance standards. Results were then verified and refined with actinide-containing resins. The final recommended formulation that passed all performance standards was determined to be a cement/water/resin (C/W/R) wt % ratio of 63/27/10 at a pH of 9 to 12. The recommendations include the acceptable compositional ranges for each component of the C/W/R ratio. Also included in this report are a recommended procedure, an equipment list, and observations/suggestions for implementation at RFETS. In addition, information is included that explains why denitration of the resin is unnecessary for stabilizing its ignitability potential.« less

  20. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Lewis, M.S.

    The Barnwell Waste Management Facility (BWMF) is scheduled to restrict access to waste generators outside of the Atlantic Compact (SC, CT, NJ) on July 1, 2008. South Carolina, authorized under the Low-Level Waste Policy Act of 1980 and Amendments Act of 1985, and in agreement with the other Atlantic Compact states, will only accept Class A, B, and C low-level radioactive waste (LLRW) generated within compact. For many years, the BWMF has been the only LLRW disposal facility to accept Class B and C waste from LLRW generators throughout the country, except those that have access to the Northwest Compactmore » Site. Many Class B/C waste generators consider this to be a national crisis situation requiring interim or possible permanent storage, changes in operation, significant cost impacts, and/or elimination of services, especially in the health care and non-power generation industries. With proper in-house waste management practices and utilization of commercial processor services, a national crisis can be avoided, although some generators with specific waste forms or radionuclides will remain without options. In summary: It is unknown what the future will bring for commercial LLRW disposal. Could the anticipated post Barnwell Class B/C crisis be avoided by any of the following? - Barnwell Site remains open for the nation's commercial Class B/C waste; - Richland Site opens back up to the nation for commercial Class B/C waste; - Texas Site opens up to the nation for commercial Class B/C waste; - Federal Government intervenes by keeping a commercial Class B/C site open for the nation's commercial Class B/C waste; - Federal Government makes a DOE site available for commercial Class B/C waste; - Federal Government revisits the LLRW Policy Act of 1980 and Amendments Act of 1985. Without a future LLRW site capable of accepting Class B/C currently on the horizon, commercial LLRW generators are faced with waste volume elimination, reduction, or storage. With proper in-house waste management practices, utilization of commercial processor services and regulatory relief, a national crisis can be avoided. Waste volumes for storage can be reduced to as little as 10% of the current Class B/C volume. Although a national LLRW crisis can be avoided, some generators with specific waste forms or radionuclides will have a significant financial and/or operational impact due to a lack of commercial LLRW management options. (authors)« less

  1. 10 CFR 961.2 - Applicability.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... ENERGY STANDARD CONTRACT FOR DISPOSAL OF SPENT NUCLEAR FUEL AND/OR HIGH-LEVEL RADIOACTIVE WASTE General... owns or generates spent nuclear fuel or high-level radioactive waste, of domestic origin, generated in... part will commit DOE to accept title to, transport, and dispose of such spent fuel and waste. In...

  2. 36 CFR 13.1118 - Solid waste disposal.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... Section 13.1118 Parks, Forests, and Public Property NATIONAL PARK SERVICE, DEPARTMENT OF THE INTERIOR NATIONAL PARK SYSTEM UNITS IN ALASKA Special Regulations-Glacier Bay National Park and Preserve General Provisions § 13.1118 Solid waste disposal. (a) A solid waste disposal site may accept non-National Park...

  3. 36 CFR 13.1118 - Solid waste disposal.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... Section 13.1118 Parks, Forests, and Public Property NATIONAL PARK SERVICE, DEPARTMENT OF THE INTERIOR NATIONAL PARK SYSTEM UNITS IN ALASKA Special Regulations-Glacier Bay National Park and Preserve General Provisions § 13.1118 Solid waste disposal. (a) A solid waste disposal site may accept non-National Park...

  4. The Adam language: Ada extended with support for multiway activities

    NASA Technical Reports Server (NTRS)

    Charlesworth, Arthur

    1993-01-01

    The Adam language is an extension of Ada that supports multiway activities, which are cooperative activities involving two or more processes. This support is provided by three new constructs: diva procedures, meet statements, and multiway accept statements. Diva procedures are recursive generic procedures having a particular restrictive syntax that facilitates translation for parallel computers. Meet statements and multiway accept statements provide two ways to express a multiway rendezvous, which is an n-way rendezvous generalizing Ada's 2-way rendezvous. While meet statements tend to have simpler rules than multiway accept statements, the latter approach is a more straightforward extension of Ada. The only nonnull statements permitted within meet statements and multiway accept statements are calls on instantiated diva procedures. A call on an instantiated diva procedure is also permitted outside a multiway rendezvous; thus sequential Adam programs using diva procedures can be written. Adam programs are translated into Ada programs appropriate for use on parallel computers.

  5. 76 FR 17970 - Board Meeting: April 27, 2011-Amherst, New York; the U.S. Nuclear Waste Technical Review Board...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-03-31

    ... presentations on the WVDP by representatives of the New York State Energy Research and Development Authority and... the 2008-9 study on Quantitative Risk Assessment of the State Licensed Radioactive Waste Disposal Area... request at that time. The meeting will be open to the public, and opportunities for public comment will be...

  6. Session 35 - Panel: Remaining US Disposition Issues for Orphan or Small Volume Low Level and Low Level Mixed Waste Streams

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Blauvelt, Richard; Small, Ken; Gelles, Christine

    2006-07-01

    Faced with closure schedules as a driving force, significant progress has been made during the last 2 years on the disposition of DOE mixed waste streams thought previously to be problematic. Generators, the Department of Energy and commercial vendors have combined to develop unique disposition paths for former orphan streams. Recent successes and remaining issues will be discussed. The session will also provide an opportunity for Federal agencies to share lessons learned on low- level and mixed low-level waste challenges and identify opportunities for future collaboration. This panel discussion was organized by PAC member Dick Blauvelt, Navarro Research and Engineeringmore » Inc who served as co-chair along with Dave Eaton from INL. In addition, George Antonucci, Duratek Barnwell and Rich Conley, AFSC were invited members of the audience, prepared to contribute the Barnwell and DOD perspective to the issues as needed. Mr. Small provide information regarding the five year 20K M3 window of opportunity at the Nevada Test Site for DOE contractors to dispose of mixed waste that cannot be received at the Energy Solutions (Envirocare) site in Utah because of activity levels. He provided a summary of the waste acceptance criteria and the process sites must follow to be certified to ship. When the volume limit or time limit is met, the site will undergo a RCRA closure. Ms. Gelles summarized the status of the orphan issues, commercial options and the impact of the EM reorganization on her program. She also announced that there would be a follow-on meeting in 2006 to the very successful St. Louis meeting of last year. It will probably take place in Chicago in July. Details to be announced. Mr. McKenney discussed progress made at the Hanford Reservation regarding disposal of their mixed waste inventory. The news is good for the Hanford site but not good for the rest of the DOE complex since shipment for out of state of both low level and low level mixed waste will continue to be prohibited until the completion of a new NEPA study. This is anticipated to take several years. Bill Franz from Portsmouth and Dave Eaton representing the INL provided the audience with information regarding some of the problematic mixed waste streams at their respective sites. Portsmouth has some unique radiological issues with isotopes such as Tc-99 while the INL is trying to deal with mixed waste in the 10-100 nCi/g range. Kaylin Loveland spoke of the new,Energy Solutions organization and provided information on mixed waste treatment capabilities at the Clive site. Mike Lauer described the licensing activities at the WCS site in Texas where they are trying to eventually have disposal capabilities for Class A, B and C mixed waste from both DOE and the commercial sector. The audience included about 75 WM'06 attendees who asked some excellent questions and provided an active and informative exchange of information on the topic. (authors)« less

  7. Analysis of local acceptance of a radioactive waste disposal facility.

    PubMed

    Chung, Ji Bum; Kim, Hong-Kew; Rho, Sam Kew

    2008-08-01

    Like many other countries in the world, Korea has struggled to site a facility for radioactive waste for almost 30 years because of the strong opposition from local residents. Finally, in 2005, Gyeongju was established as the first Korean site for a radioactive waste facility. The objectives of this research are to verify Gyeongju citizens' average level of risk perception of a radioactive waste disposal facility as compared to other risks, and to explore the best model for predicting respondents' acceptance level using variables related to cost-benefit, risk perception, and political process. For this purpose, a survey is conducted among Gyeongju residents, the results of which are as follows. First, the local residents' risk perception of an accident in a radioactive waste disposal facility is ranked seventh among a total of 13 risks, which implies that nuclear-related risk is not perceived very highly by Gyeongju residents; however, its characteristics are still somewhat negative. Second, the comparative regression analyses show that the cost-benefit and political process models are more suitable for explaining the respondents' level of acceptance than the risk perception model. This may be the result of the current economic depression in Gyeongju, residents' familiarity with the nuclear industry, or cultural characteristics of risk tolerance.

  8. Defense Waste Processing Facility Canister Closure Weld Current Validation Testing

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Korinko, P. S.; Maxwell, D. N.

    Two closure welds on filled Defense Waste Processing Facility (DWPF) canisters failed to be within the acceptance criteria in the DWPF operating procedure SW4-15.80-2.3 (1). In one case, the weld heat setting was inadvertently provided to the canister at the value used for test welds (i.e., 72%) and this oversight produced a weld at a current of nominally 210 kA compared to the operating procedure range (i.e., 82%) of 240 kA to 263 kA. The second weld appeared to experience an instrumentation and data acquisition upset. The current for this weld was reported as 191 kA. Review of the datamore » from the Data Acquisition System (DAS) indicated that three of the four current legs were reading the expected values, approximately 62 kA each, and the fourth leg read zero current. Since there is no feasible way by further examination of the process data to ascertain if this weld was actually welded at either the target current or the lower current, a test plan was executed to provide assurance that these Nonconforming Welds (NCWs) meet the requirements for strength and leak tightness. Acceptance of the welds is based on evaluation of Test Nozzle Welds (TNW) made specifically for comparison. The TNW were nondestructively and destructively evaluated for plug height, heat tint, ultrasonic testing (UT) for bond length and ultrasonic volumetric examination for weld defects, burst pressure, fractography, and metallography. The testing was conducted in agreement with a Task Technical and Quality Assurance Plan (TTQAP) (2) and applicable procedures.« less

  9. Prediction of adaptive self-regulatory responses to arthritis pain anxiety in exercising adults: does pain acceptance matter?

    PubMed

    Cary, Miranda Ashley; Gyurcsik, Nancy C; Brawley, Lawrence R

    2015-01-01

    Exercising for ≥ 150 min/week is a recommended strategy for self-managing arthritis. However, exercise nonadherence is a problem. Arthritis pain anxiety may interfere with regular exercise. According to the fear-avoidance model, individuals may confront their pain anxiety by using adaptive self-regulatory responses (eg, changing exercise type or duration). Furthermore, the anxiety-self-regulatory responses relationship may vary as a function of individuals' pain acceptance levels. To investigate pain acceptance as a moderator of the pain anxiety-adaptive self-regulatory responses relationship. The secondary objective was to examine whether groups of patients who differed in meeting exercise recommendations also differed in pain-related and self-regulatory responses. Adults (mean [± SD] age 49.75 ± 13.88 years) with medically diagnosed arthritis completed online measures of arthritis pain-related variables and self-regulatory responses at baseline, and exercise participation two weeks later. Individuals meeting (n=87) and not meeting (n=49) exercise recommendations were identified. Hierarchical multiple regression analysis revealed that pain acceptance moderated the anxiety-adaptive self-regulatory responses relationship. When pain anxiety was lower, greater pain acceptance was associated with less frequent use of adaptive responses. When anxiety was higher, adaptive responses were used regardless of pain acceptance level. MANOVA findings revealed that participants meeting the recommended exercise dose reported significantly lower pain and pain anxiety, and greater pain acceptance (P<0.05) than those not meeting the dose. Greater pain acceptance may help individuals to focus their efforts to adapt to their pain anxiety only when it is higher, leaving self-regulatory capacity to cope with additional challenges to exercise adherence (eg, busy schedule).

  10. Prediction of adaptive self-regulatory responses to arthritis pain anxiety in exercising adults: Does pain acceptance matter?

    PubMed Central

    Cary, Miranda A; Gyurcsik, Nancy C; Brawley, Lawrence R

    2015-01-01

    BACKGROUND: Exercising for ≥150 min/week is a recommended strategy for self-managing arthritis. However, exercise nonadherence is a problem. Arthritis pain anxiety may interfere with regular exercise. According to the fear-avoidance model, individuals may confront their pain anxiety by using adaptive self-regulatory responses (eg, changing exercise type or duration). Furthermore, the anxiety-self-regulatory responses relationship may vary as a function of individuals’ pain acceptance levels. OBJECTIVES: To investigate pain acceptance as a moderator of the pain anxiety-adaptive self-regulatory responses relationship. The secondary objective was to examine whether groups of patients who differed in meeting exercise recommendations also differed in pain-related and self-regulatory responses. METHODS: Adults (mean [± SD] age 49.75±13.88 years) with medically diagnosed arthritis completed online measures of arthritis pain-related variables and self-regulatory responses at baseline, and exercise participation two weeks later. Individuals meeting (n=87) and not meeting (n=49) exercise recommendations were identified. RESULTS: Hierarchical multiple regression analysis revealed that pain acceptance moderated the anxiety-adaptive self-regulatory responses relationship. When pain anxiety was lower, greater pain acceptance was associated with less frequent use of adaptive responses. When anxiety was higher, adaptive responses were used regardless of pain acceptance level. MANOVA findings revealed that participants meeting the recommended exercise dose reported significantly lower pain and pain anxiety, and greater pain acceptance (P<0.05) than those not meeting the dose. CONCLUSIONS: Greater pain acceptance may help individuals to focus their efforts to adapt to their pain anxiety only when it is higher, leaving self-regulatory capacity to cope with additional challenges to exercise adherence (eg, busy schedule). PMID:25621990

  11. 36 CFR 13.1008 - Solid waste disposal.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... Section 13.1008 Parks, Forests, and Public Property NATIONAL PARK SERVICE, DEPARTMENT OF THE INTERIOR NATIONAL PARK SYSTEM UNITS IN ALASKA Special Regulations-Gates of the Arctic National Park and Preserve § 13.1008 Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service...

  12. Waste incineration, Part I: Technology.

    PubMed

    1990-02-01

    Based upon an overview of the technology of incineration and the nature of hospital waste, HHMM offers the following suggestions: Old retort or other excess air incinerators should be replaced regardless of age. Even if emissions control equipment and monitoring devices can be retrofitted, excess-air incinerators are no longer cost-effective in terms of capacity, fuel consumption, and heat recovery. Audit (or have a specialist audit) your waste stream thoroughly. Consult a qualified engineering company experienced in hospital installations to get a system specified as exactly as possible to your individual conditions and needs. Make sure that the capacity of your incinerator will meet projections for future use. Anticipate the cost of emissions control and monitoring devices whether your state currently requires them or not. Make sure that your incinerator installation is engineered to accept required equipment in the future. Develop a strong community relations program well in advance of committing to incinerator installation. Take a proactive position by inviting your neighbors in during the planning stages. Be sure the contract governing incinerator purchase and installation has a cancellation clause, preferably without penalties, in case community action or a change in state regulations makes installation and operation impractical. The technology is available to enable hospitals to burn waste effectively, efficiently, and safely. HHMM echoes the concerns of Frank Cross--that healthcare facilities, as well as regional incinerators and municipalities, show the same concern for environmental protection as for their bottom lines. When emissions are under control and heat is recovered, both the environment and the bottom line are healthier.

  13. Report: Potential environmental impact of exempt site materials - a case study of bituminous road planings and waste soils.

    PubMed

    Bark, Marjorie; Bland, Michael; Grimes, Sue

    2009-09-01

    The use of waste materials for ecological benefit, agricultural improvement or as part of construction works are often exempt from waste management control in order to maximize the reuse of material that would otherwise be disposed of to landfill. It is important, however, to determine whether there is potential for such waste to cause environmental harm in the context of the basis for granting exemptions under the relevant framework objective to ensure that waste is recovered or disposed of without risk to water, air, soil, plants or animals. The potential for environmental harm was investigated by leaching studies on two wastes commonly found at exempt sites: bituminous road planings and waste soils. For bituminous road planings, the organic components of the waste were identified by their solubility in organic solvents but these components would have low environmental impact in terms of bioavailability. Leaching studies of the heavy metals copper, lead and zinc, into the environment, under specific conditions and particularly those modelling acid rain and landfill leachate conditions showed that, except for copper, the amounts leached fell within Waste Acceptance Criteria compliance limits for defining waste as inert waste. The fact that the amount of copper leached was greater than the Waste Acceptance Criteria level suggests that either additional testing of wastes regarded as exempt should be carried out to ensure that they are in analytical compliance or that legislation should allow for the potential benefits of reuse to supersede deviations from analytical compliance.

  14. Comparing urban solid waste recycling from the viewpoint of urban metabolism based on physical input-output model: A case of Suzhou in China

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Liang Sai, E-mail: liangsai09@gmail.com; Zhang Tianzhu, E-mail: zhangtz@mail.tsinghua.edu.cn

    Highlights: Black-Right-Pointing-Pointer Impacts of solid waste recycling on Suzhou's urban metabolism in 2015 are analyzed. Black-Right-Pointing-Pointer Sludge recycling for biogas is regarded as an accepted method. Black-Right-Pointing-Pointer Technical levels of reusing scrap tires and food wastes should be improved. Black-Right-Pointing-Pointer Other fly ash utilization methods should be exploited. Black-Right-Pointing-Pointer Secondary wastes from reusing food wastes and sludge should be concerned. - Abstract: Investigating impacts of urban solid waste recycling on urban metabolism contributes to sustainable urban solid waste management and urban sustainability. Using a physical input-output model and scenario analysis, urban metabolism of Suzhou in 2015 is predicted and impactsmore » of four categories of solid waste recycling on urban metabolism are illustrated: scrap tire recycling, food waste recycling, fly ash recycling and sludge recycling. Sludge recycling has positive effects on reducing all material flows. Thus, sludge recycling for biogas is regarded as an accepted method. Moreover, technical levels of scrap tire recycling and food waste recycling should be improved to produce positive effects on reducing more material flows. Fly ash recycling for cement production has negative effects on reducing all material flows except solid wastes. Thus, other fly ash utilization methods should be exploited. In addition, the utilization and treatment of secondary wastes from food waste recycling and sludge recycling should be concerned.« less

  15. Quantifying Silica Reactivity in Subsurface Environments: Reaction Affinity and Solute Matrix Controls on Quartz and SiO2 Glass Dissolution Kinetics

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Patricia M. Dove

    2000-12-13

    During the three years of this project, Professor Dove's laboratory made tremendous progress in understanding controls on amorphous silica dissolution kinetics in aqueous solutions. Our findings have already received considerable attention. In hydrothermal and low temperature studies, the work focused on determining quantitative and mechanistic controls on the most abundant silica polymorphs in Earth environments--quartz and amorphous silica. Our studies achieved goals set forth in the original proposal to establish a new quantitative understanding of amorphous silica dissolution. This support has resulted in 10 journal, 12 abstracts and 2 thesis publications. The PI and students were also recognized with 6more » awards during this period. The 1998 EMSP conference in Chicago was an important meeting for our project. The symposium, enabled P.I. Dove to establish valuable contacts with ''users'' having specific needs for the findings of our EMSP project related to the urgency of problems in the Tanks Focus Area (TFA). Since that time, our working relations developed as Dove interacted with TFA scientists and engineers on the problems of waste glass properties. These interactions refined our experimental objectives to better meet their needs. Dove presented the results of EMSP research findings to a TFA subgroup at a Product Acceptance Workshop held in Salt Lake City during December 1998. The travel costs to attend this unanticipated opportunity were paid from EMSP project funds. In January 2000, Dove also attended a similar meeting in Atlanta with PNNL, SRL and BNF scientists/engineers to discuss new issues and make another level of decisions on the Product Acceptance goals. Our EMSP-funded research interfaced very well with the ongoing studies of Dr. Pete McGrail and colleagues in the Applied Geochemistry Group at PNNL. The value of our work to ''users'' was further demonstrated when Dove's EMSP-funded Postdoc, Dr. Jonathan Icenhower was hired by the same PNNL group. With the Icenhower move from postdoc in the Dove lab to a senior scientist position at PNNL, we directly facilitated information transfer from the ''university to user'' environment. Icenhower brought experience in silica-water reactivity and the experimental expertise in high-quality methods of mineral-water reaction kinetics to the PNNL waste clean-up effort. In a further interaction, M.S. student Troy Lorier was hired at the Savannah River Laboratory for a staff position with the Bill Holtzcheiter glass group. His research meshed well with on-going efforts at SRL. In short, our EMSP project went well beyond the academic goals of producing high quality scientific knowledge to establish connections with on-site users to solve problems in TFA. This project also produced new talent for the waste immobilization effort. This EMSP project was highly successful and we thank our sponsors for the opportunity to advance scientific knowledge in this important area of research.« less

  16. 40 CFR 240.204-3 - Recommended procedures: Operations.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ...) SOLID WASTES GUIDELINES FOR THE THERMAL PROCESSING OF SOLID WASTES Requirements and Recommended... acceptable levels. (b) In the event of an accidental spill, the local regulatory agency should be notified...

  17. 76 FR 35137 - Vulnerability and Threat Information for Facilities Storing Spent Nuclear Fuel and High-Level...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-16

    ... High-Level Radioactive Waste AGENCY: U.S. Nuclear Regulatory Commission. ACTION: Public meeting... Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste,'' and 73... Spent Nuclear Fuel (SNF) and High-Level Radioactive Waste (HLW) storage facilities. The draft regulatory...

  18. Thirteenth annual U.S. DOE low-level radioactive waste management conference: Proceedings

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1991-12-31

    The 40 papers in this document comprise the proceedings of the Department of Energy`s Thirteenth Annual Low-Level Radioactive Waste Management Conference that was held in Atlanta, Georgia, on November 19--21, 1991. General subjects addressed during the conference included: disposal facility design; greater-than-class C low-level waste; public acceptance considerations; waste certification; site characterization; performance assessment; licensing and documentation; emerging low-level waste technologies; waste minimization; mixed waste; tracking and transportation; storage; and regulatory changes. Papers have been processed separately for inclusion on the data base.

  19. Organic Separation Test Results

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Russell, Renee L.; Rinehart, Donald E.; Peterson, Reid A.

    2014-09-22

    Separable organics have been defined as “those organic compounds of very limited solubility in the bulk waste and that can form a separate liquid phase or layer” (Smalley and Nguyen 2013), and result from three main solvent extraction processes: U Plant Uranium Recovery Process, B Plant Waste Fractionation Process, and Plutonium Uranium Extraction (PUREX) Process. The primary organic solvents associated with tank solids are TBP, D2EHPA, and NPH. There is concern that, while this organic material is bound to the sludge particles as it is stored in the tanks, waste feed delivery activities, specifically transfer pump and mixer pump operations,more » could cause the organics to form a separated layer in the tank farms feed tank. Therefore, Washington River Protection Solutions (WRPS) is experimentally evaluating the potential of organic solvents separating from the tank solids (sludge) during waste feed delivery activities, specifically the waste mixing and transfer processes. Given the Hanford Tank Waste Treatment and Immobilization Plant (WTP) waste acceptance criteria per the Waste Feed Acceptance Criteria document (24590-WTP-RPT-MGT-11-014) that there is to be “no visible layer” of separable organics in the waste feed, this would result in the batch being unacceptable to transfer to WTP. This study is of particular importance to WRPS because of these WTP requirements.« less

  20. 77 FR 59022 - Sunshine Act Meeting

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-25

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0002] Sunshine Act Meeting AGENCY HOLDING THE MEETINGS: Nuclear Regulatory Commission. DATE: Weeks of September 24, October 1, 8, 15, 22, 29, 2012. [[Page 59023... of the Nuclear Materials Users and Decommissioning and Low-Level Waste Business Lines (Public Meeting...

  1. Mini-review of the geotechnical parameters of municipal solid waste: Mechanical and biological pre-treated versus raw untreated waste.

    PubMed

    Petrovic, Igor

    2016-09-01

    The most viable option for biostabilisation of old sanitary landfills, filled with raw municipal solid waste, is the so-called bioreactor landfill. Even today, bioreactor landfills are viable options in many economically developing countries. However, in order to reduce the biodegradable component of landfilled waste, mechanical and biological treatment has become a widely accepted waste treatment technology, especially in more prosperous countries. Given that mechanical and biological treatment alters the geotechnical properties of raw waste material, the design of sanitary landfills which accepts mechanically and biologically treated waste, should be carried out with a distinct set of geotechnical parameters. However, under the assumption that 'waste is waste', some design engineers might be tempted to use geotechnical parameters of untreated raw municipal solid waste and mechanical and biological pre-treated municipal solid waste interchangeably. Therefore, to provide guidelines for use and to provide an aggregated source of this information, this mini-review provides comparisons of geotechnical parameters of mechanical and biological pre-treated waste and raw untreated waste at various decomposition stages. This comparison reveals reasonable correlations between the hydraulic conductivity values of untreated and mechanical and biological pre-treated municipal solid waste. It is recognised that particle size might have a significant influence on the hydraulic conductivity of both municipal solid waste types. However, the compression ratios and shear strengths of untreated and pre-treated municipal solid waste do not show such strong correlations. Furthermore, another emerging topic that requires appropriate attention is the recovery of resources that are embedded in old landfills. Therefore, the presented results provide a valuable tool for engineers designing landfills for mechanical and biological pre-treated waste or bioreactor landfills for untreated raw waste as well as planning landfill mining projects. © The Author(s) 2016.

  2. Radioactive Waste Management and Environmental Contamination Issues at the Chernobyl Site

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Napier, Bruce A.; Schmieman, Eric A.; Voitsekhovitch, Oleg V.

    2007-11-01

    The destruction of the Unit 4 reactor at the Chernobyl Nuclear Power Plant resulted in the generation of radioactive contamination and radioactive waste at the site and in the surrounding area (referred to as the Exclusion Zone). In the course of remediation activities, large volumes of radioactive waste were generated and placed in temporary near surface waste-storage and disposal facilities. Trench and landfill type facilities were created from 1986 to 1987 in the Chernobyl Exclusion Zone at distances 0.5 to 15 km from the NPP site. This large number of facilities was established without proper design documentation, engineered barriers, ormore » hydrogeological investigations and they do not meet contemporary waste-safety requirements. Immediately following the accident, a Shelter was constructed over the destroyed reactor; in addition to uncertainties in stability at the time of its construction, structural elements of the Shelter have degraded as a result of corrosion. The main potential hazard of the Shelter is a possible collapse of its top structures and release of radioactive dust into the environment. A New Safe Confinement (NSC) with a 100-years service life is planned to be built as a cover over the existing Shelter as a longer-term solution. The construction of the NSC will enable the dismantlement of the current Shelter, removal of highly radioactive, fuel-containing materials from Unit 4, and eventual decommissioning of the damaged reactor. More radioactive waste will be generated during NSC construction, possible Shelter dismantling, removal of fuel containing materials, and decommissioning of Unit 4. The future development of the Exclusion Zone depends on the future strategy for converting Unit 4 into an ecologically safe system, i.e., the development of the NSC, the dismantlement of the current Shelter, removal of fuel containing material, and eventual decommissioning of the accident site. To date, a broadly accepted strategy for radioactive waste management at the reactor site and in the Exclusion Zone, and especially for high-level and long-lived waste, has not been developed.« less

  3. Configuration management at an environmental restoration DOE facility (Fernald)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Beckett, C.; Pasko, W.; Kupinski, T.

    This report contains information about a meeting held to discuss the decontamination and decommissioning of the Fernald site in Ohio. This site contains two major types of waste. First is the legacy waste. This waste consists of the wastes which were left over from production which is stored in various drums and containers across the site. Second is the waste generated from the remedial activities.

  4. RH-TRU Waste Characterization by Acceptable Knowledge at the Idaho National Engineering and Environmental Laboratory

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Schulz, C.; Givens, C.; Bhatt, R.

    2003-02-24

    Idaho National Engineering and Environmental Laboratory (INEEL) is conducting an effort to characterize approximately 620 drums of remote-handled (RH-) transuranic (TRU) waste currently in its inventory that were generated at the Argonne National Laboratory-East (ANL-E) Alpha Gamma Hot Cell Facility (AGHCF) between 1971 and 1995. The waste was generated at the AGHCF during the destructive examination of irradiated and unirradiated fuel pins, targets, and other materials from reactor programs at ANL-West (ANL-W) and other Department of Energy (DOE) reactors. In support of this effort, Shaw Environmental and Infrastructure (formerly IT Corporation) developed an acceptable knowledge (AK) collection and management programmore » based on existing contact-handled (CH)-TRU waste program requirements and proposed RH-TRU waste program requirements in effect in July 2001. Consistent with Attachments B-B6 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit (HWFP) and th e proposed Class 3 permit modification (Attachment R [RH-WAP] of this permit), the draft AK Summary Report prepared under the AK procedure describes the waste generating process and includes determinations in the following areas based on AK: physical form (currently identified at the Waste Matrix Code level); waste stream delineation; applicability of hazardous waste numbers for hazardous waste constituents; and prohibited items. In addition, the procedure requires and the draft summary report contains information supporting determinations in the areas of defense relationship and radiological characterization.« less

  5. Cover design for radioactive and AMD-producing mine waste in the Ronneburg area, eastern Thuringia.

    PubMed

    Gatzweiler, R; Jahn, S; Neubert, G; Paul, M

    2001-01-01

    At the former uranium mining site of Ronneburg, large scale underground and open pit mining for nearly 40 years resulted in a production of about 113,000 tonnes of uranium and about 200 million cubic metres of mine waste. In their present state, these materials cause risks to human health and strong environmental impacts and therefore demand remedial action. The remediation options available are relocation of mine spoil into the open pit and on site remediation by landscaping/contouring, placement of a cover and revegetation. A suitable vegetated cover system combined with a surface water drainage system provides long-term stability against erosion and reduces acid generation thereby meeting the main remediation objectives which are long-term reduction of radiological exposure and contaminant emissions and recultivation. The design of the cover system includes the evaluation of geotechnical, radiological, hydrological, geochemical and ecological criteria and models. The optimized overall model for the cover system has to comply with general conditions as, e.g. economic efficiency, public acceptance and sustainability. Most critical elements for the long-term performance of the cover system designed for the Beerwalde dump are the barrier system and its long-term integrity and a largely self-sustainable vegetation.

  6. Inventory decision in a closed-loop supply chain with inspection, sorting, and waste disposal

    NASA Astrophysics Data System (ADS)

    Dwicahyani, A. R.; Jauhari, W. A.; Kurdhi, N. A.

    2016-02-01

    The study of returned item inventory management in a closed-loop supply chain system has become an important issue in recent years. So far, investigations about inventory decision making in a closed-loop supply chain system have been confined to traditional forward and reverse oriented material flow supply chain. In this study, we propose an integrated inventory model consisting a supplier, a manufacturer, and a retailer where the manufacturer inspects all of the returned items collected from the customers and classifies them as recoverable or waste. Returned items that recovered through the remanufacturing process and the newly manufactured products are then used to meet the demand of the retailer. However, some recovered items which are not comparable to the ones in quality, classified as refurbished items, are sold to a secondary market at a reduced price. This study also suggests that the flow of returned items is controlled by a decision variable, namely an acceptance quality level of recoverable item in the system. We apply multiple remanufacturing cycle and multiple production cycle policy to the proposed model and give the corresponding iterative procedure to determine the optimal solutions. Further, numerical examples are presented for illustrative purpose.

  7. The Property Value Protection Program - How the Compensation Plan is Working and Evolving to Meet Changing Needs - 13149

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Faught, Jeff; Herod, Judy; Mahabir, Alexandra

    2013-07-01

    The Property Value Protection (PVP) Program offers an innovative approach to address the risk of individual property value loss resulting from the cleanup and long-term management of historic low level radioactive waste in the Port Hope area in Southern Ontario, Canada. This cleanup is taking place through the Port Hope Area Initiative (PHAI), a federally sponsored waste remediation project. The PVP Program came into effect on October 1, 2000, having been established as a key element of the PHAI Legal Agreement between the Government of Canada and the municipalities of Port Hope and Clarington. The PVP Program was designed inmore » direct response to the concern expressed by the agreement's two municipal signatories that protection of local property owners from the risk of property value loss was critical to their acceptance of the Port Hope and Port Granby projects. The PVP Program compensates owners of residential, commercial or industrial properties for a loss in fair market value on the sale or rental of their properties. Increased mortgage refinancing costs and expenses incurred as a result of delayed sales that can be attributed to the Port Hope Area Initiative are also compensated. (authors)« less

  8. Reuse of thermosetting plastic waste for lightweight concrete.

    PubMed

    Panyakapo, Phaiboon; Panyakapo, Mallika

    2008-01-01

    This paper presents the utilization of thermosetting plastic as an admixture in the mix proportion of lightweight concrete. Since this type of plastic cannot be melted in the recycling process, its waste is expected to be more valuable by using as an admixture for the production of non-structural lightweight concrete. Experimental tests for the variation of mix proportion were carried out to determine the suitable proportion to achieve the required properties of lightweight concrete, which are: low dry density and acceptable compressive strength. The mix design in this research is the proportion of plastic, sand, water-cement ratio, aluminum powder, and lignite fly ash. The experimental results show that the plastic not only leads to a low dry density concrete, but also a low strength. It was found that the ratio of cement, sand, fly ash, and plastic equal to 1.0:0.8:0.3:0.9 is an appropriate mix proportion. The results of compressive strength and dry density are 4.14N/mm2 and 1395 kg/m3, respectively. This type of concrete meets most of the requirements for non-load-bearing lightweight concrete according to ASTM C129 Type II standard.

  9. Analysis of Possibility of Yeast Production Increase at Maintained Carbon Dioxide Emission Level

    NASA Astrophysics Data System (ADS)

    Włodarczyk, Barbara; Włodarczyk, Paweł P.

    2016-12-01

    Main parameters polluting of technological wastewater (dregs from decantation and thicken of the wort) from yeast industry are: nitrogen, potassium and COD. Such wastewater are utilized mostly on agricultural fields. Unfortunately, these fields can only accept a limited amount of wastes. The basic parameter limiting there the amount of wastewater is nitrogen. When capacity of the production is large sewages are often pretreated at an evaporator station. However, due to the fairly high running costs of the evaporator station currently such a solution is applied only to a small amount of wastes (just to meet legal requirements). Replacement of the earth gas with a biomass being supplied to the evaporator station from the agricultural fields will both allow to maintain the carbon dioxide emission level and enable the production growth. Moreover, the biomass growing on the agricultural fields being fertilized with the wastewater coming from the yeast production allows consequently to utilize the greater volume of wastewater. Theoretically, the possible increase in the yeasts production, with maintaining the carbon dioxide emission level, can reach even 70%. Therefore, the solution presented in this paper combines both intensification of the yeasts production and maintaining the carbon dioxide emission level.

  10. 40 CFR 761.218 - Certificate of disposal.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... PROHIBITIONS PCB Waste Disposal Records and Reports § 761.218 Certificate of disposal. (a) For each shipment of manifested PCB waste that the owner or operator of a disposal facility accepts by signing the manifest, the... certifying the fact of disposal of the identified PCB waste, including the date(s) of disposal, and...

  11. 40 CFR 761.218 - Certificate of disposal.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... PROHIBITIONS PCB Waste Disposal Records and Reports § 761.218 Certificate of disposal. (a) For each shipment of manifested PCB waste that the owner or operator of a disposal facility accepts by signing the manifest, the... certifying the fact of disposal of the identified PCB waste, including the date(s) of disposal, and...

  12. 40 CFR 761.218 - Certificate of disposal.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... PROHIBITIONS PCB Waste Disposal Records and Reports § 761.218 Certificate of disposal. (a) For each shipment of manifested PCB waste that the owner or operator of a disposal facility accepts by signing the manifest, the... certifying the fact of disposal of the identified PCB waste, including the date(s) of disposal, and...

  13. 40 CFR 761.218 - Certificate of disposal.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... PROHIBITIONS PCB Waste Disposal Records and Reports § 761.218 Certificate of disposal. (a) For each shipment of manifested PCB waste that the owner or operator of a disposal facility accepts by signing the manifest, the... certifying the fact of disposal of the identified PCB waste, including the date(s) of disposal, and...

  14. The efficacy of subsurface flow reed bed treatment in the removal of Campylobacter spp., faecal coliforms and Escherichia coli from poultry litter.

    PubMed

    Duggan, J; Bates, M P; Phillips, C A

    2001-06-01

    The use of poultry waste as a fertiliser on arable land is an accepted method of waste treatment. However, run-off from such practices may result in contamination of the watercourse by human pathogens. In this study the effectiveness of using constructed wetlands as an alternative treatment for poultry manure waste was evaluated. Enumeration of Campylobacter spp., Escherichia coli, total coliforms and total aerobes were carried out on influent and effluent samples from reed beds loaded with poultry waste. For both sequential loading and continuous loading there was a statistically significant mean log reduction of 3.56 and 4.25 for E. coli, 3.2 and 3.88 for coliforms, 3.85 and 4.2 for total aerobic counts and 3.13 and 2.96 for Campylobacter spp., respectively. This method, which has been previously recognised as cost-effective and environmentally acceptable, provides an efficient method for reducing numbers of these bacteria in poultry waste and therefore an effective alternative treatment for such waste or waters containing run off from land previously spread with poultry manure.

  15. 30 CFR 817.83 - Coal mine waste: Refuse piles.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 3 2013-07-01 2013-07-01 false Coal mine waste: Refuse piles. 817.83 Section... ACTIVITIES § 817.83 Coal mine waste: Refuse piles. Refuse piles shall meet the requirements of § 817.81, the... removed from the disposal area prior to placement of coal mine waste. Topsoil shall be removed, segregated...

  16. 30 CFR 816.83 - Coal mine waste: Refuse piles.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 3 2014-07-01 2014-07-01 false Coal mine waste: Refuse piles. 816.83 Section... ACTIVITIES § 816.83 Coal mine waste: Refuse piles. Refuse piles shall meet the requirements of § 816.81, the... removed from the disposal area prior to placement of coal mine waste. Topsoil shall be removed, segregated...

  17. 30 CFR 817.83 - Coal mine waste: Refuse piles.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 3 2014-07-01 2014-07-01 false Coal mine waste: Refuse piles. 817.83 Section... ACTIVITIES § 817.83 Coal mine waste: Refuse piles. Refuse piles shall meet the requirements of § 817.81, the... removed from the disposal area prior to placement of coal mine waste. Topsoil shall be removed, segregated...

  18. 30 CFR 816.83 - Coal mine waste: Refuse piles.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 3 2013-07-01 2013-07-01 false Coal mine waste: Refuse piles. 816.83 Section... ACTIVITIES § 816.83 Coal mine waste: Refuse piles. Refuse piles shall meet the requirements of § 816.81, the... removed from the disposal area prior to placement of coal mine waste. Topsoil shall be removed, segregated...

  19. 30 CFR 817.83 - Coal mine waste: Refuse piles.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 3 2012-07-01 2012-07-01 false Coal mine waste: Refuse piles. 817.83 Section... ACTIVITIES § 817.83 Coal mine waste: Refuse piles. Refuse piles shall meet the requirements of § 817.81, the... removed from the disposal area prior to placement of coal mine waste. Topsoil shall be removed, segregated...

  20. 30 CFR 816.83 - Coal mine waste: Refuse piles.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Coal mine waste: Refuse piles. 816.83 Section... ACTIVITIES § 816.83 Coal mine waste: Refuse piles. Refuse piles shall meet the requirements of § 816.81, the... removed from the disposal area prior to placement of coal mine waste. Topsoil shall be removed, segregated...

  1. 30 CFR 816.83 - Coal mine waste: Refuse piles.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 3 2011-07-01 2011-07-01 false Coal mine waste: Refuse piles. 816.83 Section... ACTIVITIES § 816.83 Coal mine waste: Refuse piles. Refuse piles shall meet the requirements of § 816.81, the... removed from the disposal area prior to placement of coal mine waste. Topsoil shall be removed, segregated...

  2. 30 CFR 816.83 - Coal mine waste: Refuse piles.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 3 2012-07-01 2012-07-01 false Coal mine waste: Refuse piles. 816.83 Section... ACTIVITIES § 816.83 Coal mine waste: Refuse piles. Refuse piles shall meet the requirements of § 816.81, the... removed from the disposal area prior to placement of coal mine waste. Topsoil shall be removed, segregated...

  3. 30 CFR 817.83 - Coal mine waste: Refuse piles.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 3 2011-07-01 2011-07-01 false Coal mine waste: Refuse piles. 817.83 Section... ACTIVITIES § 817.83 Coal mine waste: Refuse piles. Refuse piles shall meet the requirements of § 817.81, the... removed from the disposal area prior to placement of coal mine waste. Topsoil shall be removed, segregated...

  4. 30 CFR 817.83 - Coal mine waste: Refuse piles.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Coal mine waste: Refuse piles. 817.83 Section... ACTIVITIES § 817.83 Coal mine waste: Refuse piles. Refuse piles shall meet the requirements of § 817.81, the... removed from the disposal area prior to placement of coal mine waste. Topsoil shall be removed, segregated...

  5. Test plan for formulation and evaluation of grouted waste forms with shine process wastes

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Ebert, W. L.; Jerden, J. L.

    2015-09-01

    The objective of this experimental project is to demonstrate that waste streams generated during the production of Mo99 by the SHINE Medical Technologies (SHINE) process can be immobilized in cement-based grouted waste forms having physical, chemical, and radiological stabilities that meet regulatory requirements for handling, storage, transport, and disposal.

  6. Bread enriched in lycopene and other bioactive compounds by addition of dry tomato waste.

    PubMed

    Nour, Violeta; Ionica, Mira Elena; Trandafir, Ion

    2015-12-01

    The tomato processing industry generates high amounts of waste, mainly tomato skins and seeds, which create environmental problems. These residues are attractive sources of valuable bioactive components and pigments. A relatively simple recovery technology could consist of production of powders to be directly incorporated into foods. Tomato waste coming from a Romanian tomato processing unit were analyzed for the content of several bioactive compounds like ascorbic acid, β-carotene, lycopene, total phenolics, mineral and trace elements. In addition, its antioxidant capacity was assayed. Results revealed that tomato waste (skins and seeds) could be successfully utilized as functional ingredient for the formulation of antioxidant rich functional foods. Dry tomato processing waste were used to supplement wheat flour at 6 and 10 % levels (w/w flour basis) and the effects on the bread's physicochemical, baking and sensorial characteristics were studied. The following changes were observed: increase in moisture content, titratable acidity and bread crumb elasticity, reduction in specific volume and bread crumb porosity. The addition of dry tomato waste at 6 % resulted in bread with good sensory characteristics and overall acceptability but as the amount of dry tomato waste increased to 10 %, bread was less acceptable.

  7. Annual Status Report (FY2017): Performance Assessment for the Disposal of Low-Level Waste in the 200 East Area Burial Grounds.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Nichols, Will E.; Mehta, S.; Nell, R. M.

    This annual review provides the projected dose estimates of radionuclide inventories disposed in the active 200 East Area Low-Level Waste Burial Grounds (LLBGs) since September 26, 1988. The estimates are calculated using the original dose methodology developed in the performance assessment (PA) analysis (WHC-SD-WM-TI-7301). The estimates are compared with performance objectives defined in U.S. Department of Energy (DOE) requirements (DOE O 435.1 Chg 1,2 and companion documents DOE M 435.1-1 Chg 13 and DOE G 435.1-14). All performance objectives are currently satisfied, and operational waste acceptance criteria (HNF-EP-00635) and waste acceptance practices continue to be sufficient to maintain compliance withmore » performance objectives. Inventory estimates and associated dose estimates from future waste disposal actions are unchanged from previous years’ evaluations, which indicate potential impacts well below performance objectives. Therefore, future compliance with DOE O 435.1 Chg 1 is expected.« less

  8. Annual Status Report (FY2017): Performance Assessment for the Disposal of Low-Level Waste in the 200 West Area Burial Grounds.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Nichols, Will E; Nell, R. M.; Mehta, S.

    This annual review provides the projected dose estimates of radionuclide inventories disposed in the active 200 West Area Low-Level Waste Burial Grounds (LLBGs) since September 26, 1988. These estimates are calculated using the original dose methodology developed in the performance assessment (PA) analysis (WHC-EP-06451). These estimates are compared with performance objectives defined in U.S. Department of Energy (DOE) requirements (DOE O 435.1 Chg 12 and its companion documents DOE M 435.1-1 Chg 13 and DOE G 435.1-14). All performance objectives are currently satisfied, and operational waste acceptance criteria (HNF-EP-00635) and waste acceptance practices continue to be sufficient to maintain compliancemore » with performance objectives. Inventory estimates and associated dose estimates from future waste disposal actions are unchanged from previous years’ evaluations, which indicate potential impacts well below performance objectives. Therefore, future compliance with DOE O 435.1 Chg 1 is expected.« less

  9. Air pollution control residues from waste incineration: current UK situation and assessment of alternative technologies.

    PubMed

    Rani, D Amutha; Boccaccini, A R; Deegan, D; Cheeseman, C R

    2008-11-01

    Current disposal options for APC residues in the UK and alternative treatment technologies developed world-wide have been reviewed. APC residues are currently landfilled in the UK where they undergo in situ solidification, although the future acceptability of this option is uncertain because the EU waste acceptance criteria (WAC) introduce strict limits on leaching that are difficult to achieve. Other APC residue treatment processes have been developed which are reported to reduce leaching to below relevant regulatory limits. The Ferrox process, the VKI process, the WES-PHix process, stabilisation/solidification using cementitious binders and a range of thermal treatment processes are reviewed. Thermal treatment technologies convert APC residues combined with other wastes into inert glass or glass-ceramics that encapsulate heavy metals. The waste management industry will inevitably use the cheapest available option for treating APC residues and strict interpretation and enforcement of waste legislation is required if new, potentially more sustainable technologies are to become commercially viable.

  10. A successful turnaround in Dade County

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Frank, H.

    1988-10-01

    When Dade County, Fla., decided to build a waste-to-energy plant, little did it known what a stink it would bring. Odor problems and seagulls plagued the neighborhood, emissions exceeded regulatory standards, and wind-blown garbage littered the facility. Maintenance costs rose and electricity sales never came close to its rated capacity. The residents called for a change, and they got it. After a new operator took over the plant, some of the problems were quickly solved. Other problems, which required substantial capital improvements to solve, were clearly identified. And after Dade County approved a new contract with $45 million in improvements,more » the facility is back on track to meeting the community's needs in an acceptable manner. The paper describes the original plant design, early problems, improved operation, present plant operation, and the Plant Rehabilitation Program.« less

  11. Pathways for Disposal of Commercially-Generated Tritiated Waste

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Halverson, Nancy V.

    From a waste disposal standpoint, tritium is a major challenge. Because it behaves like hydrogen, tritium exchanges readily with hydrogen in the ground water and moves easily through the ground. Land disposal sites must control the tritium activity and mobility of incoming wastes to protect human health and the environment. Consequently, disposal of tritiated low-level wastes is highly regulated and disposal options are limited. The United States has had eight operating commercial facilities licensed for low-level radioactive waste disposal, only four of which are currently receiving waste. Each of these is licensed and regulated by its state. Only two ofmore » these sites accept waste from states outside of their specified regional compact. For waste streams that cannot be disposed directly at one of the four active commercial low-level waste disposal facilities, processing facilities offer various forms of tritiated low-level waste processing and treatment, and then transport and dispose of the residuals at a disposal facility. These processing facilities may remove and recycle tritium, reduce waste volume, solidify liquid waste, remove hazardous constituents, or perform a number of additional treatments. Waste brokers also offer many low-level and mixed waste management and transportation services. These services can be especially helpful for small-quantity tritiated-waste generators, such as universities, research institutions, medical facilities, and some industries. The information contained in this report covers general capabilities and requirements for the various disposal/processing facilities and brokerage companies, but is not considered exhaustive. Typically, each facility has extensive waste acceptance criteria and will require a generator to thoroughly characterize their wastes. Then a contractual agreement between the waste generator and the disposal/processing/broker entity must be in place before waste is accepted. Costs for tritiated waste transportation, processing and disposal vary based a number of factors. In many cases, wastes with very low radioactivity are priced primarily based on weight or volume. For higher activities, costs are based on both volume and activity, with the activity-based charges usually being much larger than volume-based charges. Other factors affecting cost include location, waste classification and form, other hazards in the waste, etc. Costs may be based on general guidelines used by an individual disposal or processing site, but final costs are established by specific contract with each generator. For this report, seven hypothetical waste streams intended to represent commercially-generated tritiated waste were defined in order to calculate comparative costs. Ballpark costs for disposition of these hypothetical waste streams were calculated. These costs ranged from thousands to millions of dollars. Due to the complexity of the cost-determining factors mentioned above, the costs calculated in this report should be understood to represent very rough cost estimates for the various hypothetical wastes. Actual costs could be higher or could be lower due to quantity discounts or other factors.« less

  12. Waste isolation safety assessment program. Task 4. Third contractor information meeting

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1980-06-01

    The Contractor Information Meeting (October 14 to 17, 1979) was part of the FY-1979 effort of Task 4 of the Waste Isolation Safety Assessment Program (WISAP): Sorption/Desorption Analysis. The objectives of this task are to: evaluate sorption/desorption measurement methods and develop a standardized measurement procedure; produce a generic data bank of nuclide-geologic interactions using a wide variety of geologic media and groundwaters; perform statistical analysis and synthesis of these data; perform validation studies to compare short-term laboratory studies to long-term in situ behavior; develop a fundamental understanding of sorption/desorption processes; produce x-ray and gamma-emitting isotopes suitable for the study ofmore » actinides at tracer concentrations; disseminate resulting information to the international technical community; and provide input data support for repository safety assessment. Conference participants included those subcontracted to WISAP Task 4, representatives and independent subcontractors to the Office of Nuclear Waste Isolation, representatives from other waste disposal programs, and experts in the area of waste/geologic media interaction. Since the meeting, WISAP has been divided into two programs: Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) (modeling efforts) and Waste/Rock Interactions Technology (WRIT) (experimental work). The WRIT program encompasses the work conducted under Task 4. This report contains the information presented at the Task 4, Third Contractor Information Meeting. Technical Reports from the subcontractors, as well as Pacific Northwest Laboratory (PNL), are provided along with transcripts of the question-and-answer sessions. The agenda and abstracts of the presentations are also included. Appendix A is a list of the participants. Appendix B gives an overview of the WRIT program and details the WRIT work breakdown structure for 1980.« less

  13. Dangerous Waste Characteristics of Waste from Hanford Tank 241-S-109

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Tingey, Joel M.; Bryan, Garry H.; Deschane, Jaquetta R.

    2004-11-05

    Existing analytical data from samples taken from Hanford Tank 241-S-109, along with process knowledge of the wastes transferred to this tank, are reviewed to determine whether dangerous waste characteristics currently assigned to all waste in Hanford underground storage tanks are applicable to this tank waste. Supplemental technologies are examined to accelerate the Hanford tank waste cleanup mission and to accomplish the waste treatment in a safer and more efficient manner. The goals of supplemental technologies are to reduce costs, conserve double-shell tank space, and meet the scheduled tank waste processing completion date of 2028.

  14. 75 FR 29786 - Notice of Meeting

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-05-27

    ... plans for managing spent nuclear fuel and high-level radioactive waste. Pursuant to its authority under... of Energy (DOE) plans for managing spent nuclear fuel (SNF) and high-level radioactive waste (HLW... the packaging and movement of the waste, how the recent decision to terminate the Yucca Mountain...

  15. Greater-than-Class C low-level radioactive waste shipping package/container identification and requirements study. National Low-Level Waste Management Program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Tyacke, M.

    1993-08-01

    This report identifies a variety of shipping packages (also referred to as casks) and waste containers currently available or being developed that could be used for greater-than-Class C (GTCC) low-level waste (LLW). Since GTCC LLW varies greatly in size, shape, and activity levels, the casks and waste containers that could be used range in size from small, to accommodate a single sealed radiation source, to very large-capacity casks/canisters used to transport or dry-store highly radioactive spent fuel. In some cases, the waste containers may serve directly as shipping packages, while in other cases, the containers would need to be placedmore » in a transport cask. For the purpose of this report, it is assumed that the generator is responsible for transporting the waste to a Department of Energy (DOE) storage, treatment, or disposal facility. Unless DOE establishes specific acceptance criteria, the receiving facility would need the capability to accept any of the casks and waste containers identified in this report. In identifying potential casks and waste containers, no consideration was given to their adequacy relative to handling, storage, treatment, and disposal. Those considerations must be addressed separately as the capabilities of the receiving facility and the handling requirements and operations are better understood.« less

  16. Land Disposal Restrictions for Hazardous Waste

    EPA Pesticide Factsheets

    The land disposal restrictions prohibits the land disposal of untreated hazardous wastes. EPA has specified either concentration levels or methods of treatment for hazardous constituents to meet before land disposal.

  17. 40 CFR 761.208 - Use of the manifest.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... PROHIBITIONS PCB Waste Disposal Records and Reports § 761.208 Use of the manifest. (a)(1) The generator of PCB... dilution. (ii) The PCB waste is accepted by the transporter for transport only to a storage or disposal... disposal facility listed on the manifest. (ii) The next designated transporter of PCB waste. (8) If the PCB...

  18. 40 CFR 761.208 - Use of the manifest.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... PROHIBITIONS PCB Waste Disposal Records and Reports § 761.208 Use of the manifest. (a)(1) The generator of PCB... dilution. (ii) The PCB waste is accepted by the transporter for transport only to a storage or disposal... disposal facility listed on the manifest. (ii) The next designated transporter of PCB waste. (8) If the PCB...

  19. Consideration of liners and covers in performance assessments

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Phifer, Mark A.; Seitz, Robert R.; Suttora, Linda C.

    2014-09-18

    On-site disposal cells are in use and being considered at several United States Department of Energy (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 U.S. Environmental Protection Agency under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) in addition to having to comply with requirements in DOE Order 435.1, Radioactive Waste Management due to the radioactive waste. The USDOE-Environmental Management Office of Site Restoration formed a working group to foster improved communication and sharing of information for personnelmore » associated with these CERCLA disposal cells and work towards more consistent assumptions, as appropriate, for technical and policy considerations related to CERCLA risk assessments and DOE Order 435.1 performance assessments in support of a Record of Decision and Disposal Authorization Statement, respectively. One of the issues considered by the working group, which is addressed in this report, was how to appropriately consider the performance of covers and liners/leachate collections systems in the context of a DOE Order 435.1 performance assessment (PA). This same information may be appropriate for consideration within CERCLA risk assessments for these facilities. These OSDCs are generally developed to meet hazardous waste (HW) disposal design standards under the Resource Conservation and Recovery Act (RCRA) as well as the DOE Order 435.1 performance based standards for disposal of radioactive waste. To meet the standards for HW, the facilities typically include engineered covers and liner/leachate collection systems. Thus, when considering such facilities in the context of a DOE Order 435.1 PA, there is a need to address the evolution of performance of covers and liner/leachate collection systems in the context of meeting a performance standard considering time frames of 1,000 years for compliance and potentially thousands of years based on the wastes to test the robustness of the system. Experience has shown that there are a range of expectations and perspectives from the different regulators involved at different sites when reviewing assumptions related to cover and liner/leachate collection system performance. However for HW disposal alone under RCRA the design standards are typically considered sufficient by the regulators without a requirement to assess long-term performance thus avoiding the need to consider the details addressed in this report. This report provides suggestions for a general approach to address covers and liners/leachate collection systems in a DOE Order 435.1 PA and how to integrate assessments with defense-in-depth considerations such as design, operations, and waste acceptance criteria to address uncertainties. The emphasis is on water balances and management in such assessments. 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 was then synthesized into suggestions 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. Numerous references are provided for sources of information to help describe the basis for performance of individual components of cover and liner systems.« less

  20. SOLIDIFICATION OF THE HANFORD LAW WASTE STREAM PRODUCED AS A RESULT OF NEAR-TANK CONTINUOUS SLUDGE LEACHING AND SODIUM HYDROXIDE RECOVERY

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Reigel, M.; Johnson, F.; Crawford, C.

    2011-09-20

    The U.S. Department of Energy (DOE), Office of River Protection (ORP), is responsible for the remediation and stabilization of the Hanford Site tank farms, including 53 million gallons of highly radioactive mixed wasted waste contained in 177 underground tanks. The plan calls for all waste retrieved from the tanks to be transferred to the Waste Treatment Plant (WTP). The WTP will consist of three primary facilities including pretreatment facilities for Low Activity Waste (LAW) to remove aluminum, chromium and other solids and radioisotopes that are undesirable in the High Level Waste (HLW) stream. Removal of aluminum from HLW sludge canmore » be accomplished through continuous sludge leaching of the aluminum from the HLW sludge as sodium aluminate; however, this process will introduce a significant amount of sodium hydroxide into the waste stream and consequently will increase the volume of waste to be dispositioned. A sodium recovery process is needed to remove the sodium hydroxide and recycle it back to the aluminum dissolution process. The resulting LAW waste stream has a high concentration of aluminum and sodium and will require alternative immobilization methods. Five waste forms were evaluated for immobilization of LAW at Hanford after the sodium recovery process. The waste forms considered for these two waste streams include low temperature processes (Saltstone/Cast stone and geopolymers), intermediate temperature processes (steam reforming and phosphate glasses) and high temperature processes (vitrification). These immobilization methods and the waste forms produced were evaluated for (1) compliance with the Performance Assessment (PA) requirements for disposal at the IDF, (2) waste form volume (waste loading), and (3) compatibility with the tank farms and systems. The iron phosphate glasses tested using the product consistency test had normalized release rates lower than the waste form requirements although the CCC glasses had higher release rates than the quenched glasses. However, the waste form failed to meet the vapor hydration test criteria listed in the WTP contract. In addition, the waste loading in the phosphate glasses were not as high as other candidate waste forms. Vitrification of HLW waste as borosilicate glass is a proven process; however the HLW and LAW streams at Hanford can vary significantly from waste currently being immobilized. The ccc glasses show lower release rates for B and Na than the quenched glasses and all glasses meet the acceptance criterion of < 4 g/L. Glass samples spiked with Re{sub 2}O{sub 7} also passed the PCT test. However, further vapor hydration testing must be performed since all the samples cracked and the test could not be performed. The waste loading of the iron phosphate and borosilicate glasses are approximately 20 and 25% respectively. The steam reforming process produced the predicted waste form for both the high and low aluminate waste streams. The predicted waste loadings for the monolithic samples is approximately 39%, which is higher than the glass waste forms; however, at the time of this report, no monolithic samples were made and therefore compliance with the PA cannot be determined. The waste loading in the geopolymer is approximately 40% but can vary with the sodium hydroxide content in the waste stream. Initial geopolymer mixes revealed compressive strengths that are greater than 500 psi for the low aluminate mixes and less than 500 psi for the high aluminate mixes. Further work testing needs to be performed to formulate a geopolymer waste form made using a high aluminate salt solution. A cementitious waste form has the advantage that the process is performed at ambient conditions and is a proven process currently in use for LAW disposal. The Saltstone/Cast Stone formulated using low and high aluminate salt solutions retained at least 97% of the Re that was added to the mix as a dopant. While this data is promising, additional leaching testing must be performed to show compliance with the PA. Compressive strength tests must also be performed on the Cast Stone monoliths to verify PA compliance. Based on testing performed for this report, the borosilicate glass and Cast Stone are the recommended waste forms for further testing. Both are proven technologies for radioactive waste disposal and the initial testing using simulated Hanford LAW waste shows compliance with the PA. Both are resistant to leaching and have greater than 25% waste loading.« less

  1. 33 CFR 157.106 - Letter of acceptance.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... Crude Oil Washing (COW) System on Tank Vessels General § 157.106 Letter of acceptance. The Coast Guard...) The plans submitted show that the COW system meets this subpart; or (b) The plans submitted and the scale model under § 157.104 show that the COW system meets this subpart. ...

  2. 49 CFR 1155.21 - Contents of application.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... meets the definition of a solid waste rail transfer facility at 49 U.S.C. 10909(e)(1)(H). (17) A... a solid waste rail transfer facility, and, if so, why. (c) Environmental impact. The applicant shall... OF TRANSPORTATION RULES OF PRACTICE SOLID WASTE RAIL TRANSFER FACILITIES Procedures Governing...

  3. 49 CFR 1155.21 - Contents of application.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... meets the definition of a solid waste rail transfer facility at 49 U.S.C. 10909(e)(1)(H). (17) A... OF TRANSPORTATION RULES OF PRACTICE SOLID WASTE RAIL TRANSFER FACILITIES Procedures Governing... address of the solid waste rail transfer facility, or, if not available, the city, State, and United...

  4. A Remote Absorption Process for Disposal of Evaporate and Reverse Osmosis Concentrates

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Brunsell, D.A.

    2008-07-01

    Many commercial nuclear plants and DOE facilities generate secondary waste streams consisting of evaporator bottoms and reverse osmosis (RO) concentrate. Since liquids are not permitted in disposal facilities, these waste streams must be converted to dry solids, either by evaporation to dried solids or by solidification to liquid-free solids. Evaporation of the liquid wastes reduces their volume, but requires costly energy and capital equipment. In some cases, concentration of the contaminants during drying can cause the waste to exceed Class A waste for nuclear utilities or exceed DOE transuranic limits. This means that disposal costs will be increased, or that,more » when the Barnwell, SC disposal site closes to waste outside of the Atlantic Compact in July 2008, the waste will be precluded from disposal for the foreseeable future). Solidification with cement agents requires less energy and equipment than drying, but results in a volume increase of 50-100%. The doubling or tripling of waste weight, along with the increased volume, sharply increases shipping and disposal costs. Confronted with these unattractive alternatives, Diversified Technologies Services (DTS), in conjunction with selected nuclear utilities and D and D operations at Rocky Flats, undertook an exploratory effort to convert this liquid wastewater to a solid without using cement. This would avoid the bulking effect of cement, and permit the waste to be disposed of the Energy Solutions facility in Utah as well as some DOE facilities. To address the need for an attractive alternative to drying and cement solidification, a test program was developed using a polymer absorbent media to convert the concentrate streams to a liquid-free waste form that meets the waste acceptance criteria of the pertinent burial sites. Two approaches for mixing the polymer with the liquid were tested: mechanical mixing and in-situ incorporation. As part of this test program, a process control program (PCP) was developed that is 100% scalable from a concentrate test sample as small as 50 grams to full-scale processing of 100 cubic foot containers or larger. In summary: The absorption process offers utilities a viable and less costly alternative to on-site drying or solidification of concentrates. The absorption process can be completed by site personnel or by a vendor as a turnkey service. The process is suitable for multiple types of waste, including RO and evaporator concentrates, sludges, and other difficult to process waters and wet solids. (author)« less

  5. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    The Office of Civilian Radioactive Waste Management Systems Engineering Management Plan (OCRWM SEMP) specifies the technical management approach for the development of the waste management system, and specifies the approach for the development of each of the system elements -- the waste acceptance system, the transportation system, the Monitored Retrievable Storage (MRS) facility, and the mined geologic disposal system, which includes site characterization activity. The SEMP also delineates how systems engineering will be used by OCRWM to describe the system development process; it identifies responsibilities for its implementation, and specifies the minimum requirements for systems engineering. It also identifies themore » close interrelationship of system engineering and licensing processes. This SEMP, which is a combined OCRWM and M&O SEMP, is part of the top-level program documentation and is prepared in accordance with the direction provided in the Program Management System Manual (PMSM). The relationship of this document to other top level documents in the CRWMS document hierarchy is defined in the PMSM. A systems engineering management plan for each project, which specifies the actions to be taken in implementing systems engineering at the project level, shall be prepared by the respective project managers. [``Program`` refers to the CRWMS-wide activity and ``project`` refers to that level responsible for accomplishing the specific activities of that segment of the program.] The requirements for the project level SEMPs are addressed in Section 4.2.2.2. They represent the minimum set of requirements, and do not preclude the broadening of systems engineering activities to meet the specific needs of each project.« less

  6. Simultaneous Thermal Analysis of WIPP and LANL Waste Drum Samples: A Preliminary Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Wayne, David M.

    2015-10-19

    On Friday, February 14, 2014, an incident in P7R7 of the WIPP underground repository released radioactive material into the environment. The direct cause of the event was a breached transuranic (TRU) waste container, subsequently identified as Drum 68660. Photographic and other evidence indicates that the breach of 68660 was caused by an exothermic event. Subsequent investigations (Britt, 2015; Clark and Funk, 2015; Wilson et al., 2015; Clark, 2015) indicate that the combination of nitrate salts, pH neutralizing chemicals, and organic-based adsorbent represented a potentially energetic mixture. The materials inside the breached steel drum consisted of remediated, 30- to 40-year old,more » Pu processing wastes from LANL. The contents were processed and repackaged in 2014. Processing activities at LANL included: 1) neutralization of acidic liquid contents, 2) sorption of the neutralized liquid, and 3) mixing of acidic nitrate salts with an absorber to meet waste acceptance criteria. The contents of 68660 and its sibling, 68685, were derived from the same parent drum, S855793. Drum S855793 originally contained ten plastic bags of acidic nitrate salts, and four bags of mixed nitrate and oxalate salts generated in 1985 by Pu recovery operations. These salts were predominantly oxalic acid, hydrated nitrate salts of Mg, Ca, and Fe, anhydrous Na(NO 3), and minor amounts of anhydrous and hydrous nitrate salts of Pb, Al, K, Cr, and Ni. Other major components include sorbed water, nitric acid, dissolved nitrates, an absorbent (Swheat Scoop®) and a neutralizer (KolorSafe®). The contents of 68660 are described in greater detail in Appendix E of Wilson et al. (2015)« less

  7. An investigation into waste charges in Ireland, with emphasis on public acceptability.

    PubMed

    Dunne, Louise; Convery, Frank J; Gallagher, Louise

    2008-12-01

    There are 34 local authorities in Ireland with legal responsibility to deal with waste arising in their jurisdictions. In 2003 the National government introduced legislation that allows local authorities to recover the costs of waste collection and disposal, and to do so by 'executive function', i.e., not requiring support or agreement by the relevant local political representatives. The year 2005 was set as the date by which implementation of a pay by weight or volume was to be introduced. The local authorities were given autonomy as to how they addressed this challenge, so we have - in theory - 34 potentially different experiences from which to learn. This paper examines the pay-as-you-throw (PAYT) waste system in Ireland as it develops in line with EU and National demands, with a view to assessing economic and environmental efficiency. All local authorities were surveyed and thirteen responded. While this only represents about 38% of the total number, it includes jurisdictions that contribute in total more than 50% of waste arising. Key figures in the policy and business community were also interviewed in order to identify how the charging schemes were implemented, and to what effect. These insights and parallel investigations are used to review the potential for problems regarding public acceptability of environmental taxes and examine the evidence for economic and environmental efficiency, as well as problem areas, using data from each of the responding local authority jurisdictions. Concentrating on the incentives and drivers across households, municipalities and private waste contractors, the variations in charging system, annual charges and landfill charges are compared where information was available. The various jurisdictions are also examined in terms of relative successes and problems encountered in the transition from fixed charge or free waste collection to PAYT systems. The Irish situation is placed in the context of the international literature on PAYT, the growing waste crisis, environmental attitudes vs. behaviours, and the acceptability of environmental taxes generally.

  8. E-waste: a global hazard.

    PubMed

    Perkins, Devin N; Brune Drisse, Marie-Noel; Nxele, Tapiwa; Sly, Peter D

    2014-01-01

    Waste from end-of-life electrical and electronic equipment, known as e-waste, is a rapidly growing global problem. E-waste contains valuable materials that have an economic value when recycled. Unfortunately, the majority of e-waste is recycled in the unregulated informal sector and results in significant risk for toxic exposures to the recyclers, who are frequently women and children. The aim of this study was to document the extent of the problems associated with inappropriate e-waste recycling practices. This was a narrative review that highlighted where e-waste is generated, where it is recycled, the range of adverse environmental exposures, the range of adverse health consequences, and the policy frameworks that are intended to protect vulnerable populations from inappropriate e-waste recycling practices. The amount of e-waste being generated is increasing rapidly and is compounded by both illegal exportation and inappropriate donation of electronic equipment, especially computers, from developed to developing countries. As little as 25% of e-waste is recycled in formal recycling centers with adequate worker protection. The health consequences of both direct exposures during recycling and indirect exposures through environmental contamination are potentially severe but poorly studied. Policy frameworks aimed at protecting vulnerable populations exist but are not effectively applied. E-waste recycling is necessary but it should be conducted in a safe and standardized manor. The acceptable risk thresholds for hazardous, secondary e-waste substances should not be different for developing and developed countries. However, the acceptable thresholds should be different for children and adults given the physical differences and pronounced vulnerabilities of children. Improving occupational conditions for all e-waste workers and striving for the eradication of child labor is non-negotiable. Crown Copyright © 2014. Published by Elsevier Inc. All rights reserved.

  9. Legislative and Regulatory Timeline for Fossil Fuel Combustion Wastes

    EPA Pesticide Factsheets

    This timeline walks through the history of fossil fuel combustion waste regulation since 1976 and includes information such as regulations, proposals, notices, amendments, reports and meetings and site visits conducted.

  10. Integrated software system for low level waste management

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Worku, G.

    1995-12-31

    In the continually changing and uncertain world of low level waste management, many generators in the US are faced with the prospect of having to store their waste on site for the indefinite future. This consequently increases the set of tasks performed by the generators in the areas of packaging, characterizing, classifying, screening (if a set of acceptance criteria applies), and managing the inventory for the duration of onsite storage. When disposal sites become available, it is expected that the work will require re-evaluating the waste packages, including possible re-processing, re-packaging, or re-classifying in preparation for shipment for disposal undermore » the regulatory requirements of the time. In this day and age, when there is wide use of computers and computer literacy is at high levels, an important waste management tool would be an integrated software system that aids waste management personnel in conducting these tasks quickly and accurately. It has become evident that such an integrated radwaste management software system offers great benefits to radwaste generators both in the US and other countries. This paper discusses one such approach to integrated radwaste management utilizing some globally accepted radiological assessment software applications.« less

  11. Mission analysis for cross-site transfer

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Riesenweber, S.D.; Fritz, R.L.; Shipley, L.E.

    1995-11-01

    The Mission Analysis Report describes the requirements and constraints associated with the Transfer Waste Function as necessary to support the Manage Tank Waste, Retrieve Waste, and Process Tank Waste Functions described in WHC-SD-WM-FRD-020, Tank Waste Remediation System (TWRS) Functions and Requirements Document and DOE/RL-92-60, Revision 1, TWRS Functions and Requirements Document, March 1994. It further assesses the ability of the ``initial state`` (or current cross-site transfer system) to meet the requirements and constraints.

  12. Waste receiving and processing facility module 1 data management system software project management plan

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Clark, R.E.

    1994-11-02

    This document provides the software development plan for the Waste Receiving and Processing (WRAP) Module 1 Data Management System (DMS). The DMS is one of the plant computer systems for the new WRAP 1 facility (Project W-026). The DMS will collect, store, and report data required to certify the low level waste (LLW) and transuranic (TRU) waste items processed at WRAP 1 as acceptable for shipment, storage, or disposal.

  13. Waste treatment in silicon production operations

    NASA Technical Reports Server (NTRS)

    Coleman, Larry M. (Inventor); Tambo, William (Inventor)

    1985-01-01

    A battery of special burners, each adapted for the treatment of a particular range of waste material formed during the conversion of metallurgical grade silicon to high purity silane and silicon, is accompanied by a series arrangement of filters to recover fumed silica by-product and a scrubber to recover muriatic acid as another by-product. All of the wastes are processed, during normal and plant upset waste load conditions, to produce useful by-products in an environmentally acceptable manner rather than waste materials having associated handling and disposal problems.

  14. Solid rocket propellant waste disposal/ingredient recovery study

    NASA Technical Reports Server (NTRS)

    Mcintosh, M. J.

    1976-01-01

    A comparison of facility and operating costs of alternate methods shows open burning to be the lowest cost incineration method of waste propellant disposal. The selection, development, and implementation of an acceptable alternate is recommended. The recovery of ingredients from waste propellant has the probability of being able to pay its way, and even show a profit, when large consistent quantities of composite propellant are available. Ingredients recovered from space shuttle waste propellant would be worth over $1.5 million. Open and controlled burning are both energy wasteful.

  15. The impact of council directive 2011/70/EURATOM and IAEA joint convention review meetings on the ongoing establishment of the Portuguese regulatory framework and on the future of national radioactive waste

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Paiva, Isabel; Trindade, Romao B.

    Council Directive 2011/70/EURATOM of 19 July 2011, establishing a Community framework for the responsible and safe management of spent fuel and radioactive waste will enter in force August 2013 in all EU Member States. Portugal has already started preparing its legislative framework to accommodate the new legislative piece. However, the first report of Portugal to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management of the IAEA, in Vienna, 2012, has shown that Portugal still has many steps to overcome to establish a successful and effective basic regulatory framework. The existencemore » of many competent authorities related to the radiological protection area and a newly independent commission that is still looking on how to fulfill its regulator role in other areas such as the radioactive waste management makes quite challenging the full application of the new directive as well as compliance that Portugal will have to show in the next Joint Convention review meeting in order to meet the obligations of the Convention. In this paper, the reality of the regulatory Portuguese framework on radiological protection, nuclear safety and radioactive waste management is presented. Discussion of the future impact of the new legislation and its consequences such as the need to setup the national program on radioactive waste management is critical discussed. (authors)« less

  16. 49 CFR 173.150 - Exceptions for Class 3 (flammable and combustible liquids).

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... the material meets the definition of a hazardous substance, hazardous waste, marine pollutant, or are... waste, or a marine pollutant. (3) A combustible liquid that is in a bulk packaging or a combustible liquid that is a hazardous substance, a hazardous waste, or a marine pollutant is not subject to the...

  17. 49 CFR 173.150 - Exceptions for Class 3 (flammable and combustible liquids).

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... material meets the definition of a hazardous substance, hazardous waste, marine pollutant, or is offered... that is a hazardous substance, a hazardous waste, or a marine pollutant is not subject to the... liquid in a non-bulk packaging unless the combustible liquid is a hazardous substance, a hazardous waste...

  18. 40 CFR Table 1 to Subpart Aaaa of... - Emission Limits for New Small Municipal Waste Combustion Units

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... Waste Combustion Units 1 Table 1 to Subpart AAAA of Part 60 Protection of Environment ENVIRONMENTAL... Standards of Performance for Small Municipal Waste Combustion Units for Which Construction is Commenced... Combustion Units For the following pollutants You must meet thefollowing emission limits a Using the...

  19. 40 CFR Table 1 to Subpart Aaaa of... - Emission Limits for New Small Municipal Waste Combustion Units

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... Waste Combustion Units 1 Table 1 to Subpart AAAA of Part 60 Protection of Environment ENVIRONMENTAL... Standards of Performance for Small Municipal Waste Combustion Units for Which Construction is Commenced... Combustion Units For the following pollutants You must meet thefollowing emission limits a Using the...

  20. 40 CFR Table 1 to Subpart Aaaa of... - Emission Limits for New Small Municipal Waste Combustion Units

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... Waste Combustion Units 1 Table 1 to Subpart AAAA of Part 60 Protection of Environment ENVIRONMENTAL... Standards of Performance for Small Municipal Waste Combustion Units for Which Construction is Commenced... Combustion Units For the following pollutants You must meet thefollowing emission limits a Using the...

  1. 40 CFR Table 1 to Subpart Aaaa of... - Emission Limits for New Small Municipal Waste Combustion Units

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... Waste Combustion Units 1 Table 1 to Subpart AAAA of Part 60 Protection of Environment ENVIRONMENTAL... Standards of Performance for Small Municipal Waste Combustion Units for Which Construction is Commenced... Combustion Units For the following pollutants You must meet thefollowing emission limits a Using the...

  2. 40 CFR Table 1 to Subpart Aaaa of... - Emission Limits for New Small Municipal Waste Combustion Units

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... Waste Combustion Units 1 Table 1 to Subpart AAAA of Part 60 Protection of Environment ENVIRONMENTAL... Standards of Performance for Small Municipal Waste Combustion Units for Which Construction is Commenced... Combustion Units For the following pollutants You must meet thefollowing emission limits a Using the...

  3. Solid Waste, Air Pollution and Health

    ERIC Educational Resources Information Center

    Kupchik, George J.; Franz, Gerald J.

    1976-01-01

    This article examines the relationships among solid waste disposal, air pollution, and human disease. It is estimated that solid waste disposal contributes 9.7 percent of the total air pollution and 9.9 percent of the total air pollution health effect. Certain disposal-resource recovery systems can be implemented to meet air quality standards. (MR)

  4. Quality evaluation of rice bran protein isolate-based weaning food for preschoolers.

    PubMed

    Khan, Saima H; Butt, Masood S; Anjum, Faqir M; Sameen, Ayesha

    2011-05-01

    Agro-industrial waste 'rice bran' was stabilized and the extracted protein isolates were used as ingredients to make nutritive complimentary food for the growing infants. The formulation processed through drum drying and the starchy ingredients were pregelatinized to reduce bulk in the prepared meal and facilitate spoon-feeding. The formulations had uniform texture, light golden color and good paste consistency. Nutrient composition was good enough to meet standards for supplementary infant foods. Caloric value remained up to 416 kcal/100 g with spoonable viscosity and 80.90-84.45% in vitro digestibility. A single meal could substantially contribute to the daily essential amino acid requirement. The formulation had good acceptability during a short-term infant-feeding trial. The present study can provide practical guideline for manufacturers as well as the nutritionist for the use of an economical and nutritive formulation for young children.

  5. Phase II test plan for the evaluation of the performance of container filling systems

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    BOGER, R.M.

    The PHMC will provide tank wastes for final treatment by BNFL from Hanford's waste tanks. Concerns about the ability for ''grab'' sampling to provide large volumes of representative waste samples has led to the development of a nested, fixed-depth sampling system. Preferred concepts for filling sample containers that meet RCRA organic sample criteria were identified by a PHMC Decision Board. These systems will replace the needle based sampling ''T'' that is currently on the sampling system. This test plan document identifies cold tests with simulants that will demonstrate the preferred bottle filling concepts abilities to provide representative waste samples andmore » will meet RCRA criteria. Additional tests are identified that evaluate the potential for cross-contamination between samples and the ability for the system to decontaminate surfaces which have contacted tank wastes. These tests will be performed with kaolid/water and sand/water slurry simulants in the test rig that was used by AEAT to complete Phase 1 tests in FY 1999.« less

  6. Stabilization of tannery sludge by co-treatment with aluminum anodizing sludge and phytotoxicity of end-products.

    PubMed

    Pantazopoulou, E; Zebiliadou, O; Mitrakas, M; Zouboulis, A

    2017-03-01

    A global demand for efficient re-utilization of produced solid wastes, which is based on the principles of re-use and recycling, results to a circular economy, where one industry's waste becomes another's raw material and it can be used in a more efficient and sustainable way. In this study, the influence of a by-product addition, such as aluminum anodizing sludge, on tannery waste (air-dried sludge) stabilization was examined. The chemical characterization of tannery waste leachate, using the EN 12457-2 standard leaching test, reveals that tannery waste cannot be accepted even in landfills for hazardous wastes, according to the EU Decision 2003/33/EC. The stabilization of tannery waste was studied applying different ratios of tannery waste and aluminum anodizing sludge, i.e. 50:50, 60:40, 70:30 and 80:20 ratios respectively. Subsequently, the stabilization rate of the qualified as optimum homogenized mixture of 50:50 ratio was also tested during time (7, 15 and 30days). Moreover, this stabilized product was subjected to phytotoxicity tests using the Lepidium sativum, Sinapis alba and Sorghum saccharatum seeds. The experimental results showed that aluminum anodizing sludge managed to stabilize effectively chromium and organic content of tannery waste, which are the most problematic parameters influencing its subsequent disposal. As a result, tannery waste stabilized with the addition of aluminum anodizing sludge at 50:50 ratio can be accepted in non-hazardous waste landfills, as chromium and dissolved organic carbon concentrations in the respective leachate are below the relevant regulation limits, while the stabilized waste shows decreased phytotoxicity. Copyright © 2017 Elsevier Ltd. All rights reserved.

  7. 40 CFR Table 8 to Subpart Dddd of... - Model Rule-Emission Limitations That Apply to Waste-Burning Kilns After May 20, 2011

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... Apply to Waste-Burning Kilns After May 20, 2011 8 Table 8 to Subpart DDDD of Part 60 Protection of..., Table 8 Table 8 to Subpart DDDD of Part 60—Model Rule—Emission Limitations That Apply to Waste-Burning... to Waste-Burning Kilns After May 20, 2011 For the air pollutant You must meet this emissionlimitation...

  8. Integration of Cleaner Production and Waste Water Treatment on Tofu Small Industry for Biogas Production using AnSBR Reactor

    NASA Astrophysics Data System (ADS)

    Rahayu, Suparni Setyowati; Budiyono; Purwanto

    2018-02-01

    A research on developing a system that integrates clean production and waste water treatment for biogas production in tofu small industry has been conducted. In this research, tofu waste water was turned into biogas using an AnSBR reactor. Mud from the sewage system serves as the inoculums. This research involved: (1) workshop; (2) supervising; (3) technical meeting; (4) network meeting, and (5) technical application. Implementation of clean production integrated with waste water treatment reduced the amount of waste water to be treated in a treatment plant. This means less cost for construction and operation of waste water treatment plants, as inherent limitations associated with such plants like lack of fund, limited area, and technological issues are inevitable. Implementation of clean production prior to waste water treatment reduces pollution figures down to certain levels that limitations in waste water treatment plants can be covered. Results show that biogas in 16 days HRT in an AnSBR reactor contains CH4(78.26 %) and CO2 (20.16 %). Meanwhile, treatments using a conventional bio-digester result in biogas with 72.16 % CH4 and 18.12 % CO2. Hence, biogas efficiency for the AnSBR system is 2.14 times greater than that of a conventional bio-digester.

  9. Sorption of PFOA and PFOS to Aquifer Sediment

    EPA Science Inventory

    During its years of operation, the Washington County Sanitary Landfill near St. Paul, Minnesota accepted both municipal and industrial solid waste. Several years of ground water monitoring performed by the MPCA indicates that, some of the waste disposed of at this landfill contai...

  10. MUNICIPAL SOLID WASTE COMBUSTOR ASH DEMONSTRATION PROGRAM - "THE BOATHOUSE"

    EPA Science Inventory

    The report presents the results of a research program designed to examine the engineering and environmental acceptability of using municipal solid waste (MSW) combustor ash as an aggregate substitute in the manufacture of construction quality cement blocks. 50 tons of MSW combust...

  11. Local Gov`t assistance in commercial waste reduction & recycling

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hannah, C.W.

    This paper outlines programs and strategies for reducing the waste stream by targeting the commercial, industrial and institutional sectors. The programs described are implemented by the Wake County Solid Waste Management Division, North Carolina. Findings and recommendations of a task force focusing on the role of the private sector in meeting state waste reduction mandates are summarized. Commercial initiatives, educational initiatives, and a grant program are described. Several case studies are provided which overview the variety of businesses and waste materials addressed.

  12. 49 CFR 173.154 - Exceptions for Class 8 (corrosive materials).

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... material meets the definition of a hazardous substance, hazardous waste, marine pollutant, or are offered... waste, or a marine pollutant, a material classed as a Class 8, Packing Group III, material solely...

  13. Mission analysis report for single-shell tank leakage mitigation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cruse, J.M.

    1994-09-01

    This document provides an analysis of the leakage mitigation mission applicable to past and potential future leakage from the Hanford Site`s 149 single-shell high-level waste tanks. This mission is a part of the overall missions of the Westinghouse Hanford Company Tank Waste Remediation System division to remediate the tank waste in a safe and acceptable manner. Systems engineers principles are being applied to this effort. Mission analysis supports early decision making by clearly defining program objectives. This documents identifies the initial conditions and acceptable final conditions, defines the programmatic and physical interfaces and constraints, estimates the resources to carry outmore » the mission, and establishes measures of success. The results of the mission analysis provide a consistent basis for subsequent systems engineering work.« less

  14. How to Meet Water Cleanup Deadlines

    ERIC Educational Resources Information Center

    Schmidt, Richard K.

    1976-01-01

    Most waste treatment techniques conceived to meet the 1977 standards can be separated into three distinct phases: primary, secondary and tertiary treatment. An examination of the four heaviest industrial water users, pulp and paper, steel, plating, and food processing, demonstrates these treatments use proven technology to meet specific…

  15. 76 FR 73737 - Sunshine Act Meeting

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-11-29

    ... Meeting) (Tentative) a. U.S. Department of Energy (High-Level Waste Repository), Docket No. 63-001-HLW; Staff Petition for the Commission to Exercise its Inherent Supervisory Authority to Review Board Orders...

  16. Safety analysis report for the Waste Storage Facility. Revision 2

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bengston, S.J.

    1994-05-01

    This safety analysis report outlines the safety concerns associated with the Waste Storage Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are: define and document a safety basis for the Waste Storage Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume.

  17. Adaption of the Magnetometer Towed Array geophysical system to meet Department of Energy needs for hazardous waste site characterization

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cochran, J.R.; McDonald, J.R.; Russell, R.J.

    1995-10-01

    This report documents US Department of Energy (DOE)-funded activities that have adapted the US Navy`s Surface Towed Ordnance Locator System (STOLS) to meet DOE needs for a ``... better, faster, safer and cheaper ...`` system for characterizing inactive hazardous waste sites. These activities were undertaken by Sandia National Laboratories (Sandia), the Naval Research Laboratory, Geo-Centers Inc., New Mexico State University and others under the title of the Magnetometer Towed Array (MTA).

  18. Improvement of Leaching Resistance of Low-level Waste Form in Korea

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kim, J.Y.; Lee, B.C.; Kim, C.L.

    2006-07-01

    Low-level liquid concentrate wastes including boric acid have been immobilized with paraffin wax using concentrate waste drying system in Korean nuclear power plants since 1995. Small amount of low density polyethylene (LDPE) was added to increase the leaching resistance of the existing paraffin waste form and the influence of LDPE on the leaching behavior of waste form was investigated. It was observed that the leaching of nuclides immobilized within paraffin waste form remarkably reduced as the content of LDPE increased. The acceptance criteria of paraffin waste form associated with leachability index and compressive strength after the leaching test were successfullymore » satisfied with the help of LDPE. (authors)« less

  19. Centralized waste treatment of industrial wastewater

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Saltzberg, E.R.; Cushnie, G.C. Jr.

    1985-01-01

    Centralized waste treatment (CWT) for industrial wastewater is described in this book. With the CWT approach, industrial firms send their wastes to a common processing plant. The book addresses the engineering and business-related problems that are encountered by private CWT firms, local governments, and industry in creating sufficient CWT capacity to meet the growing demand for CWT services.

  20. Sorption of PFOA and PFOS to Ground Water Sediment

    EPA Science Inventory

    During its years of operation, the Washington County Sanitary Landfill near St. Paul, Minnesota accepted both municipal and industrial solid waste. Several years of ground water monitoring performed by the MPCA indicates that, some of the waste disposed of at this landfill contai...

  1. 40 CFR 761.212 - Transporter compliance with the manifest.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ...) TOXIC SUBSTANCES CONTROL ACT POLYCHLORINATED BIPHENYLS (PCBs) MANUFACTURING, PROCESSING, DISTRIBUTION IN COMMERCE, AND USE PROHIBITIONS PCB Waste Disposal Records and Reports § 761.212 Transporter compliance with the manifest. (a) The transporter must deliver the entire quantity of PCB waste which he has accepted...

  2. 40 CFR 761.212 - Transporter compliance with the manifest.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ...) TOXIC SUBSTANCES CONTROL ACT POLYCHLORINATED BIPHENYLS (PCBs) MANUFACTURING, PROCESSING, DISTRIBUTION IN COMMERCE, AND USE PROHIBITIONS PCB Waste Disposal Records and Reports § 761.212 Transporter compliance with the manifest. (a) The transporter must deliver the entire quantity of PCB waste which he has accepted...

  3. 40 CFR 264.602 - Monitoring, analysis, inspection, response, reporting, and corrective action.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE....75, 264.76, 264.77, and -264.101 as well as meet any additional requirements needed to protect human...

  4. 40 CFR 264.602 - Monitoring, analysis, inspection, response, reporting, and corrective action.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE....75, 264.76, 264.77, and -264.101 as well as meet any additional requirements needed to protect human...

  5. 40 CFR 264.602 - Monitoring, analysis, inspection, response, reporting, and corrective action.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE....75, 264.76, 264.77, and -264.101 as well as meet any additional requirements needed to protect human...

  6. 40 CFR 264.602 - Monitoring, analysis, inspection, response, reporting, and corrective action.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE....75, 264.76, 264.77, and -264.101 as well as meet any additional requirements needed to protect human...

  7. 40 CFR 264.602 - Monitoring, analysis, inspection, response, reporting, and corrective action.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE....75, 264.76, 264.77, and -264.101 as well as meet any additional requirements needed to protect human...

  8. Meeting Regulatory Requirements

    EPA Science Inventory

    Domestic wastewater is made up of sanitary wastes from homes, commercial businesses and industry, and includes beneficial, commensal and pathogenic microorganisms. The extent to which a given strain of pathogen may be found within a waste treatment system is largely dependant up...

  9. A wasted world

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Delbello, A.

    1991-03-01

    It is still legal under American law to dump waste products in any country whose government consents to accept them. Many developing countries accept waste exports for a per ton charge. It does not matter to them whether the waste is hazardous, toxic, nonhazardous, or nontoxic. Nor does it matter to them whether or not they have the technology for the safe disposal of wastes. In some nations there is little or no thought about the long-term consequences of unsafe disposal of hazardous wastes to their land, air, water, quality of life, crops, animals and children. Some of the mainmore » culprits in the U.S. have been surprising: the Pentagon, other federal agencies, state and local governments, the American business community in general, and, of course, various brokers and entrepreneurs have all been documented, time and again, as exporters of hazardous waste to the Third World. And then there are the illegal waste shipments, perpetrated by hustlers and nice people alike in many industrialized nations. Here is a sample: In September 1987, Italian ships unloaded 10,000 steel drums of hazardous waste in the Nigerian port of Koko and stored them in a vacant residential lot. The press learned of it in June 1988. The Nigerian government ultimately imprisoned 54 people, including Italian nationals, and formally expressed outrage to the Italian government. The Italian government responded by sending a team of experts to arrange removal. A West German ship was loaded with the waste and went back to Ravenna, Italy, but Italian protestors prevented the ship form docking. It attempted to dock in Spain, France, the Netherlands and the United Kingdom, without success. Finally, a home for the waste was found in an unidentified Italian port in mid-September.« less

  10. 78 FR 11877 - Announcement of Requirements Gathering Meetings for the Electronic Manifest (e-Manifest) System

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-02-20

    ... Gathering Meetings for the Electronic Manifest (e-Manifest) System AGENCY: Environmental Protection Agency (EPA). ACTION: Notice of public meetings. SUMMARY: EPA's Office of Resource Conservation and Recovery...'') system to capture information regarding the shipment of hazardous waste from the time it leaves the...

  11. Effective Group Facilitation in Education: How to Energize Meetings and Manage Difficult Groups

    ERIC Educational Resources Information Center

    Eller, John F.

    2004-01-01

    At their worst, meetings can waste time, lack focus, foster a combative spirit, or be just plain boring. At their best, meetings can be a positive, dynamic experience that nurtures individual strengths while inspiring teamwork to successfully accomplish an established task. The fate of a meeting lies in the skill of the facilitator, and this…

  12. 75 FR 7576 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-22

    ... environmental restoration, waste management, and related activities. Tentative Agenda: The main meeting... agenda. The Deputy Designated Federal Officer is empowered to conduct the meeting in a fashion that will...

  13. 76 FR 59393 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-09-26

    ... environmental restoration, waste management, and related activities. Tentative Agenda: The main meeting... agenda. The Deputy Designated Federal Officer is empowered to conduct the meeting in a fashion that will...

  14. 76 FR 65190 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-20

    ... environmental restoration, waste management, and related activities. Tentative Agenda: The main meeting... in the agenda. The Deputy Designated Federal Officer is empowered to conduct the meeting in a fashion...

  15. 75 FR 82001 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-29

    ... environmental restoration, waste management, and related activities. Tentative Agenda: The main meeting... meeting in a fashion that will facilitate the orderly conduct of business. Individuals wishing to make...

  16. 75 FR 51027 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-08-18

    ... environmental restoration, waste management, and related activities. Tentative Agenda: The main meeting... agenda. The Deputy Designated Federal Officer is empowered to conduct the meeting in a fashion that will...

  17. 76 FR 78908 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-20

    ... environmental restoration, waste management, and related activities. Tentative Agenda: The main meeting... conduct the meeting in a fashion that will facilitate the orderly conduct of business. Individuals wishing...

  18. 76 FR 36101 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-21

    ... environmental restoration, waste management, and related activities. Tentative Agenda: The main meeting... meeting in a fashion that will facilitate the orderly conduct of business. Individuals wishing to make...

  19. 75 FR 24685 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-05-05

    ... environmental restoration, waste management, and related activities. Tentative Agenda: The main meeting... meeting in a fashion that will facilitate the orderly conduct of business. Individuals wishing to make...

  20. Secondary Waste Form Development and Optimization—Cast Stone

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sundaram, S. K.; Parker, Kent E.; Valenta, Michelle M.

    2011-07-14

    Washington River Protection Services is considering the design and construction of a Solidification Treatment Unit (STU) for the Effluent Treatment Facility (ETF) at Hanford. The ETF is a Resource Conservation and Recovery Act-permitted, multi-waste, treatment and storage unit and can accept dangerous, low-level, and mixed wastewaters for treatment. The STU needs to be operational by 2018 to receive secondary liquid wastes generated during operation of the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The STU to ETF will provide the additional capacity needed for ETF to process the increased volume of secondary wastes expected to be produced by WTP.

  1. A West Valley Demonstration Project Milestone - Achieving Certification to Ship Waste to the Nevada Test Site

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Jackson, J. P.; Pastor, R. S.

    2002-02-28

    The West Valley Demonstration Project (WVDP) has successfully pretreated and vitrified nearly all of the 600,000 gallons of liquid high-level radioactive waste that was generated at the site of the only commercial nuclear fuel reprocessing plant to have operated in the United States. Low-level waste (LLW) generated during the course of the cleanup effort now requires disposal. Currently the WVDP only ships Class A LLW for off-site disposal. It has been shipping Class A wastes to Envirocare of Utah, Inc. since 1997. However, the WVDP may also have a future need to ship Class B and Class C waste, whichmore » Envirocare is not currently authorized to accept. The Nevada Test Site (NTS), a U.S. Department of Energy (DOE) facility, can accept all three waste classifications. The WVDP set a goal to receive certification to begin shipping Class A wastes to NTS by 2001. Formal certification/approval was granted by the DOE Nevada Operations Office on July 12, 2001. This paper discusses how the WVDP contractor, West Valley Nuclear Services Company (WVNSCO), completed the activities required to achieve NTS certification in 2001 to ship waste to its facility. The information and lessons learned provided are significant because the WVDP is the only new generator receiving certification based on an NTS audit in January 2001 that resulted in no findings and only two observations--a rating that is unparalleled in the DOE Complex.« less

  2. RCRA/UST, superfund, and EPCRA hotline training module. Introduction to: Solid and hazardous waste exclusions (40 CFR section 261.4) updated as of July 1995

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1995-11-01

    This module explains each waste exclusion and its scope, so one can apply this knowledge in determining wheather a given waste is or is not regulated under RCRA Subtitle C. It cites the regulatory section for exclusions and identifies materials that are not solid wastes and solid wastes that are not hazardous wastes. It locates the manufacturing process unit exclusion and identifies the sample and treatability study exclusions and their applicability. It outlines and specifies the conditions for meeting the exclusions for household wastes and mixtures of domestic sewage.

  3. (Low-level radioactive waste management techniques)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Van Hoesen, S.D.; Kennerly, J.M.; Williams, L.C.

    1988-08-08

    The US team consisting of representatives of Oak Ridge National Laboratory (ORNL), Savannah River plant (SRP), Idaho National Engineering Laboratory (INEL), and the Department of Energy, Oak Ridge Operations participated in a training program on French low-level radioactive waste (LLW) management techniques. Training in the rigorous waste characterization, acceptance and certification procedures required in France was provided at Agence Nationale pour les Gestion des Dechets Radioactif (ANDRA) offices in Paris.

  4. Environmental health risks of toxic waste site exposures--an epidemiological perspective.

    PubMed

    von Schirnding, Y E; Ehrlich, R I

    1992-06-06

    A general account is given of the problems of assessing the impact of human exposure to toxic waste sites, including the identification of truly exposed populations and of exposure pathways. Epidemiological studies of populations at risk are briefly reviewed and methodological problems summarised. These include the use of relatively weak study designs, inadequate exposure assessment and recall biases associated with symptom reporting among anxious residents living in the vicinity of waste sites. In South Africa, health risks associated with exposure to toxic waste sites need to be viewed in the context of current community health concerns, competing causes of disease and ill-health, and the relative lack of knowledge about environmental contamination and associated health effects. A nonspecific deterioration of health and well-being is more likely to result from waste site exposures than is overt clinical disease. Socially acceptable policies and controls may have to be based on criteria other than demonstrable ill-health. Detailed inventories and registries of the nature of disposed materials need to be maintained, sites of poorly controlled disposal in the past identified and selective environmental monitoring conducted. Epidemiological studies may be justified in situations where exposures well in excess of acceptable norms are demonstrated. An integrated national waste management policy for the country is urgently needed.

  5. 16 CFR 1615.4 - Test procedure.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... three Samples meet all the test criteria of § 1615.3(b), accept the seam design. If one or more of the... additional Samples meet all the test criteria of § 1615.3(b) accept the seam design. If one or more of the... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Test procedure. 1615.4 Section 1615.4...

  6. 50 CFR 600.1006 - Accepting a request for, and determinations about conducting, a subsidized program.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 50 Wildlife and Fisheries 8 2010-10-01 2010-10-01 false Accepting a request for, and... reduction amendment, the requirements in § 600.1002(a); (2) Certify that the CFMP meets, or will meet after an appropriate reduction amendment, the requirements in § 600.1002(b)(1) and (2); and (3) Project the...

  7. WTP Waste Feed Qualification: Glass Fabrication Unit Operation Testing Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Stone, M. E.; Newell, J. D.; Johnson, F. C.

    The waste feed qualification program is being developed to protect the Hanford Tank Waste Treatment and Immobilization Plant (WTP) design, safety basis, and technical basis by assuring waste acceptance requirements are met for each staged waste feed campaign prior to transfer from the Tank Operations Contractor to the feed receipt vessels inside the Pretreatment Facility. The Waste Feed Qualification Program Plan describes the three components of waste feed qualification: 1. Demonstrate compliance with the waste acceptance criteria 2. Determine waste processability 3. Test unit operations at laboratory scale. The glass fabrication unit operation is the final step in the processmore » demonstration portion of the waste feed qualification process. This unit operation generally consists of combining each of the waste feed streams (high-level waste (HLW) and low-activity waste (LAW)) with Glass Forming Chemicals (GFCs), fabricating glass coupons, performing chemical composition analysis before and after glass fabrication, measuring hydrogen generation rate either before or after glass former addition, measuring rheological properties before and after glass former addition, and visual observation of the resulting glass coupons. Critical aspects of this unit operation are mixing and sampling of the waste and melter feeds to ensure representative samples are obtained as well as ensuring the fabrication process for the glass coupon is adequate. Testing was performed using a range of simulants (LAW and HLW simulants), and these simulants were mixed with high and low bounding amounts of GFCs to evaluate the mixing, sampling, and glass preparation steps in shielded cells using laboratory techniques. The tests were performed with off-the-shelf equipment at the Savannah River National Laboratory (SRNL) that is similar to equipment used in the SRNL work during qualification of waste feed for the Defense Waste Processing Facility (DWPF) and other waste treatment facilities at the Savannah River Site. It is not expected that the exact equipment used during this testing will be used during the waste feed qualification testing for WTP, but functionally similar equipment will be used such that the techniques demonstrated would be applicable. For example, the mixing apparatus could use any suitable mixer capable of being remoted and achieving similar mixing speeds to those tested.« less

  8. Clinical laboratory waste management in Shiraz, Iran.

    PubMed

    Askarian, Mehrdad; Motazedian, Nasrin; Palenik, Charles John

    2012-06-01

    Clinical laboratories are significant generators of infectious waste, including microbiological materials, contaminated sharps, and pathologic wastes such as blood specimens and blood products. Most waste produced in laboratories can be disposed of in the general solid waste stream. However, improper management of infectious waste, including mixing general wastes with infectious wastes and improper handling or storage, could lead to disease transmission. The aim of this study was to assess waste management processes used at clinical laboratories in Shiraz, Iran. One hundred and nine clinical laboratories participated In this cross sectional study, Data collection was by questionnaire and direct observation. Of the total amount of waste generated, 52% (by weight) was noninfectious domestic waste, 43% was non-sharps infectious waste and 5% consisted of sharps. There was no significant relationship between laboratory staff or manager education and the score for quality of waste collection and disposal at clinical laboratories. Improvements in infectious waste management processes should involve clearer, more uniformly accepted definitions of infectious waste and increased staff training.

  9. 77 FR 4321 - Sunshine Act Meeting; Open Commission Meeting; January 31, 2012

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-01-27

    ... Americans while minimizing the universal service contribution burden, including by eliminating waste, fraud... print/ type; digital disk; and audio and video tape. Best Copy and Printing, Inc. may be reached by...

  10. Formative research on a teacher accompaniment model to promote youth mental health in Haiti: Relevance to mental health task-sharing in low-resource school settings

    PubMed Central

    Eustache, Eddy; Gerbasi, Margaret E.; Severe, Jennifer; Fils-Aimé, J. Reginald; Smith Fawzi, Mary C.; Raviola, Giuseppe J.; Darghouth, Sarah; Boyd, Kate; Thérosmé, Tatiana; Legha, Rupinder; Pierre, Ermaze L.; Affricot, Emmeline; Alcindor, Yoldie; Grelotti, David J.; Becker, Anne E.

    2017-01-01

    Background Task-sharing with teachers to promote youth mental health is a promising but underdeveloped strategy in improving care access in low-income countries. Aims To assess feasibility, acceptability, and utility of the teacher accompaniment phase of a school-based teacher accompagnateur pilot study (TAPS) in Haiti. Methods We assigned student participants, ages 18–22 (n=120) to a teacher participant (n=22) within four Haitian schools; we instructed participants to arrange meetings with their assigned counterparts to discuss mental health treatment, academic skills, and/or well-being. We measured student and teacher perceived feasibility, acceptability, and utility of meetings with self-report Likert-style questions. We examined overall program feasibility by the percentage of students with a documented meeting, acceptability by a composite measure of student satisfaction, and utility by the percentage with identified mental health need who discussed treatment with a teacher. Results Favorable ratings support feasibility, acceptability, and utility of teacher-accompagnateur meetings with students. The majority of students (54%) met with a teacher. Among students with an identified mental disorder, 43.2% discussed treatment during a meeting. Conclusions This accompaniment approach to mental health task-sharing with teachers provided a school-based opportunity for students with mental health need to discuss treatment and has potential relevance to other low-income settings. PMID:28367718

  11. Formative research on a teacher accompaniment model to promote youth mental health in Haiti: Relevance to mental health task-sharing in low-resource school settings.

    PubMed

    Eustache, Eddy; Gerbasi, Margaret E; Severe, Jennifer; Fils-Aimé, J Reginald; Smith Fawzi, Mary C; Raviola, Giuseppe J; Darghouth, Sarah; Boyd, Kate; Thérosmé, Tatiana; Legha, Rupinder; Pierre, Ermaze L; Affricot, Emmeline; Alcindor, Yoldie; Grelotti, David J; Becker, Anne E

    2017-06-01

    Task-sharing with teachers to promote youth mental health is a promising but underdeveloped strategy in improving care access in low-income countries. To assess feasibility, acceptability and utility of the teacher accompaniment phase of a school-based Teacher- Accompagnateur Pilot Study (TAPS) in Haiti. We assigned student participants, aged 18-22 years ( n = 120), to teacher participants ( n = 22) within four Haitian schools; we instructed participants to arrange meetings with their assigned counterparts to discuss mental health treatment, academic skills, and/or well-being. We measured student and teacher perceived feasibility, acceptability and utility of meetings with self-report Likert-style questions. We examined overall program feasibility by the percentage of students with a documented meeting, acceptability by a composite measure of student satisfaction and utility by the percentage with identified mental health need who discussed treatment with a teacher. Favorable ratings support feasibility, acceptability and utility of teacher- accompagnateur meetings with students. The majority of students (54%) met with a teacher. Among students with an identified mental disorder, 43.2% discussed treatment during a meeting. This accompaniment approach to mental health task-sharing with teachers provided a school-based opportunity for students with mental health need to discuss treatment and has potential relevance to other low-income settings.

  12. Information brochure on the Department of Energy's proposed Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. Project overview

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    This project overview comprises the following: project history; WIPP fact sheet; legal actions required; major WIPP milestones; low-level waste volumes; nuclear waste transportation; WIPP site selection; and questions and answers from the Department of Energy request for public input prior to public meetings in Roswell and Hobbs, New Mexico.

  13. Waste Analysis Plan and Waste Characterization Survey, Barksdale AFB, Louisiana

    DTIC Science & Technology

    1991-03-01

    review to assess if analysis is needed, any analyses that are to be provided by generators, and methods to be used to meet specific waste analysis ...sampling method , sampling frequency, parameters of analysis , SW 846 test methods , Department of Transportation (DOT) shipping name and hazard class...S.e.iceA w/Atchs 2. HQ SAC/DEV Ltr, 28 Sep 90 19 119 APPENDIX B Waste Analysis Plan Rationale 21 APPENDIX B 1. SAMPLING METHOD RATIONALE: Composite Liquid

  14. Solid wastes from nuclear power production.

    PubMed Central

    Soule, H F

    1978-01-01

    Radioactivity in nuclear power effluents is negligible compared to that in retained wastes to be disposed of as solids. Two basic waste categories are those for which shallow disposal is accepted and those for which more extreme isolation is desired. The latter includes "high level" wastes and others contaminated with radionuclides with the unusual combined properties of long radioactive half-life and high specific radiotoxicity. The favored method for extreme isolation is emplacement in a deep stable geologic formation. Necessary technologies for waste treatment and disposal are considered available. The present program to implement these technologies is discussed, including the waste management significance of current policy on spent nuclear fuel reprocessing. Recent difficulties with shallow disposal of waste are summarized. PMID:738244

  15. [School meals: planning, production, distribution, and adequacy].

    PubMed

    Issa, Raquel Carvalho; Moraes, Letícia Freitas; Francisco, Raquel Rocha Jabour; dos Santos, Luana Caroline; dos Anjos, Adriana Fernandez Versiani; Pereira, Simone Cardoso Lisboa

    2014-02-01

    To evaluate the planning, production, distribution, and nutritional adequacy of meals served at city schools. This descriptive cross-sectional study was conducted between March 2011 and April 2012 and included a representative sample (n = 42 schools) of extended shift city schools from Belo Horizonte, Minas Gerais, Brazil. Five meals from each school were randomly selected and analyzed by direct weighing. Production indicators and nutritional adequacy were evaluated in contrast to the recommendations of the city food security bureau and the Brazilian National Program of School Meals (PNAE). Seventy-nine percent of the analyzed meals did not meet the recommendations of the city food security bureau. The rate of waste (food left on plates) was acceptable at 4,90%, but the rates of cooked and not served food (7,06%) and counter leftovers (5,30%) were high. Both the city planned meals and the meals served in the schools were nutritionally inadequate in terms of the PNAE, particularly for children aged 11-15 years. There was a relationship between consumption by school staff and the amount of food that was cooked (r = 0.353; P < 0.001) and the rate of cooked and not served food (r = 0.138; P = 0.045). Waste was positively correlated with the rate of counter leftovers (r = 0.145; P = 0.035), and inversely correlated with fiber intake (r = -0.143; P = 0.038). The results indicate the importance of monitoring the planning, production, and distribution of school meals and of food and nutrition education in order to improve the quality of food and to reduce waste in schools.

  16. Geologic uncertainty in a regulatory environment: An example from the potential Yucca Mountain nuclear waste repository site

    NASA Astrophysics Data System (ADS)

    Rautman, C. A.; Treadway, A. H.

    1991-11-01

    Regulatory geologists are concerned with predicting the performance of sites proposed for waste disposal or for remediation of existing pollution problems. Geologic modeling of these sites requires large-scale expansion of knowledge obtained from very limited sampling. This expansion induces considerable uncertainty into the geologic models of rock properties that are required for modeling the predicted performance of the site. One method for assessing this uncertainty is through nonparametric geostatistical simulation. Simulation can produce a series of equiprobable models of a rock property of interest. Each model honors measured values at sampled locations, and each can be constructed to emulate both the univariate histogram and the spatial covariance structure of the measured data. Computing a performance model for a number of geologic simulations allows evaluation of the effects of geologic uncertainty. A site may be judged acceptable if the number of failures to meet a particular performance criterion produced by these computations is sufficiently low. A site that produces too many failures may be either unacceptable or simply inadequately described. The simulation approach to addressing geologic uncertainty is being applied to the potential high-level nuclear waste repository site at Yucca Mountain, Nevada, U.S.A. Preliminary geologic models of unsaturated permeability have been created that reproduce observed statistical properties reasonably well. A spread of unsaturated groundwater travel times has been computed that reflects the variability of those geologic models. Regions within the simulated models exhibiting the greatest variability among multiple runs are candidates for obtaining the greatest reduction in uncertainty through additional site characterization.

  17. 40 CFR 63.1595 - List of definitions.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... a POTW that accepts a waste stream regulated by an industrial NESHAP and provides treatment and...-containing waste stream to the POTW for treatment to comply with 40 CFR part 61, Subpart FF—National Emission... receive grant assistance under the Subchapter II of the Clean Water Act, and any federally owned treatment...

  18. Cost/Benefits of Solid Waste Reuse

    ERIC Educational Resources Information Center

    Schulz, Helmut W.

    1975-01-01

    Municipalities and industry are being forced to seek alternatives to sanitary landfills and incineration as means of eliminating solid wastes. Based on the Columbia study, the two most cost-effective, environmentally acceptable alternatives are the high temperature, oxygen-fed pyrolysis process and the co-combustion of refuse-derived fuel in…

  19. Choice of noxious facilities: case of a solid waste incinerator versus a sanitary landfill in Malaysia.

    PubMed

    Othman, Jamal; Khee, Pek Chuen

    2014-05-01

    A choice experiment analysis was conducted to estimate the preference for specific waste disposal technologies in Malaysia. The study found that there were no significant differences between the choice of a sanitary landfill or an incinerator. What matters is whether any disposal technology would lead to obvious social benefits. A waste disposal plan which is well linked or integrated with the community will ensure its acceptance. Local authorities will be challenged to identify solid waste disposal sites that are technically appropriate and also socially desirable.

  20. Assessment of public perception of radioactive waste management in Korea.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Trone, Janis R.; Cho, SeongKyung; Whang, Jooho

    2011-11-01

    The essential characteristics of the issue of radioactive waste management can be conceptualized as complex, with a variety of facets and uncertainty. These characteristics tend to cause people to perceive the issue of radioactive waste management as a 'risk'. This study was initiated in response to a desire to understand the perceptions of risk that the Korean public holds towards radioactive waste and the relevant policies and policy-making processes. The study further attempts to identify the factors influencing risk perceptions and the relationships between risk perception and social acceptance.

  1. Total chemical management in photographic processing

    USGS Publications Warehouse

    Luden, Charles; Schultz, Ronald

    1985-01-01

    The mission of the U. S. Geological Survey's Earth Resources Observation Systems (EROS) Data Center is to produce high-quality photographs of the earth taken from aircraft and Landsat satellite. In order to meet the criteria of producing research-quality photographs, while at the same time meeting strict environmental restrictions, a total photographic chemical management system was installed. This involved a three-part operation consisting of the design of a modern chemical analysis laboratory, the implementation of a chemical regeneration system, and the installation of a waste treatment system, including in-plant pretreatment and outside secondary waste treatment. Over the last ten years the result of this program has yielded high-quality photographs while saving approximately 30,000 per year and meeting all Environmental Protection Agency (EPA) restrictions.

  2. Excess Weapons Plutonium Disposition: Plutonium Packaging, Storage and Transportation and Waste Treatment, Storage and Disposal Activities

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Jardine, L J; Borisov, G B

    2004-07-21

    A fifth annual Excess Weapons Plutonium Disposition meeting organized by Lawrence Livermore National Laboratory (LLNL) was held February 16-18, 2004, at the State Education Center (SEC), 4 Aerodromnya Drive, St. Petersburg, Russia. The meeting discussed Excess Weapons Plutonium Disposition topics for which LLNL has the US Technical Lead Organization responsibilities. The technical areas discussed included Radioactive Waste Treatment, Storage, and Disposal, Plutonium Oxide and Plutonium Metal Packaging, Storage and Transportation and Spent Fuel Packaging, Storage and Transportation. The meeting was conducted with a conference format using technical presentations of papers with simultaneous translation into English and Russian. There were 46more » Russian attendees from 14 different Russian organizations and six non-Russian attendees, four from the US and two from France. Forty technical presentations were made. The meeting agenda is given in Appendix B and the attendance list is in Appendix C.« less

  3. Teaching Old Packaging New Tricks - 12593

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    England, Jeffery L.; Shuler, James M.

    2012-07-01

    Waste disposition campaigns have been an industry and government focus area since the mid- 1970's. With increased focus on this issue, and a lot of hard work, most waste packaging and transportation issues have been addressed. The material has been successfully shipped and dis-positioned. DOE has successfully de-inventoried materials from multiple sites to meet material consolidation, footprint reduction, nonproliferation, and regulatory obligations with cost savings from reduced maintenance and regulatory compliance. There has been a wide range of certified shipping packagings for the transportation of hazardous materials to meet most of the waste needs. The remaining materials are problematic, generallymore » low volume, and do not meet the certified content of the existing inventory of packaging. Designing, testing and certifying new packaging designs can be a long and expensive process and for small volumes of material it is cost prohibitive. One very cost effective option is to lease and use a certified packaging to overpack waste containers. There are many robust certified packagings available with the capability to envelope the waste content. The capability to use inner containers, inside the current fleet of certified casks or packaging, to address specific content problems of additional shielding (e.g., U-233) or containment (e.g., sodium bonded nuclear material) has successfully expanded the capability for timely cost effective shipment of unique contents. This option has been used successfully in the NAC-LWT, T-3 and other packagings. (authors)« less

  4. No-migration variance petition. Appendices A--B: Volume 2, Revision 1

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1990-03-01

    Volume II contains Appendix A, emergency plan and Appendix B, waste analysis plan. The Waste Isolation Pilot Plant (WIPP) Emergency plan and Procedures (WP 12-9, Rev. 5, 1989) provides an organized plan of action for dealing with emergencies at the WIPP. A contingency plan is included which is in compliance with 40 CFR Part 265, Subpart D. The waste analysis plan provides a description of the chemical and physical characteristics of the wastes to be emplaced in the WIPP underground facility. A detailed discussion of the WIPP Waste Acceptance Criteria and the rationale for its established units are also included.

  5. Landfill alternative offers powerful case.

    PubMed

    Baillie, Jonathan

    2011-04-01

    With many of Europe's landfill sites now close to capacity, and the EU Landfill Directive requiring that, by 2020, the amount of waste sent to landfill should be just 35% of the volume similarly disposed of in 1995, pressure is mounting to find environmentally acceptable waste disposal alternatives. At a recent IHEEM waste seminar, Gary Connelly, a technical consultant at environmental technology consultancy the Cameron Corporation, described a technology which he explained can effectively convert 85% of the European Waste Catalogue of materials into an inert residue, is "cleaner and cheaper" than incineration, and can generate both electricity an waste heat. As HEJ editor Jonathan Baillie reports, a key target market is healthcare facilities.

  6. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Moghissi, A.A.; Blauvelt, R.K.; Benda, G.A.

    This volume contains the peer-reviewed and edited versions of papers submitted for presentation a the Second International Mixed Waste Symposium. Following the tradition of the First International Mixed Waste Symposium, these proceedings were prepared in advance of the meeting for distribution to participants. The symposium was organized by the Mixed Waste Committee of the American Society of Mechanical Engineers. The topics discussed at the symposium include: stabilization technologies, alternative treatment technologies, regulatory issues, vitrification technologies, characterization of wastes, thermal technologies, laboratory and analytical issues, waste storage and disposal, organic treatment technologies, waste minimization, packaging and transportation, treatment of mercury contaminatedmore » wastes and bioprocessing, and environmental restoration. Individual abstracts are catalogued separately for the data base.« less

  7. 40 CFR 267.1101 - What design and operating standards must my containment building meet?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ...) Stresses of daily operation, including the movement of heavy equipment within the unit and contact of such... characteristics of the waste to be managed. (f) If appropriate to the nature of the waste management operation to...

  8. 40 CFR 267.1101 - What design and operating standards must my containment building meet?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ...) Stresses of daily operation, including the movement of heavy equipment within the unit and contact of such... characteristics of the waste to be managed. (f) If appropriate to the nature of the waste management operation to...

  9. 40 CFR 267.1101 - What design and operating standards must my containment building meet?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ...) Stresses of daily operation, including the movement of heavy equipment within the unit and contact of such... characteristics of the waste to be managed. (f) If appropriate to the nature of the waste management operation to...

  10. 40 CFR 267.1101 - What design and operating standards must my containment building meet?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ...) Stresses of daily operation, including the movement of heavy equipment within the unit and contact of such... characteristics of the waste to be managed. (f) If appropriate to the nature of the waste management operation to...

  11. 40 CFR 267.1101 - What design and operating standards must my containment building meet?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ...) Stresses of daily operation, including the movement of heavy equipment within the unit and contact of such... characteristics of the waste to be managed. (f) If appropriate to the nature of the waste management operation to...

  12. FIELD EXPERIENCE IN SAMPLING HAZARDOUS WASTE INCINERATORS

    EPA Science Inventory

    This paper is for presentation at the 77th annual meeting of the Air Pollution Control Association, June 24-29, 1984. The paper contains much useful, pragmatic information gained through numerous hazardous waste incinerator trial burn-type investigations performed for EPA by the ...

  13. Colloid formation during waste form reaction: Implications for nuclear waste disposal

    USGS Publications Warehouse

    Bates, J. K.; Bradley, J.; Teetsov, A.; Bradley, C. R.; Buchholtz ten Brink, Marilyn R.

    1992-01-01

    Insoluble plutonium- and americium-bearing colloidal particles formed during simulated weathering of a high-level nuclear waste glass. Nearly 100 percent of the total plutonium and americium in test ground water was concentrated in these submicrometer particles. These results indicate that models of actinide mobility and repository integrity, which assume complete solubility of actinides in ground water, underestimate the potential for radionuclide release into the environment. A colloid-trapping mechanism may be necessary for a waste repository to meet long-term performance specifications.

  14. 40 CFR Table 5 to Subpart Bbbb of... - Model Rule-Carbon Monoxide Emission Limits for Existing Small Municipal Waste Combustion Units

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... Limits for Existing Small Municipal Waste Combustion Units 5 Table 5 to Subpart BBBB of Part 60... Combustion Units Constructed on or Before August 30, 1999 Pt. 60, Subpt. BBBB, Table 5 Table 5 to Subpart... Combustion Units For the following municipal waste combustion units You must meet the following carbon...

  15. 40 CFR Table 5 to Subpart Bbbb of... - Model Rule-Carbon Monoxide Emission Limits for Existing Small Municipal Waste Combustion Units

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... Limits for Existing Small Municipal Waste Combustion Units 5 Table 5 to Subpart BBBB of Part 60... Combustion Units Constructed on or Before August 30, 1999 Pt. 60, Subpt. BBBB, Table 5 Table 5 to Subpart... Combustion Units For the following municipal waste combustion units You must meet the following carbon...

  16. 40 CFR Table 5 to Subpart Bbbb of... - Model Rule-Carbon Monoxide Emission Limits for Existing Small Municipal Waste Combustion Units

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... Limits for Existing Small Municipal Waste Combustion Units 5 Table 5 to Subpart BBBB of Part 60... Combustion Units Constructed on or Before August 30, 1999 Pt. 60, Subpt. BBBB, Table 5 Table 5 to Subpart... Combustion Units For the following municipal waste combustion units You must meet the following carbon...

  17. 40 CFR Table 5 to Subpart Bbbb of... - Model Rule-Carbon Monoxide Emission Limits for Existing Small Municipal Waste Combustion Units

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... Limits for Existing Small Municipal Waste Combustion Units 5 Table 5 to Subpart BBBB of Part 60... Combustion Units Constructed on or Before August 30, 1999 Pt. 60, Subpt. BBBB, Table 5 Table 5 to Subpart... Combustion Units For the following municipal waste combustion units You must meet the following carbon...

  18. 40 CFR Table 5 to Subpart Bbbb of... - Model Rule-Carbon Monoxide Emission Limits for Existing Small Municipal Waste Combustion Units

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... Limits for Existing Small Municipal Waste Combustion Units 5 Table 5 to Subpart BBBB of Part 60... Combustion Units Constructed on or Before August 30, 1999 Pt. 60, Subpt. BBBB, Table 5 Table 5 to Subpart... Combustion Units For the following municipal waste combustion units You must meet the following carbon...

  19. Distributed and dynamic modelling of hydrology, phosphorus and ecology in the Hampshire Avon and Blashford Lakes: evaluating alternative strategies to meet WFD standards.

    PubMed

    Whitehead, P G; Jin, L; Crossman, J; Comber, S; Johnes, P J; Daldorph, P; Flynn, N; Collins, A L; Butterfield, D; Mistry, R; Bardon, R; Pope, L; Willows, R

    2014-05-15

    The issues of diffuse and point source phosphorus (P) pollution in the Hampshire Avon and Blashford Lakes are explored using a catchment model of the river system. A multibranch, process based, dynamic water quality model (INCA-P) has been applied to the whole river system to simulate water fluxes, total phosphorus (TP) and soluble reactive phosphorus (SRP) concentrations and ecology. The model has been used to assess impacts of both agricultural runoff and point sources from waste water treatment plants (WWTPs) on water quality. The results show that agriculture contributes approximately 40% of the phosphorus load and point sources the other 60% of the load in this catchment. A set of scenarios have been investigated to assess the impacts of alternative phosphorus reduction strategies and it is shown that a combined strategy of agricultural phosphorus reduction through either fertiliser reductions or better phosphorus management together with improved treatment at WWTPs would reduce the SRP concentrations in the river to acceptable levels to meet the EU Water Framework Directive (WFD) requirements. A seasonal strategy for WWTP phosphorus reductions would achieve significant benefits at reduced cost. Copyright © 2014 Elsevier B.V. All rights reserved.

  20. Cast Stone Formulation for Nuclear Waste Immobilization at Higher Sodium Concentrations

    DOE PAGES

    Fox, Kevin; Cozzi, Alex; Roberts, Kimberly; ...

    2014-11-01

    Low activity radioactive waste at U.S. Department of Energy sites can be immobilized for permanent disposal using cementitious waste forms. This study evaluated waste forms produced with simulated wastes at concentrations up to twice that of currently operating processes. The simulated materials were evaluated for their fresh properties, which determine processability, and cured properties, which determine waste form performance. The results show potential for greatly reducing the volume of material. Fresh properties were sufficient to allow for processing via current practices. Cured properties such as compressive strength meet disposal requirements. Leachability indices provide an indication of expected long-term performance.

  1. Proficiency testing criteria for clearance level in solid waste gamma measurement in Taiwan.

    PubMed

    Chen, Chun-Liang; Wang, Jeng-Jong; Chiu, Huang-Sheng

    2013-11-01

    To guarantee the measurement quality for clearance level in solid waste material, the Institute of Nuclear Energy Research (INER) established the criteria for proficiency testing of clearance level measurement. INER and the Taiwan Accreditation Foundation (TAF) organized the Technique Committee Meeting twice to discuss these criteria in 2011. The participating laboratories must completely conform to the ISO/IEC 17025, and they also must meet the requirements of the criteria. According to the criteria, the participating laboratories analyzed the minimum detectable amount (MDA) and that should be less than 20% of the clearance level (AMDA) given in the Atomic Energy Council's (AEC) "Regulations on Clearance Level for Radioactive Waste Management". The testing results should conform to the deviation and traceability requirements. Copyright © 2013 Elsevier Ltd. All rights reserved.

  2. 21 CFR 820.80 - Receiving, in-process, and finished device acceptance.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 21 Food and Drugs 8 2011-04-01 2011-04-01 false Receiving, in-process, and finished device acceptance. 820.80 Section 820.80 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN... acceptance to ensure that each production run, lot, or batch of finished devices meets acceptance criteria...

  3. 21 CFR 820.80 - Receiving, in-process, and finished device acceptance.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Receiving, in-process, and finished device acceptance. 820.80 Section 820.80 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN... acceptance to ensure that each production run, lot, or batch of finished devices meets acceptance criteria...

  4. Considerations Related To Human Intrusion In The Context Of Disposal Of Radioactive Waste-The IAEA HIDRA Project

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Seitz, Roger; Kumano, Yumiko; Bailey, Lucy

    2014-01-09

    The principal approaches for management of radioactive waste are commonly termed ‘delay and decay’, ‘concentrate and contain’ and ‘dilute and disperse’. Containing the waste and isolating it from the human environment, by burying it, is considered to increase safety and is generally accepted as the preferred approach for managing radioactive waste. However, this approach results in concentrated sources of radioactive waste contained in one location, which can pose hazards should the facility be disrupted by human action in the future. The International Commission on Radiological Protection (ICRP), International Atomic Energy Agency (IAEA), and Organization for Economic Cooperation and Development/Nuclear Energymore » Agency (OECD/NEA) agree that some form of inadvertent human intrusion (HI) needs to be considered to address the potential consequences in the case of loss of institutional control and loss of memory of the disposal facility. Requirements are reflected in national regulations governing radioactive waste disposal. However, in practice, these requirements are often different from country to country, which is then reflected in the actual implementation of HI as part of a safety case. The IAEA project on HI in the context of Disposal of RadioActive waste (HIDRA) has been started to identify potential areas for improved consistency in consideration of HI. The expected outcome is to provide recommendations on how to address human actions in the safety case in the future, and how the safety case may be used to demonstrate robustness and optimize siting, design and waste acceptance criteria within the context of a safety case.« less

  5. Sorbent Scoping Studies

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Chancellor, Christopher John

    2016-11-14

    The Los Alamos National Laboratory–Carlsbad Operations (LANL-CO) office was tasked by the DOE CBFO, Office of the Manager to perform a review of the acceptable knowledge (AK) to identify the oxidizers and sorbents in transuranic (TRU) waste streams, to conduct scoping studies on the oxidizers and sorbents identified in AK review to inform the Quality Level 1 (QL1) testing, and to conduct a series of QL1 tests to provide the scientific data to support a basis of knowledge document for determining the criteria for (1) accepting waste at the Waste Isolation Pilot Plant (WIPP) without treatment, (2) determining waste thatmore » will require treatment, and (3) if treatment is required, how the treatment must be performed. The purpose of this report is to present the results of the AK review of sorbents present in active waste streams, provide a technical analysis of the sorbent list, report the results of the scoping studies for the fastest-burning organic sorbent, and provide the list of organic and inorganic sorbents to be used in the development of a Test Plan for Preparation and Testing of Sorbents Mixed with Oxidizer found in Transuranic Waste (DWT-TP-001). The companion report, DWT-RPT-001, Oxidizer Scoping Studies, has similar information for oxidizers identified during the AK review of TRU waste streams. The results of the oxidizer and sorbent scoping studies will be used to inform the QL1 test plan. The QL1 test results will support the development of a basis of knowledge document that will evaluate oxidizing chemicals and sorbents in TRU waste and provide guidance for treatment.« less

  6. Sustainable waste management in the UK: the public health role.

    PubMed

    Mohan, R; Spiby, J; Leonardi, G S; Robins, A; Jefferis, S

    2006-10-01

    This paper discusses waste management in the UK and its relationship with health. It aims to outline the role of health professionals in the promotion of waste management, and argues for a change in their role in waste management regulation to help make the process more sustainable. The most common definition of sustainable development is that by the Brundtland commission, i.e. "development that meets the needs of the present without compromising the ability of future generations to meet their own needs". Managing waste sites in a manner that minimises toxic impacts on the current and future generations is obviously a crucial part of this. Although the management of waste facilities is extremely complex, the Integrated Pollution Prevention and Control regime, which requires the input of public health professionals on the regulation of such sites, means that all waste management installations should now be operating in a fashion that minimises any toxicological risks to human health. However, the impacts upon climate change, resource use and health inequalities, as well as the effects of waste transportation, are currently not considered to be part of public health professionals' responsibilities when dealing with these sites. There is also no requirement for public health professionals to become involved in waste management planning issues. The fact that public health professionals are not involved in any of these issues makes it unlikely that the potential impacts upon health are being considered fully, and even more unlikely that waste management will become more sustainable. This paper aims to show that by only considering direct toxicological impacts, public health professionals are not fully addressing all the health issues and are not contributing towards sustainability. There is a need for a change in the way that health professionals deal with waste management issues.

  7. Radiological Characterization Technical Report on Californium-252 Sealed Source Transuranic Debris Waste for the Off-Site Source Recovery Project at Los Alamos National Laboratory

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Feldman, Alexander

    2014-04-24

    This document describes the development and approach for the radiological characterization of Cf-252 sealed sources for shipment to the Waste Isolation Pilot Plant. The report combines information on the nuclear material content of each individual source (mass or activity and date of manufacture) with information and data on the radionuclide distributions within the originating nuclear material. This approach allows for complete and accurate characterization of the waste container without the need to take additional measurements. The radionuclide uncertainties, developed from acceptable knowledge (AK) information regarding the source material, are applied to the summed activities in the drum. The AK informationmore » used in the characterization of Cf-252 sealed sources has been qualified by the peer review process, which has been reviewed and accepted by the Environmental Protection Agency.« less

  8. Evaluation of Subsurface Engineered Barriers at Waste Sites

    DTIC Science & Technology

    1998-08-01

    28 3-4 MATRIX FOR EVALUATING BARRIER CQA/CQC AGAINST ACCEPTABLE INDSUTRY PRACTICES...STANDARDS................................................................. 66 4-2 MATRIX FOR EVALUATING CAP AGAINST ACCEPTABLE INDSUTRY PRACTICES...stated previously, the most widely used technique for containment is the soil-bentonite slurry wall. It is typically the most economical , utilizes low

  9. 40 CFR 62.15260 - What other requirements must I meet for continuous monitoring?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 40 Protection of Environment 8 2011-07-01 2011-07-01 false What other requirements must I meet for... August 30, 1999 Other Monitoring Requirements § 62.15260 What other requirements must I meet for... waste combustion unit. (b) Temperature of flue gases at the inlet of your particulate matter air...

  10. 76 FR 1472 - Agenda and Notice Meeting of the Recovery Independent Advisory Panel

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-10

    .... SUMMARY: In accordance with the American Recovery and Reinvestment Act of 2009, Public Law 111-5 (Recovery... notify the general public of their opportunity to attend the meeting. DATES: The RIAP meeting will be... dialogue, with input from the public, on issues relating to fraud, waste, and abuse of Recovery Act funds...

  11. Comparison between students and residents on determinants of willingness to separate waste and waste separation behaviour in Zhengzhou, China.

    PubMed

    Dai, Xiaoping; Han, Yuping; Zhang, Xiaohong; Hu, Wei; Huang, Liangji; Duan, Wenpei; Li, Siyi; Liu, Xiaolu; Wang, Qian

    2017-09-01

    A better understanding of willingness to separate waste and waste separation behaviour can aid the design and improvement of waste management policies. Based on the intercept questionnaire survey data of undergraduate students and residents in Zhengzhou City of China, this article compared factors affecting the willingness and behaviour of students and residents to participate in waste separation using two binary logistic regression models. Improvement opportunities for waste separation were also discussed. Binary logistic regression results indicate that knowledge of and attitude to waste separation and acceptance of waste education significantly affect the willingness of undergraduate students to separate waste, and demographic factors, such as gender, age, education level, and income, significantly affect the willingness of residents to do so. Presence of waste-specific bins and attitude to waste separation are drivers of waste separation behaviour for both students and residents. Improved education about waste separation and facilities are effective to stimulate waste separation, and charging on unsorted waste may be an effective way to improve it in Zhengzhou.

  12. Examining the Association between Hazardous Waste Facilities and Rural "Brain Drain"

    ERIC Educational Resources Information Center

    Hunter, Lori M.; Sutton, Jeannette

    2004-01-01

    Rural communities are increasingly being faced with the prospect of accepting facilities characterized as "opportunity-threat," such as facilities that generate, treat, store, or otherwise dispose of hazardous wastes. Such facilities may offer economic gains through jobs and tax revenue, although they may also act as environmental "disamenities."…

  13. 40 CFR 761.218 - Certificate of disposal.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... PROHIBITIONS PCB Waste Disposal Records and Reports § 761.218 Certificate of disposal. (a) For each shipment of manifested PCB waste that the owner or operator of a disposal facility accepts by signing the manifest, the owner or operator of the disposal facility shall prepare a Certificate of Disposal for the PCBs and PCB...

  14. IMPACT OF DECISION-MAKING STRATEGIES AND COMMUNICATION PROCESSES ON THE PUBLIC ACCEPTABILITY OF MUNICIPAL WASTE COMBUSTION RESIDUE UTILIZATION IN THE UNITED STATES

    EPA Science Inventory

    Of the identified current and proposed construction projects in which municipal solid waste combustion residues replace traditionally used materials, approximately half are located on landfills or other property controlled by project sponsors, one third are in publicly accessible...

  15. Factors affecting hazardous waste solidification/stabilization: a review.

    PubMed

    Malviya, Rachana; Chaudhary, Rubina

    2006-09-01

    Solidification/stabilization is accepted as a well-established disposal technique for hazardous waste. As a result many different types of hazardous wastes are treated with different binders. The S/S products have different property from waste and binders individually. The effectiveness of S/S process is studied by physical, chemical and microstructural methods. This paper summarizes the effect of different waste stream such as heavy metals bearing sludge, filter cake, fly ash, and slag on the properties of cement and other binders. The factors affecting strength development is studied using mix designs, including metal bearing waste alters the hydration and setting time of binders. Pore structure depends on relative quantity of the constituents, cement hydration products and their reaction products with admixtures. Carbonation and additives can lead to strength improvement in waste-binder matrix.

  16. Improvement of nuclide leaching resistance of paraffin waste form with low density polyethylene.

    PubMed

    Kim, Chang Lak; Park, Joo Wan; Kim, Ju Youl; Chung, Chang Hyun

    2002-01-01

    Low-level liquid borate wastes have been immobilized with paraffin wax using a concentrate waste drying system (CWDS) in Korean nuclear power plants. The possibility for improving chemical durability of paraffin waste form was suggested in this study. A small amount of low density polyethylene (LDPE) was added to increase the leaching resistance of the existing paraffin waste form. The influence of LDPE on the leaching behavior of waste form was investigated by performing leaching test according to ANSI/ANS-16.1 procedure during 325 days. It was observed that the leaching of nuclides immobilized within paraffin waste form made a marked reduction although little content of LDPE was added to waste form. The acceptance criteria of paraffin waste form associated with leachability index (LI) and compressive strength after the leaching test were fully satisfied with the help of LDPE.

  17. Waste-Heat-to-Power Market in the U.S., Heat is Power Annual Meeting (Presentation) – August 15, 2012

    EPA Pesticide Factsheets

    This presentation provides information about the EPA CHP Partnership, including an overview of the Partnership's tools and resources, and policy support. The presentation also describes the potential of Waste Heat to Power (WHP) systems.

  18. 77 FR 8926 - Board Meeting: March 7, 2012-Albuquerque, NM; The U.S. Nuclear Waste Technical Review Board Will...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-02-15

    ... Repository Geologies Pursuant to its authority under section 5051 of Public Law 100-203, the Nuclear Waste... repository. A representative of the U.S. Geological Survey (USGS) will provide a USGS perspective on this...

  19. OVERVIEW OF THE MINE WASTE TECHNOLOGY PROGRAM; INTERAGENCY COORDINATION MEETING ON MINING

    EPA Science Inventory

    The Mine Waste Technology Program is a Congressionally-mandated research program jointly administered by the EPA Office of Research and Development (for technical direction) and by the DoE Western Environmental Technology Office (administrative direction). The goal of the resear...

  20. BIOREMEDIATION OF HAZARDOUS WASTES - RESEARCH, DEVELOPMENT, AND FIELD EVALUATIONS - 1994

    EPA Science Inventory

    The proceedings of the 1994 Symposium on Bioremediation of Hazardous Wastes, hosted by the Office of Research and Development (ORD) of the EPA in San Francisco, California. The symposium was the seventh annual meeting for the presentation of research conducted by EPA's Biosystem...

  1. 78 FR 49737 - Environmental Management Site-Specific Advisory Board, Northern New Mexico

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-15

    ... meeting of the Environmental Monitoring and Remediation Committee, Waste Management Committee, and Waste... activities. Purpose of the Environmental Monitoring and Remediation Committee (EM&R): The EM&R Committee provides a citizens' perspective to NNMCAB on current and future environmental remediation activities...

  2. 78 FR 44941 - Environmental Management Site-Specific Advisory Board, Northern New Mexico

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-25

    ... meeting of the Environmental Monitoring and Remediation Committee, Waste Management Committee, and Waste... related activities. Purpose of the Environmental Monitoring and Remediation Committee (EM&R): The EM&R Committee provides a citizens' perspective to NNMCAB on current and future environmental remediation...

  3. 78 FR 37536 - Environmental Management Site-Specific Advisory Board, Northern New Mexico

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-21

    ... meeting of the Environmental Monitoring and Remediation Committee, Waste Management Committee, and Waste... activities. Purpose of the Environmental Monitoring and Remediation Committee (EM&R): The EM&R Committee provides a citizens' perspective to NNMCAB on current and future environmental remediation activities...

  4. 78 FR 58293 - Environmental Management Site-Specific Advisory Board, Northern New Mexico

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-23

    ... meeting of the Environmental Monitoring and Remediation Committee, Waste Management Committee, and Waste... activities. Purpose of the Environmental Monitoring and Remediation Committee (EM&R): The EM&R Committee provides a citizens' perspective to NNMCAB on current and future environmental remediation activities...

  5. Benefits, Harms, and Costs of Osteoporosis Screening in Male Veterans

    DTIC Science & Technology

    2015-10-01

    K Lyles, J LaFleur, C VanHoutven, C Pieper – accepted to American Geriatrics Society Annual Meeting, May 2016 Background: Practice guidelines...Veterans. Rasheeda K. Hall, Richard Sloane, Carl Pieper, Cathleen Colón-Emeric. – accepted to American Geriatrics Society Annual Meeting, May 2016...who had no prior diagnoses of fracture or osteoporosis therapy . Estimated glomerular filtration rate (eGFR) was estimated using baseline creatinine

  6. Environmental restoration and waste management: Five-year plan, Fiscal Years 1992--1996

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Middleman, L.I.

    1990-06-01

    This document reflects DOE's fulfillment of a major commitment of the Environmental Restoration and Waste Management Five-Year Plan: reorganization to create an Office of Environmental Restoration and Waste Management (EM) responsible for the consolidated environmental management of nuclear-related facilities and sites formerly under the Assistant Secretaries for Defense Programs and Nuclear Energy and the Director of the Office of Energy Research. The purposes of this Plan for FY 1992--1996 are to measure progress in meeting DOE's compliance, cleanup, and waste management agenda; to incorporate a revised and condensed version of the Draft Research Development, Demonstration, Testing, and Evaluation (RDDT E)more » Plan (November 1989) to describe DOE's process for developing the new technologies critically needed to solve its environmental problems; to show DOE's current strategy and planned activities through FY 1996, including reasons for changes required to meet compliance and cleanup commitments; and to increase the involvement of other agencies and the public in DOE's planning.« less

  7. 7 CFR 1493.290 - Proof of entry.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... AGRICULTURE EXPORT PROGRAMS CCC EXPORT CREDIT GUARANTEE PROGRAMS CCC Facility Guarantee Program (FGP... certified or other translation acceptable to CCC. Records acceptable to meet this requirement include: (1... documentation deemed acceptable by CCC: (i) Showing that the goods entered the emerging market; (ii) Identifying...

  8. 7 CFR 1493.290 - Proof of entry.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... AGRICULTURE EXPORT PROGRAMS CCC EXPORT CREDIT GUARANTEE PROGRAMS CCC Facility Guarantee Program (FGP... certified or other translation acceptable to CCC. Records acceptable to meet this requirement include: (1... documentation deemed acceptable by CCC: (i) Showing that the goods entered the emerging market; (ii) Identifying...

  9. 7 CFR 1493.290 - Proof of entry.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... AGRICULTURE EXPORT PROGRAMS CCC EXPORT CREDIT GUARANTEE PROGRAMS CCC Facility Guarantee Program (FGP... certified or other translation acceptable to CCC. Records acceptable to meet this requirement include: (1... documentation deemed acceptable by CCC: (i) Showing that the goods entered the emerging market; (ii) Identifying...

  10. Higher acceptance rates for abstracts written in English at a national research student meeting in a non-English speaking country.

    PubMed

    Khani, Afshin; Zarghami, Amin; Izadpanah, Fatemeh; Mahdizadeh, Hamid; Golestanifar, Leila

    2015-01-01

    The rate of English-written submissions is increasing in local meetings of non-English speaking countries. However, it seems that the quality of research and methodology of the studies has not progressed. This study aimed to evaluate the association of English writing and the acceptance for presentation following the peer-review process in the 13th Annual Research Congress of Iran's Medical Sciences Students (ARCIMSS). All 1817 complete abstracts submitted to the meeting were included in this cross-sectional study. Each was evaluated for the language of the text (English or Persian), final decision after peer review (accepted vs. rejected), presentation type (oral, poster discussion and poster) and the scores of reviewing process. There were 395 (21.7%) abstracts written in English and 1422 (78.3%) in Persian. The acceptance rate for English abstracts was 33.7% and for Persian 24.6% (OR = 1.56, 95% CI: 1.22-1.98). The rate of abstracts' acceptance for presentation in oral panels was significantly higher for English abstracts than for those in Persian (25.6% versus 15.7%, OR = 1.84, 95% CI: 1.14-2.99). By contrast, Persian abstracts were more likely to be accepted as poster panels than were English abstracts (74.9% versus 63.9%, OR = 1.68, 95% CI: 1.10-2.58). English-written abstracts have higher chance of acceptation in a non-English speaker country like Iran.

  11. Waste Isolation Safety Assessment Program. Task 4. Third Contractor Information Meeting. [Adsorption-desorption on geological media

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1980-06-01

    The study subject of this meeting was the adsorption and desorption of radionuclides on geologic media under repository conditions. This volume contans eight papers. Separate abstracts were prepared for all eight papers. (DLC)

  12. OVERVIEW OF THE EPA/DOE MINE WASTE TECHNOLOGY PROGRAM

    EPA Science Inventory

    This meeting was held at the Hilton Cincinnati Netherland plaza in Cincinnati, OH. The purpose of thie meeting was to discuss current Hazardous Substance Research Center and USEPA/ ORD superfund research, identify research needs, and foster collaborative efforts. The presentatio...

  13. 7 CFR 1493.490 - Proof of entry.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... AGRICULTURE EXPORT PROGRAMS CCC EXPORT CREDIT GUARANTEE PROGRAMS CCC Supplier Credit Guarantee Program... translation acceptable to CCC. Records acceptable to meet this requirement include an original certification...

  14. 7 CFR 1493.490 - Proof of entry.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... AGRICULTURE EXPORT PROGRAMS CCC EXPORT CREDIT GUARANTEE PROGRAMS CCC Supplier Credit Guarantee Program... translation acceptable to CCC. Records acceptable to meet this requirement include an original certification...

  15. 7 CFR 1493.490 - Proof of entry.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... AGRICULTURE EXPORT PROGRAMS CCC EXPORT CREDIT GUARANTEE PROGRAMS CCC Supplier Credit Guarantee Program... translation acceptable to CCC. Records acceptable to meet this requirement include an original certification...

  16. Site Selection for the Disposal of LLW in Taiwan

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Chuang, W.S.; Chi, L.M.; Tien, N.C.

    2006-07-01

    This paper presents the implementation status of the low-level radioactive waste (LLW) disposal program in Taiwan, including the disposal facility regulations, status of waste management, final disposal program, licensing procedures, waste acceptance criteria, site selection criteria and processes and preliminary disposal concepts. The first phase of site selection for low-level radioactive waste final disposal in Taiwan was implemented between 1992 and 2002. The site selection process adopted a Geographic Information System (GIS), Hierarchical Analysis System, Expert Evaluation System, and site reconnaissance. An incentive program for voluntary sites was also initiated. After a series of evaluations and discussion of 30 potentialmore » candidate sites, including 8 recommended sites, 5 qualified voluntary townships, and several remote uninhabited small islets, Hsiao-chiou islet was selected as the first priority candidate site in February 1998. The geological investigation work in Hsiao-chiou was conducted from March 1999 through October 2000. An Environmental Impact Statement Report (EIS) and the Investment Feasibility Study Report (IFS) were submitted to the Environmental Protection Agency (EPA) in November 2000 and to the Ministry of Economic Affairs (MOEA) in June 2001, respectively. Unfortunately, the site investigation was discontinued in 2002 due to political and public acceptance consideration. After years of planning, the second phase of the site selection process was launched in August 2004 and will be conducted through 2008. It is planned that a repository will be constructed in early 2009 and start to operate in 2014. The site selection process for the second phase is based on the earlier work and four potential candidate sites were selected for evaluation until 2005. A near surface disposal concept is proposed for a site located in the Taiwan strait, and cavern disposal concepts are proposed for three other sites located on the main island. This paper presents the implementation status of the LLW disposal program in Taiwan, including the disposal facility regulations, status of waste management, final disposal program, licensing procedures, waste acceptance criteria, site selection criteria and processes, and preliminary disposal concepts 'NIMBY' (Not in my backyard) is a critical problem for implementation of the final disposal project. Resistance from local communities has been continuously received during site characterization. To overcome this, an incentive program to encourage community acceptance has been approved by the Government. Programs for community promotion are being proposed and negotiations are also underway. (authors)« less

  17. Techno-economic evaluation of a tandem dry batch, garage-style digestion-compost process for remote work camp environments.

    PubMed

    Hayes, Alexander C; Enongene Ekwe, S; Mervin, Steve; Jenson, Earl

    2016-12-01

    The extraction of natural resources often involves housing workers in remote work camps far from population centres. These camps are prevalent in northern Alberta where they house approximately 40,000 workers involved in oil sands processing. The central, full-service cafeterias at these camps produce a significant quantity of food and cardboard waste. Due to their remote nature, these camps face high waste disposal costs associated with trucking waste long distances to the landfill. In this study, we investigated the techno-economic feasibility of on-site treatment of food and cardboard waste in a tandem dry batch, garage-style anaerobic digestion-compost process in which the waste material is converted into renewable energy used to heat the camp water supply and a nutrient-rich soil amendment for local land reclamation projects. Dry batch digestion and windrow composting pilot trials were performed on a simulated work camp waste in order to assess technical performance. The quality of the final compost was found to meet regulatory standards. A complete mass balance was then developed for a facility treating 3000 tonnes food waste and 435 tonnes waste cardboard annually. An economic assessment of such a facility was performed and, depending on the level of capital support and recognition of carbon credits for landfill methane mitigation, would require waste disposal costs to be between $115 and $195 CAD per tonne to meet financial criteria for project selection in Alberta's oil and gas industry. Copyright © 2016 Elsevier Ltd. All rights reserved.

  18. Results For The Fourth Quarter 2014 Tank 50 WAC Slurry Sample: Chemical And Radionuclide Contaminants

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Crawford, C.

    2015-09-30

    This report details the chemical and radionuclide contaminant results for the characterization of the Calendar Year (CY) 2014 Fourth Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC) in effect at that time. Information from this characterization will be used by DWPF & Saltstone Facility Engineering (DSFE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System.

  19. RH-TRU Waste Inventory Characterization by AK and Proposed WIPP RH-TRU Waste Characterization Objectives

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Most, W. A.; Kehrman, R.; Gist, C.

    2002-02-26

    The U.S. Department of Energy (DOE)-Carlsbad Field Office (CBFO) has developed draft documentation to present the proposed Waste Isolation Pilot Plant (WIPP) remote-handled (RH-) transuranic (TRU) waste characterization program to its regulators, the U.S. Environmental Protection Agency and the New Mexico Environment Department. Compliance with Title 40, Code of Federal Regulations, Parts 191 and 194; the WIPP Land Withdrawal Act (PL 102-579); and the WIPP Hazardous Waste Facility Permit, as well as the Certificates of Compliance for the 72-B and 10-160B Casks, requires that specific waste parameter limits be imposed on DOE sites disposing of TRU waste at WIPP. Themore » DOE-CBFO must control the sites' compliance with the limits by specifying allowable characterization methods. As with the established WIPP contact handled TRU waste characterization program, the DOE-CBFO has proposed a Remote-Handled TRU Waste Acceptance Criteria (RH-WAC) document consolidating the requirements from various regulatory drivers and proposed allowable characterization methods. These criteria are consistent with the recommendation of a recent National Academy Sciences/National Research Council to develop an RH-TRU waste characterization approach that removes current self imposed requirements that lack a legal or safety basis. As proposed in the draft RH-WAC and other preliminary documents, the DOE-CBFO RH-TRU waste characterization program proposes the use of acceptable knowledge (AK) as the primary method for obtaining required characterization information. The use of AK involves applying knowledge of the waste in light of the materials or processes used to generate the waste. Documentation, records, or processes providing information about various attributes of a waste stream, such as chemical, physical, and radiological properties, may be used as AK and may be applied to individual waste containers either independently or in conjunction with radiography, visual examination, assay, and other sampling and analytical data. RH-TRU waste cannot be shipped to WIPP on the basis of AK alone if documentation demonstrating that all of the prescribed limits in the RH-WAC are met is not available, discrepancies exist among AK source documents describing the same waste stream and the most conservative assumptions regarding those documents indicates that a limit will not be met, or all required data are not available for a given waste stream.« less

  20. Development of an Integrated Waste Plan for Chalk River Laboratories - 13376

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Jones, L.

    2013-07-01

    To further its Strategic Planning, the Atomic Energy of Canada Limited (AECL) required an effective approach to developing a fully integrated waste plan for its Chalk River Laboratories (CRL) site. Production of the first Integrated Waste Plan (IWP) for Chalk River was a substantial task involving representatives from each of the major internal stakeholders. Since then, a second revision has been produced and a third is underway. The IWP remains an Interim IWP until all gaps have been resolved and all pathways are at an acceptable level of detail. Full completion will involve a number of iterations, typically annually formore » up to six years. The end result of completing this process is a comprehensive document and supporting information that includes: - An Integrated Waste Plan document summarizing the entire waste management picture in one place; - Details of all the wastes required to be managed, including volume and timings by waste stream; - Detailed waste stream pathway maps for the whole life-cycle for each waste stream to be managed from pre-generation planning through to final disposition; and - Critical decision points, i.e. decisions that need to be made and timings by when they need to be made. A waste inventory has been constructed that serves as the master reference inventory of all waste that has been or is committed to be managed at CRL. In the past, only the waste that is in storage has been effectively captured, and future predictions of wastes requiring to be managed were not available in one place. The IWP has also provided a detailed baseline plan at the current level of refinement. Waste flow maps for all identified waste streams, for the full waste life cycle complete to disposition have been constructed. The maps identify areas requiring further development, and show the complexities and inter-relationships between waste streams. Knowledge of these inter-dependencies is necessary in order to perform effective options studies for enabling facilities that may be necessary for multiple related waste streams. The next step is to engage external stakeholders in the optioneering work required to provide enhanced confidence that the path forward identified within future iterations of the IWP will be acceptable to all. (authors)« less

  1. BIOREMEDIATION OF HAZARDOUS WASTES - RESEARCH, DEVELOPMENT, AND FIELD EVALUATIONS - 1993

    EPA Science Inventory

    The proceedings of the 1993 Symposium on Bioremediation of Hazardous Wastes, hosted by the Office of Research and Development (ORD) of the EPA in Dallas, Texas The symposium was the sixth annual meeting for the presentation of research conducts (by EPA's Biosystems Technology Dev...

  2. Municipal Solid Waste Landfills and Wood Pallets - What's Happening in the United States

    Treesearch

    Philip A. Araman; Robert J. Bush; Vijay S. Reddy

    1997-01-01

    This article on pallet disposal and Municipal Solid Waste sites includes material presented by Dr. Bush at the recent NWPCA Recycling Meeting. This is the first in a two-part series; the second discusses pallet disposal in construction and demolition sites.

  3. BIOREMEDIATION OF HAZARDOUS WASTES - RESEARCH, DEVELOPMENT AND FIELD EVALUATIONS - 1995

    EPA Science Inventory

    The proceedings of the 1995 Symposium on Bioremediation of Hazardous Wastes, hosted by the Office of Research and Development (ORD) of the EPA in Rye Brook, New York. he symposium was the eighth annual meeting for the presentation of research conducted by EPA's Biosystems Technol...

  4. 40 CFR 600.007-08 - Vehicle acceptability.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 40 Protection of Environment 30 2011-07-01 2011-07-01 false Vehicle acceptability. 600.007-08... FUEL ECONOMY AND CARBON-RELATED EXHAUST EMISSIONS OF MOTOR VEHICLES Fuel Economy and Carbon-Related... Vehicle acceptability. (a) All certification vehicles and other vehicles tested to meet the requirements...

  5. 40 CFR 600.007-80 - Vehicle acceptability.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 40 Protection of Environment 30 2011-07-01 2011-07-01 false Vehicle acceptability. 600.007-80... FUEL ECONOMY AND CARBON-RELATED EXHAUST EMISSIONS OF MOTOR VEHICLES Fuel Economy and Carbon-Related... Vehicle acceptability. (a) All certification vehicles and other vehicles tested to meet the requirements...

  6. 7 CFR 1493.290 - Proof of entry.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... AGRICULTURE LOANS, PURCHASES, AND OTHER OPERATIONS CCC EXPORT CREDIT GUARANTEE PROGRAMS CCC Facility Guarantee... accompanied by a certified or other translation acceptable to CCC. Records acceptable to meet this requirement... documentation deemed acceptable by CCC: (i) Showing that the goods entered the emerging market; (ii) Identifying...

  7. 7 CFR 1493.290 - Proof of entry.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... AGRICULTURE LOANS, PURCHASES, AND OTHER OPERATIONS CCC EXPORT CREDIT GUARANTEE PROGRAMS CCC Facility Guarantee... accompanied by a certified or other translation acceptable to CCC. Records acceptable to meet this requirement... documentation deemed acceptable by CCC: (i) Showing that the goods entered the emerging market; (ii) Identifying...

  8. The Integrated Waste Tracking System - A Flexible Waste Management Tool

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Anderson, Robert Stephen

    2001-02-01

    The US Department of Energy (DOE) Idaho National Engineering and Environmental Laboratory (INEEL) has fully embraced a flexible, computer-based tool to help increase waste management efficiency and integrate multiple operational functions from waste generation through waste disposition while reducing cost. The Integrated Waste Tracking System (IWTS)provides comprehensive information management for containerized waste during generation,storage, treatment, transport, and disposal. The IWTS provides all information necessary for facilities to properly manage and demonstrate regulatory compliance. As a platformindependent, client-server and Web-based inventory and compliance system, the IWTS has proven to be a successful tracking, characterization, compliance, and reporting tool that meets themore » needs of both operations and management while providing a high level of management flexibility.« less

  9. 7 CFR 1493.490 - Proof of entry.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... AGRICULTURE LOANS, PURCHASES, AND OTHER OPERATIONS CCC EXPORT CREDIT GUARANTEE PROGRAMS CCC Supplier Credit... translation acceptable to CCC. Records acceptable to meet this requirement include an original certification...

  10. 7 CFR 1493.490 - Proof of entry.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... AGRICULTURE LOANS, PURCHASES, AND OTHER OPERATIONS CCC EXPORT CREDIT GUARANTEE PROGRAMS CCC Supplier Credit... translation acceptable to CCC. Records acceptable to meet this requirement include an original certification...

  11. Screening and Spectral Summing of LANL Empty Waste Drums - 13226

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Gruetzmacher, Kathleen M.; Bustos, Roland M.; Ferran, Scott G.

    2013-07-01

    Empty 55-gallon drums that formerly held transuranic (TRU) waste (often over-packed in 85- gallon drums) are generated at LANL and require radiological characterization for disposition. These drums are typically measured and analyzed individually using high purity germanium (HPGe) gamma detectors. This approach can be resource and time intensive. For a project requiring several hundred drums to be characterized in a short time frame, an alternative approach was developed. The approach utilizes a combination of field screening and spectral summing that was required to be technically defensible and meet the Nevada Nuclear Security Site (NNSS) Waste Acceptance Criteria (WAC). In themore » screening phase of the operation, the drums were counted for 300 seconds (compared to 600 seconds for the typical approach) and checked against Low Level (LL)/TRU thresholds established for each drum configuration and detector. Multiple TRU nuclides and multiple gamma rays for each nuclide were evaluated using an automated spreadsheet utility that can process data from up to 42 drums at a time. Screening results were reviewed by an expert analyst to confirm the field LL/TRU determination. The spectral summing analysis technique combines spectral data (channel-by-channel) associated with a group of individual waste containers producing a composite spectrum. The grouped drums must meet specific similarity criteria. Another automated spreadsheet utility was used to spectral sum data from an unlimited number of similar drums grouped together. The composite spectrum represents a virtual combined drum for the group of drums and was analyzed using the SNAP{sup TM}/Radioassay Data Sheet (RDS)/Batch Data Report (BDR) method. The activity results for a composite virtual drum were divided equally amongst the individual drums to generate characterization results for each individual drum in the group. An initial batch of approximately 500 drums were measured and analyzed in less than 2 months in 2011. A second batch of approximately 500 more drums were measured and analyzed during the following 2 1/2 months. Four different HPGe detectors were employed for the operation. The screening and spectral summing approach can reduce the overall measurement and analysis time required. However, developing the technical details and automation spreadsheets requires a significant amount of expert time prior to beginning field operations and must be considered in the overall project schedule. This approach has continued to be used for characterizing several hundred more empty drums in 2012 and is planned to continue in 2013. (authors)« less

  12. Life sciences and space research XXIII(3): Natural and artificial ecosystems; Proceedings of the Topical Meetings of the 27th COSPAR Plenary Meeting, Espoo, Finland, July 18-29, 1988

    NASA Technical Reports Server (NTRS)

    Macelroy, R. D. (Editor); Tibbitts, T. W. (Editor); Thompson, B. G. (Editor); Volk, T. (Editor)

    1989-01-01

    The present conference discusses topics in the fields of higher plant growth under controlled environmental conditions, waste oxidation, carbon cycling, and biofermentor design and operation. Attention is given to CO2 and O2 effects on the development and fructification of wheat in closed systems, transpiration during life cycle in controlled wheat growth, sources and processing of CELSS wastes, waste-recycling in bioregenerative life support, and the effect of iodine disinfection products on higher plants. Also discussed are carbon cycling by cellulose-fermenting nitrogen-fixing bacteria, a bioreactor design with sunlight supply and operations systems for use in the space environment, gas bubble coalescence in reduced gravity conditions, and model system studies of a phase-separated membrane bioreactor.

  13. Options for management of municipal solid waste in New York City: A preliminary comparison of health risks and policy implications

    PubMed Central

    Moy, Pearl; Krishnan, Nikhil; Ulloa, Priscilla; Cohen, Steven; Brandt-Rauf, Paul W.

    2008-01-01

    Landfill disposal and waste-to-energy (WTE) incineration remain the two principal options for managing municipal solid waste (MSW). One critical determinant of the acceptability of these options is the different health risks associated with each. In this analysis relying on published data and exposure modeling, we have performed health risk assessments for landfill disposal versus WTE treatment options for the management of New York City’s MSW. These are based on the realistic scenario of using a waste transfer station (WTS) in Brooklyn and then transporting the untreated MSW by truck to a landfill in Pennsylvania or using a WTE facility in Brooklyn and then transporting the resultant ash by truck to a landfill in Pennsylvania. The overall results indicate that the individual cancer risks for both options would be considered generally acceptable, although the risk from landfilling is approximately 5 times greater than from WTE treatment; the individual non-cancer health risks for both options would be considered generally unacceptable, although once again the risk from landfilling is approximately 5 times greater than from WTE treatment. If one considers only the population in Brooklyn that would be directly affected by the siting of either a WTS or a WTE facility in their immediate neighborhood, individual cancer and non-cancer health risks for both options would be considered generally acceptable, but risks for the former remain considerably higher than for the latter. These results should be considered preliminary due to several limitations of this study such as: consideration of risks only from inhalation exposures; assumption that only volume and not composition of the waste stream is altered by WTE treatment; reliance on data from the literature rather than actual measurements of the sites considered, assuming comparability of the sites. However, the results of studies such as this, in conjunction with ecological, socioeconomic and equity considerations, should prove useful to environmental managers, regulators, policy makers, community representatives and other stakeholders in making sound and acceptable decisions regarding the optimal handling of MSW. PMID:17379391

  14. High-level waste disposal, ethics and thermodynamics

    NASA Astrophysics Data System (ADS)

    Schwartz, Michael O.

    2008-06-01

    Moral philosophy applied to nuclear waste disposal can be linked to paradigmatic science. Simple thermodynamic principles tell us something about rightness or wrongness of our action. Ethical judgement can be orientated towards the chemical compatibility between waste container and geological repository. A container-repository system as close as possible to thermodynamic equilibrium is ethically acceptable. It aims at unlimited stability, similar to the stability of natural metal deposits within the Earth’s crust. The practicability of the guideline can be demonstrated.

  15. Decide, design, and dewater de waste: A blueprint from Fitzpatrick

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Robert, D.E.

    1994-04-01

    Using a different process to clean concentrated waste tanks at the James A. FitzPatrick nuclear power plant in New York saved nearly half million dollars. The plan essentially allowed processing concentrator bottoms as waste sludge (solidification versus dewatering) that could still meet burial ground requirements. The process reduced the volume from 802.2 to 55 cubic feet. This resin throwaway system eliminated chemicals in the radwaste systems and was designed to ease pressure on the pradwaste processing system, reduce waste and improve plant chemistry. This article discusses general aspects of the process.

  16. Recyclable Materials (Waste) Management in Enterprise’s Production Process

    NASA Astrophysics Data System (ADS)

    Malevskaia-Malevich, E. D.; Demidenko, D. S.

    2017-10-01

    Currently, in view of the increasing garbage crisis, the notion of a “new lease of life” for waste becomes even more relevant. Waste recycling makes it possible not only to solve obvious environmental problems, but also to offer new resource opportunities for industries. Among the obvious economic, social and environmental advantages, however, waste recycling meets various problems. These problems and solutions for them, as well as the problems of economic efficiency improvement and recycling activities’ appeal for industrial companies in Leningrad region, are discussed in the present study.

  17. Environmental assessment, finding of no significant impact, and response to comments. Radioactive waste storage

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    The Department of Energy`s (DOE) Rocky Flats Environmental Technology Site (the Site), formerly known as the Rocky Flats Plant, has generated radioactive, hazardous, and mixed waste (waste with both radioactive and hazardous constituents) since it began operations in 1952. Such wastes were the byproducts of the Site`s original mission to produce nuclear weapons components. Since 1989, when weapons component production ceased, waste has been generated as a result of the Site`s new mission of environmental restoration and deactivation, decontamination and decommissioning (D&D) of buildings. It is anticipated that the existing onsite waste storage capacity, which meets the criteria for low-levelmore » waste (LL), low-level mixed waste (LLM), transuranic (TRU) waste, and TRU mixed waste (TRUM) would be completely filled in early 1997. At that time, either waste generating activities must cease, waste must be shipped offsite, or new waste storage capacity must be developed.« less

  18. USEPA'S SITE PROGRAM IMPACT ON THE DEVELOPMENT AND USE OF INNOVATIVE HAZARDOUS WASTE TREATMENT

    EPA Science Inventory

    The USEPA's SITE Program was created to meet the increased demand for innovative technologies for hazardous waste treatment. The primary mission of the SITe Program is to expedite the cleanup of sites on the NPL. The SITE Program has two components: The Demonstration Program and ...

  19. Don't Waste Your Attorney's Time: Heed This Wise Counsel on When Legal Advice Is Vital and When It's Wasteful.

    ERIC Educational Resources Information Center

    Rice, Wandalyn

    1982-01-01

    Based on interviews with school board attorneys, this article discourages boards from paying an attorney to attend every meeting and encourages them to call a lawyer for problems regarding civil rights, bidding, finance, or policies that affect employees. (JM)

  20. 40 CFR 63.4493 - What work practice standards must I meet?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... National Emission Standards for Hazardous Air Pollutants for Surface Coating of Plastic Parts and Products... materials used in, and waste materials generated by the controlled coating operation(s) for which you use..., thinners and/or other additives, cleaning materials, and waste materials must be stored in closed...

  1. Energy Department Selects Partners...

    Science.gov Websites

    agricultural and forest wastes and other types of biomass. Six partnerships totaling $1 million in cost shared industrial chemical. Feedstocks are organic material, such as agricultural wastes or crops grown specifically are developed. Agricultural residues, such as corn stover, are the most likely candidates to help meet

  2. 40 CFR 258.58 - Implementation of the corrective action program.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... (CONTINUED) SOLID WASTES CRITERIA FOR MUNICIPAL SOLID WASTE LANDFILLS Ground-Water Monitoring and Corrective...) Establish and implement a corrective action ground-water monitoring program that: (i) At a minimum, meet the requirements of an assessment monitoring program under § 258.55; (ii) Indicate the effectiveness of the...

  3. 40 CFR 258.58 - Implementation of the corrective action program.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... WASTES CRITERIA FOR MUNICIPAL SOLID WASTE LANDFILLS Ground-Water Monitoring and Corrective Action § 258... implement a corrective action ground-water monitoring program that: (i) At a minimum, meet the requirements of an assessment monitoring program under § 258.55; (ii) Indicate the effectiveness of the corrective...

  4. 40 CFR 258.58 - Implementation of the corrective action program.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... (CONTINUED) SOLID WASTES CRITERIA FOR MUNICIPAL SOLID WASTE LANDFILLS Ground-Water Monitoring and Corrective...) Establish and implement a corrective action ground-water monitoring program that: (i) At a minimum, meet the requirements of an assessment monitoring program under § 258.55; (ii) Indicate the effectiveness of the...

  5. 40 CFR 258.58 - Implementation of the corrective action program.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... (CONTINUED) SOLID WASTES CRITERIA FOR MUNICIPAL SOLID WASTE LANDFILLS Ground-Water Monitoring and Corrective...) Establish and implement a corrective action ground-water monitoring program that: (i) At a minimum, meet the requirements of an assessment monitoring program under § 258.55; (ii) Indicate the effectiveness of the...

  6. 75 FR 39008 - Environmental Management Site-Specific Advisory Board, Idaho National Laboratory

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-07-07

    ... Dry Storage. Waste Area Group--7 Update. In-Situ Grouting. Comment Resolution--Environmental... meeting be announced in the Federal Register. DATES: Wednesday, July 14, 2010 8 a.m.-5 p.m. Opportunities... management in the areas of environmental restoration, waste management, and related activities. Tentative...

  7. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Elicio, Andy U.

    My ERM 593 applied project will provide guidance for the Los Alamos National Laboratory Waste Stream Profile reviewer (i.e. RCRA reviewer) in regards to Reviewing and Approving a Waste Stream Profile in the Waste Compliance and Tracking System. The Waste Compliance and Tracking system is called WCATS. WCATS is a web-based application that “supports the generation, characterization, processing and shipment of LANL radioactive, hazardous, and industrial waste.” The LANL generator must characterize their waste via electronically by filling out a waste stream profile (WSP) in WCATS. Once this process is completed, the designated waste management coordinator (WMC) will perform amore » review of the waste stream profile to ensure the generator has completed their waste stream characterization in accordance with applicable state, federal and LANL directives particularly P930-1, “LANL Waste Acceptance Criteria,” and the “Waste Compliance and Tracking System User's Manual, MAN-5004, R2,” as applicable. My guidance/applied project will describe the purpose, scope, acronyms, definitions, responsibilities, assumptions and guidance for the WSP reviewer as it pertains to each panel and subpanel of a waste stream profile.« less

  8. Avoidance of plants unsuitable for the symbiotic fungus in leaf-cutting ants: Learning can take place entirely at the colony dump.

    PubMed

    Arenas, Andrés; Roces, Flavio

    2017-01-01

    Plants initially accepted by foraging leaf-cutting ants are later avoided if they prove unsuitable for their symbiotic fungus. Plant avoidance is mediated by the waste produced in the fungus garden soon after the incorporation of the unsuitable leaves, as foragers can learn plant odors and cues from the damaged fungus that are both present in the recently produced waste particles. We asked whether avoidance learning of plants unsuitable for the symbiotic fungus can take place entirely at the colony dump. In order to investigate whether cues available in the waste chamber induce plant avoidance in naïve subcolonies, we exchanged the waste produced by subcolonies fed either fungicide-treated privet leaves or untreated leaves and measured the acceptance of untreated privet leaves before and after the exchange of waste. Second, we evaluated whether foragers could perceive the avoidance cues directly at the dump by quantifying the visits of labeled foragers to the waste chamber. Finally, we asked whether foragers learn to specifically avoid untreated leaves of a plant after a confinement over 3 hours in the dump of subcolonies that were previously fed fungicide-treated leaves of that species. After the exchange of the waste chambers, workers from subcolonies that had access to waste from fungicide-treated privet leaves learned to avoid that plant. One-third of the labeled foragers visited the dump. Furthermore, naïve foragers learned to avoid a specific, previously unsuitable plant if exposed solely to cues of the dump during confinement. We suggest that cues at the dump enable foragers to predict the unsuitable effects of plants even if they had never been experienced in the fungus garden.

  9. Avoidance of plants unsuitable for the symbiotic fungus in leaf-cutting ants: Learning can take place entirely at the colony dump

    PubMed Central

    Roces, Flavio

    2017-01-01

    Plants initially accepted by foraging leaf-cutting ants are later avoided if they prove unsuitable for their symbiotic fungus. Plant avoidance is mediated by the waste produced in the fungus garden soon after the incorporation of the unsuitable leaves, as foragers can learn plant odors and cues from the damaged fungus that are both present in the recently produced waste particles. We asked whether avoidance learning of plants unsuitable for the symbiotic fungus can take place entirely at the colony dump. In order to investigate whether cues available in the waste chamber induce plant avoidance in naïve subcolonies, we exchanged the waste produced by subcolonies fed either fungicide-treated privet leaves or untreated leaves and measured the acceptance of untreated privet leaves before and after the exchange of waste. Second, we evaluated whether foragers could perceive the avoidance cues directly at the dump by quantifying the visits of labeled foragers to the waste chamber. Finally, we asked whether foragers learn to specifically avoid untreated leaves of a plant after a confinement over 3 hours in the dump of subcolonies that were previously fed fungicide-treated leaves of that species. After the exchange of the waste chambers, workers from subcolonies that had access to waste from fungicide-treated privet leaves learned to avoid that plant. One-third of the labeled foragers visited the dump. Furthermore, naïve foragers learned to avoid a specific, previously unsuitable plant if exposed solely to cues of the dump during confinement. We suggest that cues at the dump enable foragers to predict the unsuitable effects of plants even if they had never been experienced in the fungus garden. PMID:28273083

  10. Invention, design and performance of coconut agrowaste fiberboards for ecologically efficacious buildings

    NASA Astrophysics Data System (ADS)

    Lokko, Mae-ling Jovenes

    As global quantities of waste by-products from food production as well as the range of their applications increase, researchers are realizing critical opportunities to transform the burden of underutilized wastes into ecological profits. Within the tropical hot-humid region, where half the world's current and projected future population growth is concentrated, there is a dire demand for building materials to meet ambitious development schemes and rising housing deficits. However, the building sector has largely overlooked the potential of local agricultural wastes to serve as alternatives to energy-intensive, imported building technologies. Industrial ecologists have recently investigated the use of agrowaste biocomposites to replace conventional wood products that use harmful urea-formaldehyde, phenolic and isocyanate resins. Furthermore, developments in the performance of building material systems with respect to cost, energy, air quality management and construction innovation have evolved metrics about what constitutes material 'upcycling' within building life cycle. While these developments have largely been focused on technical and cost performance, much less attention has been paid to addressing deeply-seated social and cultural barriers to adoption that have sedimented over decades of importation. This dissertation evaluates the development coconut agricultural building material systems in four phases: (i) non-toxic, low-energy production of medium-high density boards (500-1200 kg/m3) from coconut fibers and emerging biobinders; (ii) characterization and evaluation of coconut agricultural building materials hygrothermal performance (iii) scaled-up design development of coconut modular building material systems and (iv) development of a value translation framework for the bottom-up distribution of value to stakeholders within the upcycling framework. This integrated design methodological approach is significant to develop ecological thinking around agrowaste building materials, influence social and cultural acceptability and create value translation frameworks that sufficiently characterize the composite value proposition of upcycled building systems.

  11. Meeting report: threats to human health and environmental sustainability in the pacific basin.

    PubMed

    Arnold, Robert G; Carpenter, David O; Kirk, Donald; Koh, David; Armour, Margaret-Ann; Cebrian, Mariano; Cifuentes, Luis; Khwaja, Mahmood; Ling, Bo; Makalinao, Irma; Paz-Y-Miño, César; Peralta, Genandrialine; Prasad, Rajendra; Singh, Kirpal; Sly, Peter; Tohyama, Chiharu; Woodward, Alistair; Zheng, Baoshan; Maiden, Todd

    2007-12-01

    The coastal zone of the Pacific Rim is home for about one-third of the world's population. Disproportionate growth of Far Eastern economies has produced a disproportionate share of related environmental difficulties. As the region searches for acceptable compromises between growth and environmental quality, its influence on global environmental health is certain to increase. Consequences of global environmental change such as habitat alteration, storms, and sea level rise will be particularly acute among Pacific Rim nations. Adverse health effects from arsenic exposure in Pacific Rim nations have been used to justify drinking water standards in the United States and elsewhere. As global manufacturing in the Pacific Rim increases, the centroid of global air quality and waste management issues will shift further toward Far Eastern nations. The Eleventh International Conference of the Pacific Basin Consortium (PBC) was held in September 2005 in Honolulu, Hawaii. The purpose of the conference was to bring together individuals to discuss regional challenges to sustainable growth. The historic emphasis of the conference on hazardous wastes in relation to human health makes the PBC an ideal forum for discussing technical aspects of sustainable economic growth in the Pacific region. That role is reflected in the 2005 PBC conference themes, which included management of arsenic in potable waters, air quality, climate change, pesticides, mercury, and electronics industry waste-each with emphasis on relationships to human health. Arsenic management exemplifies the manner in which the PBC can focus interdisciplinary discussion in a single technical area. The conference program provided talks on arsenic toxicology, treatment technologies, management of arsenic-bearing residuals from water treatment, and the probable societal costs and benefits of arsenic management.

  12. Performance Measures for Evaluating Public Participation Activities in the Office of Environmental Management (DOE)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Carnes, S.A.

    2001-02-15

    Public participation in Office of Environmental Management (EM) activities throughout the DOE complex is a critical component of the overall success of remediation and waste management efforts. The challenges facing EM and its stakeholders over the next decade or more are daunting (Nuclear Waste News 1996). Achieving a mission composed of such challenges will require innovation, dedication, and a significant degree of good will among all stakeholders. EM's efforts to date, including obtaining and using inputs offered by EM stakeholders, have been notable. Public participation specialists have accepted and met challenges and have consistently tried to improve their performance. Theymore » have reported their experiences both formally and informally (e.g., at professional conferences and EM Public Participation Network Workshops, other internal meetings of DOE and contractor public participation specialists, and one-on-one consultations) in order to advance the state of their practice. Our research, and our field research in particular (including our interactions with many representatives of numerous stakeholder groups at nine DOE sites with diverse EM problems), have shown that it, is possible to develop coherent results even in a problem domain as complex as that of EM. We conclude that performance-based evaluations of public participation appear possible, and we have recommended an approach, based on combined and integrated multi-stakeholder views on the attributes of successful public participation and associated performance indicators, that seems workable and should be acceptable to diverse stakeholders. Of course, as an untested recommendation, our approach needs the validation that can only be achieved by application (perhaps at a few DOE sites with ongoing EM activities). Such an application would serve to refine the proposed approach in terms of its clarity, its workability, and its potential for full-scale use by EM and, potentially, other government agencies and private sector concerns.« less

  13. 33 CFR 175.130 - Visual distress signals accepted.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 33 Navigation and Navigable Waters 2 2012-07-01 2012-07-01 false Visual distress signals accepted... (CONTINUED) BOATING SAFETY EQUIPMENT REQUIREMENTS Visual Distress Signals § 175.130 Visual distress signals accepted. (a) Any of the following signals, when carried in the number required, can be used to meet the...

  14. 33 CFR 175.130 - Visual distress signals accepted.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 33 Navigation and Navigable Waters 2 2013-07-01 2013-07-01 false Visual distress signals accepted... (CONTINUED) BOATING SAFETY EQUIPMENT REQUIREMENTS Visual Distress Signals § 175.130 Visual distress signals accepted. (a) Any of the following signals, when carried in the number required, can be used to meet the...

  15. 33 CFR 175.130 - Visual distress signals accepted.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 33 Navigation and Navigable Waters 2 2014-07-01 2014-07-01 false Visual distress signals accepted... (CONTINUED) BOATING SAFETY EQUIPMENT REQUIREMENTS Visual Distress Signals § 175.130 Visual distress signals accepted. (a) Any of the following signals, when carried in the number required, can be used to meet the...

  16. Resource Management Plan for the US Department of Energy Oak Ridge Reservation. Volume 15, Appendix P: waste management

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kelly, B.A.

    1984-07-01

    Since their inception, the DOE facilities on the Oak Ridge Reservation have been the source of a variety of airborne, liquid, and solid wastes which are characterized as nonhazardous, hazardous, and/or radioactive. The major airborne releases come from three primary sources: steam plant emissions, process discharge, and cooling towers. Liquid wastes are handled in various manners depending upon the particular waste, but in general, major corrosive waste streams are neutralized prior to discharge with the discharge routed to holding or settling ponds. The major solid wastes are derived from construction debris, sanitary operation, and radioactive processes, and the machining operationsmore » at Y-12. Nonradioactive hazardous wastes are disposed in solid waste storage areas, shipped to commercial disposal facilities, returned in sludge ponds, or sent to radioactive waste burial areas. The radioactive-hazardous wastes are treated in two manners: storage of the waste until acceptable disposal options are developed, or treatment of the waste to remove or destroy one of the components prior to disposal. 5 references, 4 figures, 13 tables.« less

  17. The Joint Convention - Its Structure, the Articles and its Administration

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Metcalf, P.; Louvat, D.

    The objective of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (The Joint Convention) is to achieve a high level of safety worldwide in the management of spent nuclear and fuel and radioactive waste. [1] It is an incentive convention designed to encourage and assist countries to achieve the objective. Contracting Parties to the Joint Convention are required to compile and submit a national report on how they meet the articles of the Joint Convention. The reports are peer reviewed by other Contracting Parties to the Joint Convention and thenmore » countries have to defend the report at a review meeting of all the Contracting Parties. The process entails both a self appraisal in compiling the report and independent international peer review. Summaries are compiled of the various reviews and these are presented in plenary, with a view to identifying generic issues and areas in which countries are improving safety or have identified for further development. The process also presents an opportunity for countries involved to benchmark their national spent fuel and radioactive waste safety programmes against prevailing international practice. The paper elaborates the detailed elements involved and discusses the experience from the first review meeting of Contracting Parties, and issues envisaged for consideration at the second review meeting scheduled for May 2006. (authors)« less

  18. 76 FR 39074 - Mid-Atlantic Fishery Management Council; Public Meetings

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-05

    ... Bluefish, Summer Flounder, Scup, and Black Sea Bass Monitoring Committees will hold public meetings. DATES... Bluefish, Summer Flounder, Scup, and Black Sea Bass Monitoring Committees will meet on Friday, July 29... and specify overfishing level and acceptable biological catch (ABC) for bluefish, summer flounder...

  19. Planning and conducting meetings effectively, part I: planning a meeting.

    PubMed

    Harolds, Jay

    2011-12-01

    Meetings are held by leaders for many purposes, including conveying information, raising morale, asking for opinions, brain storming, making people part of the problem-solving process, building trust, getting to a consensus, and making decisions. However, many meetings waste time, some undermine the leader's power, and some decrease morale. Part I of this series of articles gives some tips on basic planning for decision-making meetings. Part II of this series of articles analyzes selected components of decision-making meetings. Part III of this series will be on how the chairperson keeps decision-making meetings on track to make them efficient and productive.

  20. Managing previously disposed waste to today's standards

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1990-01-01

    A Radioactive Waste Management Complex (RWMC) was established at the Idaho National Engineering Laboratory (INEL) in 1952 for controlled disposal of radioactive waste generated at the INEL. Between 1954 and 1970 waste characterized by long lived, alpha emitting radionuclides from the Rocky Flats Plant was also buried at this site. Migration of radionuclides and other hazardous substances from the buried Migration of radionuclides and other hazardous substances from the buried waste has recently been detected. A Buried Waste Program (BWP) was established to manage cleanup of the buried waste. This program has four objectives: (1) determine contaminant sources, (2) determinemore » extent of contamination, (3) mitigate migration, and (4) recommend an alternative for long term management of the waste. Activities designed to meet these objectives have been under way since the inception of the program. The regulatory environment governing these activities is evolving. Pursuant to permitting activities under the Resource Conservation and Recovery Act (RCRA), the Department of Energy (DOE) and the Environmental Protection Agency (EPA) entered into a Consent Order Compliance Agreement (COCA) for cleanup of past practice disposal units at the INEL. Subsequent to identification of the RWMC as a release site, cleanup activities proceeded under dual regulatory coverage of RCRA and the Atomic Energy Act. DOE, EPA, and the State of Idaho are negotiating a RCRA/Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Interagency Agreement (IAG) for management of waste disposal sites at the INEL as a result of the November 1989 listing of the INEL on the National Priority List (NPL). Decision making for selection of cleanup technology will be conducted under the CERCLA process supplemented as required to meet the requirements of the National Environmental Policy Act (NEPA). 7 figs.« less

  1. 10 CFR 960.3-1-4-1 - Site identification as potentially acceptable.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 4 2010-01-01 2010-01-01 false Site identification as potentially acceptable. 960.3-1-4-1 Section 960.3-1-4-1 Energy DEPARTMENT OF ENERGY GENERAL GUIDELINES FOR THE PRELIMINARY SCREENING OF POTENTIAL SITES FOR A NUCLEAR WASTE REPOSITORY Implementation Guidelines § 960.3-1-4-1 Site identification...

  2. 10 CFR 960.3-2-2-1 - Evaluation of all potentially acceptable sites.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 4 2010-01-01 2010-01-01 false Evaluation of all potentially acceptable sites. 960.3-2-2-1 Section 960.3-2-2-1 Energy DEPARTMENT OF ENERGY GENERAL GUIDELINES FOR THE PRELIMINARY SCREENING OF POTENTIAL SITES FOR A NUCLEAR WASTE REPOSITORY Implementation Guidelines § 960.3-2-2-1 Evaluation...

  3. Don’t forget the posters! Quality and content variables associated with accepted abstracts at a national trauma meeting

    PubMed Central

    Dossett, Lesly A.; Fox, Erin E.; del Junco, Deborah J.; Zaydfudim, Victor; Kauffmann, Rondi; Shelton, Julia; Wang, Weiwei; Cioffi, William G.; Holcomb, John B.; Cotton, Bryan A.

    2014-01-01

    BACKGROUND As a primary venue for presenting research results, abstracts selected for presentation at national meetings should be of the highest scientific merit and research quality. It is uncertain to what degree this is achieved as the methodological quality of abstracts submitted to national surgical meetings has not been previously described. The objective of this study was to evaluate abstracts presented at a leading trauma meeting for methodological quality. METHODS All abstracts accepted for the 2009 American Association for the Surgery of Trauma meeting were reviewed and scored for methodological quality based on 10 criteria (scores, 0–10; 10 being the highest). Criteria were based on nationally published methodology guidelines. Two independent reviewers who were blinded to institution, region, and author reviewed each abstract. RESULTS A total of 187 abstracts were accepted for presentation (67 oral and 120 posters). The most frequent clinical topics were shock/transfusion (23%), abdomen (12%), and nervous system (11%). Shock/transfusion abstracts were more common in the oral presentations (31% vs. 19%; p =0.06). Abstracts from the northeast and south regions were the most common in both oral (26% and 29%) and posters (25% and 24%). Basic science accounted for 12% of accepted studies, while 51% were clinical and 28% were health services/outcomes. Only 8% of abstracts presented randomized data and only 11% reported null findings. Overall abstract scores ranged from 3 to 10 (median, 7; mean, 7.4). Abstracts selected for poster presentation had an overall higher score than those selected for oral presentation (7.4 ±1.7 vs. 6.8 ±1.7; p =0.02). CONCLUSION Although oral presentations traditionally receive the most attention and interest, the methodological quality of abstracts accepted for poster presentation equals (and sometimes exceeds) that of oral abstracts. Attendees of these national meetings should reconsider their time spent in viewing and visiting these poster sessions as with the oral presentations. In light of our findings, we highly encourage that all members and guests attend the American Association for the Surgery of Trauma Poster Rounds at each year’s scientific assembly. PMID:22673278

  4. Don't forget the posters! Quality and content variables associated with accepted abstracts at a national trauma meeting.

    PubMed

    Dossett, Lesly A; Fox, Erin E; del Junco, Deborah J; Zaydfudim, Victor; Kauffmann, Rondi; Shelton, Julia; Wang, Weiwei; Cioffi, William G; Holcomb, John B; Cotton, Bryan A

    2012-05-01

    As a primary venue for presenting research results, abstracts selected for presentation at national meetings should be of the highest scientific merit and research quality. It is uncertain to what degree this is achieved as the methodological quality of abstracts submitted to national surgical meetings has not been previously described. The objective of this study was to evaluate abstracts presented at a leading trauma meeting for methodological quality. All abstracts accepted for the 2009 American Association for the Surgery of Trauma meeting were reviewed and scored for methodological quality based on 10 criteria (scores, 0-10; 10 being the highest). Criteria were based on nationally published methodology guidelines. Two independent reviewers who were blinded to institution, region, and author reviewed each abstract. A total of 187 abstracts were accepted for presentation (67 oral and 120 posters). The most frequent clinical topics were shock/transfusion (23%), abdomen (12%), and nervous system (11%). Shock/transfusion abstracts were more common in the oral presentations (31% vs. 19%; p = 0.06). Abstracts from the northeast and south regions were the most common in both oral (26% and 29%) and posters (25% and 24%). Basic science accounted for 12% of accepted studies, while 51% were clinical and 28% were health services/outcomes. Only 8% of abstracts presented randomized data and only 11% reported null findings. Overall abstract scores ranged from 3 to 10 (median, 7; mean, 7.4). Abstracts selected for poster presentation had an overall higher score than those selected for oral presentation (7.4 ± 1.7 vs. 6.8 ± 1.7; p = 0.02). Although oral presentations traditionally receive the most attention and interest, the methodological quality of abstracts accepted for poster presentation equals (and sometimes exceeds) that of oral abstracts. Attendees of these national meetings should reconsider their time spent in viewing and visiting these poster sessions as with the oral presentations. In light of our findings, we highly encourage that all members and guests attend the American Association for the Surgery of Trauma Poster Rounds at each year's scientific assembly.

  5. 75 FR 82004 - Environmental Management Site-Specific Advisory Board, Idaho National Laboratory

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-29

    ... Laboratory AGENCY: Department of Energy. ACTION: Notice of open meeting. SUMMARY: This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Idaho National Laboratory...--Radioactive Waste Management. Public Participation: The EM SSAB, Idaho National Laboratory, welcomes the...

  6. Federal environmental standards of potential importance to operations and activities at US Department of Energy sites. Draft

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Fowler, K.M.; Bilyard, G.R.; Davidson, S.A.

    1993-06-01

    The US Department of Energy (DOE) is now engaged in a program of environmental restoration nationwide across its 45 sites. It is also bringing its facilities into compliance with environmental regulations, decontaminating and decommissioning unwanted facilities, and constructing new waste management facilities. One of the most difficult questions that DOE must face in successfully remediating its inactive waste sites, decontaminating and decommissioning its inactive facilities, and operating its waste management facilities is: ``What criteria and standards should be met?`` Acceptable standards or procedures for determining standards will assist DOE in its conduct of ongoing waste management and pending cleanup activitiesmore » by helping to ensure that those activities are conducted in compliance with applicable laws and regulations and are accepted by the regulatory community and the public. This document reports on the second of three baseline activities that are being conducted as prerequisites to either the development of quantitative standards that could be used by DOE, or consistent procedures for developing such standards. The first and third baseline activities are also briefly discussed in conjunction with the second of the three activities.« less

  7. Evaluation and comparison of alternative designs for water/solid-waste processing systems for spacecraft

    NASA Technical Reports Server (NTRS)

    Spurlock, J. M.

    1975-01-01

    Promising candidate designs currently being considered for the management of spacecraft solid waste and waste-water materials were assessed. The candidate processes were: (1) the radioisotope thermal energy evaporation/incinerator process; (2) the dry incineration process; and (3) the wet oxidation process. The types of spacecraft waste materials that were included in the base-line computational input to the candidate systems were feces, urine residues, trash and waste-water concentrates. The performance characteristics and system requirements for each candidate process to handle this input and produce the specified acceptable output (i.e., potable water, a storable dry ash, and vapor phase products that can be handled by a spacecraft atmosphere control system) were estimated and compared. Recommendations are presented.

  8. Radioactive Waste Management in Non-Nuclear Countries - 13070

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kubelka, Dragan; Trifunovic, Dejan

    2013-07-01

    This paper challenges internationally accepted concepts of dissemination of responsibilities between all stakeholders involved in national radioactive waste management infrastructure in the countries without nuclear power program. Mainly it concerns countries classified as class A and potentially B countries according to International Atomic Energy Agency. It will be shown that in such countries long term sustainability of national radioactive waste management infrastructure is very sensitive issue that can be addressed by involving regulatory body in more active way in the infrastructure. In that way countries can mitigate possible consequences on the very sensitive open market of radioactive waste management services,more » comprised mainly of radioactive waste generators, operators of end-life management facilities and regulatory body. (authors)« less

  9. Release Report for Building Debris for TA-21 Sewage Treatment Facility

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Whicker, Jeffrey Jay; Gillis, Jessica; Ruedig, Elizabeth

    2017-05-03

    ENV-ES finds that the materials associated with TA-21 Buildings 227 (superstructure only), and 229 (see Figure 1) meet the criteria for unrestricted release to the public for recycle or as sanitary/commercial waste. The interior and exterior of the metal shed, building 387, passed the release criteria collectively; however, results from the roof of the structure were above reference background measurements. Waste management should be consulted for waste disposition options for the roofing metal. These findings are consistent with the requirements of DOE Order 458.1 “Radiation Protection of the Public and the Environment” and LANL Policy 412 “Environmental Radiation Protection.” Samplingmore » and data analysis, as described in this report, were sufficient to meet measurement objectives under the Multi-Agency Radiation Survey and Assessment of Materials and Equipment (MARSAME) manual (2009).« less

  10. CSER-98-002: Criticality analysis for the storage of special nuclear material sources and standards in the WRAP facility

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    GOLDBERG, H.J.

    1999-05-18

    The Waste Receiving and Processing (WRAP) Facility will store uranium and transuranic (TRU) sources and standards for certification that WRAP meets the requirements of the Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP). In addition, WRAP must meet internal requirements for testing and validation of measuring instruments for nondestructive assay (NDA). In order to be certified for WIPP, WRAP will participate in the NDA Performance Demonstration Program (PDP). This program is a blind test of the NDA capabilities for TRU waste. It is intended to ensure that the NDA capabilities of this facility satisfy the requirementsmore » of the quality assurance program plan for the WIPP. The PDP standards have been provided by the Los Alamos National Laboratory (LANL) for this program. These standards will be used in the WRAP facility.« less

  11. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Melody, M.

    Waste Technologies Industries (WTI; East Liverpool, Ohio) is trying to wing what it hopes will be its final battle in a 13-year, $160 million war with the government, and community and environmental groups. The company since 1980 has sought EPA approval to operate a hazardous waste incinerator in East Liverpool, Ohio. WTI late last year conducted a pre-test burn, or shakedown, during which the incinerator burned certain types of hazardous waste. The test demonstrates the incinerator's performance under normal operating conditions, Regulatory authorities, including EPA and the Ohio Environmental Protection Agency (OEPA), monitored activity during the shakedown, which was limitedmore » to 720 hours of operation. In accordance with RCRA requirements, the company in March conducted a trial burn to demonstrate that the incinerator meets permit standards. WTI's permit specifies three performance parameters the incinerator must meet -- particulate and hydrogen chloride emissions limits, and destruction removal efficiencies (DREs).« less

  12. Treatment options for tank farms long-length contaminated equipment

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Josephson, W.S.

    1995-10-16

    This study evaluated a variety of treatment and disposal technologies for mixed waste (MW) meeting the following criteria: 1. Single-Shell and Double-Shell Tank System (tank farms) equipment and other debris; 2. length greater than 12 feet; and contaminated with listed MW from the tank farms. This waste stream, commonly referred to as tank farms long-length contaminated equipment (LLCE), poses a unique and costly set of challenges during all phases of the waste management lifecycle.

  13. Parametric Criticality Safety Calculations for Arrays of TRU Waste Containers

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Gough, Sean T.

    The Nuclear Criticality Safety Division (NCSD) has performed criticality safety calculations for finite and infinite arrays of transuranic (TRU) waste containers. The results of these analyses may be applied in any technical area onsite (e.g., TA-54, TA-55, etc.), as long as the assumptions herein are met. These calculations are designed to update the existing reference calculations for waste arrays documented in Reference 1, in order to meet current guidance on calculational methodology.

  14. 77 FR 109 - Inquiry To Learn Whether Businesses Assert Business Confidentiality Claims Regarding Waste Import...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-01-03

    ... definition of ``affected business,'' and are not covered by today's notice. They consist of any business that.... Certain businesses, however, do not meet the definition of ``affected business,'' and are not covered by... Businesses Assert Business Confidentiality Claims Regarding Waste Import and Export AGENCY: Environmental...

  15. 40 CFR 426.135 - Standards of performance for new sources.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... greater than 50 gallons per day of process waste water, and employs hydrofluoric acid finishing techniques... any 1 day Average of daily values for 30 consecutive days shall not exceed— Lead 0.2 0.1 Fluoride 26.0... waste water, and employs hydrofluoric acid finishing techniques shall meet the following limitations...

  16. 40 CFR 426.135 - Standards of performance for new sources.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... greater than 50 gallons per day of process waste water, and employs hydrofluoric acid finishing techniques... any 1 day Average of daily values for 30 consecutive days shall not exceed— Lead 0.2 0.1 Fluoride 26.0... waste water, and employs hydrofluoric acid finishing techniques shall meet the following limitations...

  17. 40 CFR 426.135 - Standards of performance for new sources.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... greater than 50 gallons per day of process waste water, and employs hydrofluoric acid finishing techniques... any 1 day Average of daily values for 30 consecutive days shall not exceed— Lead 0.2 0.1 Fluoride 26.0... waste water, and employs hydrofluoric acid finishing techniques shall meet the following limitations...

  18. Teaching and Learning about Solid Waste: Aspects of Content Knowledge

    ERIC Educational Resources Information Center

    Cinquetti, Heloisa Chalmers Sisla; de Carvalho, Luiz Marcelo

    2007-01-01

    This paper investigates aspects of content knowledge related to teaching and learning about solid waste, focusing on the processes of learning and teaching by Elementary School teachers in Brazil, in two modalities of continuing education: courses and school-based meetings. We analyse elements of teachers' reflections whilst referring to three…

  19. 40 CFR 267.190 - Does this subpart apply to me?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... (CONTINUED) STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE FACILITIES OPERATING UNDER A STANDARDIZED... part 270 subpart J standardized permit, except as provided in § 267.1(b). (a) You do not have to meet... presence of free liquids in the stored/treated waste, using Method 9095B (Paint Filter Liquids Test) as...

  20. 1999 Report on Hanford Site land disposal restriction for mixed waste

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    BLACK, D.G.

    This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-26-011. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of managing land-disposal-restricted mixed waste at the Hanford Facility.

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