WRAP low level waste (LLW) glovebox operational test report

International Nuclear Information System (INIS)

Kersten, J.K.

1998-01-01

The Low Level Waste (LLW) Process Gloveboxes are designed to: receive a 55 gallon drum in an 85 gallon overpack in the Entry glovebox (GBIOI); and open and sort the waste from the 55 gallon drum, place the waste back into drum and relid in the Sorting glovebox (GB 102). In addition, waste which requires further examination is transferred to the LLW RWM Glovebox via the Drath and Schraeder Bagiess Transfer Port (DO-07-201) or sent to the Sample Transfer Port (STC); crush the drum in the Supercompactor glovebox (GB 104); place the resulting puck (along with other pucks) into another 85 gallon overpack in the Exit glovebox (GB 105). The status of the waste items is tracked by the Data Management System (DMS) via the Plant Control System (PCS) barcode interface. As an item is moved from the entry glovebox to the exit glovebox, the Operator will track an items location using a barcode reader and enter any required data on the DMS console. The Operational Test Procedure (OTP) will perform evolution's (described below) using the Plant Operating Procedures (POP) in order to verify that they are sufficient and accurate for controlled glovebox operation

LLW Forum meeting report

International Nuclear Information System (INIS)

1996-01-01

This report summarizes the Low-Level Radioactive Waste Forum (LLW Forum) meeting on May 29 through May 31, 1996.The LLW Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW Forum meeting report

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-08-01

This report summarizes the Low-Level Radioactive Waste Forum (LLW Forum) meeting on May 29 through May 31, 1996.The LLW Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

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

International Nuclear Information System (INIS)

Quinn, G.J.

1992-01-01

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

Guidance for closure of existing DOE LLW disposal sites

International Nuclear Information System (INIS)

Blanchfield, L.

1987-01-01

During FY 1986, a closure guidance document was developed. The purpose of this document is to provide guidance in support of DOE Order 5820.2 to site operating contractors for the stabilization and closure of existing low-level waste (LLW) shallow land disposal sites at US Department of Energy (DOE) facilities. Guidance is provided to aid operators in placing existing LLW sites in a closed conditions, i.e., a condition in which a nonoperational site meets postclosure performance requirements and can be shown, within a high degree of confidence, to perform as anticipated in the future, under the most cost-effective maintenance approach. Guidance is based on the philosophy that closure should be planned and performed using a systems approach. Plans for FY 1987 call for revision of the document to incorporate more information on closure of LLW sites also containing radioactive mixed waste and/or transuranic waste. 4 references, 3 figures, 2 tables

LLW notes. Vol. 11, No. 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-02-01

`LLW Notes` is distributed by Afton Associates, Inc. to Low-Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive `LLW Notes`. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

LLW notes. Volume 11, No.8

International Nuclear Information System (INIS)

1996-12-01

'LLW Notes' is distributed by Afton Associates, Inc. to Low-Level Radioactive Waste Forum Participants and other state, and compact officials identified by those Participants to receive 'LLW Notes'. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW notes. Vol. 11, No. 1

International Nuclear Information System (INIS)

1996-02-01

'LLW Notes' is distributed by Afton Associates, Inc. to Low-Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive 'LLW Notes'. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW notes, Vol. 11, No. 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-01

`LLW Notes` is distributed by Afton Associates, Inc. to Low-Level Radioactive Waste Forum Participants and other state, and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

LLW notes, Vol. 11, No. 2

International Nuclear Information System (INIS)

1996-03-01

'LLW Notes' is distributed by Afton Associates, Inc. to Low-Level Radioactive Waste Forum Participants and other state, and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

Investigations with respect to pressure build-up in 200 l drums with supercompacted low level waste (LLW)

International Nuclear Information System (INIS)

Kroth, K.; Lammertz, H.

1988-04-01

In the drum storage facilities of various nuclear power stations, ballooning effects have recently been observed on a limited number of 200 l drums filled with hypercompacted mixed LLW. The ballooning of the drums lid and bottom is due to internal overpressure caused by gas formation in the waste. The internal drum pressures and the composition of the drum gases were measured on a considerable number of 200 l drums. Hydrogen, formed by chemical reactions between the waste components, was identified as the pressure generating gas. The reasons for the hydrogen formation were investigated on both real and simulated wastes. (orig.) [de

LLW (Low-Level Waste) Notes, Volume 13, Number 1, February 1998

International Nuclear Information System (INIS)

1998-02-01

LLW Notes is a newsletter distributed to Low-Level Radioactive Waste Forum Participants and other state and compact officials. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties. This issue focuses on the following topics: DOI approves Ward Valley permit application; Project evidentiary hearings begin in Texas; and Summary judgment motions in California breach of contract action

LLW (Low-Level Waste) Notes, Volume 13, Number 1, February 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-02-01

LLW Notes is a newsletter distributed to Low-Level Radioactive Waste Forum Participants and other state and compact officials. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties. This issue focuses on the following topics: DOI approves Ward Valley permit application; Project evidentiary hearings begin in Texas; and Summary judgment motions in California breach of contract action.

The Department of Energy's National Disposition Strategy for the Treatment and Disposal of Low Level and Mixed Low Level Waste

International Nuclear Information System (INIS)

Peterson, G.R.; Tonkay, D.W.

2006-01-01

The U.S. Department of Energy's (DOE) Environmental Management (EM) program is committed to the environmental remediation of DOE sites. This cleanup mission will continue to produce large amounts of Low Level Waste (LLW) and Mixed Low-Level Waste (MLLW). This paper reports on the development of the DOE LLW/MLLW National Disposition Strategy that maps the Department's long-range strategy to manage LLW and MLLW. Existing corporate LLW and MLLW data proved insufficient to develop this strategy. Therefore, new data requirements were developed in conjunction with waste managers. The paper will report on the results of this data collection effort, which will result in development of DOE LLW/MLLW disposition maps. (authors)

Updated Strategic Assessment of the U.S. NRC Low-Level Radioactive Waste (LLW) Program and the new WCS Commercial Disposal Facility for LLW

Energy Technology Data Exchange (ETDEWEB)

Kessel, David S.; Kim, Chang-Lak [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2015-05-15

The purpose of this paper is to review the updated NRC low level radioactive waste regulatory strategy and also present an update on a significant change in the LLW disposal landscape in the U.S., the opening of a new commercial disposal facility, the Texas Compact Waste Facility (CWF) in Andrews, Texas. Operational since spring of 2012, the CWF is owned and licensed by the state of Texas and operated by Waste Control Specialists LLC (WCS). The WCS facility in western Andrews County is the only commercial facility in the United States licensed to dispose of Class A, B and C LLW in the U.S. in the past 40 years. Based on the observation that other suitable sites have been identified such as the Clive, Utah site that meet (almost) all of these criteria it would appear that the first and last factors in our list are the most problematic and it will require a change in the public acceptance and the political posture of states to help solve the national issue of safe and cost-effective LLW disposal.

Development of a mixed waste management facility at the Nevada Test Site

International Nuclear Information System (INIS)

Dodge, R.L.; Brich, R.F.

1988-01-01

The U.S. Department of Energy (DOE) produces radioactive low-level wastes (LLW) which contain hazardous components as identified by 40 Code of Federal Regulations (CFR) 261. Management of those mixed wastes (MW) requires compliance with U.S.Environmental Protection Agency (EPA) regulations for hazardous wastes and DOE regulations for LLW. In 1988, DOE's Nevada Operations Office (NV) began disposing of MW at the Nevada Test Site (NTS) under interim status as authorized by the state of Nevada. MW disposal is limited to Pit 3 while operating under interim status. This paper discusses how preparations for operation of a separate mixed waste management facility (MWMF) are underway. Those preparations include revising the NTS Part B Permit application, developing a MW certification program, developing and operating a vadose zone monitoring system, preparing an Environmental Assessment (EA), developing protocols for analysis of MW, and facility design and construction

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

International Nuclear Information System (INIS)

Leist, K.J.

1997-01-01

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 of 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

National Institutes of Health: Mixed waste minimization and treatment

International Nuclear Information System (INIS)

1995-08-01

The Appalachian States Low-Level Radioactive Waste Commission requested the US Department of Energy's National Low-Level Waste Management Program (NLLWMP) to assist the biomedical community in becoming more knowledgeable about its mixed waste streams, to help minimize the mixed waste stream generated by the biomedical community, and to identify applicable treatment technologies for these mixed waste streams. As the first step in the waste minimization process, liquid low-level radioactive mixed waste (LLMW) streams generated at the National Institutes of Health (NIH) were characterized and combined into similar process categories. This report identifies possible waste minimization and treatment approaches for the LLMW generated by the biomedical community identified in DOE/LLW-208. In development of the report, on site meetings were conducted with NIH personnel responsible for generating each category of waste identified as lacking disposal options. Based on the meetings and general waste minimization guidelines, potential waste minimization options were identified

National Institutes of Health: Mixed waste minimization and treatment

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-08-01

The Appalachian States Low-Level Radioactive Waste Commission requested the US Department of Energy`s National Low-Level Waste Management Program (NLLWMP) to assist the biomedical community in becoming more knowledgeable about its mixed waste streams, to help minimize the mixed waste stream generated by the biomedical community, and to identify applicable treatment technologies for these mixed waste streams. As the first step in the waste minimization process, liquid low-level radioactive mixed waste (LLMW) streams generated at the National Institutes of Health (NIH) were characterized and combined into similar process categories. This report identifies possible waste minimization and treatment approaches for the LLMW generated by the biomedical community identified in DOE/LLW-208. In development of the report, on site meetings were conducted with NIH personnel responsible for generating each category of waste identified as lacking disposal options. Based on the meetings and general waste minimization guidelines, potential waste minimization options were identified.

Mixed Waste Management Options: 1995 Update. National Low-Level Waste Management Program

Energy Technology Data Exchange (ETDEWEB)

Kirner, N.; Kelly, J.; Faison, G.; Johnson, D. [Foster Wheeler Environmental Corp. (United States)

1995-05-01

In the original mixed Waste Management Options (DOE/LLW-134) issued in December 1991, the question was posed, ``Can mixed waste be managed out of existence?`` That study found that most, but not all, of the Nation`s mixed waste can theoretically be managed out of existence. Four years later, the Nation is still faced with a lack of disposal options for commercially generated mixed waste. However, since publication of the original Mixed Waste Management Options report in 1991, limited disposal capacity and new technologies to treat mixed waste have become available. A more detailed estimate of the Nation`s mixed waste also became available when the US Environmental Protection Agency (EPA) and the US Nuclear Regulatory Commission (NRC) published their comprehensive assessment, titled National Profile on Commercially Generated Low-Level Radioactive Mixed Waste (National Profile). These advancements in our knowledge about mixed waste inventories and generation, coupled with greater treatment and disposal options, lead to a more applied question posed for this updated report: ``Which mixed waste has no treatment option?`` Beyond estimating the volume of mixed waste requiring jointly regulated disposal, this report also provides a general background on the Atomic Energy Act (AEA) and the Resource Conservation and Recovery Act (RCRA). It also presents a methodical approach for generators to use when deciding how to manage their mixed waste. The volume of mixed waste that may require land disposal in a jointly regulated facility each year was estimated through the application of this methodology.

Mixed Waste Management Options: 1995 Update. National Low-Level Waste Management Program

International Nuclear Information System (INIS)

Kirner, N.; Kelly, J.; Faison, G.; Johnson, D.

1995-05-01

In the original mixed Waste Management Options (DOE/LLW-134) issued in December 1991, the question was posed, ''Can mixed waste be managed out of existence?'' That study found that most, but not all, of the Nation's mixed waste can theoretically be managed out of existence. Four years later, the Nation is still faced with a lack of disposal options for commercially generated mixed waste. However, since publication of the original Mixed Waste Management Options report in 1991, limited disposal capacity and new technologies to treat mixed waste have become available. A more detailed estimate of the Nation's mixed waste also became available when the US Environmental Protection Agency (EPA) and the US Nuclear Regulatory Commission (NRC) published their comprehensive assessment, titled National Profile on Commercially Generated Low-Level Radioactive Mixed Waste (National Profile). These advancements in our knowledge about mixed waste inventories and generation, coupled with greater treatment and disposal options, lead to a more applied question posed for this updated report: ''Which mixed waste has no treatment option?'' Beyond estimating the volume of mixed waste requiring jointly regulated disposal, this report also provides a general background on the Atomic Energy Act (AEA) and the Resource Conservation and Recovery Act (RCRA). It also presents a methodical approach for generators to use when deciding how to manage their mixed waste. The volume of mixed waste that may require land disposal in a jointly regulated facility each year was estimated through the application of this methodology

Greater-than-Class C low-level radioactive waste characterization. Appendix E-3: GTCC LLW assumptions matrix

International Nuclear Information System (INIS)

1995-01-01

This study identifies four categories of GTCC LLW: nuclear utility; sealed sources; DOE-held; and other generators. Within each category, inventory and projection data are modeled in three scenarios: (1) Unpackaged volume--this is the unpackaged volume of waste that would exceed Class C limits if the waste calculation methods in 10 CFR 61.55 were applied to the discrete items before concentration averaging methods were applied to the volume; (2) Not-concentration-averaged (NCA) packaged volume--this is the packaged volume of GTCC LLW assuming that no concentration averaging is allowed; and (3) After-concentration-averaging (ACA) packaged volume--this is the packaged volume of GTCC LLW, which, for regulatory or practical reasons, cannot be disposed of in a LLW disposal facility using allowable concentration averaging practices. Three cases are calculated for each of the volumes described above. These values are defined as the low, base, and high cases. The following tables explain the assumptions used to determine low, base, and high case estimates for each scenario, within each generator category. The appendices referred to in these tables are appendices to Greater-Than-Class C Low-Level Radioactive Waste Characterization: Estimated Volumes, Radionuclide Activities, and Other Characteristics (DOE/LLW-114, Revision 1)

Disposal of low-level and mixed low-level radioactive waste during 1990

International Nuclear Information System (INIS)

1993-08-01

Isotopic inventories and other data are presented for low-level radioactive waste (LLW) and mixed LLW disposed (and occasionally stored) during calendar year 1990 at commercial disposal facilities and Department of Energy (DOE) sites. Detailed isotopic information is presented for the three commercial disposal facilities located near Barnwell, SC, Richland, WA, and Beatty, NV. Less information is presented for the Envirocare disposal facility located near Clive, UT, and for LLW stored during 1990 at the West Valley site. DOE disposal information is included for the Savannah River Site (including the saltstone facility), Nevada Test Site, Los Alamos National Laboratory, Idaho National Engineering Laboratory, Hanford Site, Y-12 Site, and Oak Ridge National Laboratory. Summary information is presented about stored DOE LLW. Suggestions are made about improving LLW disposal data

Packaging LLW and ILW

International Nuclear Information System (INIS)

Flowers, R.H.; Owen, R.G.

1991-01-01

Low level waste (LLW) accounts for 70-80% by volume of all radioactive wastes produced by the nuclear industry. It has low specific activity, negligible actinide content and requires little, if any, shielding to protect workers. Volume reduction for LLW of high volume but low density may be achieved by incineration and compaction as appropriate, before packaging for disposal by near surface burial. Intermediate level waste (ILW) is treated and packed to convert it into a stable form to minimize any release of activity and make handling easier. The matrix chosen for immobilization, usually cement, polymers or bitumen, depends on the nature of the waste and the acceptance criteria of the disposal facility. The special case of LLW and ILW which will arise from reactor decommissioning is discussed. Packaging methods adopted by individual countries are reviewed. The range of costs involved for packaging ILW is indicated. There is no international consensus on the performance required from packaged waste to ensure its suitability both for interim storage and final disposal. (UK)

Implementation of Waste Tracking System for LLW and MLW

International Nuclear Information System (INIS)

Won, Y. S.; Lee, K. H.; Kim, H. J.; Lee, K. H.

2010-01-01

The real-time Waste Tracking System (WTS) has been implemented for the integrated management of LLW and MLW from the receiving time at the production area till the managing period after the shutdown of disposal site. The relevant information by each process on take-over and receiving plan, preliminary inspection, receiving, transportation, site inspection, disposal and shutdown is over all managed by WTS

UK strategy for nuclear industry LLW - 16393

International Nuclear Information System (INIS)

Clark, Matthew; Fisher, Joanne

2009-01-01

In March 2007 the UK Government and devolved administrations (for Scotland, Wales and Northern Ireland, from here on referred to as 'Government') published their policy for the management of solid low level waste ('the Policy'). The Policy sets out a number of core principles for the management of low level waste (LLW) and charges the Nuclear Decommissioning Authority with developing a UK-wide strategy in the case of LLW from nuclear sites. The UK Nuclear Industry LLW Strategy has been developed within the framework of the principles set out in the policy. A key factor in the development of this strategy has been the strategic partnership the NDA shares with the Low Level Waste Repository near Drigg (LLWR), who now have a role in developing strategy as well as delivering an optimised waste management service at the LLWR. The strategy aims to support continued hazard reduction and decommissioning by ensuring uninterrupted capability and capacity for the management and disposal of LLW in the UK. The continued availability of a disposal route for LLW is considered vital by both the nuclear industry and non-nuclear industry low level waste producers. Given that the UK will generate significantly more low level waste (∼ 3.1 million m 3 ) than there is capacity at the LLWR (∼0.75 million m 3 ), developing alternative effective ways to manage LLW is critical. The waste management hierarchy is central to the strategy, which includes strategic goals at all levels of the hierarchy to improve its application across the industry. (authors)

Certification Plan, Radioactive Mixed Waste Hazardous Waste Handling Facility

International Nuclear Information System (INIS)

Albert, R.

1992-01-01

The purpose of this plan is to describe the organization and methodology for the certification of radioactive mixed waste (RMW) handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). RMW is low-level radioactive waste (LLW) or transuranic (TRU) waste that is co-contaminated with dangerous waste as defined in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and the Washington State Dangerous Waste Regulations, 173-303-040 (18). This waste is to be transferred to the Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington. This plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF (Section 4); and a list of the current and planned implementing procedures used in waste certification

Overview of EPA's environmental standards for the land disposal of LLW and NARM waste - 1988

International Nuclear Information System (INIS)

Gruhlke, J.M.; Galpin, F.L.; Holcomb, W.F.

1988-01-01

The Environmental Protection Agency program to develop proposed generally applicable environmental standards for land disposal of low-level radioactive waste (LLW) and certain naturally occurring and accelerator-produced radioactive wastes has been completed. The elements of the proposed standards include the following: (a) exposure limits for predisposal management and storage operations, (b) criteria for other regulatory agencies to follow in specifying wastes that are below regulatory concern; (c) postdisposal exposure limits, (d) groundwater protection requirements, and (e) qualitative implementation requirements. In addition to covering those radioactive wastes subject to the Atomic Energy Act, the Agency also intends to propose a standard to require the disposal of high concentration, naturally occurring and accelerator-produced radioactive materials wastes exceeding 2 nCi/g, excluding a few consumer items, in regulated LLW disposal facilities

Advancing towards commonsense regulation of mixed waste: Regulatory update

International Nuclear Information System (INIS)

Porter, C.L.

1996-01-01

The author previously presented the basis for regulating mixed waste according to the primary hazard (either chemical or radiological) in order to avoid the inefficient practice of open-quotes dual regulationclose quotes of mixed waste. In addition to covering the technical basis, recommendations were made on how to capitalize upon a window of opportunity for implementation of a open-quotes primary hazards approachclose quotes. Some of those recommendations have been pursued and the resulting advances on the regulatory front are exciting. This paper chronicles those pursuits, presents in capsule form the massive amount of data assembled, and summarizes the changing regulatory framework. The data supports the premise that disposal of stabilized mixed waste in a low-level radioactive waste (LLW) disposal facility is protective of human health and the environment. Based on that premise, proposed regulatory changes, if finalized, will eliminate much of the open-quotes dual regulationclose quotes of mixed waste

LLW Notes, Volume 12, Number 3

International Nuclear Information System (INIS)

Norris, C.; Brown, H.; Colsant, J.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-03-01

Contents include articles entitled: California DHS sues US Interior Department to compel land transfer; LLW Forum holds winter meeting; LLW Forum waste information working group meets; LLW Forum regulatory issues discussion group meets; Envirocare investigation transferred to feds; Host state TCC meets in Laughlin, Nevada; BLM to require new permit for California site testing; Federal agencies and committees; Pena sworn in as Energy Secretary, Grumbly departs DOE; U.S. Supreme Court tackles property rights issues; GAO to study DOI's actions; Congress scrutinizes FY '98 budget requests; and Senate committee passes high-level waste bill: Clinton threatens to veto

WRAP low level waste (LLW) glovebox acceptance test report

International Nuclear Information System (INIS)

Leist, K.J.

1998-01-01

In June 28, 1997, the Low Level Waste (LLW) glovebox was tested using glovebox acceptance test procedure 13031A-85. The primary focus of the glovebox acceptance test was to examine control system interlocks, display menus, alarms, and operator messages. Limited mechanical testing involving the drum ports, hoists, drum lifter, compacted drum lifter, drum tipper, transfer car, conveyors, lidder/delidder device and the supercompactor were also conducted. As of November 24, 1997, 2 of the 131 test exceptions that affect the LLW glovebox remain open. These items will be tracked and closed via the WRAP Master Test Exception Database. As part of Test Exception resolution/closure the responsible individual closing the Test Exception performs a retest of the affected item(s) to ensure the identified deficiency is corrected, and, or to test items not previously available to support testing. Test Exceptions are provided as appendices to this report

WRAP low level waste (LLW) glovebox acceptance test report

Energy Technology Data Exchange (ETDEWEB)

Leist, K.J.

1998-02-17

In June 28, 1997, the Low Level Waste (LLW) glovebox was tested using glovebox acceptance test procedure 13031A-85. The primary focus of the glovebox acceptance test was to examine control system interlocks, display menus, alarms, and operator messages. Limited mechanical testing involving the drum ports, hoists, drum lifter, compacted drum lifter, drum tipper, transfer car, conveyors, lidder/delidder device and the supercompactor were also conducted. As of November 24, 1997, 2 of the 131 test exceptions that affect the LLW glovebox remain open. These items will be tracked and closed via the WRAP Master Test Exception Database. As part of Test Exception resolution/closure the responsible individual closing the Test Exception performs a retest of the affected item(s) to ensure the identified deficiency is corrected, and, or to test items not previously available to support testing. Test Exceptions are provided as appendices to this report.

Incineration systems for low level and mixed wastes

International Nuclear Information System (INIS)

Vavruska, J.

1986-01-01

A variety of technologies has emerged for incineration of combustible radioactive, hazardous, and mixed wastes. Evaluation and selection of an incineration system for a particular application from such a large field of options are often confusing. This paper presents several current incineration technologies applicable to Low Level Waste (LLW), hazardous waste, and mixed waste combustion treatment. The major technologies reviewed include controlled-air, rotary kiln, fluidized bed, and liquid injection. Coupled with any incineration technique is the need to select a compatible offgas effluent cleaning system. This paper also reviews the various methods of treating offgas emissions for acid vapor, particulates, organics, and radioactivity. Such effluent control systems include the two general types - wet and dry scrubbing with a closer look at quenching, inertial systems, fabric filtration, gas absorption, adsorption, and various other filtration techniques. Selection criteria for overall waste incineration systems are discussed as they relate to waste characterization

Mixed waste treatment at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Larsen, M.M.; Hunt, L.F.; Sanow, D.J.

1988-01-01

The Idaho Operations Office of the Department of Energy (DOE) made the decision in 1984 to prohibit the disposal of mixed waste (MW) (combustible waste-toxic metal waste) in the Idaho National Engineering Laboratory (INEL) low-level radioactive waste (LLW) disposal facility. As a result of this decision and due to there being no EPA-permitted MW treatment/storage/disposal (T/S/D) facilities, the development of waste treatment methods for MW was initiated and a storage facility was established to store these wastes while awaiting development of treatment systems. This report discusses the treatment systems developed and their status. 3 refs., 2 figs., 1 tab

DOE LLW classification rationale

International Nuclear Information System (INIS)

Flores, A.Y.

1991-01-01

This report was about the rationale which the US Department of Energy had with low-level radioactive waste (LLW) classification. It is based on the Nuclear Regulatory Commission's classification system. DOE site operators met to review the qualifications and characteristics of the classification systems. They evaluated performance objectives, developed waste classification tables, and compiled dose limits on the waste. A goal of the LLW classification system was to allow each disposal site the freedom to develop limits to radionuclide inventories and concentrations according to its own site-specific characteristics. This goal was achieved with the adoption of a performance objectives system based on a performance assessment, with site-specific environmental conditions and engineered disposal systems

Ensuring robust decisions and deployable solutions in UK LLW management

International Nuclear Information System (INIS)

Clark, Matthew

2014-01-01

The Nuclear Decommissioning Authority (NDA) is responsible for the decommissioning and site restoration of civil nuclear liabilities in the UK. Our decommissioning programme will last over 100 years and generate approximately 3.8 million m3 of LLW, three quarters of which will be VLLW. As well as decommissioning sites, our estate includes operations, such as power generation at Wylfa and reprocessing and waste management at Sellafield. As a result we have a clear interest in effective and affordable management of low level waste. This is further enhanced by two important aspects: our role in developing and implementing strategy for the management of nuclear industry LLW in the UK and our ownership of the Low Level Waste Repository, a critical part of the UK's radioactive waste management infrastructure. Disposal capacity at LLWR is a precious resource; recognition of this fact has provided effective leverage to changing the way LLW is managed in the UK. In 2010 we published the UK Nuclear Industry LLW Strategy which comprised three main themes: the waste hierarchy; making the best use of existing LLW management assets; and, the need for new fit-for-purpose waste management routes. In order to preserve disposal capacity at LLWR we wanted to increase choice for organisations that manage LLW. Regulation of the LLW management has also had to keep pace with and enable this change. Increasing choice requires an increased focus on making robust, and not always easy, decisions. In the past, 'LLW' was simply consigned for disposal at LLWR, now LLW managers have to make decisions between clearance, exemption, reuse, recycling, incineration and disposal. Arguably, these decisions become more finely balanced at the lower end of the LLW spectrum. In the UK, a number of tools and sources of support are in place to help with this process, including: the National LLW Programme; good practice guidance (industry led) on assessing Best Available Techniques; and a

Feasibility study on equipment of LLW management business system

International Nuclear Information System (INIS)

Shimizu, Takafumi

2010-01-01

LLW from university and private company has been kept in their own nuclear facilities in Japan. RANDEC has been studying business system for the treatment and conditioning of LLW before disposal. Reference to proven waste treatment process used in Nuclear Power Plant, it was studied that the appropriate treatment process for the LLW from university and private company. The waste will be collected from the university and private company to a central treatment facility. After operations such as unpacking, classification, compression, incineration and others, the waste will be treated to waste form. Most equipment are adopted by the process technology used in Nuclear Power Plant. But some equipment such as measurement of radio activity and solidification of powder need to be studied for the treatment of LLW from university and private company. (author)

Shipment of LLW by intercoastal maritime service

International Nuclear Information System (INIS)

Barbour, D.A.

1985-01-01

Transportation costs are a significant element of total waste disposal costs. In 1982, Nuclear Metals, Inc. (NMI) began a series of tests and investigations to examine the feasibility of using alternative modes for its low-level waste (LLW) shipments. NMI's investigations and experience have identified significant problems in transporting LLW by rail. Intercoastal maritime service, however, has been demonstrated as a safe and cost-effective way of transporting LLW from eastern seaboard generation sites to the repository at Beatty, Nevada. Intuition is an unreliable guide in this area. Waste managers need to periodically assess and compare combined transportation and burial costs for all site options to ensure that disposal operations are conducted in the most rational way

The cost of LLW disposal - Is it sound economics?

International Nuclear Information System (INIS)

Stelluto, Janis D.

1992-01-01

Low-level radioactive waste (LLW) management is a growth industry. Since 1980, when the LLW Policy Act was passed, regional and state LLW bureaucracies have grown, and LLW services and consulting businesses have prospered. Most states and federal agencies have LLW programs with increased regulation of LLW management. Costs of all these programs have soared as facilities for LLW disposal are proposed in sixteen, or more, locations in the country. LLW management costs have also increased as licensees implement comprehensive programs for volume reduction and waste form stabilization. Yet, the total cost of LLW management service is borne by nearly the same universe of payers as in 1980: taxpayers and radioactive materials licensees. Those costs are, in turn, passed on through taxes and consumer costs. Ultimately, everybody pays. Despite this investment, the LLW situation is adrift. New facilities have not been built, and existing facilities are closing or limiting access. LLW management has not advanced to a respected field of engineering and science. Nor does it include exceptional benefit and opportunity to host communities. A new focus is needed to allow an economically sound solution to emerge, one where the supply of LLW management and disposal fits the demand for service. (author)

Environmental assessment for the treatment of Class A low-level radioactive waste and mixed low-level waste generated by the West Valley Demonstration Project

International Nuclear Information System (INIS)

1995-11-01

The U.S. Department of Energy (DOE) is currently evaluating low-level radioactive waste management alternatives at the West Valley Demonstration Project (WVDP) located on the Western New York Nuclear Service Center (WNYNSC) near West Valley, New York. The WVDP's mission is to vitrify high-level radioactive waste resulting from commercial fuel reprocessing operations that took place at the WNYNSC from 1966 to 1972. During the process of high-level waste vitrification, low-level radioactive waste (LLW) and mixed low-level waste (MILLW) will result and must be properly managed. It is estimated that the WVDP's LLW storage facilities will be filled to capacity in 1996. In order to provide sufficient safe storage of LLW until disposal options become available and partially fulfill requirements under the Federal Facilities Compliance Act (FFCA), the DOE is proposing to use U.S. Nuclear Regulatory Commission-licensed and permitted commercial facilities in Oak Ridge, Tennessee; Clive, Utah; and Houston, Texas to treat (volume-reduce) a limited amount of Class A LLW and MLLW generated from the WVDP. Alternatives for ultimate disposal of the West Valley LLW are currently being evaluated in an environmental impact statement. This proposed action is for a limited quantity of waste, over a limited period of time, and for treatment only; this proposal does not include disposal. The proposed action consists of sorting, repacking, and loading waste at the WVDP; transporting the waste for commercial treatment; and returning the residual waste to the WVDP for interim storage. For the purposes of this assessment, environmental impacts were quantified for a five-year operating period (1996 - 2001). Alternatives to the proposed action include no action, construction of additional on-site storage facilities, construction of a treatment facility at the WVDP comparable to commercial treatment, and off-site disposal at a commercial or DOE facility

Mixed waste disposal facility at the Nevada Test Site

International Nuclear Information System (INIS)

Dickman, P.T.; Kendall, E.W.

1987-01-01

In 1984, a law suit brought against DOE resulted in the requirement that DOE be subject to regulation by the state and US Environmental Protection Agency (EPA) for all hazardous wastes, including mixed wastes. Therefore, all DOE facilities generating, storing, treating, or disposing of mixed wastes will be regulated under the Resource Conservation and Recovery Act (RCTA). In FY 1985, DOE Headquarters requested DOE low-level waste (LLW) sites to apply for a RCRA Part B Permit to operate radioactive mixed waste facilities. An application for the Nevada Test Site (NTS) was prepared and submitted to the EPA, Region IX in November 1985 for review and approval. At that time, the state of Nevada had not yet received authorization for hazardous wastes nor had they applied for regulatory authority for mixed wastes. In October 1986, DOE Nevada Operations Office was informed by the Rocky Flats Plant that some past waste shipments to NTS contained trace quantities of hazardous substances. Under Colorado law, these wastes are defined as mixed. A DOE Headquarters task force was convened by the Under Secretary to investigate the situation. The task force concluded that DOE has a high priority need to develop a permitted mixed waste site and that DOE Nevada Operations Office should develop a fast track project to obtain this site and all necessary permits. The status and issues to be resolved on the permit for a mixed waste site are discussed

Mixed incineration of RAIW and liquid scintillator waste after storage for decay

International Nuclear Information System (INIS)

Naba, K.; Nakazato, K.; Kataoka, K.

1993-01-01

Most medical radioactive waste is combustible after radioactive decay. Moreover mixed incineration of LLW with biomedical radioactive waste will lessen radiation exposure to the public. This paper describes the total system flowsheet for the processing of liquid scintillator wastes and radioimmunoassay tube wastes containing iodine 125 (after a two-year storage for decay). The process was tested with a 60 kg/hr capacity incinerator from 1987 to 1991; this has been upgraded to a 150 kg/hr incinerator which is used for nonradioactive biomedical waste incineration as well

Development of a mixed waste management facility at the Nevada Test Site

International Nuclear Information System (INIS)

Dolenc, M.R.; Kendall, E.W.

1989-01-01

The US Department of Energy (DOE) produces some radioactive low-level wastes (LLW) which contain hazardous components. By definition, the management of those mixed wastes (MW) at the Nevada Test Site (NTS) requires compliance with US Environmental Protection Agency (EPA) and state of Nevada regulations for hazardous wastes, and DOE regulations for LLW. Preparations for operation of a separate Mixed Waste Management Unit (MWMU) in the 1990s are underway. The 167-acre MWMU will be a part of the 732-acre Area 5 Radioactive Waste Management Site (RWMS). The MWMU is being developed in response to a DOE Office of Defense Waste and Transporation Management need to provide enhanced capabilities and facilities for safe, secure, and efficient disposal of defense-related MW in accordance with DOE, EPA, and state of Nevada requirements. Planned activities relating to the development of the MWMU include completing National Environmental Policy Act (NEPA) requirements; responding to any notices of deficiencies (NODs) on the NTS Part B Permit application; conducting generator audits as part of the NTS MW certification program; optimizing the design and operation of the vadose zone monitoring system; developing protocols for the sampling and analysis of MW, and facility construction. This paper describes the permitting and regulatory environment, the specific application of the permit process to the NTS, and the phased development of an MWMU at the NTS

LLW disposal, 1996 and beyond, an industry perspective

International Nuclear Information System (INIS)

Genoa, P.H.

1996-01-01

In this article the author reviews what has been done in the past 15 years in terms of opening sites for disposal of low-level radioactive wastes, and what seems to be on the horizon. He reviews process timelines, timelines from regional efforts, and timelines for LLW facilities. The author also looks at what types of changes have been made in the generation, control, and volume of LLW. He examines the pressures which have driven these changes, both from society and from cost control economics. The author tries to look at what government, waste generators, and the waste management industry should do to make progress toward adequate solutions to address the LLW disposal problems

Identification of permit and waste acceptance criteria provisions requiring modification for acceptance of commercial mixed waste

International Nuclear Information System (INIS)

1994-03-01

In October 1990, representatives of States and compact regions requested that the US Department of Energy (DOE) explore an agreement with host States and compact regions under which DOE would accept commercial mixed low-level radioactive waste (LLW) at DOE's own treatment and disposal facilities. A program for DOE management of commercial mixed waste is made potentially more attractive in light of the low commercial mixed waste volumes, high regulatory burdens, public opposition to new disposal sites, and relatively high cost of constructing commercial disposal facilities. Several studies were identified as essential in determining the feasibility of DOE accepting commercial mixed waste for disposal. The purpose of this report is to identify any current or proposed waste acceptance criteria (WAC) or Resource Conservation and Recovery Act (RCRA) provisions that would have to be modified for commercial mixed waste acceptance at specified DOE facilities. Following the introduction, Section 2 of this report (a) provides a background summary of existing and proposed mixed waste disposal facilities at each DOE site, and (b) summarizes the status of any RCRA Part B permit and WAC provisions relating to the disposal of mixed waste, including provisions relating to acceptance of offsite waste. Section 3 provides overall conclusions regarding the current status and permit modifications that must be implemented in order to grant DOE sites authority under their permits to accept commercial mixed waste for disposal. Section 4 contains a list of references

LLW Forum meeting report, May 7--9, 1997

International Nuclear Information System (INIS)

Norris, C.; Brown, H.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-05-01

The Low-Level Radioactive Waste Forum met in Chicago, Illinois, on may 7--9, 1997. Twenty-three Forum Participants, Alternate Forum Participants, and meeting designees representing 20 compacts and states participated. A report on the meeting is given under the following subtitles: New developments in states and compacts; Upgrading an existing disposal facility; Revisions to DOE Order 5820 re DOE waste management; Conference of radiation control program directors: Recent and upcoming activities; National Conference of State Legislatures' (NCSL) low-level radioactive waste working group: Recent and upcoming activities; Executive session; LLW forum business session; Public involvement and risk communication: Success at West Valley, New York; DOE low-level waste management program; impact of the International Atomic Energy Agency's convention on waste; Panel discussion: The environmental justice concept--Past, present and future; New technologies for processing and disposal of LLRW; High-level and low-level radioactive waste: A dialogue on parallels and intersections; Draft agreement re uniform application of manifesting procedures; Regulatory issues focus; LLW forum October 1997 agenda planning; Resolutions; LLW forum regulatory issues discussion group meets; and Attendance

The Hybrid Treatment Process for mixed radioactive and hazardous waste treatment

International Nuclear Information System (INIS)

Ross, W.A.; Kindle, C.H.

1992-06-01

This paper describes a new process for treating mixed hazardous and radioactive waste, commonly called mixed waste. The process is called the Hybrid Treatment Process (HTP), so named because it is built on the 20 years of experience with vitrification of wastes in melters, and the 12 years of experience with treatment of wastes by the in situ vitrification (ISV) process. It also uses techniques from several additional technologies. Mixed wastes are being generated by both the US Department of Energy (DOE) and by commercial sources. The wastes are those that contain both a hazardous waste regulated under the US Environmental Protection Agency's (EPA) Resource, Conservation, and Recovery Act (RCRA) regulations and a radioactive waste with source, special nuclear, or byproduct materials. The dual regulation of the wastes increases the complexity of the treatment, handling, and storage of the waste. The DOE is the largest holder and generator of mixed waste. Its mixed wastes are classified as either high-level, transuranic (TRU), or low-level waste (LLW). High-level mixed wastes will be treated in vitrification plants. Transuranic wastes may be disposed of without treatment by obtaining a no-migration variance from the EPA. Lowlevel wastes, however, will require treatment, but treatment systems with sufficient capacity are not yet available to DOE. Various facilities are being proposed for the treatment of low-level waste. The concept described in this paper represents one option for establishing that treatment capacity

ASSESSING EXPOSURE TO THE PUBLIC FROM LOW LEVEL RADIOACTIVE WASTE (LLW) TRANSPORTATION TO THE NEVADA TEST SITE

International Nuclear Information System (INIS)

Miller, J.J.; Campbell, S.; Church, B.W.; Shafer, D. S.; Gillespie, D.; Sedano, S.; Cebe, J.J.

2003-01-01

The United States (U.S.) Department of Energy (DOE) Nevada Test Site (NTS) is one of two regional sites where low-level radioactive waste (LLW) from approved DOE and U.S. DOD generators across the United States is disposed. In federal fiscal year (FY) 2002, over 57,000 cubic meters of waste was transported to and disposed at the NTS. DOE and U.S. Department of Transportation (DOT) regulations ensure that radiation exposure from truck shipments to members of the public is negligible. Nevertheless, particularly in rural communities along transportation routes in Utah and Nevada, there is perceived risk from members of the public about incremental exposure from LLW trucks, especially when ''Main Street'' and the LLW transportation route are the same. To better quantify the exposure to gamma radiation, a stationary monitoring array of four pressurized ion chambers (PICs) have been set up in a pullout just before LLW trucks reach the entrance to the NTS. The PICs are positioned at a distance of one meter from the sides of the truck trailer and at a height appropriate for the design of the trucks that will be used in FY2003 to haul LLW to the NTS. The use of four PICs (two on each side of the truck) is to minimize and to correct for non-uniformity where radiation levels from waste packages vary from side to side, and from front to back in the truck trailer. The PIC array is being calibrated by collecting readings from each PIC exposed to a known 137Cs source that was positioned at different locations on a flatbed stationed in the PIC array, along with taking secondary readings from other known sources. Continuous data collection using the PICs, with and without a truck in the array, is being used to develop background readings. In addition, acoustic sensors are positioned on each side of the PIC array to record when a large object (presumably a truck) enters the array. In FY2003, PIC surveys from as many incoming LLW trucks as possible will be made and survey data

Nevada test site low-level and mixed waste repository design in the unsaturated zone

International Nuclear Information System (INIS)

Kawamura, T.A.; Warren, D.M.

1989-01-01

The Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS) is used for shallow land disposal of Low-Level Radioactive (LLW) and for retrievable disposal of Mixed Wastes (MW) from various Department of Energy (DOE) facilities. The site is situated in southern Nevada, one of the most arid regions of the United States. Design considerations include vadose zone monitoring in lieu of groundwater monitoring, stringent waste acceptance and packaging criteria, a waste examination and real-time radiography facility, and trench design. 4 refs

Stabilization Using Phosphate Bonded Ceramics. Salt Containing Mixed Waste Treatment. Mixed Waste Focus Area. OST Reference No. 117

International Nuclear Information System (INIS)

1999-01-01

Throughout the Department of Energy (DOE) complex there are large inventories of homogeneous mixed waste solids, such as wastewater treatment residues, fly ashes, and sludges that contain relatively high concentrations (greater than 15% by weight) of salts. The inherent solubility of salts (e.g., nitrates, chlorides, and sulfates) makes traditional treatment of these waste streams difficult, expensive, and challenging. One alternative is low-temperature stabilization by chemically bonded phosphate ceramics (CBPCs). The process involves reacting magnesium oxide with monopotassium phosphate with the salt waste to produce a dense monolith. The ceramic makes a strong environmental barrier, and the metals are converted to insoluble, low-leaching phosphate salts. The process has been tested on a variety of surrogates and actual mixed waste streams, including soils, wastewater, flyashes, and crushed debris. It has also been demonstrated at scales ranging from 5 to 55 gallons. In some applications, the CBPC technology provides higher waste loadings and a more durable salt waste form than the baseline method of cementitious grouting. Waste form test specimens were subjected to a variety of performance tests. Results of waste form performance testing concluded that CBPC forms made with salt wastes meet or exceed both RCRA and recommended Nuclear Regulatory Commission (NRC) low-level waste (LLW) disposal criteria. Application of a polymer coating to the CBPC may decrease the leaching of salt anions, but continued waste form evaluations are needed to fully assess the deteriorating effects of this leaching, if any, over time.

Low-level waste certification plan

International Nuclear Information System (INIS)

Greenhalph, W.O.

1995-01-01

This plan describes the organization and methodology for the certification of solid low-level waste (LLW) and mixed-waste (MW) generated at any of the facilities or major work activities of the Engineered Process Application (EPA) organization. The primary LLW and MW waste generating facility operated by EPA is the 377 Building. This plan does not cover the handling of hazardous or non-regulated waste, though they are mentioned at times for completeness

LLW Notes, Volume 9, Number 6. October 1994

International Nuclear Information System (INIS)

1994-10-01

LLW Notes is distributed to Low-Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum is an association of state and compact representatives appointed by governors and compact commissions, established to facilitate state and compact commission implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW Notes, Volume 9, Number 6. October 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-10-01

LLW Notes is distributed to Low-Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum is an association of state and compact representatives appointed by governors and compact commissions, established to facilitate state and compact commission implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies and other interested parties.

LLW Forum meeting report, October 26--27, 1994

International Nuclear Information System (INIS)

1994-01-01

The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties. This report details activities of the meeting held October 26-27, 1994

LLW Forum meeting report, October 26--27, 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties. This report details activities of the meeting held October 26-27, 1994.

LLW Forum meeting report, February 13--16, 1996

International Nuclear Information System (INIS)

1996-01-01

The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties. This report details activities at the meeting held February 13-16, 1996

Nevada Test Site Waste Acceptance Criteria (NTSWAC)

Energy Technology Data Exchange (ETDEWEB)

NNSA/NSO Waste Management Project

2008-06-01

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.

Nevada Test Site Waste Acceptance Criteria (NTSWAC)

International Nuclear Information System (INIS)

NNSA/NSO Waste Management Project

2008-01-01

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

The Evolution of Low-Level Radioactive Waste (LLW) Disposal Practices at the Savannah River Site Coupled with Vigorous Stakeholder Interaction

International Nuclear Information System (INIS)

Goldston, W. T.; Wilhite, E. L.; Cook, J. R.; Sauls, V. W.

2002-01-01

Low-level radioactive waste (LLW) disposal practices at SRS evolved from trench disposal with little long-term performance basis to disposal in robust concrete vaults, again without modeling long-term performance. Now, based on an assessment of long-term performance of various waste forms and methods of disposal, the LLW disposal program allows for a ''smorgasbord'' of various disposal techniques and waste forms, all modeled to ensure long-term performance is understood. New disposal techniques include components-in-grout, compaction/volume reduction prior to disposal, and trench disposal of extremely low activity waste. Additionally, factoring partition coefficient (Kd) measurements based on waste forms has been factored into performance models. This paper will trace the development of the different disposal methods, and the extensive public communications effort that resulted in endorsement of the changes by the SRS Citizens Advisory Board

LLW Notes, vol. 9, no. 1. February/March 1994

International Nuclear Information System (INIS)

1994-03-01

LLW Notes is published ten times each year and is distributed to Low- Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum is an association of representatives of states and compacts established to facilitate state and compact commission implementation of the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies

Low-level radioactive waste (LLW) management at the Nevada Test Site (NTS)

International Nuclear Information System (INIS)

Becker, B.D.; Gertz, C.P.; Clayton, W.A.; Crowe, B.M.

1998-01-01

In 1978, the Department of Energy, Nevada Operations Office (DOE/NV), established a managed LLW disposal project at the Nevada Test Site (NTS). Two, sites which were already accepting limited amounts of on-site generated waste for disposal and off-site generated Transuranic Waste for interim storage, were selected to house the disposal facilities. In those early days, these sites, located about 15 miles apart, afforded the DOE/NV the opportunity to use at least two technologies to manage its waste cost effectively. The Area 5 Radioactive Waste Management Site (RWMS) uses engineered shallow-land burial cells to dispose packaged waste while the Area 3 RWMS uses subsidence craters formed from underground testing of nuclear weapons for the disposal of packaged and unpackaged bulk waste. The paper describes the technical attributes of both Area 5 and Area 3 facilities, the acceptance process, the disposal processes, and present and future capacities of both sites

Bioprocessing of concentrated mixed hazardous industrial waste

International Nuclear Information System (INIS)

Wolfram, J.H.; Rogers, R.D.; Silver, G.; Attalla, A.; Prisc, M.

1994-01-01

The use of selected microorganisms for the degradation and/or the detoxification of hazardous organic compounds is gaining wide acceptance as an alternative waste treatment technology. This work describes the unique capabilities of an isolated strain of Pseudomonas for metabolizing methylated aromatic compounds. This strain of Pseudomonas putida Idaho is unique in that it can tolerate and grow under a layer of neat p-xylene. A bioprocess has been developed to degrade LLW and mixed wastes containing methylated aromatic compounds, i.e., pseudocumene, toluene and p-xylene. The process is now in the demonstration phase at a DOE facility and has been running for one year. Feed concentrations of 21200 ppm of the toxic organic substrate have been fed to the bioreactor. This report describes the results obtained thus far

Los Alamos controlled air incinerator upgrade for TRU/mixed waste operations

International Nuclear Information System (INIS)

Vavruska, J.S.; Borduin, L.C.; Hutchins, D.A.; Warner, C.L.; Thompson, T.K.

1989-01-01

The Los Alamos Controlled Air Incinerator (CAI) is undergoing a major process upgrade to accept Laboratory-generated transuranic (TRU) and TRU mixed wastes on a production basis. In the interim,prior to the scheduled 1992 operation of a new on-site LLW/mixed waste incinerator, the CAI will also be accepting solid and liquid low-level mixed wastes. This paper describes major modifications that have been made to the process to enhance safety and ensure reliability for long-term, routine waste incineration operations. The regulatory requirements leading to operational status of the system are also briefly described. The CAI was developed in the mid-1970s as a demonstration system for volume reduction of TRU combustible solid wastes. It continues as a successful R and D system well into the 1980s during which incineration tests on a wide variety of radioactive and chemical waste forms were performed. In 1985, a DOE directive required Los Alamos to reduce the volume of its TRU waste prior to ultimate placement in the geological repository at the Waste Isolation Pilot Project (WIPP). With only minor modifications to the original process flowsheet, the Los Alamos CAI was judged capable of conversion to a TRU waste operations mode. 9 refs., 1 fig

SITE GENERATED RADIOLOGICAL WASTE HANDLING SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

S. C. Khamankar

2000-06-20

The Site Generated Radiological Waste Handling System handles radioactive waste products that are generated at the geologic repository operations area. The waste is collected, treated if required, packaged for shipment, and shipped to a disposal site. Waste streams include low-level waste (LLW) in solid and liquid forms, as-well-as mixed waste that contains hazardous and radioactive constituents. Liquid LLW is segregated into two streams, non-recyclable and recyclable. The non-recyclable stream may contain detergents or other non-hazardous cleaning agents and is packaged for shipment. The recyclable stream is treated to recycle a large portion of the water while the remaining concentrated waste is packaged for shipment; this greatly reduces the volume of waste requiring disposal. There will be no liquid LLW discharge. Solid LLW consists of wet solids such as ion exchange resins and filter cartridges, as-well-as dry active waste such as tools, protective clothing, and poly bags. Solids will be sorted, volume reduced, and packaged for shipment. The generation of mixed waste at the Monitored Geologic Repository (MGR) is not planned; however, if it does come into existence, it will be collected and packaged for disposal at its point of occurrence, temporarily staged, then shipped to government-approved off-site facilities for disposal. The Site Generated Radiological Waste Handling System has equipment located in both the Waste Treatment Building (WTB) and in the Waste Handling Building (WHB). All types of liquid and solid LLW are processed in the WTB, while wet solid waste from the Pool Water Treatment and Cooling System is packaged where received in the WHB. There is no installed hardware for mixed waste. The Site Generated Radiological Waste Handling System receives waste from locations where water is used for decontamination functions. In most cases the water is piped back to the WTB for processing. The WTB and WHB provide staging areas for storing and shipping LLW

SITE GENERATED RADIOLOGICAL WASTE HANDLING SYSTEM DESCRIPTION DOCUMENT

International Nuclear Information System (INIS)

S. C. Khamankar

2000-01-01

The Site Generated Radiological Waste Handling System handles radioactive waste products that are generated at the geologic repository operations area. The waste is collected, treated if required, packaged for shipment, and shipped to a disposal site. Waste streams include low-level waste (LLW) in solid and liquid forms, as-well-as mixed waste that contains hazardous and radioactive constituents. Liquid LLW is segregated into two streams, non-recyclable and recyclable. The non-recyclable stream may contain detergents or other non-hazardous cleaning agents and is packaged for shipment. The recyclable stream is treated to recycle a large portion of the water while the remaining concentrated waste is packaged for shipment; this greatly reduces the volume of waste requiring disposal. There will be no liquid LLW discharge. Solid LLW consists of wet solids such as ion exchange resins and filter cartridges, as-well-as dry active waste such as tools, protective clothing, and poly bags. Solids will be sorted, volume reduced, and packaged for shipment. The generation of mixed waste at the Monitored Geologic Repository (MGR) is not planned; however, if it does come into existence, it will be collected and packaged for disposal at its point of occurrence, temporarily staged, then shipped to government-approved off-site facilities for disposal. The Site Generated Radiological Waste Handling System has equipment located in both the Waste Treatment Building (WTB) and in the Waste Handling Building (WHB). All types of liquid and solid LLW are processed in the WTB, while wet solid waste from the Pool Water Treatment and Cooling System is packaged where received in the WHB. There is no installed hardware for mixed waste. The Site Generated Radiological Waste Handling System receives waste from locations where water is used for decontamination functions. In most cases the water is piped back to the WTB for processing. The WTB and WHB provide staging areas for storing and shipping LLW

LLW Notes, vol.9, no. 5. August/September 1994

International Nuclear Information System (INIS)

1994-09-01

LLW Notes is distributed to Low-Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum is an association of state and compact representatives appointed by governors and compact commissions, established to facilitate state and compact commission implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW Notes, vol.9, no. 5. August/September 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-09-01

LLW Notes is distributed to Low-Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum is an association of state and compact representatives appointed by governors and compact commissions, established to facilitate state and compact commission implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies and other interested parties.

LLW Forum meeting report, January 31--February 3, 1995

International Nuclear Information System (INIS)

1995-01-01

The Low-Level Radioactive Waste Forum (LLW) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties. This report details activities of the meeting held January 31-February 3, 1995

LLW Forum meeting report, January 31--February 3, 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-31

The Low-Level Radioactive Waste Forum (LLW) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties. This report details activities of the meeting held January 31-February 3, 1995.

Removal of radioactive caesium from low level radioactive waste (LLW) streams using cobalt ferrocyanide impregnated organic anion exchanger

Energy Technology Data Exchange (ETDEWEB)

Valsala, T.P., E-mail: tpvalsala@yahoo.co.in [Waste Management Division, Bhabha Atomic Research Centre, Trombay 400 085 (India); Roy, S.C. [PREFRE Division, Bhabha Atomic Research Centre, Tarapur 401 502 (India); Shah, J.G. [Back End Technology Division, Bhabha Atomic Research Centre, Trombay 400 085 (India); Gabriel, J.; Raj, Kanwar [Waste Management Division, Bhabha Atomic Research Centre, Trombay 400 085 (India); Venugopal, V. [Radiochemistry Division, Bhabha Atomic Research Centre, Trombay 400 085 (India)

2009-07-30

The volumes of low level waste (LLW) generated during the operation of nuclear reactor are very high and require a concentration step before suitable matrix fixation. The volume reduction (concentration) is achieved either by co-precipitating technique or by the use of highly selective sorbents and ion exchange materials. The present study details the preparation of cobalt ferrocyanide impregnated into anion exchange resin and its evaluation with respect to removal of Cs in LLW streams both in column mode and batch mode operations. The Kd values of the prepared exchanger materials were found to be very good in actual reactor LLW solutions also. It was observed that the exchanger performed very well in the pH range of 3-9. A batch size of 6 g l{sup -1} of the exchanger was enough to give satisfactory decontamination for Cs in actual reactor LLW streams. The lab scale and pilot plant scale performance of the exchanger material in both batch mode and column mode operations was very good.

LLW Notes, volume 9, No. 7. November and December 1994

International Nuclear Information System (INIS)

1994-12-01

LLW Notes is distributed to Low-Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum is an association of state and compact representatives appointed by governors and compact commissions, established to facilitate state and compact commission implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW Notes, volume 9, No. 7. November and December 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-01

LLW Notes is distributed to Low-Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum is an association of state and compact representatives appointed by governors and compact commissions, established to facilitate state and compact commission implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies and other interested parties.

Comparison of modified sulfur cement and hydraulic cement for encapsulation of radioactive and mixed wastes

International Nuclear Information System (INIS)

Kalb, P.D.; Heiser, J.H. III; Colombo, P.

1990-01-01

The majority of solidification/stabilization systems for low-level radioactive waste (LLW) and mixed waste, both in the commercial sector and at Department of Energy (DOE) facilities, utilize hydraulic cement (such as portland cement) to encapsulate waste materials and yield a monolithic solid waste form for disposal. Because hydraulic cement requires a chemical hydration reaction for setting and hardening, it is subject to potential interactions between elements in the waste and binder that can retard or prevent solidification. A new and innovative process utilizing modified sulfur cement developed by the US Bureau of Mines has been applied at Brookhaven National Laboratory (BNL) for the encapsulation of many of these problem wastes. Modified sulfur cement is a thermoplastic material, and as such, it can be heated above its melting point, combined with dry waste products to form a homogeneous mixture, and cooled to form a monolithic solid product. Under sponsorship of the DOE, research and development efforts at BNL have successfully applied the modified sulfur cement process for treatment of a range of LLWs including sodium sulfate salts, boric acid salts, and incinerator bottom ash and for mixed waste contaminated incinerator fly ash. Process development studies were conducted to determine optimal waste loadings for each waste type. Property evaluation studies were conducted to test waste form behavior under disposal conditions by applying relevant performance testing criteria established by the Nuclear Regulatory Commission (for LLW) and the Environmental Protection Agency (for hazardous wastes). Based on both processing and performance considerations, significantly greater waste loadings were achieved using modified sulfur cement when compared with hydraulic cement. Technology demonstration of the modified sulfur cement encapsulation system using production-scale equipment is scheduled for FY 1991

Regionalization as a strategy for management of low-level and mixed wastes in the DOE system

International Nuclear Information System (INIS)

Bradford, J.D.; Garcia, E.C.; Gillins, R.L.

1988-01-01

The Department of Energy has been routinely performing low-level waste volume reduction and/or stabilization treatment at various sites for some time. In general, treatment is performed on waste generated onsite. Disposal is also usually performed onsite since most DOE sites have their own LLW disposal facilities. The DOE initiated studies to evaluate strategies for treatment, storage, and disposal of hazardous and mixed wastes covered in the Resource Conservation and Recovery Act (RCRA) and to ensure that DOE sites are in compliance with RCRA. These studies recommend regionalization as the most cost-effective solution to the treatment and disposal of hazardous and mixed wastes. The DOE's Defense Low-Level Waste Management Program conducted an additional survey of DOE sites to evaluate the status of one specific treatment method, incineration, at these sites. This study included facilities currently in use or intended for treatment of low-level and mixed wastes. A summary of the findings is presented in this paper

Management challenges in remediating a mixed waste site at the Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Riddle, S.P.; Wilson, R.C.; Branscom, K.S.

1992-07-01

Martin Marietta Energy Systems, Inc., manages the Oak Ridge National Laboratory (ORNL) for the US Department of Energy (DOE). Since ORNL's beginning in the 1940's, a variety of solid and liquid low-level radioactive waste (LLW), hazardous waste, and mixed waste has been generated. The solid wastes have been disposed of on site, primarily in shallow trenches called solid waste storage areas (SWSAs). SWSA 6, opened in 1969, is the only operational disposal site at ORNL for solid LLW. In 1984, SWSA 6 was closed for three months when it was discovered that wastes regulated by the Resource Conservation and Recovery Act (RCRA) were being inadvertently disposed of there. SWSA 6 was then added to ORNL's Part A RCRA permit, administrative controls were modified to exclude RCRA regulated wastes from being disposed of at SWSA 6, and a RCRA closure plan was prepared. This paper describes the regulatory challenges of integrating RCRA,- the Comprehensive Environmental Response, Compensation, and Liability Act; and the National Environmental Policy Act into a cohesive remediation strategy while managing the project with multiple DOE contractors and integrating the regulatory approval cycle with the DOE budget cycle. The paper does not dwell on the recommended alternative but presents instead a case study of how some difficult challenges, unique to DOE and other federal facilities, were handled

Preliminary Disposal Analysis for Selected Accelerator Production of Tritium Waste Streams

International Nuclear Information System (INIS)

Ades, M.J.; England, J.L.

1998-06-01

A preliminary analysis was performed for two selected Accelerator Production of Tritium (APT) generated mixed and low-level waste streams to determine if one mixed low-level waste (MLLW) stream that includes the Mixed Waste Lead (MWL) can be disposed of at the Nevada Test Site (NTS) and at the Hanford Site and if one low-level radioactive waste (LLW) stream, that includes the Tungsten waste stream (TWS) generated by the Tungsten Neutron Source modules and used in the Target/Blanket cavity vessel, can be disposed of in the LLW Vaults at the Savannah River Plant (SRP). The preliminary disposal analysis that the radionuclide concentrations of the two selected APT waste streams are not in full compliance with the Waste Acceptance Criteria (WAC) and the Performance Assessment (PA) radionuclide limits of the disposal sites considered

Comments on EPA's LLW preproposal

International Nuclear Information System (INIS)

Littleton, B.K.; Weinstock, L.

1995-01-01

The Environmental Protection Agency (EPA) is currently developing standards for the management, storage, and disposal of Low-Level Radioactive Waste (LLW). The Atomic Energy Act delegated EPA, among other provisions, the authority to establish generally applicable standards for the disposal of radioactive waste to ensure that the public and the environment are adequately protected from potential radiation impacts. As an initial effort to open communications on a standard for LLW, the Agency developed a preproposal draft (Preproposal Draft of 40 CFR Part 193 - 30 Nov 94) and circulated it to interested parties for review and comment. The extended comment period ended April 12, 1995. A summary of the comments received and analyzed to date follows. After all comments have been analyzed, the rule will undergo an Agency clearance process and be sent to the Office of Management and Budget for review. After that review, the formal process of publication of the proposed rule in the Federal Register and the formal public comment period will begin

Development of the advanced package system for miscellaneous LLW

International Nuclear Information System (INIS)

Miyamoto, K.

1991-01-01

Miscellaneous LLW (low-level radioactive miscellaneous solid wastes) such as parts of machines, pieces of piping, HEPA filter, incineration ashes from nuclear power plants will be disposed in shallow land after stuffing into 200 liter steel drums. The package system of these miscellaneous LLW is required to contain such radionuclides as 14 C, 137 Cs and etc. for a few hundred years. The advanced package system for miscellaneous LLW has been developed. This package system is composed of steel drums with resin mortar inner liner and non shrinkage fills with high flowability. Resin mortar liners have stronger water permeability resistance and higher compressive strength than other cement mortars. Strong water permeability resistance of resin mortar liners prevent underground water from infiltration into fills and solid wastes. On the other hand, as the high flowabilities and non shrinkage of this fills give very low gross void fraction of the package system and have strong adsorption ability of radionuclides. In addition, steel drums with resin mortar inner liners have merits in their high density, uniformity and simplicity in manufacturing. Consequently, this package system is promising candidate barrier for the containment of radionuclides from miscellaneous LLW. (J.P.N.)

Facility status and progress of the INEL's WERF MLLW and LLW incinerator

International Nuclear Information System (INIS)

Conley, D.; Corrigan, S.

1996-01-01

The Idaho National Engineering Laboratory's (INEL) Waste Experimental Reduction Facility (WERF) incinerator began processing beta/gamma- emitting low-level waste (LLW) in September 1984. A Resource Conservation and Recovery Act (RCRA) trial burn for the WERF incinerator was conducted in 1986, and in 1989 WERF began processing (hazardous and low-level radioactive) waste known as mixed low-level waste (MLLW). On February 14, 1991 WERF operations were suspended to improve operating procedures and configuration management. On July 12, 1995, WERF initiated incineration of LLW; and on September 20, 1995 WERF resumed its primary mission of incinerating MLLW. MLLW incineration is proceeding under RCRA interim status. State of Idaho issuance of the Part B permit is one of the State's highest permitting priorities. The State of Idaho's Division of Environmental Quality is reviewing the permit application along with a revised trial burn plan that was also submitted with the application. The trial burn has been proposed to be performed in 1996 to demonstrate compliance with the current incinerator guidance. This paper describes the experiences and problems associated with WERF's operations, incineration of MLLW, and the RCRA Part B Permit Application. Some of the challenges that have been overcome include waste characterization, waste repackaging, repackaged waste storage, and implementation of RCRA interim status requirements. A number of challenges remain. They include revision of the RCRA Part B Permit Application and the Trial Burn Plan in response to comments from the state permit application reviewers as well as facility and equipment upgrades required to meet RCRA Permitted Status

Verifying generator waste certification: NTS waste characterization QA requirements

International Nuclear Information System (INIS)

Williams, R.E.; Brich, R.F.

1988-01-01

Waste management activities managed by the US Department of Energy (DOE) at the Nevada Test Site (NTS) include the disposal of low-level wastes (LLW) and mixed waste (MW), waste which is both radioactive and hazardous. A majority of the packaged LLW is received from offsite DOE generators. Interim status for receipt of MW at the NTS Area 5 Radioactive Waste Management Site (RWMS) was received from the state of Nevada in 1987. The RWMS Mixed Waste Management Facility (MWMF) is expected to be operational in 1988 for approved DOE MW generators. The Nevada Test Site Defense Waste Acceptance Criteria and Certification Requirements (NVO-185, Revision 5) delineates waste acceptance criteria for waste disposal at the NTS. Regulation of the hazardous component of mixed waste requires the implementation of US Environmental Protection Agency (EPA) requirements pursuant to the Resource Conservation and Recovery Act (RCRA). Waste generators must implement a waste certification program to provide assurance that the disposal site waste acceptance criteria are met. The DOE/Nevada Operations Office (NV) developed guidance for generator waste certification program plans. Periodic technical audits are conducted by DOE/NV to assess performance of the waste certification programs. The audit scope is patterned from the waste certification program plan guidance as it integrates and provides a common format for the applicable criteria. The criteria focus on items and activities critical to processing, characterizing, packaging, certifying, and shipping waste

Economy may be harmed by lack of LLW disposal

International Nuclear Information System (INIS)

Anon.

1994-01-01

A study released by Organizations United for Responsible Low-Level Radioactive Waste Solutions warns that the substantial benefits of using radioactive materials are threatened by the lack of a low-level waste (LLW) disposal facility. The main point of the study is the threat to the American economy posed by insufficient facilities for disposal of the 1.7 billion ft 3 of LLW produced by the use of radioactive materials every year only 34.8 percent of which comes from nuclear power plants. open-quotes Thirty years of experience have provided the technical knowledge to design waste disposal facilities that protect the public and environment. But an impending lack of adequate disposal facilities jeopardizes our continued use of radioactive materials,close quotes according to the study

Intruder scenarios for site-specific waste classification

International Nuclear Information System (INIS)

Kennedy, W.E. Jr.

1988-01-01

The US Department of Energy (DOE) is currently revising its low-level radioactive waste (LLW) management requirements and guidelines for waste generated at its facilities that support defense missions. Specifically, draft DOE 5820.2A, Chapter 3, describes the purpose, policy, and requirements necessary for the management of defense LLW. The draft DOE policy calls for DOE LLW operations to be managed to protect the health and safety of the public, preserve the environment, and ensure that no remedial action will be necessary after termination of operations. The requirements and guidelines apply to radioactive wastes but are also intended to apply to mixed hazardous and radioactive wastes as defined in draft DOE 5400.5, Hazardous and Radioactive Mixed Waste. The basic approach used by DOE is to establish overall performance objectives in terms of ground-water protection and public radiation dose limits and to require site-specific performance assessments to determine compliance. As a result of these performance assessments, each site shall develop waste acceptance criteria that define the allowable quantities and concentrations of specific radioisotopes. Additional limitations on waste disposal design, waste form, and waste treatment shall also be developed on a site-specific basis. As a key step in the site-specific performance assessments, an evaluation must be conducted of potential radiation doses to intruders who may inadvertently move onto a closed DOE LLW disposal site after loss of institutional controls must be conducted. This paper describes the types of intruder scenarios that should be considered when performing this step of the site-specific performance assessment

Current status of low-level-waste-segregation technology

International Nuclear Information System (INIS)

Clark, D.E.; Colombo, P.; Sailor, V.L.

1982-01-01

The adoption of improved waste segregation practices by waste generators and burial sites will result in the improved disposal of low-level wastes (LLW) in the future. Many of the problems connected with this disposal mode are directly attributable to or aggravated by the indiscriminate mixing of various waste types in burial trenches. Thus, subsidence effects, contact with ground fluids, movement of radioactivity in the vapor phase, migration of radionuclides due to the presence of chelating agents or products of biological degradation, deleterious chemical reactions, and other problems have occurred. Regulations are currently being promulgated which will require waste segregation to a high degree at LLW burial sites. The state-of-the-art of LLW segregation technology and current practices in the USA have been surveyed at representative facilities. Favorable experience has been reported at various sites following the application of segregation controls. This paper reports on the state-of-the-art survey and addresses current and projected LLW segregation practices and their relationship to other waste management activities

DBMS: a tool for managing LLW data

International Nuclear Information System (INIS)

Vlajcic, P.

1984-01-01

As part of the DOE's National Low-Level Radioactive Waste Management Program, a Data Base Management System (DBMS) has been developed by EG and G Idaho, lead contractor for the national LLW management program, in cooperation with the DOE and the Southern States Energy Board, a regional research group sponsored by 17 states. Basically, DBMS offers states free use of a powerful central computer (located in Idaho) for the storage, processing, and retrieval of LLW data, and the capability to forecast their handling, treatment, transport, and disposal needs

The Yami's opposition to the Lanyu LLW storage installation

International Nuclear Information System (INIS)

Li, K.K.; Chang, S.Y.

1993-01-01

Since 1982, the solidified low-level radioactive wastes (LLW) in Taiwan, regardless of the origins, have been sent to Lanyu for interim storage. Lanyu is a small island located 80 kilometers southeast of Taiwan. Its unique Polynesian cultural characteristics make it an attractive tourist spot. Dissatisfaction of being the commonly neglected powerless minority, in addition to the political claims from the outside environmental activists made the majority of the Lanyu residents oppose the operation of the storage facility. Approximately 80,000 drums of these wastes have been sent to Lanyu. Although the radiological monitoring results demonstrated that the current operation causes negligible impact on the environment. Accounting for the fast changing social and political situations in Taiwan today, without a good public acceptance program for both sides, the continuous operation of the Lanyu LLW storage facility until the year 2002, at which time the LLW disposal facility will be commissioned, could be in limbo

'Strategy is a commodity, implementation is an art' - 2 years of implementation of the UK national LLW strategy

International Nuclear Information System (INIS)

Cassidy, Helen; Rossiter, David

2013-01-01

The Low Level Waste Repository (LLWR) is the primary facility for disposal of Low Level Waste (LLW) in the United Kingdom (UK), serving the UK nuclear industry and a diverse range of other sectors. Management of LLW in the UK historically was dominated by disposal to the LLWR. The value of the LLWR as a national asset was recognised by the 2007 UK Governmental Policy on management of solid LLW. At this time, analysis of the projected future demand for disposal at LLWR against facility capacity was undertaken identifying a credible risk that the capacity of LLWR would be insufficient to meet future demand if existing waste management practices were perpetuated. To mitigate this risk a National Strategy for the management of LLW in the UK was developed by the Nuclear Decommissioning Authority (NDA), partnered with LLW Repository Ltd. (the organisation established in 2008 to manage the LLWR on behalf of NDA). This strategy was published in 2010 and identified three mechanisms for protection of the capacity of LLWR - application of the Waste Hierarchy by waste producers; optimised use of existing assets for LLW management; and opening of new waste treatment and disposal routes to enable diversion of waste away from the LLWR. (authors)

LLW Notes: Volume 10, Number 7

International Nuclear Information System (INIS)

Norris, C.

1995-10-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW notes: Volume 10, Number 5

International Nuclear Information System (INIS)

1995-07-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW Notes: Volume 10, Number 3

International Nuclear Information System (INIS)

1995-04-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW Notes: Volume 10, Number 4

International Nuclear Information System (INIS)

1995-06-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW Notes: Volume 10, Number 8

International Nuclear Information System (INIS)

Norris, C.

1995-01-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW notes: Volume 10, Number 6

International Nuclear Information System (INIS)

Norris, C.

1995-09-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW Notes: Volume 10, Number 7

Energy Technology Data Exchange (ETDEWEB)

Norris, C. [ed.] [Afton Associates, Inc., Washington, DC (United States)

1995-10-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

LLW notes: Volume 10, Number 5

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

LLW Notes: Volume 10, Number 4

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

LLW notes: Volume 10, Number 6

Energy Technology Data Exchange (ETDEWEB)

Norris, C. [ed.] [Afton Associates, Inc., Washington, DC (United States)

1995-09-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

Inventory and characteristics of current and projected low-level radioactive materials and waste in the United States

International Nuclear Information System (INIS)

Bisaria, A.; Bugos, R.G.; Pope, R.B.; Salmon, R.; Storch, S.N.; Lester, P.B.

1994-01-01

The Integrated Data Base (IDB), under US Department of Energy (DOE) funding and guidance, provides an annual update of compiled data on current and projected inventories and characteristics of DOE and commercially owned radioactive wastes. The data base addresses also the inventories of DOE and commercial spent fuel. These data are derived from reliable information from government sources, open literature, technical reports, and direct contacts. The radioactive materials considered are spent nuclear fuel, high-level waste (HLW), transuranic (TRU) waste, low-level waste (LLW), commercial uranium mill tailings, environmental restoration wastes, and mixed-LLW. This paper primarily focuses on LLW inventory and characterization

Test Plan: Phase 1, Hanford LLW melter tests, GTS Duratek, Inc

International Nuclear Information System (INIS)

Eaton, W.C.

1995-01-01

This document provides a test plan for the conduct of vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. The vendor providing this test plan and conducting the work detailed within it [one of seven selected for glass melter testing under Purchase Order MMI-SVV-384215] is GTS Duratek, Inc., Columbia, Maryland. The GTS Duratek project manager for this work is J. Ruller. This test plan is for Phase I activities described in the above Purchase Order. Test conduct includes melting of glass with Hanford LLW Double-Shell Slurry Feed waste simulant in a DuraMelter trademark vitrification system

Environmental assessment for the Radioactive and Mixed Waste Management Facility: Sandia National Laboratories/New Mexico

International Nuclear Information System (INIS)

1993-06-01

The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-0466) under the National Environmental Policy Act (NEPA) of 1969 for the proposed completion of construction and subsequent operation of a central Radioactive and Mixed Waste Management Facility (RMWMF), in the southeastern portion of Technical Area III at Sandia National Laboratory, Albuquerque (SNLA). The RMWMF is designed to receive, store, characterize, conduct limited bench-scale treatment of, repackage, and certify low-level waste (LLW) and mixed waste (MW) (as necessary) for shipment to an offsite disposal or treatment facility. The RMWMF was partially constructed in 1989. Due to changing regulatory requirements, planned facility upgrades would be undertaken as part of the proposed action. These upgrades would include paving of road surfaces and work areas, installation of pumping equipment and lines for surface impoundment, and design and construction of air locks and truck decontamination and water treatment systems. The proposed action also includes an adjacent corrosive and reactive metals storage area, and associated roads and paving. LLW and MW generated at SNLA would be transported from the technical areas to the RMWMF in containers approved by the Department of Transportation. The RMWMF would not handle nonradioactive hazardous waste. Based on the analysis in the EA, the proposed completion of construction and operation of the RMWMF does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of NEPA. Therefore, preparation of an environmental impact statement for the proposed action is not required

Determination of a radioactive waste classification system

Energy Technology Data Exchange (ETDEWEB)

Cohen, J.J.; King, W.C.

1978-03-01

Several classification systems for radioactive wastes are reviewed and a system is developed that provides guidance on disposition of the waste. The system has three classes: high-level waste (HLW), which requires complete isolation from the biosphere for extended time periods; low-level waste (LLW), which requires containment for shorter periods; and innocuous waste (essentially nonradioactive), which may be disposed of by conventional means. The LLW/innocuous waste interface was not defined in this study. Reasonably conservative analytical scenarios were used to calculate that HLW/LLW interface level which would ensure compliance with the radiological exposure guidelines of 0.5 rem/y maximum exposure for a few isolated individuals and 0.005 rem/y for large population groups. The recommended HLW/LLW interface level for /sup 239/Pu or mixed transuranic waste is 1.0 ..mu..Ci/cm/sup 3/ of waste. Levels for other radionuclides are based upon a risk equivalent to this level. A cost-benefit analysis in accordance with as low as reasonably achievable (ALARA) and National Environmental Protection Act (NEPA) guidance indicates that further reduction of this HLW/LLL interface level would entail marginal costs greater than $10/sup 8/ per man-rem of dose avoided. The environmental effects considered were limited to those involving human exposure to radioactivity.

Determination of a radioactive waste classification system

International Nuclear Information System (INIS)

Cohen, J.J.; King, W.C.

1978-03-01

Several classification systems for radioactive wastes are reviewed and a system is developed that provides guidance on disposition of the waste. The system has three classes: high-level waste (HLW), which requires complete isolation from the biosphere for extended time periods; low-level waste (LLW), which requires containment for shorter periods; and innocuous waste (essentially nonradioactive), which may be disposed of by conventional means. The LLW/innocuous waste interface was not defined in this study. Reasonably conservative analytical scenarios were used to calculate that HLW/LLW interface level which would ensure compliance with the radiological exposure guidelines of 0.5 rem/y maximum exposure for a few isolated individuals and 0.005 rem/y for large population groups. The recommended HLW/LLW interface level for 239 Pu or mixed transuranic waste is 1.0 μCi/cm 3 of waste. Levels for other radionuclides are based upon a risk equivalent to this level. A cost-benefit analysis in accordance with as low as reasonably achievable (ALARA) and National Environmental Protection Act (NEPA) guidance indicates that further reduction of this HLW/LLL interface level would entail marginal costs greater than $10 8 per man-rem of dose avoided. The environmental effects considered were limited to those involving human exposure to radioactivity

Progress on management business system of LLW generated from research and industrial nuclear facilities

International Nuclear Information System (INIS)

Izumida, Tatsuo

2014-01-01

RANDEC has been studying a management business system of LLW (Low Level Waste) generated from research and industrial facilities since 2008. To examine economical problems, the income and expenditure of LLW treatment business was simulated. As a result, raising method of the funds which is required in preparatory stage of LLW treatment business is an obvious issue to carry out as public utility works. (author)

Models and criteria for LLW disposal performance

International Nuclear Information System (INIS)

Smith, C.F.; Cohen, J.J.

1980-12-01

A primary objective of the Low Level Waste (LLW) Management Program is to assure that public health is protected. Predictive modeling, to some extent, will play a role in meeting this objective. This paper considers the requirements and limitations of predictive modeling in providing useful inputs to waste mangement decision making. In addition, criteria development needs and the relation between criteria and models are discussed

Models and criteria for LLW disposal performance

International Nuclear Information System (INIS)

Smith, C.F.; Cohen, J.J.

1980-01-01

A primary objective of the Low Level Waste (LLW) Management Program is to assure that public health is protected. Predictive modeling, to some extent, will play a role in meeting this objective. This paper considers the requirements and limitations of predictive modeling in providing useful inputs to waste management decision making. In addition, criteria development needs and the relation between criteria and models are discussed

Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics. Revision 1

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

The Department of Energy`s (DOE`s) planning for the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of the waste. This report estimates volumes, radionuclide activities, and waste forms of GTCC LLW to the year 2035. It groups the waste into four categories, representative of the type of generator or holder of the waste: Nuclear Utilities, Sealed Sources, DOE-Held, and Other Generator. GTCC LLW includes activated metals (activation hardware from reactor operation and decommissioning), process wastes (i.e., resins, filters, etc.), sealed sources, and other wastes routinely generated by users of radioactive material. Estimates reflect the possible effect that packaging and concentration averaging may have on the total volume of GTCC LLW. Possible GTCC mixed LLW is also addressed. Nuclear utilities will probably generate the largest future volume of GTCC LLW with 65--83% of the total volume. The other generators will generate 17--23% of the waste volume, while GTCC sealed sources are expected to contribute 1--12%. A legal review of DOE`s obligations indicates that the current DOE-Held wastes described in this report will not require management as GTCC LLW because of the contractual circumstances under which they were accepted for storage. This report concludes that the volume of GTCC LLW should not pose a significant management problem from a scientific or technical standpoint. The projected volume is small enough to indicate that a dedicated GTCC LLW disposal facility may not be justified. Instead, co-disposal with other waste types is being considered as an option.

Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics. Revision 1

International Nuclear Information System (INIS)

1994-09-01

The Department of Energy's (DOE's) planning for the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of the waste. This report estimates volumes, radionuclide activities, and waste forms of GTCC LLW to the year 2035. It groups the waste into four categories, representative of the type of generator or holder of the waste: Nuclear Utilities, Sealed Sources, DOE-Held, and Other Generator. GTCC LLW includes activated metals (activation hardware from reactor operation and decommissioning), process wastes (i.e., resins, filters, etc.), sealed sources, and other wastes routinely generated by users of radioactive material. Estimates reflect the possible effect that packaging and concentration averaging may have on the total volume of GTCC LLW. Possible GTCC mixed LLW is also addressed. Nuclear utilities will probably generate the largest future volume of GTCC LLW with 65--83% of the total volume. The other generators will generate 17--23% of the waste volume, while GTCC sealed sources are expected to contribute 1--12%. A legal review of DOE's obligations indicates that the current DOE-Held wastes described in this report will not require management as GTCC LLW because of the contractual circumstances under which they were accepted for storage. This report concludes that the volume of GTCC LLW should not pose a significant management problem from a scientific or technical standpoint. The projected volume is small enough to indicate that a dedicated GTCC LLW disposal facility may not be justified. Instead, co-disposal with other waste types is being considered as an option

How a developing country is facing LLW disposal problem

International Nuclear Information System (INIS)

Huang, C.C.; Shao, Y.T.; Tsai, C.M.

1993-01-01

Taiwan is a small island which measures about 36,000 square kilometers with over 70% mountainous area. Today over 90% of low-level radioactive waste (LLW) is produced from six nuclear power units operated by the Taiwan Power Company (Taipower or TPC). The rest of the country's LLW is produced from medical, agricultural, industrial, educational and research programs. Due to the fact that over 90% of Taiwan's LLW is produced by Taipower, Taipower was designated by the Government to dispose of LLW for entire country. This paper will focus on the planning and implementation of the first phase. Through area screening and potential site evaluation, candidate sites will be selected based on currently available information and sites investigation. At the same time, the disposal methods will be evaluated in terms of safety, cost, and Taiwan's generic conditions of climate, geology, and topography. The conceptual design of the disposal method(s) will then be developed. Also, during site investigation, preliminary designs will be made

Waste inspection tomography (WIT)

Energy Technology Data Exchange (ETDEWEB)

Bernardi, R.T. [Bio-Imaging Research, Inc., Lincolnshire, IL (United States)

1995-10-01

Waste Inspection Tomography (WIT) provides mobile semi-trailer mounted nondestructive examination (NDE) and assay (NDA) for nuclear waste drum characterization. WIT uses various computed tomography (CT) methods for both NDE and NDA of nuclear waste drums. Low level waste (LLW), transuranic (TRU), and mixed radioactive waste can be inspected and characterized without opening the drums. With externally transmitted x-ray NDE techniques, WIT has the ability to identify high density waste materials like heavy metals, define drum contents in two- and three-dimensional space, quantify free liquid volumes through density and x-ray attenuation coefficient discrimination, and measure drum wall thickness. With waste emitting gamma-ray NDA techniques, WIT can locate gamma emitting radioactive sources in two- and three-dimensional space, identify gamma emitting, isotopic species, identify the external activity levels of emitting gamma-ray sources, correct for waste matrix attenuation, provide internal activity approximations, and provide the data needed for waste classification as LLW or TRU.

Waste inspection tomography (WIT)

International Nuclear Information System (INIS)

Bernardi, R.T.

1995-01-01

Waste Inspection Tomography (WIT) provides mobile semi-trailer mounted nondestructive examination (NDE) and assay (NDA) for nuclear waste drum characterization. WIT uses various computed tomography (CT) methods for both NDE and NDA of nuclear waste drums. Low level waste (LLW), transuranic (TRU), and mixed radioactive waste can be inspected and characterized without opening the drums. With externally transmitted x-ray NDE techniques, WIT has the ability to identify high density waste materials like heavy metals, define drum contents in two- and three-dimensional space, quantify free liquid volumes through density and x-ray attenuation coefficient discrimination, and measure drum wall thickness. With waste emitting gamma-ray NDA techniques, WIT can locate gamma emitting radioactive sources in two- and three-dimensional space, identify gamma emitting, isotopic species, identify the external activity levels of emitting gamma-ray sources, correct for waste matrix attenuation, provide internal activity approximations, and provide the data needed for waste classification as LLW or TRU

Waste management facilities cost information for transportation of radioactive and hazardous materials

International Nuclear Information System (INIS)

Feizollahi, F.; Shropshire, D.; Burton, D.

1995-06-01

This report contains cost information on the U.S. Department of Energy (DOE) Complex waste streams that will be addressed by DOE in the programmatic environmental impact statement (PEIS) project. It describes the results of the task commissioned by DOE to develop cost information for transportation of radioactive and hazardous waste. It contains transportation costs for most types of DOE waste streams: low-level waste (LLW), mixed low-level waste (MLLW), alpha LLW and alpha MLLW, Greater-Than-Class C (GTCC) LLW and DOE equivalent waste, transuranic (TRU) waste, spent nuclear fuel (SNF), and hazardous waste. Unit rates for transportation of contact-handled ( 200 mrem/hr contact dose) radioactive waste are estimated. Land transportation of radioactive and hazardous waste is subject to regulations promulgated by DOE, the U.S. Department of Transportation (DOT), the U.S. Nuclear Regulatory Commission (NRC), and state and local agencies. The cost estimates in this report assume compliance with applicable regulations

Waste management facilities cost information for transportation of radioactive and hazardous materials

Energy Technology Data Exchange (ETDEWEB)

Feizollahi, F.; Shropshire, D.; Burton, D.

1995-06-01

This report contains cost information on the U.S. Department of Energy (DOE) Complex waste streams that will be addressed by DOE in the programmatic environmental impact statement (PEIS) project. It describes the results of the task commissioned by DOE to develop cost information for transportation of radioactive and hazardous waste. It contains transportation costs for most types of DOE waste streams: low-level waste (LLW), mixed low-level waste (MLLW), alpha LLW and alpha MLLW, Greater-Than-Class C (GTCC) LLW and DOE equivalent waste, transuranic (TRU) waste, spent nuclear fuel (SNF), and hazardous waste. Unit rates for transportation of contact-handled (<200 mrem/hr contact dose) and remote-handled (>200 mrem/hr contact dose) radioactive waste are estimated. Land transportation of radioactive and hazardous waste is subject to regulations promulgated by DOE, the U.S. Department of Transportation (DOT), the U.S. Nuclear Regulatory Commission (NRC), and state and local agencies. The cost estimates in this report assume compliance with applicable regulations.

LLW Dumpster study: Task 009

International Nuclear Information System (INIS)

Frye, J.A.

1989-08-01

Over a span of several years, the public has reported visible leakage emanating from ten cubic yard Dumpsters used to transport Low Level Radioactive Wastes (LLW) from LANL generation sites to the disposal site at TA-54, Area G. The purpose of this study was to: Investigate probable causes of leakages, Inspect existing Dumpsters in the fields Propose immediate short-range solutions to the problem, and Propose long-range solutions based on predicted future requirements. Field investigations indicated that LLW is handled carefully and professional at the individual generation sites and again during pick-up delivery, and disposal at TA-54. It was also apparent, however, that Dumpsters not designed for LLW service are used to store this radioactive material for extended time periods while being subjected to the full range of Northern New Mexico weather conditions. All Dumpsters inspected had 1/8 in to 2 in gaps in their closures (loading doors and discharge ramps) through which driving rain or melting snow could easily enter. Seven Dumpsters were located outside secure areas. No cases of actual contamination were discovered, only the appearance of contamination i.e. the dripping of collected rainwater or melting ice and snow from Dumpsters being transported over public roads

Comparison of low-level waste disposal programs of DOE and selected international countries

International Nuclear Information System (INIS)

Meagher, B.G.; Cole, L.T.

1996-06-01

The purpose of this report is to examine and compare the approaches and practices of selected countries for disposal of low-level radioactive waste (LLW) with those of the US Department of Energy (DOE). The report addresses the programs for disposing of wastes into engineered LLW disposal facilities and is not intended to address in-situ options and practices associated with environmental restoration activities or the management of mill tailings and mixed LLW. The countries chosen for comparison are France, Sweden, Canada, and the United Kingdom. The countries were selected as typical examples of the LLW programs which have evolved under differing technical constraints, regulatory requirements, and political/social systems. France was the first country to demonstrate use of engineered structure-type disposal facilities. The UK has been actively disposing of LLW since 1959. Sweden has been disposing of LLW since 1983 in an intermediate-depth disposal facility rather than a near-surface disposal facility. To date, Canada has been storing its LLW but will soon begin operation of Canada's first demonstration LLW disposal facility

Use of a Shielded High Resolution Gamma Spectrometry System to Segregate LLW from Contact Handleable ILW Containing Plutonium - 13046

Energy Technology Data Exchange (ETDEWEB)

Lester, Rosemary; Wilkins, Colin [Canberra UK Ltd, Unit 1 B528.1, Harwell Science Campus, Oxfordshire OX11 0DF (United Kingdom); Chard, Patrick [Canberra UK Ltd, Forss Business and Technology park, Thurso, Caithness KW14 7UZ (United Kingdom); Jaederstroem, Henrik; LeBlanc, Paul; Mowry, Rick [Canberra Industries, Inc., 800 Research Parkway, Meriden, Connecticut, 06450 (United States); MacDonald, Sanders; Gunn, William [Dounreay Site Restoration Limited, Dounreay, Thurso, Caithness, KW14 7TZ (United Kingdom)

2013-07-01

Dounreay Site Restoration Limited (DSRL) have a number of drums of solid waste that may contain Plutonium Contaminated Material. These are currently categorised as Contact Handleable Intermediate Level Waste (CHILW). A significant fraction of these drums potentially contain waste that is in the Low Level Waste (LLW) category. A Canberra Q2 shielded high resolution gamma spectrometry system is being used to quantify the total activity of drums that are potentially in the LLW category in order to segregate those that do contain LLW from CHILW drums and thus to minimise the total volume of waste in the higher category. Am-241 is being used as an indicator of the presence of plutonium in the waste from its strong 59.54 keV gamma-ray; a knowledge of the different waste streams from which the material originates allows a pessimistic waste 'fingerprint' to be used in order to determine an upper limit to the activities of the weak and non-gamma-emitting plutonium and associated radionuclides. This paper describes the main features of the high resolution gamma spectrometry system being used by DSRL to perform the segregation of CHILW and LLW and how it was configured and calibrated using the Canberra In-Situ Object Counting System (ISOCS). It also describes how potential LLW drums are selected for assay and how the system uses the existing waste stream fingerprint information to determine a reliable upper limit for the total activity present in each measured drum. Results from the initial on-site commissioning trials and the first measurements of waste drums using the new monitor are presented. (authors)

Integration of U.S. Department of Energy (DOE) contractor installations for the purpose of optimizing treatment, storage, and disposal of low-level radioactive waste (LLW)

International Nuclear Information System (INIS)

Lucas, M.; Gnoose, J.; Coony, M.; Martin, E.; Piscitella, R.

1998-02-01

The US Department of Energy (DOE) manages a multibillion dollar environmental management (EM) program. In June 1996, the Assistant Secretary of Energy for EM issued a memorandum with guidance and a vision for a ten year planning process for the EM Program. The purpose of this process, which became known as the Accelerated Cleanup: Focus on 2006, is to make step changes within the DOE complex regarding the approach for making meaningful environmental cleanup progress. To augment the process, Assistant Secretary requested the site contractors to engage in an effort to identify and evaluate integration alternatives for EM waste stream treatment, storage, and disposal (TSD) that would parallel the 2006 Plan. In October 1996, ten DOE contractor installations began the task of identifying alternative opportunities for low level radioactive waste (LLW). Cost effective, efficient solutions were necessary to meet all requirements associated with storing, characterizing, treating, packaging, transporting, and disposing of LLW while protecting the workers' health and safety, and minimizing impacts to the environment. To develop these solutions, a systems engineering approach was used to establish the baseline requirements, to develop alternatives, and to evaluate the alternatives. Key assumptions were that unique disposal capabilities exist within the DOE that must be maintained; private sector disposal capability for some LLW may not continue to exist into the foreseeable future; and decisions made by the LLW Team must be made on a system or complex wide basis to fully realize the potential cost and schedule benefits. This integration effort promoted more accurate waste volume estimates and forecasts; enhanced recognition of existing treatment, storage, and disposal capabilities and capacities; and improved identification of cost savings across the complex

Idaho Chemical Processing Plant low-level waste grout stabilization development program FY-96 status report

International Nuclear Information System (INIS)

Herbst, A.K.

1996-09-01

The general purpose of the Grout Stabilization Development Program is to solidify and stabilize the liquid low-level wastes (LLW) generated at the Idaho Chemical Processing Plant (ICPP). It is anticipated that LLW will be produced from the following: (1) chemical separation of the tank farm high-activity sodium-bearing waste; (2) retrieval, dissolution, and chemical separation of the aluminum, zirconium, and sodium calcines; (3) facility decontamination processes; and (4) process equipment waste. The main tasks completed this fiscal year as part of the program were chromium stabilization study for sodium-bearing waste and stabilization and solidification of LLW from aluminum and zirconium calcines. The projected LLW will be highly acidic and contain high amounts of nitrates. Both of these are detrimental to Portland cement chemistry; thus, methods to precondition the LLW and to cure the grout were explored. A thermal calcination process, called denitration, was developed to solidify the waste and destroy the nitrates. A three-way blend of Portland cement, blast furnace slag, and fly ash was successfully tested. Grout cubes were prepared at various waste loadings to maximize loading while meeting compressive strength and leach resistance requirements. For the sodium LLW, a 25% waste loading achieves a volume reduction of 3.5 and a compressive strength of 2,500 pounds per square inch while meeting leach, mix, and flow requirements. It was found that the sulfur in the slag reduces the chromium leach rate below regulatory limits. For the aluminum LLW, a 15% waste loading achieves a volume reduction of 8.5 and a compressive strength of 4,350 pounds per square inch while meeting leach requirements. Likewise for zirconium LLW, a 30% waste loading achieves a volume reduction of 8.3 and a compressive strength of 3,570 pounds per square inch

Final waste management programmatic environmental impact statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Summary

International Nuclear Information System (INIS)

1997-05-01

This Waste Management Programmatic Environmental Impact Statement (WM PEIS) is a nationwide study examining the environmental impacts of managing five types of radioactive and hazardous wastes generated by past and future nuclear defense and research activities at a variety of sites located around the United States. The five waste types are low-level mixed waste (LLMW), low-level waste (LLW), transuranic waste (TRUW), high-level waste (HLW), and hazardous waste (HW)

WRAP Module 1 waste characterization plan

International Nuclear Information System (INIS)

Mayancsik, B.A.

1995-01-01

The purpose of this document is to present the characterization methodology for waste generated, processed, or otherwise the responsibility of the Waste Receiving and Processing (WRAP) Module 1 facility. The scope of this document includes all solid low level waste (LLW), transuranic (TRU), mixed waste (MW), and dangerous waste. This document is not meant to be all-inclusive of the waste processed or generated within WRAP Module 1, but to present a methodology for characterization. As other streams are identified, the method of characterization will be consistent with the other streams identified in this plan. The WRAP Module 1 facility is located in the 200 West Area of the Hanford Site. The facility's function is two-fold. The first is to verify/characterize, treat and repackage contact handled (CH) waste currently in retrievable storage in the LLW Burial Grounds, Hanford Central Waste Complex, and the Transuranic Storage and Assay Facility (TRUSAF). The second is to verify newly generated CH TRU waste and LLW, including MW. The WRAP Module 1 facility provides NDE and NDA of the waste for both drums and boxes. The NDE is used to identify the physical contents of the waste containers to support waste characterization and processing, verification, or certification. The NDA results determine the radioactive content and distribution of the waste

Treatment of low level radioactive liquid waste containing appreciable concentration of TBP degraded products.

Science.gov (United States)

Valsala, T P; Sonavane, M S; Kore, S G; Sonar, N L; De, Vaishali; Raghavendra, Y; Chattopadyaya, S; Dani, U; Kulkarni, Y; Changrani, R D

2011-11-30

The acidic and alkaline low level radioactive liquid waste (LLW) generated during the concentration of high level radioactive liquid waste (HLW) prior to vitrification and ion exchange treatment of intermediate level radioactive liquid waste (ILW), respectively are decontaminated by chemical co-precipitation before discharge to the environment. LLW stream generated from the ion exchange treatment of ILW contained high concentrations of carbonates, tributyl phosphate (TBP) degraded products and problematic radio nuclides like (106)Ru and (99)Tc. Presence of TBP degraded products was interfering with the co-precipitation process. In view of this a modified chemical treatment scheme was formulated for the treatment of this waste stream. By mixing the acidic LLW and alkaline LLW, the carbonates in the alkaline LLW were destroyed and the TBP degraded products got separated as a layer at the top of the vessel. By making use of the modified co-precipitation process the effluent stream (1-2 μCi/L) became dischargeable to the environment after appropriate dilution. Based on the lab scale studies about 250 m(3) of LLW was treated in the plant. The higher activity of the TBP degraded products separated was due to short lived (90)Y isotope. The cement waste product prepared using the TBP degraded product was having good chemical durability and compressive strength. Copyright © 2011 Elsevier B.V. All rights reserved.

Taking the UK's national LLW programme from strategy development to implementation - 59059

International Nuclear Information System (INIS)

Rossiter, David; O'Donnell, Rachel

2012-01-01

In 2008 UK Nuclear Waste Management Ltd (UKNWM) became the Parent Body Organisation (PBO) at the Low Level Waste Repository (LLWR) in the UK. LLWR is the primary disposal facility for the UK's LLW, supporting a wide range of industries across the nuclear power generation, reprocessing, defence, health care, education, and oil and gas sectors. One of the key tasks following the appointment of the new PBO was to work with the Nuclear Decommissioning Authority (NDA) to develop a national strategy for LLW generated in the UK, predominantly in the NDA estate. The new National Strategy for LLW was required to address the gap between the forecast waste arisings and predicted capacity at LLWR. The National Strategy for LLW Management was published in August 2010 following an 18 month development period. The main focus of the strategy is on three areas: - Application of the waste management hierarchy to extend the life of LLWR and ensure waste is managed in a risk-based, fit-for-purpose manner - Making best use of existing assets such as transport, packaging, treatment and disposal facilities - Opening up new fit-for-purpose waste management routes to divert waste away from LLWR Developing a robust strategy is vital to provide strategic direction to Government, waste producers, regulators, and stakeholders. Once the strategy is developed and approved, the key challenge is then to implement the strategy on a national scale in an efficient and cost-effective manner that delivers maximum value for money to the UK taxpayer. As well as developing the strategy, LLWR has been actively working to develop the enablers to implement the strategy. Since the publication of the strategy in August 2010 LLWR has been re-organised to reflect the shift in focus, from strategy development to implementation and delivery of the strategy. New resources have been brought in with international waste management experience to help integrate delivery with waste producers. This paper covers the

LLW Forum meeting report, July 20--22, 1994

International Nuclear Information System (INIS)

1994-01-01

The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representative, appointed by governors and compact commissions, established to facilitate state and compact commission implementation of the Low-Level radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies. This report details activities of the meeting held July 20-22, 1994

Packaged low-level waste verification system

International Nuclear Information System (INIS)

Tuite, K.T.; Winberg, M.; Flores, A.Y.; Killian, E.W.; McIsaac, C.V.

1996-01-01

Currently, states and low-level radioactive waste (LLW) disposal site operators have no method of independently verifying the radionuclide content of packaged LLW that arrive at disposal sites for disposal. At this time, disposal sites rely on LLW generator shipping manifests and accompanying records to insure that LLW received meets the waste acceptance criteria. An independent verification system would provide a method of checking generator LLW characterization methods and help ensure that LLW disposed of at disposal facilities meets requirements. The Mobile Low-Level Waste Verification System (MLLWVS) provides the equipment, software, and methods to enable the independent verification of LLW shipping records to insure that disposal site waste acceptance criteria are being met. The MLLWVS system was developed under a cost share subcontract between WMG, Inc., and Lockheed Martin Idaho Technologies through the Department of Energy's National Low-Level Waste Management Program at the Idaho National Engineering Laboratory (INEL)

Does the choice of reactor affect public acceptance of wastes?

International Nuclear Information System (INIS)

Inhaber, H.

1993-01-01

A prime goal of this conference is to suggest future reactor types that would produce greater public acceptability. Presumably the wastes generated by these cycles would, because of lesser amounts or activities, engender fewer disputes over policy than in the past. However, the world-wide arguments over low-level wastes (LLW) suggest this intent is not likely to be achieved. While the activity of these wastes is a tiny fraction of high-level wastes (HLW), the controversies over the former, in Korea, the US and elsewhere, have been as great as for the latter. There is no linear relationship between activity and political desirability. What is needed is a new approach to disposing of and siting all nuclear wastes: LLW, mixed and HLW

Long-range low-level waste management needs

International Nuclear Information System (INIS)

Gloyna, E.F.

1980-01-01

In all waste management considerations, it is necessary to establish the waste source; characterize the waste components; determine treatability; evaluate specific details that comprise a systems approach to overall waste management; and implement practical collection, packaging, storage disposal and monitoring technology. This paper evaluates management considerations by defining the source and magnitude of low-level wastes (LLW), relating LLW disposal, defining principles of LLW burial, and listing LLW burial considerations. 17 refs

Encapsulation of mixed radioactive and hazardous waste contaminated incinerator ash in modified sulfur cement

International Nuclear Information System (INIS)

Kalb, P.D.; Heiser, J.H. III; Colombo, P.

1990-01-01

Some of the process waste streams incinerated at various Department of Energy (DOE) facilities contain traces of both low-level radioactive (LLW) and hazardous constituents, thus yielding ash residues that are classified as mixed waste. Work is currently being performed at Brookhaven National Laboratory (BNL) to develop new and innovative materials for encapsulation of DOE mixed wastes including incinerator ash. One such material under investigation is modified sulfur cement, a thermoplastic developed by the US Bureau of Mines. Monolithic waste forms containing as much as 55 wt % incinerator fly ash from Idaho national Engineering Laboratory (INEL) have been formulated with modified sulfur cement, whereas maximum waste loading for this waste in hydraulic cement is 16 wt %. Compressive strength of these waste forms exceeded 27.6 MPa. Wet chemical and solid phase waste characterization analyses performed on this fly ash revealed high concentrations of soluble metal salts including Pb and Cd, identified by the Environmental Protection Agency (EPA) as toxic metals. Leach testing of the ash according to the EPA Toxicity Characteristic Leaching Procedure (TCLP) resulted in concentrations of Pb and Cd above allowable limits. Encapsulation of INEL fly ash in modified sulfur cement with a small quantity of sodium sulfide added to enhance retention of soluble metal salts reduced TCLP leachate concentrations of Pb and Cd well below EPA concentration criteria for delisting as a toxic hazardous waste. 12 refs., 4 figs., 2 tabs

Superconducting Open-Gradient Magnetic Separation for the Pretreatment of Radioactive or Mixed Waste Vitrification Feeds

International Nuclear Information System (INIS)

Nunez', L.; Kaminsky', M.D.; Crawford, C.; Ritter, J.A.

1999-01-01

An open-gradient magnetic separation (OGMS) process is being considered to separate deleterious elements from radioactive and mixed waste streams prior to vitrification or stabilization. By physically segregating solid wastes and slurries based on the magnetic properties of the solid constituents, this potentially low-cost process may serve the U.S. Department of Energy (DOE) by reducing the large quantities of glass produced from defense-related high-level waste (HLW). Furthermore, the separation of deleterious elements from low-level waste (LLW) also can reduce the total quantity of waste produced in LLW immobilization activities. Many HLW 'and LLW waste' streams at both Hanford and the Savannah River Site (SRS) include constituents deleterious to the durability of borosilicate glass and the melter many of the constituents also possess paramagnetism. For example, Fe, Cr, Ni, and other transition metals may limit the waste loading and affect the durability of the glass by forming spine1 phases at the high operating temperature used in vitrification. Some magnetic spine1 phases observed in glass formation are magnetite (Fe,O,), chromite (FeCrO,), and others [(Fe, Ni, Mg, Zn, Mn)(Al, Fe, Ti, Cr)O,] as described elsewhere [Bates-1994, Wronkiewicz-1994] Stable spine1 phases can cause segregation between the glass and the crystalline phases. As a consequence of the difference in density, the spine1 phases tend to accumulate at the bottom of the glass melter, which decreases the conductivity and melter lifetime [Sproull-1993]. Crystallization also can affect glass durability [Jantzen-1985, Turcotte- 1979, Buechele-1990] by changing the chemical composition of the matrix glass surrounding the crystals or causing stress at the glass/crystal interface. These are some of the effects that can increase leaching [Jantzen-1985]. A SRS glass that was partially crystallized to contain 10% vol. crystals composed of spinels, nepheline, and acmite phases showed minimal changes in

LLW Forum meeting report, April 18--19, 1991

International Nuclear Information System (INIS)

1991-01-01

The Low-Level Radioactive Waste Forum is an association of representatives of states and compacts established to facilitate state and compact commission implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies. LLW Forum participants include representatives from regional compacts, designated host states, unaffiliated states, and states with currently- operating low-level radioactive waste facilities. This quarterly meeting was held on April 18-19, 1991

LLW Forum meeting report, October 20--22, 1997

International Nuclear Information System (INIS)

Norris, C.; Brown, H.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-10-01

The Low-Level Radioactive Waste Forum met in Annapolis, Maryland, on October 20--22, 1997. Twenty-six Forum Participants, Alternate Forum Participants, and meeting designees representing 22 compacts and states participated. A report on the meeting is given under the following subtitles: New developments in states and compacts; Discussion with NRC Commissioner McGaffigan; Regulatory issues session; Executive session; LLW forum business session; DOE low-level waste management program; Transportation of radioactive waste; Environmental equity: Title VI; Congressional studies on Ward Valley Site; Implementation of DOE's strategy for waste management; Relicensing Envirocare; Draft agreement for uniform application of manifesting procedures; CRCPD report; Panel: Future of low-level radioactive waste management; Agenda planning: February 1998; Resolutions; and Attendance

LLW Forum meeting report, April 25--27, 1994

International Nuclear Information System (INIS)

1994-01-01

The Low-Level radioactive Waste Forum is an association of representatives of states and compacts established to facilitate state and compact commission implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies. LLW Forum participants include representatives from regional compacts, designated host states, unaffiliated states, and states with currently-operating low-level radioactive waste facilities. This quarterly meeting was held April 25-27, 1994 and activities during the first quarter of 1994 are detailed

LLW Forum meeting report, April 25--27, 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

The Low-Level radioactive Waste Forum is an association of representatives of states and compacts established to facilitate state and compact commission implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies. LLW Forum participants include representatives from regional compacts, designated host states, unaffiliated states, and states with currently-operating low-level radioactive waste facilities. This quarterly meeting was held April 25-27, 1994 and activities during the first quarter of 1994 are detailed..

Waste Management Facilities Cost Information for transportation of radioactive and hazardous materials. Revision 1

International Nuclear Information System (INIS)

Feizollahi, F.; Shropshire, D.; Burton, D.

1994-09-01

This report contains transportation costs for most types of DOE waste streams: low-level waste (LLW), mixed low-level waste (MLLW), alpha LLW and alpha MLLW, greater-than-Class C (GTCC) LLW and DOE equivalent waste, transuranic waste (TRU), spent nuclear fuel (SNF), and hazardous waste. Unit rates for transportation of contact-handled ( 200 mrem/hr contact dose) radioactive waste have been estimated previously, and a summary has been included in earlier WMFCI reports. In order to have a single source for obtaining transportation cost for all radioactive waste, the transportation costs for the contact- and remote-handled wastes are repeated in this report. Land transportation of radioactive and hazardous waste is subject to regulations promulgated by DOE, the US Department of Transportation (DOT), the US Nuclear Regulatory Commission (NRC), and state and local agencies. The cost estimates in this report assume compliance with applicable regulations. It should be noted that the trend is toward greater restrictions on transportation of radioactive waste (e.g., truck or rail car speed, shipping route, security escort, and personnel training requirements), which may have a significant impact on future costs

Low-level radioactive waste, mixed low-level radioactive waste, and biomedical mixed waste

International Nuclear Information System (INIS)

Anon.

1994-01-01

This document describes the proceedings of a workshop entitled: Low-Level Radioactive Waste, Mixed Low-Level Radioactive Waste, and Biomedical Mixed Waste presented by the National Low-Level Waste Management Program at the University of Florida, October 17-19, 1994. The topics covered during the workshop include technical data and practical information regarding the generation, handling, storage and disposal of low-level radioactive and mixed wastes. A description of low-level radioactive waste activities in the United States and the regional compacts is presented

Closure Strategy for a Waste Disposal Facility with Multiple Waste Types and Regulatory Drivers at the Nevada Test Site - 8422

International Nuclear Information System (INIS)

D Wieland; V Yucel; L Desotell; G Shott; J Wrapp

2008-01-01

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) plans to close the waste and classified material storage cells in the southeast quadrant of the Area 5 Radioactive Waste Management Site (RWMS), informally known as the '92-Acre Area', by 2011. The 25 shallow trenches and pits and the 13 Greater Confinement Disposal (GCD) borings contain various waste streams including low-level waste (LLW), low-level mixed waste (LLMW), transuranic (TRU), mixed transuranic (MTRU), and high specific activity LLW. The cells are managed under several regulatory and permit programs by the U.S. Department of Energy (DOE) and the Nevada Division of Environmental Protection (NDEP). Although the specific closure requirements for each cell vary, 37 closely spaced cells will be closed under a single integrated monolayer evapotranspirative (ET) final cover. One cell will be closed under a separate cover concurrently. The site setting and climate constrain transport pathways and are factors in the technical approach to closure and performance assessment. Successful implementation of the integrated closure plan requires excellent communication and coordination between NNSA/NSO and the regulators

78 FR 75913 - Final Tank Closure and Waste Management Environmental Impact Statement for the Hanford Site...

Science.gov (United States)

2013-12-13

... site, including the disposal of Hanford's low-level radioactive waste (LLW) and mixed low-level... would be processed for disposal in Low- Level Radioactive Waste Burial Grounds (LLBGs) Trenches 31 and... treating radioactive waste from 177 underground storage tanks (149 Single-Shell Tanks [SSTs] and 28 Double...

A Novel and Cost Effective Approach to the Decommissioning and Decontamination of Legacy Glove Boxes - Minimizing TRU Waste and Maximizing LLW Waste - 13634

Energy Technology Data Exchange (ETDEWEB)

Pancake, Daniel; Rock, Cynthia M.; Creed, Richard [Argonne National Laboratory, 9700 South Cass Avenue, Lemont, IL 60439 (United States); Donohoue, Tom; Martin, E. Ray; Mason, John A. [ANTECH Corporation 9050 Marshall Court, Westminster, CO, 80031 (United States); Norton, Christopher J.; Crosby, Daniel [Environmental Alternatives, Inc., 149 Emerald Street, Suite R, Keene, NH 03431 (United States); Nachtman, Thomas J. [InstaCote, Inc., 160 C. Lavoy Road, Erie, MI, 48133 (United States)

2013-07-01

This paper describes the process of decommissioning two gloveboxes at the Argonne National Laboratory (ANL) that were employed for work with plutonium and other radioactive materials. The decommissioning process involved an initial phase of clearing tools and materials from the glove boxes and disconnecting them from the laboratory infrastructure. The removed materials, assessed as Transuranic (TRU) waste, were packaged into 55 gallon (200 litre) drums and prepared for ultimate disposal at the Waste Isolation Pilot Plant (WIPP) at Carlsbad New Mexico. The boxes were then sampled to determine the radioactive contents by means of smears that were counted with alpha and beta detectors to determine the residual surface contamination, especially in terms of alpha particle emitters that are an indicator of TRU activity. Paint chip samples were also collected and sent for laboratory analysis in order to ascertain the radioactive contamination contributing to the TRU activity as a fixed contamination. The investigations predicted that it may be feasible to reduce the residual surface contamination and render the glovebox structure low level waste (LLW) for disposal. In order to reduce the TRU activity a comprehensive decontamination process was initiated using chemical compounds that are particularly effective for lifting and dissolving radionuclides that adhere to the inner surfaces of the gloveboxes. The result of the decontamination process was a reduction in the TRU surface activity on the inner surfaces of the gloveboxes by four orders of magnitude in terms of disintegrations per unit area (DPA). The next phase of the process involved a comprehensive assay of the gloveboxes using a combination of passive neutron and gamma ray scintillation detectors and a shielded and collimated high purity Germanium (HPGe) gamma ray detector. The HPGe detector was used to obtain gamma ray spectra for a variety of measurement positions within the glovebox. The spectra were used to

A Novel and Cost Effective Approach to the Decommissioning and Decontamination of Legacy Glove Boxes - Minimizing TRU Waste and Maximizing LLW Waste - 13634

International Nuclear Information System (INIS)

Pancake, Daniel; Rock, Cynthia M.; Creed, Richard; Donohoue, Tom; Martin, E. Ray; Mason, John A.; Norton, Christopher J.; Crosby, Daniel; Nachtman, Thomas J.

2013-01-01

This paper describes the process of decommissioning two gloveboxes at the Argonne National Laboratory (ANL) that were employed for work with plutonium and other radioactive materials. The decommissioning process involved an initial phase of clearing tools and materials from the glove boxes and disconnecting them from the laboratory infrastructure. The removed materials, assessed as Transuranic (TRU) waste, were packaged into 55 gallon (200 litre) drums and prepared for ultimate disposal at the Waste Isolation Pilot Plant (WIPP) at Carlsbad New Mexico. The boxes were then sampled to determine the radioactive contents by means of smears that were counted with alpha and beta detectors to determine the residual surface contamination, especially in terms of alpha particle emitters that are an indicator of TRU activity. Paint chip samples were also collected and sent for laboratory analysis in order to ascertain the radioactive contamination contributing to the TRU activity as a fixed contamination. The investigations predicted that it may be feasible to reduce the residual surface contamination and render the glovebox structure low level waste (LLW) for disposal. In order to reduce the TRU activity a comprehensive decontamination process was initiated using chemical compounds that are particularly effective for lifting and dissolving radionuclides that adhere to the inner surfaces of the gloveboxes. The result of the decontamination process was a reduction in the TRU surface activity on the inner surfaces of the gloveboxes by four orders of magnitude in terms of disintegrations per unit area (DPA). The next phase of the process involved a comprehensive assay of the gloveboxes using a combination of passive neutron and gamma ray scintillation detectors and a shielded and collimated high purity Germanium (HPGe) gamma ray detector. The HPGe detector was used to obtain gamma ray spectra for a variety of measurement positions within the glovebox. The spectra were used to

Nevada Test Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

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

2005-01-01

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

Mixed waste management options

International Nuclear Information System (INIS)

Owens, C.B.; Kirner, N.P.

1992-01-01

Currently, limited storage and treatment capacity exists for commercial mixed waste streams. No commercial mixed waste disposal is available, and it has been estimated that if and when commercial mixed waste disposal becomes available, the costs will be high. If high disposal fees are imposed, generators may be willing to apply extraordinary treatment or regulatory approaches to properly dispose of their mixed waste. This paper explores the feasibility of several waste management scenarios and management options. Existing data on commercially generated mixed waste streams are used to identify the realm of mixed waste known to be generated. Each waste stream is evaluated from both a regulatory and technical perspective in order to convert the waste into a strictly low-level radioactive or a hazardous waste. Alternative regulatory approaches evaluated in this paper include a delisting petition) no migration petition) and a treatability variance. For each waste stream, potentially available treatment options are identified that could lead to these variances. Waste minimization methodology and storage for decay are also considered. Economic feasibility of each option is discussed broadly. Another option for mixed waste management that is being explored is the feasibility of Department of Energy (DOE) accepting commercial mixed waste for treatment, storage, and disposal. A study has been completed that analyzes DOE treatment capacity in comparison with commercial mixed waste streams. (author)

Economic analysis of alternative LLW disposal methods

International Nuclear Information System (INIS)

Foutes, C.E.

1987-01-01

The Environmental Protection Agency (EPA) has evaluated the costs and benefits of alternative disposal technologies as part of its program to develop generally applicable environmental standards for the land disposal of low-level radioactive waste (LLW). Costs, population health effects and Critical Population Group (CPG) exposures resulting from alternative waste treatment and disposal methods were developed and input into the analysis. The cost-effectiveness analysis took into account a number of waste streams, hydrogeologic and climatic region settings, and waste treatment and disposal methods. Total costs of each level of a standard included costs for packaging, processing, transportation, and burial of waste. Benefits are defined in terms of reductions in the general population health risk (expected fatal cancers and genetic effects) evaluated over 10,000 years. A cost-effectiveness ratio, was calculated for each alternative standard. This paper describes the alternatives considered and preliminary results of the cost-effectiveness analysis

IMPROVEMENTS IN CONTAINER MANAGEMENT OF TRANSURANIC (TRU) AND LOW LEVEL RADIOACTIVE WASTE STORED AT THE CENTRAL WASTE COMPLEX (CWC) AT HANFORD

International Nuclear Information System (INIS)

UYTIOCO EM

2007-01-01

The Central Waste Complex (CWC) is the interim storage facility for Resource Conservation and Recovery Act (RCRA) mixed waste, transuranic waste, transuranic mixed waste, low-level and low-level mixed radioactive waste at the Department of Energy's (DOE'S) Hanford Site. The majority of the waste stored at the facility is retrieved from the low-level burial grounds in the 200 West Area at the Site, with minor quantities of newly generated waste from on-site and off-site waste generators. The CWC comprises 18 storage buildings that house 13,000 containers. Each waste container within the facility is scanned into its location by building, module, tier and position and the information is stored in a site-wide database. As waste is retrieved from the burial grounds, a preliminary non-destructive assay is performed to determine if the waste is transuranic (TRU) or low-level waste (LLW) and subsequently shipped to the CWC. In general, the TRU and LLW waste containers are stored in separate locations within the CWC, but the final disposition of each waste container is not known upon receipt. The final disposition of each waste container is determined by the appropriate program as process knowledge is applied and characterization data becomes available. Waste containers are stored within the CWC based on their physical chemical and radiological hazards. Further segregation within each building is done by container size (55-gallon, 85-gallon, Standard Waste Box) and waste stream. Due to this waste storage scheme, assembling waste containers for shipment out of the CWC has been time consuming and labor intensive. Qualitatively, the ratio of containers moved to containers in the outgoing shipment has been excessively high, which correlates to additional worker exposure, shipment delays, and operational inefficiencies. These inefficiencies impacted the LLW Program's ability to meet commitments established by the Tri-Party Agreement, an agreement between the State of Washington

Mixed Waste Management Facility

International Nuclear Information System (INIS)

Brummond, W.; Celeste, J.; Steenhoven, J.

1993-08-01

The DOE has developed a National Mixed Waste Strategic Plan which calls for the construction of 2 to 9 mixed waste treatment centers in the Complex in the near future. LLNL is working to establish an integrated mixed waste technology development and demonstration system facility, the Mixed Waste Management Facility (MWMF), to support the DOE National Mixed Waste Strategic Plan. The MWMF will develop, demonstrate, test, and evaluate incinerator-alternatives which will comply with regulations governing the treatment and disposal of organic mixed wastes. LLNL will provide the DOE with engineering data for design and operation of new technologies which can be implemented in their mixed waste treatment centers. MWMF will operate under real production plant conditions and process samples of real LLNL mixed waste. In addition to the destruction of organic mixed wastes, the development and demonstration will include waste feed preparation, material transport systems, aqueous treatment, off-gas treatment, and final forms, thus making it an integrated ''cradle to grave'' demonstration. Technologies from offsite as well as LLNL's will be tested and evaluated when they are ready for a pilot scale demonstration, according to the needs of the DOE

Current status of sea transport of nuclear fuel materials and LLW in Japan

International Nuclear Information System (INIS)

Kitagawa, Hiroshi; Akiyama, Hideo

2000-01-01

Along with the basic policy of the nuclear fuel cycle of Japan, many fuel cycle facilities have been already constructed in Rokkasho-Mura, Aomori prefecture, such as the uranium enrichment plant, the low level waste disposal center and the receiving pool of the spent nuclear fuels for reprocessing. These facilities belong to the Japan Nuclear Fuel Limited. (JNFL). Domestic sea transport of the spent nuclear fuels (SF) has been carried out since 1977 to the Tokai Reprocessing Plant, and the first sea transport of the SF to the fuel cycle facility in Rokkasho-Mura was done in Oct, 1998 using a new exclusive ship 'Rokuei-Maru'. Sea transport of the low level radioactive wastes (LLW) has been carried out since 1992 to the Rokkasho LLW Disposal Center, and about 130,000 LLW drams were transported from the nuclear power plant sites. These sea transport have demonstrated the safety of the transport of the nuclear fuel cycle materials. It is hoped that the safe sea transport of the nuclear fuel materials will contribute to the more progress of the nuclear fuel cycle activities of Japan. (author)

Implementation of a geological disposal facility (GDF) in the UK by the NDA Radioactive Waste Management Directorate (RWMD): the potential for interaction between the co-located ILW/LLW and HLW/SF components of a GDF - 16306

International Nuclear Information System (INIS)

Towler, George; Hicks, Tim; Watson, Sarah; Norris, Simon

2009-01-01

In June 2008 the UK government published a 'White Paper' as part of the 'Managing Radioactive Waste Safety' (MRWS) programme to provide a framework for managing higher activity radioactive wastes in the long-term through geological disposal. The White Paper identifies that there are benefits to disposing all of the UK's higher activity wastes (Low and Intermediate Level Waste (LLW and ILW), High Level Waste (HLW), Spent Fuel (SF), Uranium (U) and Plutonium (Pu)) at the same site, and this is currently the preferred option. It also notes that research will be required to support the detailed design and safety assessment in relation to any potentially detrimental interactions between the different modules. Different disposal system designs and associated Engineered Barrier Systems (EBS) will be required for these different waste types, i.e. ILW/LLW and HLW/SF. If declared as waste U would be disposed as ILW and Pu as HLW/SF. The Geological Disposal Facility (GDF) would therefore comprise two co-located modules (respectively for ILW/LLW and HLW/SF). This paper presents an overview of a study undertaken to assess the implications of co-location by identifying the key Thermo-Hydro-Mechanical-Chemical (THMC) interactions that might occur during both the operational and post-closure phases, and their consequences for GDF design, performance and safety. The MRWS programme is currently seeking expressions of interest from communities to host a GDF. Therefore, the study was required to consider a wide range of potential GDF host rocks and consistent, conceptual disposal system designs. Two example disposal concepts (i.e. combinations of host rock, GDF design including wasteform and layout, etc.) were carried forward for detailed assessment and a third for qualitative analysis. Dimensional and 1D analyses were used to identify the key interactions, and 3D models were used to investigate selected interactions in more detail. The results of this study show that it is possible

Strategic environmental assessment for UK LLW management - 16392

International Nuclear Information System (INIS)

Craze, Andrew; Clark, Matthew; Davis, Pete

2009-01-01

NDA is delivering a Strategic Environmental Assessment (SEA) to underpin the UK Nuclear Industry Low Level Waste Strategy. The purpose of this assessment is embed sustainability issues into our decision making and to fulfill our requirements under the European Union's Strategic Environmental Assessment (SEA) Directive (2004/42/EU) and transposing UK Regulations, and to underpin the development of the strategy. The outputs of the SEA have provided input into particular aspects of the strategy, leading to a more robust and better informed result. Development of options to be assessed under the SEA has looked at a number of factors, including: - what the strategy is aiming to achieve - expectation from stakeholders as to what should be addressed - consideration of tactical approaches to implementation of the strategy in addition to high level strategic issues - links to other projects and programmes (for example the Environmental Safety Case for the Low Level Waste Repository. The SEA aims to provide a robust assessment of the environmental and sustainability impacts of alternative strategies for providing continued capability and capacity for the management and disposal of LLW in the UK. The assessment also considers other, more tactical, issues around implementation of the strategy, for example: issues around the location of LLW management facilities; the environmental impacts of alternative waste treatment options (metal recycling etc); considerations of alternative approaches to the classification of radioactive waste and opportunities that would result. Critical to the development of the SEA has been the involvement of statutory and non-statutory stakeholders, who have informed both the output and the approach taken. (authors)

1st Quarter Transportation Report FY 2015: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

Energy Technology Data Exchange (ETDEWEB)

Gregory, Louis [National Security Technologies, LLC, Las Vegas, NV (United States)

2015-02-20

This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to and from the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the 1st quarter of Fiscal Year (FY) 2015 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. Tabular summaries are provided which include the following: Sources of and carriers for LLW and MLLW shipments to and from the NNSS; Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report include minor volumes of non-radioactive classified waste/material that were approved for disposal (non-radioactive classified or nonradioactive classified hazardous). Volume reports showing cubic feet generated using the Low-Level Waste Information System may vary slightly due to rounding conventions for volumetric conversions from cubic meters to cubic feet.

Nevada National Security Site Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

none,

2013-06-01

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: • DOE hazardous and non-hazardous non-radioactive classified waste • DOE low-level radioactive waste (LLW) • DOE mixed low-level waste (MLLW) • U.S. Department of Defense (DOD) classified waste The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

Nevada National Security Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

2013-01-01

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: DOE hazardous and non-hazardous non-radioactive classified waste; DOE low-level radioactive waste (LLW); DOE mixed low-level waste (MLLW); and, U.S. Department of Defense (DOD) classified waste. The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

Waste-form development

International Nuclear Information System (INIS)

Neilson, R.M. Jr.; Colombo, P.

1982-01-01

Contemporary solidification agents are being investigated relative to their applications to major fuel cycle and non-fuel cycle low-level waste (LLW) streams. Work is being conducted to determine the range of conditions under which these solidification agents can be applied to specific LLW streams. These studies are directed primarily towards defining operating parameters for both improved solidification of problem wastes and solidification of new LLW streams generated from advanced volume reduction technologies. Work is being conducted to measure relevant waste form properties. These data will be compiled and evaluated to demonstrate compliance with waste form performance and shallow land burial acceptance criteria and transportation requirements

An overview of commercial low-level radioactive waste disposal technology

International Nuclear Information System (INIS)

Plummer, T.L.; Morreale, B.J.

1991-01-01

The primary objective of low-level radioactive (LLW) waste management is to safely dispose of LLW while protecting the health of the public and the quality of the environment. LLW in the United States is generated through both Department of Energy (DOE) and commercial activities. In this paper, waste from commercial activities will be referred to as ''commercial LLW.'' The DOE waste will not be discussed in this paper. Commercial LLW is waste that is generated by Nuclear Regulatory Commission (NRC) designated licensees or Agreement States. Commercial LLW is generated by nuclear power reactors, hospitals, universities, and manufacturers. This paper will give an overview of the current disposal technologies planned by selected States' for disposing of their LLW and the processes by which those selections were made. 3 refs

Preliminary low-level waste feed definition guidance - LLW pretreatment interface

International Nuclear Information System (INIS)

Shade, J.W.; Connor, J.M.; Hendrickson, D.W.; Powell, W.J.; Watrous, R.A.

1995-02-01

The document describes limits for key constituents in the LLW feed, and the bases for these limits. The potential variability in the stream is then estimated and compared to the limits. Approaches for accomodating uncertainty in feed inventory, processing strategies, and process design (melter and disposal system) are discussed. Finally, regulatory constraints are briefly addressed

Preliminary fee methodology for recovering GTCC-LLW management costs

International Nuclear Information System (INIS)

Clark, L.L.

1990-06-01

The US Department of Energy (DOE) is currently planning a fee to recover costs of managing Greater-Than-Class-C Low-Level Waste (GTCC-LLW). A cash flow basis will be used for fee calculations to ensure recovery of all applicable program costs. Positive cash flows are revenues received from waste generators. Negative cash flows are program expenses for storage, transportation, treatment, and disposal of the wastes and for program development, evaluation, and administration. Program balances are the net result of positive and negative cash flows each year. The methodology calculates fees that will recovery all program expenses taking into account cost inflation. 3 refs., 1 tab

Lawrence Livermore National Laboratory low-level waste systems performance assessment

International Nuclear Information System (INIS)

1990-11-01

This Low-Level Radioactive Waste (LLW) Systems Performance Assessment (PA) presents a systematic analysis of the potential risks posed by the Lawrence Livermore National Laboratory (LLNL) waste management system. Potential risks to the public and environment are compared to established performance objectives as required by DOE Order 5820.2A. The report determines the associated maximum individual committed effective dose equivalent (CEDE) to a member of the public from LLW and mixed waste. A maximum annual CEDE of 0.01 mrem could result from routine radioactive liquid effluents. A maximum annual CEDE of 0.003 mrem could result from routine radioactive gaseous effluents. No other pathways for radiation exposure of the public indicated detectable levels of exposure. The dose rate, monitoring, and waste acceptance performance objectives were found to be adequately addressed by the LLNL Program. 88 refs., 3 figs., 17 tabs

Mixed waste: Proceedings

International Nuclear Information System (INIS)

Moghissi, A.A.; Blauvelt, R.K.; Benda, G.A.; Rothermich, N.E.

1993-01-01

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 contaminated wastes and bioprocessing, and environmental restoration. Individual abstracts are catalogued separately for the data base

Mixed waste: Proceedings

Energy Technology Data Exchange (ETDEWEB)

Moghissi, A.A.; Blauvelt, R.K.; Benda, G.A.; Rothermich, N.E. [eds.] [Temple Univ., Philadelphia, PA (United States). Dept. of Environmental Safety and Health

1993-12-31

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 contaminated wastes and bioprocessing, and environmental restoration. Individual abstracts are catalogued separately for the data base.

Mixed Waste Integrated Program: A technology assessment for mercury-containing mixed wastes

International Nuclear Information System (INIS)

Perona, J.J.; Brown, C.H.

1993-03-01

The treatment of mixed wastes must meet US Environmental Protection Agency (EPA) standards for chemically hazardous species and also must provide adequate control of the radioactive species. The US Department of Energy (DOE) Office of Technology Development established the Mixed Waste Integrated Program (MWIP) to develop mixed-waste treatment technology in support of the Mixed Low-Level Waste Program. Many DOE mixed-waste streams contain mercury. This report is an assessment of current state-of-the-art technologies for mercury separations from solids, liquids, and gases. A total of 19 technologies were assessed. This project is funded through the Chemical-Physical Technology Support Group of the MWIP

3rd Quarter Transportation Report FY 2014: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

International Nuclear Information System (INIS)

Gregory, Louis

2014-01-01

This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the 3rd quarter of Fiscal Year (FY) 2014 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. This report also includes annual summaries for FY 2014 in Tables 4 and 5. Tabular summaries are provided which include the following: Sources of and carriers for LLW and MLLW shipments to and from the NNSS; Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report do not include minor volumes of non-radioactive materials that were approved for disposal. Volume reports showing cubic feet generated using the Low-Level Waste Information System may vary slightly due to differing rounding conventions.

LLW Forum meeting report

International Nuclear Information System (INIS)

1991-01-01

This document reports the details of the Quarterly Meeting of the Low- Level Radioactive Waste Forum held in San Diego, California during January 23-25, 1991. Topics discussed include: State and Compact Progress Reports; Legal Updates; Update on Technical Assistance; Advanced Notice of Proposed Rulemaking Regarding Surcharge Rebates; Update on TCC Activities; NRC Update; Disposal of Commercial Mixed Waste; Update on EPA Activities; ACNW Working Group on Mixed Waste; National Profile on Mixed Waste; Commercial Perspective on Mixed Waste; Update on DOT Activities; Source Terms; Materials and Waste; Storage: and Waste Acceptance Criteria and Packaging

Guidelines for mixed waste minimization

International Nuclear Information System (INIS)

Owens, C.

1992-02-01

Currently, there is no commercial mixed waste disposal available in the United States. Storage and treatment for commercial mixed waste is limited. Host States and compacts region officials are encouraging their mixed waste generators to minimize their mixed wastes because of management limitations. This document provides a guide to mixed waste minimization

Complex-wide review of DOE's Low-Level Waste Management ES ampersand H vulnerabilities. Volume I. Final report

International Nuclear Information System (INIS)

1996-05-01

The Department of Energy (DOE) conducted a comprehensive complex-wide review of its management of low-level waste (LLW) and the radioactive component of mixed low-level waste (MLLW). This review was conducted in response to a recommendation from the Defense Nuclear Facilities Safety Board (DNFSB) which was established and authorized by Congress to oversee DOE. The DNFSB's recommendation concerning conformance with safety standards at DOE LLW sites was issued on September 8, 1994 and is referred to as Recommendation 94-2. DOE's Implementation Plan for its response to Recommendation 94-2 was submitted to the DNFSB on March 31, 1995. The DNFSB recommended that a complex-wide review of DOE's LLW management be initiated. The goal of the complex-wide review of DOE's LLW management system was to identify both programmatic and physical vulnerabilities that could lead to unnecessary radiation exposure of workers or the public or unnecessary releases of radioactive materials to the environment. Additionally, the DNFSB stated that an objective of the complex-wide review should be to establish the dimensions of the DOE LLW problem and support the identification of corrective actions to address safe disposition of past, present, and future volumes of LLW. The complex-wide review involved an evaluation of LLW management activities at 38 DOE facilities at 36 sites that actively manage LLW and MLLW

Processing mixed-waste compressed-gas cylinders at the Oak Ridge Reservation

International Nuclear Information System (INIS)

Morris, M.I.; Conley, T.B.; Osborne-Lee, I.W.

1998-05-01

Until recently, several thousand kilograms of compressed gases were stored at the Oak Ridge Reservation (ORR), in Oak Ridge, Tennessee, because these cylinders could not be taken off-site in their state of configuration for disposal. Restrictions on the storage of old compressed-gas cylinders compelled the Waste Management Organization of Lockheed Martin Energy Systems, Inc. (LMES) to dispose of these materials. Furthermore, a milestone in the ORR Site Treatment Plan required repackaging and shipment off-site of 21 cylinders by September 30, 1997. A pilot project, coordinated by the Chemical Technology Division (CTD) at the Oak Ridge National Laboratory (ORNL), was undertaken to evaluate and recontainerize or neutralize these cylinders, which are mixed waste, to meet that milestone. Because the radiological component was considered to be confined to the exterior of the cylinder, the contents (once removed from the cylinder) could be handled as hazardous waste, and the cylinder could be handled as low-level waste (LLW). This pilot project to process 21 cylinders was important because of its potential impact. The successful completion of the project provides a newly demonstrated technology which can now be used to process the thousands of additional cylinders in inventory across the DOE complex. In this paper, many of the various aspects of implementing this project, including hurdles encountered and the lessons learned in overcoming them, are reported

Low-level radioactive waste disposal technologies used outside the United States

International Nuclear Information System (INIS)

Templeton, K.J.; Mitchell, S.J.; Molton, P.M.; Leigh, I.W.

1994-01-01

Low-level radioactive waste (LLW) disposal technologies are an integral part of the waste management process. In the United States, commercial LLW disposal is the responsibility of the State or groups of States (compact regions). The United States defines LLW as all radioactive waste that is not classified as spent nuclear fuel, high- level radioactive waste, transuranic waste, or by-product material as defined in Section II(e)(2) of the Atomic Energy Act. LLW may contain some long-lived components in very low concentrations. Countries outside the United States, however, may define LLW differently and may use different disposal technologies. This paper outlines the LLW disposal technologies that are planned or being used in Canada, China, Finland, France, Germany, Japan, Sweden, Taiwan, and the United Kingdom (UK)

Development of a plan for a national LLW information management system based on data acquired from a uniform manifest

International Nuclear Information System (INIS)

Gingerich, R.; Shimer, R.P.

1986-01-01

The Western Governors' Association (WGA), with funding from the Department of Energy's (DOE) National Low-Level Radioactive Waste Management Program, has completed an 18-month national project to develop a plan for a national low-level waste (LLW) information management system based on data from a uniform manifest for shipments of LLW. Under the plan, waste generators would fill out a manifest for a shipment just as they do currently, but they would use a nationally standard form. Shortly after a shipment arrives at a disposal facility or a processor, data from the manifest would be entered into the Program's Low-Level Waste Information Management System (LLWIMS). The data would be available via computer to state, compact and federal officials. This paper provides an overview of the plan for implementing and operating a national information management system linked to manifest data. It reports on the progress that has been made toward implementing the system and outlines the work that remains to be done. Finally, the paper examines the crucial role the system will play in the development of an acceptable system for managing the nation's LLW, particularly in the post-1986 transition period

Estimating heel retrieval costs for underground storage tank waste at Hanford. Draft

International Nuclear Information System (INIS)

DeMuth, S.

1996-01-01

Approximately 100 million gallons (∼400,000 m 3 ) of existing U.S. Department of Energy (DOE) owned radioactive waste stored in underground tanks can not be disposed of as low-level waste (LLW). The current plan for disposal of UST waste which can not be disposed of as LLW is immobilization as glass and permanent storage in an underground repository. Disposal of LLW generally can be done sub-surface at the point of origin. Consequently, LLW is significantly less expensive to dispose of than that requiring an underground repository. Due to the lower cost for LLW disposal, it is advantageous to separate the 100 million gallons of waste into a small volume of high-level waste (HLW) and a large volume of LLW

Development of multi-purpose containers for managing LLW/VLLW from D and D

International Nuclear Information System (INIS)

Lee, Jae Sol; Park, Jae Ho; Sung, Nak Hoon; Yang, Ge Hyung

2016-01-01

Radioactive waste container designs should comply with the requirements for safety (i.e., transportation, storage, disposal) and other criteria such as economics and technology. These criteria are also applicable to the future management of the large amount of LLW and VLLW to arise from decontamination and decommissioning (D and D) of nuclear power plants, which have different features compared to that of wastes from operation and maintenance (O and M). This paper proposes to develop a set of standard containers of multi-purpose usage for transportation, storage and disposal. The concepts of the containers were optimized for management of D and D wastes in consideration of national system for radioactive waste management, in particular the Gyeongju Repository and associated infrastructures. A set of prototype containers were designed and built : a soft bag for VLLW, two metallic containers for VLLW/LLW (a standard IP2 container for sea transport and ISO container for road transport). Safety analyses by simulation and tests of these designs show they are in compliance with the regulatory requirements. A further development of a container with concrete is foreseen for 2016

Development of multi-purpose containers for managing LLW/VLLW from D and D

Energy Technology Data Exchange (ETDEWEB)

Lee, Jae Sol; Park, Jae Ho; Sung, Nak Hoon; Yang, Ge Hyung [KONES Corporation., Seoul (Korea, Republic of)

2016-06-15

Radioactive waste container designs should comply with the requirements for safety (i.e., transportation, storage, disposal) and other criteria such as economics and technology. These criteria are also applicable to the future management of the large amount of LLW and VLLW to arise from decontamination and decommissioning (D and D) of nuclear power plants, which have different features compared to that of wastes from operation and maintenance (O and M). This paper proposes to develop a set of standard containers of multi-purpose usage for transportation, storage and disposal. The concepts of the containers were optimized for management of D and D wastes in consideration of national system for radioactive waste management, in particular the Gyeongju Repository and associated infrastructures. A set of prototype containers were designed and built : a soft bag for VLLW, two metallic containers for VLLW/LLW (a standard IP2 container for sea transport and ISO container for road transport). Safety analyses by simulation and tests of these designs show they are in compliance with the regulatory requirements. A further development of a container with concrete is foreseen for 2016.

Generation and release of radioactive gases in LLW disposal facilities

Energy Technology Data Exchange (ETDEWEB)

Yim, M.S. [Harvard School Public Health, Boston, MA (United States); Simonson, S.A. [Massachusetts Institute of Technology, Cambridge, MA (United States)

1995-02-01

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

Conceptual designs for waste quality checking facilities for low level and intermediate level radioactive wastes and hazardous waste

International Nuclear Information System (INIS)

Driver, S.; Griffiths, M.; Leonard, C.D.; Smith, D.L.G.

1992-01-01

This report summarises work carried out on the design of facilities for the quality checking of Intermediate and Low Level Radioactive Waste and Hazardous Waste. The procedures used for the quality checking of these categories of waste are summarised. Three building options are considered: a separate LLW facility, a combined facility for LLW and HW and a Waste Quality Checking Facility for the three categories of waste. Budget Cost Estimates for the three facilities are given based on 1991 prices. (author)

Waste form development

International Nuclear Information System (INIS)

Neilson, R.M. Jr.; Colombo, P.

1982-01-01

In this program, contemporary solidification agents are being investigated relative to their applications to major fuel cycle and non-fuel cycle low-level waste (LLW) streams. Work is being conducted to determine the range of conditions under which these solidification agents can be applied to specific LLW streams. These studies are directed primarily towards defining operating parameters for both improved solidification of problem wastes and solidification of new LLW streams generated from advanced volume reduction technologies. Work is being conducted to measure relevant waste form properties. These data will be compiled and evaluated to demonstrate compliance with waste form performance and shallow land burial acceptance criteria and transportation requirements (both as they exist and as they are modified with time). 6 tables

Practical Model of Cement Based Grout Mix Design, for Use into Low Level Radiation Waste Management

Directory of Open Access Journals (Sweden)

Radu Lidia

2015-12-01

Full Text Available The cement based grouts, as functional performance composite materials, are widely used for both immobilisation and encapsulation as well as for stabilization in the field of inorganic waste management. Also, to ensure that low level radioactive waste (LLW are contained for storage and ultimate disposal, they are encapsulated or immobilized in monolithic waste forms, with cement –based grouts.

Economic analysis of alternative LLW disposal methods

International Nuclear Information System (INIS)

Foutes, C.E.; Queenan, C.J. III

1987-01-01

The Environmental Protection Agency (EPA) has evaluated the costs and benefits of alternative disposal technologies as part of its program to develop generally applicable environmental standards for the land disposal of low-level radioactive waste (LLW). Costs, population health effects and Critical Population Group (CPG) exposures resulting from alternative waste treatment and disposal methods were evaluated both in absolute terms and also relative to a base case (current practice). Incremental costs of the standard included costs for packaging, processing, transportation, and burial of waste. Benefits are defined in terms of reductions in the general population health risk (expected fatal cancers and genetic effects) evaluated over 10,000 years. A cost-effectiveness ratio, defined as the incremental cost per avoided health effect, was calculated for each alternative standard. The cost-effectiveness analysis took into account a number of waste streams, hydrogeologic and climatic region settings, and waste treatment and disposal methods. This paper describes the alternatives considered and preliminary results of the cost-effectiveness analysis. 15 references, 7 figures, 3 tables

Implementation plan for the Waste Experimental Reduction Facility Restart Operational Readiness Review

International Nuclear Information System (INIS)

1993-03-01

The primary technical objective for the WERF Restart Project is to assess, upgrade where necessary, and implement management, documentation, safety, and operation control systems that enable the resumption and continued operation of waste treatment and storage operations in a manner that is compliant with all environment, safety, and quality requirements of the US Department of Energy and Federal and State regulatory agencies. Specific processes that will be resumed at WERF include compaction of low-level compatible waste; size reduction of LLW, metallic and wood waste; incineration of combustible LLW and MLLW; and solidification of low-level and mixed low-level incinerator bottom ash, baghouse fly ash, and compatible sludges and debris. WERF will also provide for the operation of the WWSB which includes storage of MLLW in accordance with Resource Conservation and Recovery Act requirements

Certification Plan, low-level waste Hazardous Waste Handling Facility

International Nuclear Information System (INIS)

Albert, R.

1992-01-01

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan also incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. This plan provides guidance from the HWHF to waste generators, waste handlers, and the Waste Certification Specialist to enable them to conduct their activities and carry out their responsibilities in a manner that complies with the requirements of WHC-WAC. Waste generators have the primary responsibility for the proper characterization of LLW. The Waste Certification Specialist verifies and certifies that LBL LLW is characterized, handled, and shipped in accordance with the requirements of WHC-WAC. Certification is the governing process in which LBL personnel conduct their waste generating and waste handling activities in such a manner that the Waste Certification Specialist can verify that the requirements of WHC-WAC are met

Solid low level waste management guidelines: Final report

International Nuclear Information System (INIS)

Castagnacci, A.; Dalton, D.; Genoa, P.

1994-11-01

Since 1989, the nuclear industry has been moving in the direction of greater minimization of low level radioactive waste (LLW). This has been driven in part by increasing regulatory attention, but it also is in response to the desire on the part of nuclear utilities to be more cost efficient and to be environmentally responsive. Over the past half-dozen years, LLW disposal costs have increased dramatically. In addition, improvements in LLW volume reduction technologies have substantially reduced the volume of LLW that is disposed. At the same time, utilities are implementing aggressive source reduction programs and programs to reuse materials so as to extend the useful life of many materials. Thus, there has been a dramatic change in LLW economics and LLW management practices in just the past few years. This report was developed by utility nuclear experts to provide guidance to all utilities on mechanisms for integrating the program economics, advanced volume reduction techniques, and approaches to source reduction. Thus, utilizes will be able to use this report as a guide to optimizing their LLW program economics and minimizing LLW disposal volumes to the smallest reasonable fraction. This report discusses the implementation of these guidelines, management support, waste materials and waste inventory, radioactive tool and equipment management, protective clothing management, processing and volume reduction, solid LLW tracking, outage LLW management, and interim storage of LLW

Mixed Waste Working Group report

International Nuclear Information System (INIS)

1993-01-01

The treatment of mixed waste remains one of this country's most vexing environmental problems. Mixed waste is the combination of radioactive waste and hazardous waste, as defined by the Resource Conservation and Recovery Act (RCRA). The Department of Energy (DOE), as the country's largest mixed waste generator, responsible for 95 percent of the Nation's mixed waste volume, is now required to address a strict set of milestones under the Federal Facility Compliance Act of 1992. DOE's earlier failure to adequately address the storage and treatment issues associated with mixed waste has led to a significant backlog of temporarily stored waste, significant quantities of buried waste, limited permanent disposal options, and inadequate treatment solutions. Between May and November of 1993, the Mixed Waste Working Group brought together stakeholders from around the Nation. Scientists, citizens, entrepreneurs, and bureaucrats convened in a series of forums to chart a course for accelerated testing of innovative mixed waste technologies. For the first time, a wide range of stakeholders were asked to examine new technologies that, if given the chance to be tested and evaluated, offer the prospect for better, safer, cheaper, and faster solutions to the mixed waste problem. In a matter of months, the Working Group has managed to bridge a gap between science and perception, engineer and citizen, and has developed a shared program for testing new technologies

Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics

International Nuclear Information System (INIS)

Hulse, R.A.

1991-08-01

Planning for storage or disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of that waste to estimate volumes, radionuclide activities, and waste forms. Data from existing literature, disposal records, and original research were used to estimate the characteristics and project volumes and radionuclide activities to the year 2035. GTCC LLW is categorized as: nuclear utilities waste, sealed sources waste, DOE-held potential GTCC LLW; and, other generator waste. It has been determined that the largest volume of those wastes, approximately 57%, is generated by nuclear power plants. The Other Generator waste category contributes approximately 10% of the total GTCC LLW volume projected to the year 2035. Waste held by the Department of Energy, which is potential GTCC LLW, accounts for nearly 33% of all waste projected to the year 2035; however, no disposal determination has been made for that waste. Sealed sources are less than 0.2% of the total projected volume of GTCC LLW

Methods for verifying compliance with low-level radioactive waste acceptance criteria

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-09-01

This report summarizes the methods that are currently employed and those that can be used to verify compliance with low-level radioactive waste (LLW) disposal facility waste acceptance criteria (WAC). This report presents the applicable regulations representing the Federal, State, and site-specific criteria for accepting LLW. Typical LLW generators are summarized, along with descriptions of their waste streams and final waste forms. General procedures and methods used by the LLW generators to verify compliance with the disposal facility WAC are presented. The report was written to provide an understanding of how a regulator could verify compliance with a LLW disposal facility`s WAC. A comprehensive study of the methodology used to verify waste generator compliance with the disposal facility WAC is presented in this report. The study involved compiling the relevant regulations to define the WAC, reviewing regulatory agency inspection programs, and summarizing waste verification technology and equipment. The results of the study indicate that waste generators conduct verification programs that include packaging, classification, characterization, and stabilization elements. The current LLW disposal facilities perform waste verification steps on incoming shipments. A model inspection and verification program, which includes an emphasis on the generator`s waste application documentation of their waste verification program, is recommended. The disposal facility verification procedures primarily involve the use of portable radiological survey instrumentation. The actual verification of generator compliance to the LLW disposal facility WAC is performed through a combination of incoming shipment checks and generator site audits.

Methods for verifying compliance with low-level radioactive waste acceptance criteria

International Nuclear Information System (INIS)

1993-09-01

This report summarizes the methods that are currently employed and those that can be used to verify compliance with low-level radioactive waste (LLW) disposal facility waste acceptance criteria (WAC). This report presents the applicable regulations representing the Federal, State, and site-specific criteria for accepting LLW. Typical LLW generators are summarized, along with descriptions of their waste streams and final waste forms. General procedures and methods used by the LLW generators to verify compliance with the disposal facility WAC are presented. The report was written to provide an understanding of how a regulator could verify compliance with a LLW disposal facility's WAC. A comprehensive study of the methodology used to verify waste generator compliance with the disposal facility WAC is presented in this report. The study involved compiling the relevant regulations to define the WAC, reviewing regulatory agency inspection programs, and summarizing waste verification technology and equipment. The results of the study indicate that waste generators conduct verification programs that include packaging, classification, characterization, and stabilization elements. The current LLW disposal facilities perform waste verification steps on incoming shipments. A model inspection and verification program, which includes an emphasis on the generator's waste application documentation of their waste verification program, is recommended. The disposal facility verification procedures primarily involve the use of portable radiological survey instrumentation. The actual verification of generator compliance to the LLW disposal facility WAC is performed through a combination of incoming shipment checks and generator site audits

A comparison of solidification media for the stabilization of low- level radioactive wastes

International Nuclear Information System (INIS)

Cowgill, M.G.

1991-10-01

When requirements exist to stabilize low-level radioactive waste (LLW) prior to disposal, efforts to achieve this stability often center on the mixing of the waste with a solidification medium. Although historically the medium of choice has been based on the use of portland cement as the binder material, several other options have been developed and subsequently implemented. These include thermoplastic polymers, thermosetting polymers and gypsum. No one medium has thus far been successful in providing stability to all forms of LLW. The characteristics and attributes of these different binder materials are reviewed and compared. The aspects examined include availability of information, limitations to use, sensitivity to process or waste chemistry changes, radionuclide retention ability, modeling of radionuclide release processes, ease and safety of use, and relative costs

INEL waste reduction: summary paper

International Nuclear Information System (INIS)

Rhoades, W.A.

1987-01-01

The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE) facility located in southeastern Idaho. Located at the INEL are a Waste Experimental Reduction Facility (WERF) which processes low level radioactive waste (LLW) materials and a Radioactive Waste Management Complex (RWMC) which provides for disposal of radioactive waste materials. There are currently 9 active facilities (waste generators) at the INEL which produce an average total volume of about 5000 cubic meters of solid LLW annually. This boxed or bulk waste is ultimately disposed of at the RWMC Subsurface Disposal Area (SDA). The SDA is currently the only active LLW disposal site at the INEL, and the prospects for opening another shallow land burial disposal facility are uncertain. Therefore, it has become imperative that EG and G Idaho Waste Management Department make every reasonable effort to extend the disposal life of the SDA. Among Waste Management Department's principal efforts to extend the SDA disposal life are operation of the Waste Experimental Reduction Facility (WERF) and administration of the INEL Waste Reduction Program. The INEL Waste Reduction Program is charged with providing assistance to all INEL facilities in reducing LLW generation rates to the lowest practical levels while at the same time encouraging optimum utilization of the volume reduction capabilities of WERF. Both waste volume and waste generation reductions are discussed

HAZWDDD [Hazardous Waste Development, Demonstration, and Disposal]: An exercise in corporate planning

International Nuclear Information System (INIS)

McGinnis, C.P.; Pechin, W.H.

1988-01-01

Both Energy Systems corporate management and US Department of Energy's Oak Ridge Operations Office (DOE-ORO) management have recognized the seriousness of these problems and have established several programs to determine acceptable courses of action. A plan has been developed for low-level radioactive waste (LLW), and an active dialogue pertaining to LLW is maintained with the state and federal regulators. During 1986, DOE-ORO and Energy Systems identified the need for a plan to address hazardous and mixed wastes. Each installation supports the concept of HAZWDDD through funding and the development of individual HAZWDDD implementation plans. A corporate plan is being developed to integrate the issues discussed in the five installation plans. This paper describes the approach taken in collecting the necessary information for the plan, some of the techniques used in analyzing the information provided, preliminary data that have been collected in preparation of this plan, the identification of common concerns and issues, and the integration of this information into a corporate approach to mixed and hazardous waste management. 1 fig., 5 tabs

LLW disposal wasteform preparation in the UK: the role of high force compaction

Energy Technology Data Exchange (ETDEWEB)

Johnson, L. F.; Fearnley, I. G. [British Nuclear Fuels Ltd., Sellafield (United Kingdom)

1991-07-01

British Nuclear Fuels plc (BNFL) owns and operates the principal UK solid low level radioactive waste (LLW) disposal site. The site is located at Drigg in West Cumbria some 6 km to the south east of BNFL's Sellafield reprocessing complex. Sellafield is the major UK generator of LLW, accounting for about 85% of estimated future arisings of raw (untreated, unpackaged) waste. Non-Sellafield consignors to the Drigg site include other BNFL production establishments, nuclear power stations, sites of UKAEA, Ministry of Defence facilities, hospitals, universities, radioisotope production sites and various other industrial organisations. In September 1987, BNFL announced a major upgrade of operations at the Drigg site aimed at improving management practices, the efficiency of space utilisation and enhancing the visual impact of disposal operations. During 1989 a review of plans for compaction and containerisation of Sellafield waste identified that residual voidage in ISO freight containers could be significant even after the introduction of compaction. Subsequent studies which examined a range of compaction and packaging options concluded that the preferred scheme centred on the use of high force compaction (HFC) of compactable waste, and grouting to take up readily accessible voidage in the wasteform. The paper describes the emergence of high force compaction as the preferred scheme for wasteform preparation and subsequent benefits against the background of the overall development of Low Level Waste disposal operations at Drigg.

LLW disposal wasteform preparation in the UK: the role of high force compaction

International Nuclear Information System (INIS)

Johnson, L. F.; Fearnley, I. G.

1991-01-01

British Nuclear Fuels plc (BNFL) owns and operates the principal UK solid low level radioactive waste (LLW) disposal site. The site is located at Drigg in West Cumbria some 6 km to the south east of BNFL's Sellafield reprocessing complex. Sellafield is the major UK generator of LLW, accounting for about 85% of estimated future arisings of raw (untreated, unpackaged) waste. Non-Sellafield consignors to the Drigg site include other BNFL production establishments, nuclear power stations, sites of UKAEA, Ministry of Defence facilities, hospitals, universities, radioisotope production sites and various other industrial organisations. In September 1987, BNFL announced a major upgrade of operations at the Drigg site aimed at improving management practices, the efficiency of space utilisation and enhancing the visual impact of disposal operations. During 1989 a review of plans for compaction and containerisation of Sellafield waste identified that residual voidage in ISO freight containers could be significant even after the introduction of compaction. Subsequent studies which examined a range of compaction and packaging options concluded that the preferred scheme centred on the use of high force compaction (HFC) of compactable waste, and grouting to take up readily accessible voidage in the wasteform. The paper describes the emergence of high force compaction as the preferred scheme for wasteform preparation and subsequent benefits against the background of the overall development of Low Level Waste disposal operations at Drigg

Greater-than-Class-C low-level radioactive waste management concepts

International Nuclear Information System (INIS)

Knecht, M.A.

1988-01-01

In 1986, Public Law 99-240, the Low-Level Radioactive Waste Policy Amendments Act of 1985 assigned to the Federal Government responsibility for the disposal of commercial greater-than-Class-C (GTCC) low-level radioactive waste (LLW). In 1987, DOE committed to Congress to accept GTCC LLW and provide storage and other waste management as necessary until disposal capacity is available. Current estimates are that about 6,000 m 3 of unpackaged GTCC LLW will be generated to the year 2020. Generators estimate that 100 m 3 of raw GTCC LLW might exceed planned storage capacity to the year 2020. This paper reports the activities of the National Low-Level Waste Program to manage GTCC low-level radioactive waste

Lessons learned from international siting experiences of LLW Disposal facilities

International Nuclear Information System (INIS)

McCabe, G.H.

1990-01-01

This paper reports that the United States can gain insight into successfully siting low-level radioactive waste (LLW) disposal facilities by studying the process in other nations. Siting experiences in France and Sweden are compared to experiences in the United States. Three factors appear to making siting of LLW disposal facilities easier in France and Sweden than in the United States. First, the level of public trust in the government and the entities responsible for siting, developing, and operating a LLW disposal facility is much greater in France and Sweden than in the United States. Second, France and Sweden are much more dependent on nuclear power than is the United States. Third, French and Swedish citizens do not have the same access to the siting process (i.e., legal means to intervene) as do U.S. citizens. To compensate for these three factors, public officials responsible for siting a facility may need to better listen to the concerns of public interest groups and citizen advisory committees and amend their siting process accordingly and better share power and control with the public. If these two techniques are implemented earnestly by the states, siting efforts may be increasingly more successful in the United States

The role of the national low level waste repository operator in delivering new solutions for the management of low level wastes in the UK - 16217

International Nuclear Information System (INIS)

Walkingshaw, Martin

2009-01-01

The UK National Low Level Waste Repository (LLWR) is located near to the village of Drigg in West Cumbria. It is the principal site for disposal of solid Low Level Radioactive Waste (LLW) in the United Kingdom. This paper describes the program of work currently being undertaken by the site's operators, (LLW Repository Ltd and its newly appointed Parent Body Organisation), to extend the life of the LLWR and reduce the overall cost of LLW management to the UK taxpayer. The current focus of this program is to prevent disposal capacity being taken up at LLWR by waste types which lend themselves to alternative treatment and/or disposition routes. The chosen approach enables consignors to segregate LLW at source into formats which allow further treatment for volume reduction or, (for wastes with lower levels of activity), consignment in the future to alternative disposal facilities. Segregated waste services are incorporated into LLW Disposal commercial agreements between the LLWR operator and waste consignors. (author)

Defense waste management operations at the Nevada Test Site

International Nuclear Information System (INIS)

Williams, R.E.; Kendall, E.W.

1988-01-01

Waste management activities were initiated at the Nevada Test Site (NTS) to dispose of low-level wastes (LLW) produced by the Department of Energy's (DOE's) weapons testing program. Disposal activities have expanded from the burial of atmospheric weapons testing debris to demonstration facilities for greater-than-Class C (GTCC) waste, transuranic (TRU) waste storage and certification, and the development of a mixed waste (MW) facility. Site specific operational research projects support technology development required for the various disposal facilities. The annual cost of managing the facilities is about $6 million depending on waste volumes and types

HAXWDDD (Hazardous Waste Development, Demonstration, and Disposal) - An exercise in corporate planning

International Nuclear Information System (INIS)

McGinnis, C.P.; Pechin, W.H.

1988-01-01

The Hazardous Waste Development, Demonstration, and Disposal (HAZWDDD) program is a corporate initiative that is coordinated between Martin Marietta Energy Systems, Inc. (Energy Systems), and the US Department of Energy's Oak Ridge Operations Office (DOE-ORO). The major objective of HAZWDDD is to develop a comprehensive management strategy for the hazardous and mixed wastes generated by the five Energy Systems installations. This program is of prime importance because federal and state regulations for handling hazardous wastes are becoming increasingly stringent and the generator of such wastes retains legally mandated liability for their disposal indefinitely. In addition, no acceptable method is currently available for handling mixed (hazardous and radioactive) wastes. Both Energy Systems corporate management and DOE-ORO management have recognized the seriousness of these problems and have established several programs to determine acceptable courses of action. A plan has been developed for low-level radioactive waste (LLW), and an active dialogue pertaining to LLW is maintained with the state and federal regulators. During 1986, DOE-ORO and Energy Systems identified the need for a plan to address hazardous and mixed wastes. Each installation supports the concept of HAZWDDD through funding and the development of individual HAZWDDD implementation plans. A corporate plan is being developed to integrate the issues discussed in the five installation plans. This paper describes: (1) the approach taken in collecting the necessary information for the plan; (2) some of the techniques used in analyzing the information provided; (3) preliminary data that have been collected in preparation of this plan, (4) the identification of common concerns and issues, and (5) the integration of this information into a corporate approach to mixed and hazardous waste management

Waste Inspection Tomography (WIT)

International Nuclear Information System (INIS)

Bernardi, R.T.

1995-01-01

Waste Inspection Tomography (WIT) provides mobile semi-trailer mounted nondestructive examination (NDE) and assay (NDA) for nuclear waste drum characterization. WIT uses various computed tomography (CT) methods for both NDE and NDA of nuclear waste drums. Low level waste (LLW), transuranic (TRU), and mixed radioactive waste can be inspected and characterized without opening the drums. With externally transmitted x-ray NDE techniques, WIT has the ability to identify high density waste materials like heavy metals, define drum contents in two- and three-dimensional space, quantify free liquid volumes through density and x-ray attenuation coefficient discrimination, and measure drum wall thickness. With waste emitting gamma-ray NDA techniques, WIT can locate gamma emitting radioactive sources in two- and three-dimensional space, identify gamma emitting isotopic species, identify the external activity levels of emitting gamma-ray sources, correct for waste matrix attenuation, provide internal activity approximations, and provide the data needed for waste classification as LLW or TRU. The mobile feature of WIT allows inspection technologies to be brought to the nuclear waste drum storage site without the need to relocate drums for safe, rapid, and cost-effective characterization of regulated nuclear waste. The combination of these WIT characterization modalities provides the inspector with an unprecedented ability to non-invasively characterize the regulated contents of waste drums as large as 110 gallons, weighing up to 1,600 pounds. Any objects that fit within these size and weight restrictions can also be inspected on WIT, such as smaller waste bags and drums that are five and thirty-five gallons

Impacts of hazardous waste regulation on low-level waste management

International Nuclear Information System (INIS)

Sharples, F.E.; Eyman, L.D.

1987-01-01

Since passage of the 1984 amendments to the Resource Conservation and Recovery Act (RCRA), major changes have occurred in the regulation of hazardous waste. The US Environmental Protection Agency (EPA) has also greatly modified its interpretation of how these regulations apply to wastes from federal facilities, including defense wastes from US Department of Energy (DOE) sites. As a result, the regulatory distinctions between low-level radioactive waste (LLW) and hazardous waste are becoming blurred. This paper discusses recent statutory and regulatory changes and how they might affect the management of LLW at DOE facilities. 6 references

Restraint effect of water infiltration by soil cover types of LLW disposal facility

International Nuclear Information System (INIS)

Park, S. M.; Lee, E. Y.; Lee, C. K.; Kim, C. L.

2002-01-01

Since soil cover for LLW disposal vault shows quite different restraint effect of water infiltration depending on its type, four different types of soil cover were studied and simulated using HELP code. Simulation result showed that Profile B1 is the most effective type in restraint of water infiltration to the disposal vault. Profile B1 is totally 6m thick and composed of silt, gravelly sand, pea gravel, sand and clayey soil mixed with bentonite 20%. Profile B1 also includes artificial layers, such as asphalt and geomembrane layers. This profile is designed conceptually by NETEC for the soil cover of the near surface disposal facility of the low-level radioactive waste. For comparison, 3 types of different profile were tested. One profile includes bentonite mixed layer only as water barrier layer, or one as same as profile B1 but without geomembrane layer or one without asphalt layer respectively. The simulation using HELP code showed that the water balance in profile B1 was effectively controlled

AECL's mixed waste management program

International Nuclear Information System (INIS)

Peori, R.; Hulley, V.

2006-01-01

Every nuclear facility has it, they wish that they didn't but they have generated and do possess m ixed waste , and until now there has been no permanent disposition option; it has been for the most been simply maintained in interim storage. The nuclear industry has been responsibly developing permanent solutions for solid radioactive waste for over fifty years and for non-radioactive, chemically hazardous waste, for the last twenty years. Mixed waste (radioactive and chemically hazardous waste) however, because of its special, duo-hazard nature, has been a continuing challenge. The Hazardous Waste and Segregation Program (HW and SP) at AECL's CRL has, over the past ten years, been developing solutions to deal with their own in-house mixed waste and, as a result, have developed solutions that they would like to share with other generators within the nuclear industry. The main aim of this paper is to document and describe the early development of the solutions for both aqueous and organic liquid wastes and to advertise to other generators of this waste type how these solutions can be implemented to solve their mixed waste problems. Atomic Energy of Canada Limited (AECL) and in particular, CRL has been satisfactorily disposing of mixed waste for the last seven years. CRL has developed a program that not only disposes of mixed waste, but offers a full service mixed waste management program to customers within Canada (that could eventually include U.S. sites as well) that has developed the experience and expertise to evaluate and optimize current practices, dispose of legacy inventories, and set up an efficient segregation system to reduce and effectively manage, both the volumes and expense of, the ongoing generation of mixed waste for all generators of mixed waste. (author)

Greater-than-Class C low-level radioactive waste characterization. Appendix E-4: Packaging factors for greater-than-Class C low-level radioactive waste

International Nuclear Information System (INIS)

Quinn, G.; Grant, P.; Winberg, M.; Williams, K.

1994-09-01

This report estimates packaging factors for several waste types that are potential greater-than-Class C (GTCC) low-level radioactive waste (LLW). The packaging factor is defined as the volume of a GTCC LLW disposal container divided by the as-generated or ''unpackaged'' volume of the waste loaded into the disposal container. Packaging factors reflect any processes that reduce or increase an original unpackaged volume of GTCC LLW, the volume inside a waste container not occupied by the waste, and the volume of the waste container itself. Three values are developed that represent (a) the base case or most likely value for a packaging factor, (b) a high case packaging factor that corresponds to the largest anticipated disposal volume of waste, and (c) a low case packaging factor for the smallest volume expected. GTCC LLW is placed in three categories for evaluation in this report: activated metals, sealed sources, and all other waste

Analysis of the low-level waste radionuclide inventory for the Radioactive Waste Management Complex performance assessment

Energy Technology Data Exchange (ETDEWEB)

Plansky, L.E.; Hoiland, S.A.

1992-02-01

This report summarizes the results of a study to improve the estimates of the radionuclides in the low-level radioactive waste (LLW) inventory which is buried in the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC) Subsurface Disposal Area (SDA). The work is done to support the RWMC draft performance assessment (PA). Improved radionuclide inventory estimates are provided for the INEL LLW generators. Engineering, environmental assessment or other research areas may find use for the information in this report. It may also serve as a LLW inventory baseline for data quality assurance. The individual INEL LLW generators, their history and their activities are also described in detail.

Analysis of the low-level waste radionuclide inventory for the Radioactive Waste Management Complex performance assessment

International Nuclear Information System (INIS)

Plansky, L.E.; Hoiland, S.A.

1992-02-01

This report summarizes the results of a study to improve the estimates of the radionuclides in the low-level radioactive waste (LLW) inventory which is buried in the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC) Subsurface Disposal Area (SDA). The work is done to support the RWMC draft performance assessment (PA). Improved radionuclide inventory estimates are provided for the INEL LLW generators. Engineering, environmental assessment or other research areas may find use for the information in this report. It may also serve as a LLW inventory baseline for data quality assurance. The individual INEL LLW generators, their history and their activities are also described in detail

Secondary Low-Level Waste Treatment Strategy Analysis

International Nuclear Information System (INIS)

D.M. LaRue

1999-01-01

The objective of this analysis is to identify and review potential options for processing and disposing of the secondary low-level waste (LLW) that will be generated through operation of the Monitored Geologic Repository (MGR). An estimate of annual secondary LLW is generated utilizing the mechanism established in ''Secondary Waste Treatment Analysis'' (Reference 8.1) and ''Secondary Low-Level Waste Generation Rate Analysis'' (Reference 8.5). The secondary LLW quantities are based on the spent fuel and high-level waste (HLW) arrival schedule as defined in the ''Controlled Design Assumptions Document'' (CDA) (Reference 8.6). This analysis presents estimates of the quantities of LLW in its various forms. A review of applicable laws, codes, and standards is discussed, and a synopsis of those applicable laws, codes, and standards and their impacts on potential processing and disposal options is presented. The analysis identifies viable processing/disposal options in light of the existing laws, codes, and standards, and then evaluates these options in regard to: (1) Process and equipment requirements; (2) LLW disposal volumes; and (3) Facility requirements

Managing a mixed waste program

International Nuclear Information System (INIS)

Koch, J.D.

1994-01-01

IT Corporation operates an analytical laboratory in St. Louis capable of analyzing environmental samples that are contaminated with both chemical and radioactive materials. Wastes generated during these analyses are hazardous in nature; some are listed wastes others exhibit characteristic hazards. When the original samples contain significant quantities of radioactive material, the waste must be treated as a mixed waste. A plan was written to document the waste management program describing the management of hazardous, radioactive and mixed wastes. This presentation summarizes the methods employed by the St. Louis facility to reduce personnel exposures to the hazardous materials, minimize the volume of mixed waste and treat the materials prior to disposal. The procedures that are used and the effectiveness of each procedure will also be discussed. Some of the lessons that have been learned while dealing with mixed wastes will be presented as well as the solutions that were applied. This program has been effective in reducing the volume of mixed waste that is generated. The management program also serves as a method to manage the costs of the waste disposal program by effectively segregating the different wastes that are generated

Defense waste management operations at the Nevada Test Site

International Nuclear Information System (INIS)

Williams, R.E.; Kendall, E.W.

1988-01-01

Waste management activities were initiated at the Nevada Test Site (NTS) to dispose of low-level wastes (LLW) produced by the Department of Energy's (DOE's) weapons testing program. Disposal activities have expanded from the burial of atmospheric weapons testing debris to demonstration facilities for greater-than-Class-C (GTCC) waste, transuranic (TRU) waste storage and certification, and the development of a mixed waste (MW) facility. Site specific operational research projects support technology development required for the various disposal facilities. The annual cost of managing the facilities is about $6 million depending on waste volumes and types. The paper discusses site selection; establishment of the Radioactive Waste Management Project; operations with respect to low-level radioactive wastes, transuranic waste storage, greater confinement disposal test, and mixed waste management facility; and related research activities such as tritium migration studies, revegetation studies, and in-situ monitoring of organics

Modeling the economics of LLW volume reduction

International Nuclear Information System (INIS)

Voth, M.H.; Witzig, W.F.

1986-01-01

Generators of low-level (radioactive) waste (LLW) are under pressure to implement volume reduction (VR) programs for political and economic reasons. Political reasons include the appearance of generating less waste or meeting quotas. Economic reasons include avoiding high disposal costs and associated surcharges. Volume reduction results in less total volume over which fixed disposal costs are allocated and therefore higher unit costs for disposal. As numerous small compacts are developed, this often overlooked effect becomes more pronounced. The described model presents two unique significant features. First, a feedback loop considers the impact of VR on disposal rates, and second, it appeals to logic without extensive knowledge of VR technology or computer modeling. The latter feature is especially useful in conveying information to students and nontechnical decision makers, demonstrating the impact of each of a complicated set of variables with reproducible results

Nondestructive and quantitative characterization of TRU and LLW mixed-waste using active and passive gamma-ray spectrometry and computed tomography

Energy Technology Data Exchange (ETDEWEB)

Camp, D.C.; Martz, H.E.

1991-11-12

The technology being proposed by LLNL is an Active and Passive Computed Tomography (A P CT) Drum Scanner for contact-handled (CH) wastes. It combines the advantages offered by two well-developed nondestructive assay technologies: gamma-ray spectrometry and computed tomography (CT). Coupled together, these two technologies offer to nondestructively and quantitatively characterize mixed- wastes forms. Gamma-ray spectroscopy uses one or more external radiation detectors to passively and nondestructively measure the energy spectrum emitted from a closed container. From the resulting spectrum one can identify most radioactivities detected, be they transuranic isotopes, mixed-fission products, activation products or environmental radioactivities. Spectral libraries exist at LLNL for all four. Active (A) or transmission CT is a well-developed, nondestructive medical and industrial technique that uses an external-radiation beam to map regions of varying attenuation within a container. Passive (P) or emission CT is a technique mainly developed for medical application, e.g., single-photon emission CT. Nondestructive industrial uses of PCT are under development and just coming into use. This report discuses work on the A P CT Drum Scanner at LLNL.

Low-level radioactive waste research program plan

International Nuclear Information System (INIS)

O'Donnell, E.; Lambert, J.

1989-11-01

The Waste Management Branch, Division of Engineering, Office of Nuclear Regulatory Research, has developed a strategy for conducting research on issues of concern to the US Nuclear Regulatory Commission (NRC) in its efforts to ensure safe disposal of low-level radioactive waste (LLW). The resulting LLW research program plan provides an integrated framework for planning the LLW research program to ensure that the program and its products are responsive and timely for use in NRC's LLW regulatory program. The plan discusses technical and scientific issues and uncertainties associated with the disposal of LLW, presents programmatic goals and objectives for resolving them, establishes a long-term strategy for conducting the confirmatory and investigative research needed to meet these goals and objectives, and includes schedules and milestones for completing the research. Areas identified for investigation include waste form and other material concerns, failure mechanisms and radionuclide releases, engineered barrier performance, site characterization and monitoring, and performance assessment. The plan proposes projects that (1) analyze and test actual LLW and solidified LLW under laboratory and field conditions to determine leach rates and radionuclide releases, (2) examine the short- and long-term performance of concrete-enhanced LLW burial structures and high-integrity containers, and (3) attempt to predict water movement and contaminant transport through low permeability saturated media and unsaturated porous media. 4 figs., 3 tabs

Low-level radioactive waste disposal in the USA - Use of mill tailings impoundments as a new policy option

International Nuclear Information System (INIS)

Farrell, C.W.

2006-01-01

Disposal of low-level radioactive waste (LLW) in the United States is facing severe and immediate capacity limitations. Seemingly intractable regulatory and jurisdictional conflicts make establishment of new LLW disposal sites effectively impossible. Uranium mill tailings impoundments constructed at conventional uranium open-cast and underground mines could offer approximately 40 to 80+ million tons of disposal capacity for low activity radioactive waste. Such impoundments would provide an enhanced, high level of environmental and health and safety protection for the direct disposal of depleted uranium, special nuclear material, technologically-enhanced, naturally-occurring radioactive material (TENORM) and mixed waste. Many waste streams, such as TENORM and decommissioning rubble, will be high-volume, low activity materials and ideally suited for disposal in such structures. Materials in a given decay chain with a total activity from all radionuclides present of ∼820 Bq/g (2.22 x 10 -08 Ci/g) with no single radionuclide present in an activity greater than ∼104 Bq/g (2,800 pCi/g) should be acceptable for disposal. Materials of this type could be accepted without any site-specific dose modelling, so long as the total activity of the tailings impoundment not exceed its design capacity (generally 82 x 10 07 Bq/metric tonne) (0.020 Ci/short ton) and the cover design requirements to limit radon releases are satisfied. This paper provides background on US LLW disposal regulations, examines LLW disposal options under active consideration by the US Environmental Protection Agency and Department of Energy, develops generic waste acceptance criteria and identifies policy needs for federal and state governments to facilitate use of uranium mill tailings impoundments for LLW disposal. (author)

Low-level waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the US Department of Energy waste management programmatic environmental impact statement

Energy Technology Data Exchange (ETDEWEB)

Goyette, M.L.; Dolak, D.A.

1996-12-01

This report provides technical support information for use in analyzing environmental impacts associated with U.S. Department of Energy (DOE) low-level radioactive waste (LLW) management alternatives in the Waste-Management (WM) Programmatic Environmental Impact Statement (PEIS). Waste loads treated and disposed of for each of the LLW alternatives considered in the DOE WM PEIS are presented. Waste loads are presented for DOE Waste Management (WM) wastes, which are generated from routine operations. Radioactivity concentrations and waste quantities for treatment and disposal under the different LLW alternatives are described for WM waste. 76 refs., 14 figs., 42 tabs.

Mixed wasted integrated program: Logic diagram

International Nuclear Information System (INIS)

Mayberry, J.; Stelle, S.; O'Brien, M.; Rudin, M.; Ferguson, J.; McFee, J.

1994-01-01

The Mixed Waste Integrated Program Logic Diagram was developed to provide technical alternative for mixed wastes projects for the Office of Technology Development's Mixed Waste Integrated Program (MWIP). Technical solutions in the areas of characterization, treatment, and disposal were matched to a select number of US Department of Energy (DOE) treatability groups represented by waste streams found in the Mixed Waste Inventory Report (MWIR)

Mixed wasted integrated program: Logic diagram

Energy Technology Data Exchange (ETDEWEB)

Mayberry, J.; Stelle, S. [Science Applications International Corp., Idaho Falls, ID (United States); O`Brien, M. [Univ. of Arizona, Tucson, AZ (United States); Rudin, M. [Univ. of Nevada, Las Vegas, NV (United States); Ferguson, J. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); McFee, J. [I.T. Corp., Albuquerque, NM (United States)

1994-11-30

The Mixed Waste Integrated Program Logic Diagram was developed to provide technical alternative for mixed wastes projects for the Office of Technology Development`s Mixed Waste Integrated Program (MWIP). Technical solutions in the areas of characterization, treatment, and disposal were matched to a select number of US Department of Energy (DOE) treatability groups represented by waste streams found in the Mixed Waste Inventory Report (MWIR).

Feed Materials Production Center Waste Management Plan

International Nuclear Information System (INIS)

Watts, R.E.; Allen, T.; Castle, S.A.; Hopper, J.P.; Oelrich, R.L.

1986-01-01

In the process of producing uranium metal products used in Department of Energy (DOE) defense programs at other DOE facilities, various types of wastes are generated at the Feed Materials Production Center (FMPC). Process wastes, both generated and stored, are discussed in the Waste Management Plan and include low-level radioactive waste (LLW), mixed hazardous/radioactive waste, and sanitary/industrial waste. Scrap metal waste and wastes requiring special remediation are also addressed in the Plan. The Waste Management Plan identifies the comprehensive programs developed to address safe storage and disposition of all wastes from past, present, and future operations at the FMPC. Waste streams discussed in this Plan are representative of the waste generated and waste types that concern worker and public health and safety. Budgets and schedules for implementation of waste disposition are also addressed. The waste streams receiving the largest amount of funding include LLW approved for shipment by DOE/ORO to the Nevada Test Site (NTS) (MgF 2 , slag leach filter cake, and neutralized raffinate); remedial action wastes (waste pits, K-65 silo waste); thorium; scrap metal (contaminated and noncontaminated ferrous and copper scrap); construction rubble and soil generated from decontamination and decommissioning of outdated facilities; and low-level wastes that will be handled through the Low-Level Waste Processing and Shipping System (LLWPSS). Waste Management milestones are also provided. The Waste Management Plan is divided into eight major sections: Introduction; Site Waste and Waste Generating Process; Strategy; Projects and Operations; Waste Stream Budgets; Milestones; Quality Assurance for Waste Management; and Environmental Monitoring Program

The establishment of computer codes for radiological assessment on LLW final disposal in Taiwan

International Nuclear Information System (INIS)

Yang, C.C.; Chen, H.T.; Shih, C.L.; Yeh, C.S.; Tsai, C.M.

1988-01-01

For final shallow land disposal of Low Level Waste (LLW) in Taiwan, an effort was initiated to establish the evaluation codes for the needs of environmental impact analysis. The objective of the computer code is to set up generic radiological standards for future evaluation on 10 CFR Part 61 Licensing Requirements for Land Disposal of Radioactive Wastes. In determining long-term influences resulting from radiological impacts of LLW at disposal sites there are at least three quantifiable impact measures selected for calculation: dose to members of the public (individual and population), occupational exposures and costs. The computer codes are from INTRUDE, INVERSI and INVERSW of NUREG-0782, OPTIONR and GRWATRR of NUREG-0945. They are both installed in FACOM-M200 and IBM PC/AT systems of Institute of Nuclear Energy Research (INER). The systematic analysis of the computer codes depends not only on the data bases supported by NUREG/CR-1759 - Data Base for Radioactive Waste Management, Volume 3, Impact Analysis Methodology Report but also the information collected from the different exposure scenarios and pathways. The sensitivity study is also performed to assure the long-term stability and security for needs of determining performance objectives

Nonradiological groundwater quality at low-level radioactive waste disposal sites

International Nuclear Information System (INIS)

Goode, D.J.

1986-04-01

The NRC is investigating appropriate regulatory options for disposal of low-level radioactive waste containing nonradiological hazardous constituents, as defined by EPA regulations. Standard EPA/RCRA procedures to determine hazardous organics, metals, indicator parameters, and general water quality are applied to samples from groundwater monitoring wells at two commercial low-level radioactive waste disposal sites. At the Sheffield, IL site (nonoperating), several typical organic solvents are identified in elevated concentrations in onsite wells and in an offsite area exhibiting elevated tritium concentrations. At the Barnwell, SC site (operating), only very low concentrations of three organics are found in wells adjacent to disposal units. Hydrocarbons associated with petroleum products are detected at both sites. Hazardous constituents associated with previosuly identified major LLW mixed waste streams, toluene, xylene, chromium, and lead, are at or below detection limits or at background levels in all samples. Review of previously collected data also supports the conclusion that organic solvents are the primary nonradiological contaminants associated with LLW disposal

Regulatory aspects of mixed waste

International Nuclear Information System (INIS)

Boyle, R.R.; Orlando, D.A.

1990-01-01

Mixed waste is waste that satisfies the definition of low-level radioactive waste in the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) and contains hazardous waste that is either: (1) listed as a hazardous waste in 40 CFR 261, Subpart D; or (2) causes the waste to exhibit any of the characteristics identified in 40 CFR 261, Subpart C. Low-level radioactive waste is defined in the LLRWPAA as radioactive material that is not high level waste, spent nuclear fuel, or byproduct material, as defined in Section 11e(2) of the Atomic Energy Act of 1954, and is classified as low-level waste by the U.S. Nuclear Regulatory Commission (NRC). This paper discusses dual regulatory (NRC and Environmental Protection Agency) responsibility, overview of joint NRC/EPA guidance, workshops, national mixed waste survey, and principal mixed waste uncertainties

Scenario sensitivity analyses performed on the PRESTO-EPA LLW risk assessment models

International Nuclear Information System (INIS)

Bandrowski, M.S.

1988-01-01

The US Environmental Protection Agency (EPA) is currently developing standards for the land disposal of low-level radioactive waste. As part of the standard development, EPA has performed risk assessments using the PRESTO-EPA codes. A program of sensitivity analysis was conducted on the PRESTO-EPA codes, consisting of single parameter sensitivity analysis and scenario sensitivity analysis. The results of the single parameter sensitivity analysis were discussed at the 1987 DOE LLW Management Conference. Specific scenario sensitivity analyses have been completed and evaluated. Scenario assumptions that were analyzed include: site location, disposal method, form of waste, waste volume, analysis time horizon, critical radionuclides, use of buffer zones, and global health effects

Quality checking of radioactive and hazardous waste

International Nuclear Information System (INIS)

Billington, D.M.; Burgoyne, S.M.J.; Dale, C.J.

1992-01-01

This report describes the work of the HMIP Waste Quality Checking Laboratory (WQCL) for the period September 1989 -August 1991. The WQCL has conducted research and development of procedures for the receipt, sampling and analysis of low level solid radioactive waste (LLW), intermediate level radioactive waste (ILW) and hazardous chemical waste (HW). Operational facilities have been commissioned for quality checking both LLW and HW. Waste quality checking has been completed on LLW packages seized from the UK waste disposal route by HMIP Inspectors. Packages have ranged in size from the 200 litre steel drum to half-height ISO freight container. Development work was continued on methods of sample extraction and radio-chemical analysis for cement encapsulated ILW in the form of magnox, graphite and stainless steel. This work was undertaken on non-radioactive simulants. (author)

Mixed Waste Focus Area - Waste form initiative

International Nuclear Information System (INIS)

Nakaoka, R.; Waters, R.; Pohl, P.; Roach, J.

1998-01-01

The mission of the US Department of Energy's (DOE) Mixed Waste Focus Area (MWFA) is to provide acceptable technologies that enable implementation of mixed waste treatment systems which are developed in partnership with end-users, stakeholders, tribal governments, and regulators. To accomplish this mission, a technical baseline was established in 1996 and revised in 1997. The technical baseline forms the basis for determining which technology development activities will be supported by the MWFA. The primary attribute of the technical baseline is a set of prioritized technical deficiencies or roadblocks related to implementation of mixed waste treatment systems. The Waste Form Initiative (WFI) was established to address an identified technical deficiency related to waste form performance. The primary goal of the WFI was to ensure that the mixed low-level waste (MLLW) treatment technologies being developed, currently used, or planned for use by DOE would produce final waste forms that meet the waste acceptance criteria (WAC) of the existing and/or planned MLLW disposal facilities. The WFI was limited to an evaluation of the disposal requirements for the radioactive component of MLLW. Disposal requirements for the hazardous component are dictated by the Resource Conservation and Recovery Act (RCRA), and were not addressed. This paper summarizes the technical basis, strategy, and results of the activities performed as part of the WFI

Radioactive waste management complex low-level waste radiological composite analysis

Energy Technology Data Exchange (ETDEWEB)

McCarthy, J.M.; Becker, B.H.; Magnuson, S.O.; Keck, K.N.; Honeycutt, T.K.

1998-05-01

The composite analysis estimates the projected cumulative impacts to future members of the public from the disposal of low-level radioactive waste (LLW) at the Idaho National Engineering and Environmental Laboratory (INEEL) Radioactive Waste Management Complex (RWMC) and all other sources of radioactive contamination at the INEEL that could interact with the LLW disposal facility to affect the radiological dose. Based upon the composite analysis evaluation, waste buried in the Subsurface Disposal Area (SDA) at the RWMC is the only source at the INEEL that will significantly interact with the LLW facility. The source term used in the composite analysis consists of all historical SDA subsurface disposals of radionuclides as well as the authorized LLW subsurface disposal inventory and projected LLW subsurface disposal inventory. Exposure scenarios evaluated in the composite analysis include all the all-pathways and groundwater protection scenarios. The projected dose of 58 mrem/yr exceeds the composite analysis guidance dose constraint of 30 mrem/yr; therefore, an options analysis was conducted to determine the feasibility of reducing the projected annual dose. Three options for creating such a reduction were considered: (1) lowering infiltration of precipitation through the waste by providing a better cover, (2) maintaining control over the RWMC and portions of the INEEL indefinitely, and (3) extending the period of institutional control beyond the 100 years assumed in the composite analysis. Of the three options investigated, maintaining control over the RWMC and a small part of the present INEEL appears to be feasible and cost effective.

Radioactive waste management complex low-level waste radiological composite analysis

International Nuclear Information System (INIS)

McCarthy, J.M.; Becker, B.H.; Magnuson, S.O.; Keck, K.N.; Honeycutt, T.K.

1998-05-01

The composite analysis estimates the projected cumulative impacts to future members of the public from the disposal of low-level radioactive waste (LLW) at the Idaho National Engineering and Environmental Laboratory (INEEL) Radioactive Waste Management Complex (RWMC) and all other sources of radioactive contamination at the INEEL that could interact with the LLW disposal facility to affect the radiological dose. Based upon the composite analysis evaluation, waste buried in the Subsurface Disposal Area (SDA) at the RWMC is the only source at the INEEL that will significantly interact with the LLW facility. The source term used in the composite analysis consists of all historical SDA subsurface disposals of radionuclides as well as the authorized LLW subsurface disposal inventory and projected LLW subsurface disposal inventory. Exposure scenarios evaluated in the composite analysis include all the all-pathways and groundwater protection scenarios. The projected dose of 58 mrem/yr exceeds the composite analysis guidance dose constraint of 30 mrem/yr; therefore, an options analysis was conducted to determine the feasibility of reducing the projected annual dose. Three options for creating such a reduction were considered: (1) lowering infiltration of precipitation through the waste by providing a better cover, (2) maintaining control over the RWMC and portions of the INEEL indefinitely, and (3) extending the period of institutional control beyond the 100 years assumed in the composite analysis. Of the three options investigated, maintaining control over the RWMC and a small part of the present INEEL appears to be feasible and cost effective

Volume Reduction of Decommissioning Radioactive Burnable and Metal Wastes

Energy Technology Data Exchange (ETDEWEB)

Min, B. Y.; Lee, Y. J.; Yun, G. S.; Lee, K. W.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Choi, Y. K.; Cho, J. H. [SunKwang Atomic Energy Safety Co., Seoul (Korea, Republic of)

2014-10-15

A large quantity of radioactive waste was generated during the decommissioning projects. For the purpose of the volume reduction and clearance for decommissioning wastes from decommissioning projects, the incineration and high melting technology has been selected for the decommissioning wastes treatment. The volume reduction of the combustible wastes through the incineration technologies has merits from the view point of a decrease in the amount of waste to be disposed of resulting in a reduction of the disposal cost. Incineration is generally accepted as a method of reducing the volume of radioactive waste. The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. Incinerator burns waste at high temperature. Incineration of a mixture of chemically hazardous and radioactive materials, known as 'mixed waste,' has two principal goals: to reduce the volume and total chemical toxicity of the waste. Incineration itself does not destroy the metals or reduce the radioactivity of the waste. A proven melting technology is currently used for low-level waste (LLW) at several facilities worldwide. These facilities use melting as a means of processing LLW for unrestricted release of the metal or for recycling within the nuclear sector. About 16.4 tons of decommissioning combustible waste has been treated using Oxygen Enriched incineration. The incineration facility operated quite smoothly through the analysis major critical parameters of off-gas.

Volume Reduction of Decommissioning Radioactive Burnable and Metal Wastes

International Nuclear Information System (INIS)

Min, B. Y.; Lee, Y. J.; Yun, G. S.; Lee, K. W.; Moon, J. K.; Choi, Y. K.; Cho, J. H.

2014-01-01

A large quantity of radioactive waste was generated during the decommissioning projects. For the purpose of the volume reduction and clearance for decommissioning wastes from decommissioning projects, the incineration and high melting technology has been selected for the decommissioning wastes treatment. The volume reduction of the combustible wastes through the incineration technologies has merits from the view point of a decrease in the amount of waste to be disposed of resulting in a reduction of the disposal cost. Incineration is generally accepted as a method of reducing the volume of radioactive waste. The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. Incinerator burns waste at high temperature. Incineration of a mixture of chemically hazardous and radioactive materials, known as 'mixed waste,' has two principal goals: to reduce the volume and total chemical toxicity of the waste. Incineration itself does not destroy the metals or reduce the radioactivity of the waste. A proven melting technology is currently used for low-level waste (LLW) at several facilities worldwide. These facilities use melting as a means of processing LLW for unrestricted release of the metal or for recycling within the nuclear sector. About 16.4 tons of decommissioning combustible waste has been treated using Oxygen Enriched incineration. The incineration facility operated quite smoothly through the analysis major critical parameters of off-gas

Mixed waste, preparing for 1996

International Nuclear Information System (INIS)

Duke, D.L.

1995-01-01

The Environmental Protection Agency has recently approved an extension to the enforcement policy for the storage of restricted mixed waste. Under this policy, EPA assigns a reduced enforcement priority to violations of the 40CFR268.50 prohibition on storage of restricted waste. Eligibility for the lower enforcement priority afforded by the policy is subject to specified conditions. The recent extension is for a two year period, and agency personnel have advised that it may be difficult to extend the enforcement policy again. This paper reviews anticipated changes in mixed waste treatment and disposal capabilities. Types of mixed waste that may be generated, or in storage, at commercial nuclear power plants are identified. This information is evaluated to determine if the two year extension in the storage enforcement policy will be adequate for the nuclear power industry to treat or dispose of the mixed waste inventories that are identified, and if not, where potential problem areas may reside. Recommendations are then made on mixed waste management strategies

Mercury removal from solid mixed waste

International Nuclear Information System (INIS)

Gates, D.D.; Morrissey, M.; Chava, K.K.; Chao, K.

1994-01-01

The removal of mercury from mixed wastes is an essential step in eliminating the temporary storage of large inventories of mixed waste throughout the Department of Energy (DOE) complex. Currently thermal treatment has been identified as a baseline technology and is being developed as part of the DOE Mixed Waste Integrated Program (MWIP). Since thermal treatment will not be applicable to all mercury containing mixed waste and the removal of mercury prior to thermal treatment may be desirable, laboratory studies have been initiated at Oak Ridge National Laboratory (ORNL) to develop alternative remediation technologies capable of removing mercury from certain mixed waste. This paper describes laboratory investigations of the KI/I 2 leaching processes to determine the applicability of this process to mercury containing solid mixed waste

Thermal denitration and mineralization of waste constituents

Energy Technology Data Exchange (ETDEWEB)

Nenni, J.A.; Boardman, R.D.

1997-08-01

In order to produce a quality grout from LLW using hydraulic cements, proper conditioning of the waste is essential for complete cement curing. Several technologies were investigated as options for conditions. Since the LLW is dilute, removal of all, or most, of the water will significantly reduce the final waste volume. Neutralization of the LLW is also desirable since acidic liquids to not allow cement to cure properly. The nitrate compounds are very soluble and easily leached from solid waste forms; therefore, denitration is desirable. Thermal and chemical denitration technologies have the advantages of water removal, neutralization, and denitration. The inclusion of additives during thermal treatment were investigated as a method of forming insoluable waste conditions.

Thermal denitration and mineralization of waste constituents

International Nuclear Information System (INIS)

Nenni, J.A.; Boardman, R.D.

1997-01-01

In order to produce a quality grout from LLW using hydraulic cements, proper conditioning of the waste is essential for complete cement curing. Several technologies were investigated as options for conditions. Since the LLW is dilute, removal of all, or most, of the water will significantly reduce the final waste volume. Neutralization of the LLW is also desirable since acidic liquids to not allow cement to cure properly. The nitrate compounds are very soluble and easily leached from solid waste forms; therefore, denitration is desirable. Thermal and chemical denitration technologies have the advantages of water removal, neutralization, and denitration. The inclusion of additives during thermal treatment were investigated as a method of forming insoluable waste conditions

Proceedings of the US Department of Energy Office of Environmental Restoration and Waste Management: Waste reduction workshop 7

International Nuclear Information System (INIS)

1991-11-01

The focus of this workshop was on goal setting and the methods of establishing meaningful goals for a waste minimization program. These workshops assist DOE waste-generating sites in implementing waste minimization plans and programs, thus providing for optimal waste reduction within the DOE complex. All wastes are considered liquid, solid, and airborne within the categories of high-level waste, transuranic waste (TRU), low-level waste (LLW), hazardous waste, mixed waste, office waste, and sanitary waste. Topics of discussion within workshops encompass a wide range of subjects. Subjects include any method or technical activity from waste generation to disposal, such as process design or improvements, substitution of materials, waste segregation and recycling/reuse, waste treatment and processing, and administrative controls (procurement and waste awareness training). Consideration is also given to activities for remedial action and for decontamination and decommissioning

Nondestructive and quantitative characterization of TRU and LLW mixed-waste using active and passive gamma-ray spectrometry and computed tomography

International Nuclear Information System (INIS)

Camp, D.C.; Martz, H.E.

1991-01-01

The technology being proposed by LLNL is an Active and Passive Computed Tomography (A ampersand P CT) Drum Scanner for contact-handled (CH) wastes. It combines the advantages offered by two well-developed nondestructive assay technologies: gamma-ray spectrometry and computed tomography (CT). Coupled together, these two technologies offer to nondestructively and quantitatively characterize mixed- wastes forms. Gamma-ray spectroscopy uses one or more external radiation detectors to passively and nondestructively measure the energy spectrum emitted from a closed container. From the resulting spectrum one can identify most radioactivities detected, be they transuranic isotopes, mixed-fission products, activation products or environmental radioactivities. Spectral libraries exist at LLNL for all four. Active (A) or transmission CT is a well-developed, nondestructive medical and industrial technique that uses an external-radiation beam to map regions of varying attenuation within a container. Passive (P) or emission CT is a technique mainly developed for medical application, e.g., single-photon emission CT. Nondestructive industrial uses of PCT are under development and just coming into use. This report discuses work on the A ampersand P CT Drum Scanner at LLNL

Status of mixed-waste regulation

International Nuclear Information System (INIS)

Bahadur, S.

1988-01-01

Mixed waste is waste containing radionuclides regulated by the US Nuclear Regulatory Commission (NRC) under the Atomic Energy Act, as well as hazardous waste materials regulated by the Environmental Protection Agency (EPA) under the Resource Conservation and Recovery Act (RCRA). This has led to a situation of dual regulation in which both NRC and EPA regulate the same waste under requirements that at times appear conflicting. The NRC has been working with the EPA to resolve the issues associated with the dual regulation of mixed waste. Discussions between the two agencies indicate that dual regulation of mixed wastes appears technically achievable, although the procedures may be complex and burdensome to the regulated community. The staffs of both agencies have been coordinating their efforts to minimize the burden of dual regulation on state agencies and the industry. Three major issues were identified as sources of potential regulatory conflict: (a) definition and identification of mixed waste, (b) siting guidelines for disposal facilities, and (c) design concepts for disposal units

Characterization of waste streams on the Oak Ridge Reservation

International Nuclear Information System (INIS)

Rivera, A.L.; Osborne-Lee, I.W.; Jackson, A.M.; Butcher, B.T. Jr.; Van Cleve, J.E. Jr.

1987-01-01

The Oak Ridge Reservation (ORR) plants generate solid low-level waste (LLW) that must be disposed of or stored on-site. The available disposal capacity of the current sites is projected to be fully utilized during the next decade. An LLW disposal strategy has been developed by the Low-Level Waste Disposal Development and Demonstration (LLWDDD) Program as a framework for bringing new, regulator-approved disposal capacity to the ORR. An increasing level of waste stream characterization will be needed to maintain the ability to effectively manage solid LLW by the facilities on the ORR under the new regulatory scenario. In this paper, current practices for solid LLW stream characterization, segregation, and certification are described. In addition, the waste stream characterization requirements for segregation and certification under the LLWDDD Program strategy are also examined. 6 refs., 3 figs., 4 tabs

The Hazardous Waste/Mixed Waste Disposal Facility

International Nuclear Information System (INIS)

Bailey, L.L.

1991-01-01

The Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF) will provide permanent Resource Conservation and Recovery Act (RCRA) permitted storage, treatment, and disposal for hazardous and mixed waste generated at the Department of Energy's (DOE) Savannah River Site (SRS) that cannot be disposed of in existing or planned SRS facilities. Final design is complete for Phase I of the project, the Disposal Vaults. The Vaults will provide RCRA permitted, above-grade disposal capacity for treated hazardous and mixed waste generated at the SRS. The RCRA Part B Permit application was submitted upon approval of the Permit application, the first Disposal Vault is scheduled to be operational in mid 1994. The technical baseline has been established for Phase II, the Treatment Building, and preliminary design work has been performed. The Treatment Building will provide RCRA permitted treatment processes to handle a variety of hazardous and mixed waste generated at SRS in preparation for disposal. The processes will treat wastes for disposal in accordance with the Environmental Protection Agency's (EPA's) Land Disposal Restrictions (LDR). A RCRA Part B Permit application has not yet been submitted to SCDHEC for this phase of the project. The Treatment Building is currently scheduled to be operational in late 1996

Waste minimization for commercial radioactive materials users generating low-level radioactive waste

International Nuclear Information System (INIS)

Fischer, D.K.; Gitt, M.; Williams, G.A.; Branch, S.; Otis, M.D.; McKenzie-Carter, M.A.; Schurman, D.L.

1991-07-01

The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature

Proceedings of the sixth annual Participants' Information Meeting DOE Low-Level Waste Management Program

International Nuclear Information System (INIS)

1984-12-01

Sessions were held on disposal technology, characteristics and treatment of low-level waste, environmental aspects and performance prediction, predicting source terms for low-level wastes (LLW), performance assessment for LLW disposal facilities, and approaches to LLW facility siting and characteristics. Fifty-six papers were indexed separately

Impacts of hazardous waste regulation on low-level waste management

International Nuclear Information System (INIS)

Sharples, F.E.; Eyman, L.D.

1986-01-01

The Hazardous and Solid Waste Amendments of 1984 have greatly expanded the universe of what, and who, is regulated under Resource Conservation and Recovery Act (RCRA). Handling requirements for hazardous waste are becoming increasingly more stringent, particularly where land disposal is concerned. DOE needs to begin actively pursuing strategies directed at keeping the management of LLW clearly separated from wastes that are legitimately regulated under RCRA. Such strategies would include instituting systemwide changes in internal management practices, establishing improved location standards for LLW disposal, and negotiating interagency compromise agreements to obtain variances from RCRA requirements where necessary and appropriate

Waste management system functional requirements for Interim Waste Management Facilities (IWMFs) and technology demonstrations, LLWDDD [Low-Level Disposal Development and Demonstration] Program

International Nuclear Information System (INIS)

1988-03-01

The purpose of this report is to build upon the preceding decisions and body of information to prepare draft system functional requirements for each classification of waste disposal currently proposed for Low-Level Waste Disposal Development Demonstration (LLWDDD) projects. Functional requirements identify specific information and data needs necessary to satisfy engineering design criteria/objectives for Interim Waste Management Facilities. This draft will suppor the alternatives evaluation process and will continue to evolve as strategy is implemented, regulatory limits are established, technical and economic uncertainties are resolved, and waste management plans are being implemented. This document will become the planning basis for the new generation of solid LLW management facilities on new sites on the Reservation. Eighteen (18) general system requirements are identified which are applicable to all four Low-Level Waste (LLW) disposal classifications. Each classification of LLW disposal is individually addressed with respect ot waste characteristics, site considerations, facility operations, facility closure/post-closure, intruder barriers, institutional control, and performance monitoring requirements. Three initial LLW disposal sites have been proposed as locations on the ORR for the first demonstrations

Greater-than-Class C low-level waste characterization technical review process

Energy Technology Data Exchange (ETDEWEB)

Hutchison, D.; Magleby, M.

1990-01-01

Existing volume projections of greater-than-Class C low-level waste (GTCC LLW) vary significantly. The Department of Energy (DOE) National Low-Level Waste Management Program (NLLWMP) has undertaken activities to develop a best estimate of GTCC LLW volumes and activities for use as the planning basis. Initial information about the generation of GTCC LLW was obtained through a DOE Energy Information Administration survey. That information, combined with information from other related literature, formed the basis of a computer model, which projects potential GTCC LLW. This paper describes uncertainties in existing GTCC LLW characterization and volume projections data and describes the technical review process that is being used to assist in projections of GTCC LLW expected for storage and disposal. 8 refs., 2 tabs.

Greater-than-Class C low-level waste characterization technical review process

International Nuclear Information System (INIS)

Hutchison, D.; Magleby, M.

1990-01-01

Existing volume projections of greater-than-Class C low-level waste (GTCC LLW) vary significantly. The Department of Energy (DOE) National Low-Level Waste Management Program (NLLWMP) has undertaken activities to develop a best estimate of GTCC LLW volumes and activities for use as the planning basis. Initial information about the generation of GTCC LLW was obtained through a DOE Energy Information Administration survey. That information, combined with information from other related literature, formed the basis of a computer model, which projects potential GTCC LLW. This paper describes uncertainties in existing GTCC LLW characterization and volume projections data and describes the technical review process that is being used to assist in projections of GTCC LLW expected for storage and disposal. 8 refs., 2 tabs

Mixed and Low-Level Treatment Facility Project. Appendix B, Waste stream engineering files, Part 1, Mixed waste streams

Energy Technology Data Exchange (ETDEWEB)

1992-04-01

This appendix contains the mixed and low-level waste engineering design files (EDFS) documenting each low-level and mixed waste stream investigated during preengineering studies for Mixed and Low-Level Waste Treatment Facility Project. The EDFs provide background information on mixed and low-level waste generated at the Idaho National Engineering Laboratory. They identify, characterize, and provide treatment strategies for the waste streams. Mixed waste is waste containing both radioactive and hazardous components as defined by the Atomic Energy Act and the Resource Conservation and Recovery Act, respectively. Low-level waste is waste that contains radioactivity and is not classified as high-level waste, transuranic waste, spent nuclear fuel, or 11e(2) byproduct material as defined by DOE 5820.2A. Test specimens of fissionable material irradiated for research and development only, and not for the production of power or plutonium, may be classified as low-level waste, provided the concentration of transuranic is less than 100 nCi/g. This appendix is a tool that clarifies presentation format for the EDFS. The EDFs contain waste stream characterization data and potential treatment strategies that will facilitate system tradeoff studies and conceptual design development. A total of 43 mixed waste and 55 low-level waste EDFs are provided.

Project Execution Plan for the Remote Handled Low-Level Waste Disposal Project

Energy Technology Data Exchange (ETDEWEB)

Danny Anderson

2014-07-01

As part of ongoing cleanup activities at the Idaho National Laboratory (INL), closure of the Radioactive Waste Management Complex (RWMC) is proceeding under the Comprehensive Environmental Response, Compensation, and Liability Act (42 USC 9601 et seq. 1980). INL-generated radioactive waste has been disposed of at RWMC since 1952. The Subsurface Disposal Area (SDA) at RWMC accepted the bulk of INL’s contact and remote-handled low-level waste (LLW) for disposal. Disposal of contact-handled LLW and remote-handled LLW ion-exchange resins from the Advanced Test Reactor in the open pit of the SDA ceased September 30, 2008. Disposal of remote-handled LLW in concrete disposal vaults at RWMC will continue until the facility is full or until it must be closed in preparation for final remediation of the SDA (approximately at the end of fiscal year FY 2017). The continuing nuclear mission of INL, associated ongoing and planned operations, and Naval spent fuel activities at the Naval Reactors Facility (NRF) require continued capability to appropriately dispose of contact and remote handled LLW. A programmatic analysis of disposal alternatives for contact and remote-handled LLW generated at INL was conducted by the INL contractor in Fiscal Year 2006; subsequent evaluations were completed in Fiscal Year 2007. The result of these analyses was a recommendation to the Department of Energy (DOE) that all contact-handled LLW generated after September 30, 2008, be disposed offsite, and that DOE proceed with a capital project to establish replacement remote-handled LLW disposal capability. An analysis of the alternatives for providing replacement remote-handled LLW disposal capability has been performed to support Critical Decision-1. The highest ranked alternative to provide this required capability has been determined to be the development of a new onsite remote-handled LLW disposal facility to replace the existing remote-handled LLW disposal vaults at the SDA. Several offsite DOE

Innovative Disposal Practices at the Nevada Test Site to Meet Its Low-Level Waste Generators' Future Disposal Needs

International Nuclear Information System (INIS)

Di Sanza, E.F.; Carilli, J.T.

2006-01-01

Low-level radioactive waste (LLW) streams which have a clear, defined pathway to disposal are becoming less common as U.S. Department of Energy accelerated cleanup sites enters their closure phase. These commonly disposed LLW waste streams are rapidly being disposed and the LLW inventory awaiting disposal is dwindling. However, more complex waste streams that have no path for disposal are now requiring attention. The U.S. Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NSO) Environmental Management Program is charged with the responsibility of carrying out the disposal of onsite and off-site defense-generated and research-related LLW at the Nevada. Test Site (NTS). The NSO and its generator community are constantly pursuing new LLW disposal techniques while meeting the core mission of safe and cost-effective disposal that protects the worker, the public and the environment. From trenches to present-day super-cells, the NTS disposal techniques must change to meet the LLW generator's disposal needs. One of the many ways the NTS is addressing complex waste streams is by designing waste specific pits and trenches. This ensures unusual waste streams with high-activity or large packaging have a disposal path. Another option the NTS offers is disposal of classified low-level radioactive-contaminated material. In order to perform this function, the NTS has a safety plan in place as well as a secure facility. By doing this, the NTS can accept DOE generated classified low-level radioactive-contaminated material that would be equivalent to U.S. Nuclear Regulatory Commission Class B, C, and Greater than Class C waste. In fiscal year 2006, the NTS will be the only federal disposal facility that will be able to dispose mixed low-level radioactive waste (MLLW) streams. This is an activity that is highly anticipated by waste generators. In order for the NTS to accept MLLW, generators will have to meet the stringent requirements of the NTS

Microbial degradation of low-level radioactive waste

International Nuclear Information System (INIS)

Rogers, R.D.; Hamilton, M.A.; Veeh, R.H.; McConnell, J.W. Jr.

1994-04-01

The Nuclear Regulatory Commission stipulates that disposed low-level radioactive waste (LLW) be stabilized. Because of apparent ease of use and normal structural integrity, cement has been widely used as a binder to solidify LLW. However, the resulting waste forms are sometimes susceptible to failure due to the actions of waste constituents, stress, and environment. This report reviews laboratory efforts that are being developed to address the effects of microbiologically influenced chemical attack on cement-solidified LLW. Groups of microorganisms are being employed that are capable of metabolically converting organic and inorganic substrates into organic and mineral acids. Such acids aggressively react with cement and can ultimately lead to structural failure. Results on the application of mechanisms inherent in microbially influenced degradation of cement-based material are the focus of this report. Sufficient data-validated evidence of the potential for microbially influenced deterioration of cement-solidified LLW has been developed during the course of this study. These data support the continued development of appropriate tests necessary to determine the resistance of cement-solidified LLW to microbially induced degradation that could impact the stability of the waste form. They also justify the continued effort of enumeration of the conditions necessary to support the microbiological growth and population expansion

Microbial degradation of low-level radioactive waste. Final report

International Nuclear Information System (INIS)

Rogers, R.D.; Hamilton, M.A.; Veeh, R.H.; McConnell, J.W. Jr.

1996-06-01

The Nuclear Regulatory Commission stipulates in 10 CFR 61 that disposed low-level radioactive waste (LLW) be stabilized. To provide guidance to disposal vendors and nuclear station waste generators for implementing those requirements, the NRC developed the Technical Position on Waste Form, Revision 1. That document details a specified set of recommended testing procedures and criteria, including several tests for determining the biodegradation properties of waste forms. Information has been presented by a number of researchers, which indicated that those tests may be inappropriate for examining microbial degradation of cement-solidified LLW. Cement has been widely used to solidify LLW; however, the resulting waste forms are sometimes susceptible to failure due to the actions of waste constituents, stress, and environment. The purpose of this research program was to develop modified microbial degradation test procedures that would be more appropriate than the existing procedures for evaluation of the effects of microbiologically influenced chemical attack on cement-solidified LLW. The procedures that have been developed in this work are presented and discussed. Groups of microorganisms indigenous to LLW disposal sites were employed that can metabolically convert organic and inorganic substrates into organic and mineral acids. Such acids aggressively react with cement and can ultimately lead to structural failure. Results on the application of mechanisms inherent in microbially influenced degradation of cement-based material are the focus of this final report. Data-validated evidence of the potential for microbially influenced deterioration of cement-solidified LLW and subsequent release of radionuclides developed during this study are presented

Mixed waste study, Lawrence Livermore National Laboratory Hazardous Waste Management facilities

International Nuclear Information System (INIS)

1990-11-01

This document addresses the generation and storage of mixed waste at Lawrence Livermore National Laboratory (LLNL) from 1984 to 1990. Additionally, an estimate of remaining storage capacity based on the current inventory of low-level mixed waste and an approximation of current generation rates is provided. Section 2 of this study presents a narrative description of Environmental Protection Agency (EPA) and Department of Energy (DOE) requirements as they apply to mixed waste in storage at LLNL's Hazardous Waste Management (HWM) facilities. Based on information collected from the HWM non-TRU radioactive waste database, Section 3 presents a data consolidation -- by year of storage, location, LLNL generator, EPA code, and DHS code -- of the quantities of low-level mixed waste in storage. Related figures provide the distribution of mixed waste according to each of these variables. A historical review follows in Section 4. The trends in type and quantity of mixed waste managed by HWM during the past five years are delineated and graphically illustrated. Section 5 provides an estimate of remaining low-level mixed waste storage capacity at HWM. The estimate of remaining mixed waste storage capacity is based on operational storage capacity of HWM facilities and the volume of all waste currently in storage. An estimate of the time remaining to reach maximum storage capacity is based on waste generation rates inferred from the HWM database and recent HWM documents. 14 refs., 18 figs., 9 tabs

Evaluating Options for Disposal of Low-Level Waste at LANL

International Nuclear Information System (INIS)

Hargis, K.M.; French, S.B.; Boyance, J.A.

2009-01-01

Los Alamos National Laboratory (LANL) generates a wide range of waste types, including solid low-level radioactive waste (LLW), in conducting its national security mission and other science and technology activities. Although most of LANL's LLW has been disposed on-site, limitations on expansion, stakeholder concerns, and the potential for significant volumes from environmental remediation and decontamination and demolition (D and D) have led LANL to evaluate the feasibility of increasing off-site disposal. It appears that most of the LLW generated at LANL would meet the Waste Acceptance Criteria at the Nevada Test Site or available commercial LLW disposal sites. Some waste is considered to be problematic to transport to off-site disposal even though it could meet the off-site Waste Acceptance Criteria. Cost estimates for off-site disposal are being evaluated for comparison to estimated costs under the current plans for continued on-site disposal. An evaluation of risks associated with both on-site and off-site disposal will also be conducted. (authors)

Mechanisms of long-term concrete degradation in LLW disposal facilities

International Nuclear Information System (INIS)

Rogers, V.C.

1987-01-01

Most low-level waste (LLW) disposal alternatives, except shallow land burial and improved shallow land burial, involve the use of concrete as an extra barrier for containment. Because concrete is a porous-type material, its moisture retention and transport properties can be characterized with parameters that are also used to characterize the geohydrologic properties of soils. Several processes can occur with the concrete to degrade it and to increase both the movement of water and contaminants through the disposal facility. The effect of these processes must be quantified in designing and estimating the long-term performance of disposal facilities. Modeling the long-term performance of LLW disposal technologies involves, first, estimating the degradation rate of the concrete in a particular facility configuration and environmental setting; second, calculating the water flow through the facility as a function of time; third, calculating the contaminant leaching usually by diffusion or dissolution mechanisms, and then coupling the facility water and contaminant outflow to a hydrogeological and environmental uptake model for environmental releases or doses

Waste-Form Development Program. Annual progress report, October 1981-September 1982

International Nuclear Information System (INIS)

Neilson, R.M. Jr.; Colombo, P.

1982-09-01

Low-level wastes (LLW) at nuclear facilities have traditionally been solidified using portland cement (with and without additives). Urea-formaldehyde has been used for LLW solidification while bitumen (asphalt) and thermosetting polymers will be applied to domestic wastes in the near future. Operational difficulties have been observed with each of these solidification agents. Such difficulties include incompatibility with waste constitutents inhibiting solidification, premature setting, free standing water and fires. Some specific waste types have proven difficult to solidify with one or more of the contemporary agents. Similar problems are also anticipated for the solidification of new wastes, which are generated using advanced volume reduction technologies, and with the application of additional agents which may be introduced in the near future for the solidification of LLW. In the Waste Form Development program, contemporary solidification agents are being investigated relative to their potential applications to major fuel cycle and non-fuel cycle LLW streams. The range of conditions under which these solidification agents can be satisfactorily applied to specific LLW streams is being determined. These studies are primarily directed towards defining operating parameters for both improved solidification of problem wastes such as ion exchange resins, organic liquids and oils for which prevailing processes, as currently employed, appear to be inadequate, and solidification of new LLW streams including high solids content evaporator concentrates, dry solids, and incinerator ash generated from advanced volume reduction technologies. Solidified waste forms are tested and evaluated to demonstrate compliance with waste form performance and shallow land burial (SLB) acceptance criteria and transportation requirements (both as they currently exist and as they are anticipated to be modified with time)

Predisposal management of low and intermediate level radioactive waste. Safety guide

International Nuclear Information System (INIS)

2003-01-01

Radioactive waste is generated in the generation of electricity in nuclear power reactors and in the use of radioactive material in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized. The principles and requirements that govern the safety of the management of radioactive waste are presented in 'The Principles of Radioactive Waste Management', 'Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety' and 'Predisposal Management of Radioactive Waste, Including Decommissioning'. The objective of this Safety Guide is to provide regulatory bodies and the operators that generate and manage radioactive waste with recommendations on how to meet the principles and requirements established in Refs for the predisposal management of LLW. This Safety Guide deals with the safety issues associated with the predisposal management of LLW from nuclear fuel cycle facilities, large research and development installations and radioisotope production facilities. This includes all steps and activities in the management of waste, from its initial generation to its final acceptance at a waste disposal facility or the removal of regulatory control. The predisposal management of radioactive waste includes decommissioning. The term 'decommissioning' encompasses both the process of decommissioning a facility and the management of the waste that results (prior to its disposal). Recommendations on the process of decommissioning are provided in Refs. Recommendations on the management of the waste resulting from decommissioning are included in this Safety Guide. Although the mining and milling of uranium and thorium ores is part of the nuclear fuel cycle, the management of the operational waste (e.g. waste rock, tailings and effluent treatment waste) from these activities is not within the scope of this Safety Guide. The LLW that is

Geochemical effects on the behavior of LLW radionuclides in soil/groundwater environments

Energy Technology Data Exchange (ETDEWEB)

Krupka, K.M.; Sterne, R.J. [Pacific Northwest Lab., Richland, WA (United States)

1995-12-31

Assessing the migration potential of radionuclides leached from low-level radioactive waste (LLW) and decommissioning sites necessitates information on the effects of sorption and precipitation on the concentrations of dissolved radionuclides. Such an assessment requires that the geochemical processes of aqueous speciation, complexation, oxidation/reduction, and ion exchange be taken into account. The Pacific Northwest National Laboratory (PNNL) is providing technical support to the U.S. Nuclear Regulatory Commission (NRC) for defining the solubility and sorption behavior of radionuclides in soil/ground-water environments associated with engineered cementitious LLW disposal systems and decommissioning sites. Geochemical modeling is being used to predict solubility limits for radionuclides under geochemical conditions associated with these environments. The solubility limits are being used as maximum concentration limits in performance assessment calculations describing the release of contaminants from waste sources. Available data were compiled regarding the sorption potential of radionuclides onto {open_quotes}fresh{close_quotes} cement/concrete where the expected pH of the cement pore waters will equal to or exceed 10. Based on information gleaned from the literature, a list of preferred minimum distribution coefficients (Kd`s) was developed for these radionuclides. The K{sub d} values are specific to the chemical environments associated with the evolution of the compositions of cement/concrete pore waters.

Low-level radioactive waste facility siting in the Rocky Mountain compact region

International Nuclear Information System (INIS)

Whitman, M.

1983-09-01

The puprose of the Rocky Mountain Low-Level Radioactive Waste Compact is to develop a regional management system for low-level waste (LLW) generated in the six states eligible for membership: Arizona, Colorado, Nevada, New Mexico, Utah and Wyoming. Under the terms of the compact, any party state generating at least 20% of the region's waste becomes responsible for hosting a regional LLW management facility. However, the compact prescribes no system which the host state must follow to develop a facility, but rather calls on the state to fulfill its responsibility through reliance on its own laws and regulations. Few of the Rocky Mountain compact states have legislation dealing specifically with LLW facility siting. Authority for LLW facility siting is usually obtained from radiation control statutes and solid or hazardous waste statutes. A state-by-state analysis of the siting authorities of each of the Rock Mountain compact states as they pertain to LLW disposal facility siting is presented. Siting authority for LLW disposal facilities in the Rocky Mountain compact region runs from no authority, as in Wyoming, to general statutory authority for which regulations would have to be promulgated, as in Arizona and Nevada, to more detailed siting laws, as in Colorado and New Mexico. Barring an amendment to, or different interpretation of, the Utah Hazardous Waste Facility Siting Act, none of the Rocky Mountain States' LLW facility siting authorities preempt local veto authorities

Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement, Richland, Washington

International Nuclear Information System (INIS)

2003-01-01

This ''Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement'' (HSW EIS) covers three primary aspects of waste management at Hanford--waste treatment, storage, and disposal. It also addresses four kinds of solid waste--low-level waste (LLW), mixed (radioactive and chemically hazardous) low-level waste (MLLW), transuranic (TRU) waste, and immobilized low-activity waste (ILAW). It fundamentally asks the question: how should we manage the waste we have now and will have in the future? This EIS analyzes the impacts of the LLW, MLLW, TRU waste, and ILAW we currently have in storage, will generate, or expect to receive at Hanford. The HSW EIS is intended to help us determine what specific facilities we will continue to use, modify, or construct to treat, store, and dispose of these wastes (Figure S.1). Because radioactive and chemically hazardous waste management is a complex, technical, and difficult subject, we have made every effort to minimize the use of acronyms (making an exception for our four waste types listed above), use more commonly understood words, and provide the ''big picture'' in this summary. An acronym list, glossary of terms, and conversions for units of measure are provided in a readers guide in Volume 1 of this EIS

Addressing mixed waste in plutonium processing

International Nuclear Information System (INIS)

Christensen, D.C.; Sohn, C.L.; Reid, R.A.

1991-01-01

The overall goal is the minimization of all waste generated in actinide processing facilities. Current emphasis is directed toward reducing and managing mixed waste in plutonium processing facilities. More specifically, the focus is on prioritizing plutonium processing technologies for development that will address major problems in mixed waste management. A five step methodological approach to identify, analyze, solve, and initiate corrective action for mixed waste problems in plutonium processing facilities has been developed

Mixed Waste Landfill Integrated Demonstration

International Nuclear Information System (INIS)

1994-02-01

The mission of the Mixed Waste Landfill Integrated Demonstration (MWLID) is to demonstrate, in contaminated sites, new technologies for clean-up of chemical and mixed waste landfills that are representative of many sites throughout the DOE Complex and the nation. When implemented, these new technologies promise to characterize and remediate the contaminated landfill sites across the country that resulted from past waste disposal practices. Characterization and remediation technologies are aimed at making clean-up less expensive, safer, and more effective than current techniques. This will be done by emphasizing in-situ technologies. Most important, MWLID's success will be shared with other Federal, state, and local governments, and private companies that face the important task of waste site remediation. MWLID will demonstrate technologies at two existing landfills. Sandia National Laboratories' Chemical Waste Landfill received hazardous (chemical) waste from the Laboratory from 1962 to 1985, and the Mixed-Waste Landfill received hazardous and radioactive wastes (mixed wastes) over a twenty-nine year period (1959-1988) from various Sandia nuclear research programs. Both landfills are now closed. Originally, however, the sites were selected because of Albuquerque's and climate and the thick layer of alluvial deposits that overlay groundwater approximately 480 feet below the landfills. This thick layer of ''dry'' soils, gravel, and clays promised to be a natural barrier between the landfills and groundwater

Fixation of waste materials in grouts. Part II. An empirical equation for estimating compressive strength for grouts from different wastes

International Nuclear Information System (INIS)

Tallent, O.K.; McDaniel, E.W.; Godsey, T.T.

1986-04-01

Compressive strength data for grouts prepared from three different nuclear waste materials have been correlated. The wastes include ORNL low-level waste (LLW) solution, Hanford Facility Waste (HFW) solution, and Hanford cladding removal waste (CRW) slurry. Data for the three wastes can be represented with a 0.96 coefficient of correlation by the following equation: S = -9.56 + 9.27 D/I + 18.11/C + 0.010 R, where S denotess 28-d compressive strength, in mPa; D designates Waste concentration, fraction of the original; I is ionic strength; C denotes Attapulgite-150 clay content of dry blend, in wt %; and R is the mix ratio, kg/m 3 . The equation may be used to estimate 28-d compressive strengths of grouts prepared within the compositional range of this investigation

Assessing mixed waste treatment technologies

International Nuclear Information System (INIS)

Berry, J.B.; Bloom, G.A.; Hart, P.W.

1994-01-01

The US Department of Energy (DOE) is responsible for the management and treatment of its mixed low-level wastes (MLLW). As discussed earlier in this conference MLLW are regulated under both the Resource Conservation and Recovery Act and various DOE orders. During the next 5 years, DOE will manage over 1,200,000 m 3 of MLLW and mixed transuranic (MTRU) waste at 50 sites in 22 states (see Table 1). The difference between MLLW and MTRU waste is in the concentration of elements that have a higher atomic weight than uranium. Nearly all of this waste will be located at 13 sites. More than 1400 individual mixed waste streams exist with different chemical and physical matrices containing a wide range of both hazardous and radioactive contaminants. Their containment and packaging vary widely (e.g., drums, bins, boxes, and buried waste). This heterogeneity in both packaging and waste stream constituents makes characterization difficult, which results in costly sampling and analytical procedures and increased risk to workers

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

International Nuclear Information System (INIS)

Dorries, Alison M.

2010-01-01

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 knowledge (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.

Determining how much mixed waste will require disposal

International Nuclear Information System (INIS)

Kirner, N.P.

1990-01-01

Estimating needed mixed-waste disposal capacity to 1995 and beyond is an essential element in the safe management of low-level radioactive waste disposal capacity. Information on the types and quantities of mixed waste generated is needed by industry to allow development of treatment facilities and by states and others responsible for disposal and storage of this type of low-level radioactive waste. The design of a mixed waste disposal facility hinges on a detailed assessment of the types and quantities of mixed waste that will ultimately require land disposal. Although traditional liquid scintillation counting fluids using toluene and xylene are clearly recognized as mixed waste, characterization of other types of mixed waste has, however, been difficult. Liquid scintillation counting fluids comprise most of the mixed waste generated and this type of mixed waste is generally incinerated under the supplemental fuel provisions of the Resource Conservation and Recovery Act (RCRA) Because there are no Currently operating mixed waste land disposal facilities, it is impossible to make projections of waste requiring land disposal based on a continuation of current waste disposal practices. Evidence indicates the volume of mixed waste requiring land disposal is not large, since generators are apparently storing these wastes. Surveys conducted to date confirm that relatively small volumes of commercially generated mixed waste volume have relied heavily oil generators' knowledge of their wastes. Evidence exists that many generators are confused by the differences between the Atomic Energy Act and the Resource Conservation and Recovery Act (RCRA) on the issue of when a material becomes a waste. In spite of uncertainties, estimates of waste volumes requiring disposal can be made. This paper proposes an eight-step process for such estimates

Delivering step change improvements to UK low level waste strategy - 16188

International Nuclear Information System (INIS)

Dean, Jason; Rossiter, David

2009-01-01

The UK Nuclear Industry continues to produce significant quantities of Low Level Waste (LLW) as decommissioning projects generating waste become more prevalent. Current infrastructure and projected increasing waste volumes will deliver a volumetric shortfall of storage capacity in the near future. Recently established as a standalone site licence company, the Low Level Waste Repository (LLWR) near Drigg, in West Cumbria (formerly operated and owned by British Nuclear Group) is tasked with managing the safe treatment and disposal of LLW in the UK, on behalf of the Nuclear Decommissioning Authority (NDA). The problem is complex involving many stakeholders with potentially different priorities. Previously, most nuclear waste generators operated independently with limited integration with other similar organisations. However, the current financial, programme and technical pressures require collaborative working to facilitate a step-change improvement in LLW management. Achieving this quickly is as much of a challenge as delivering robust cost effective technical solutions. NDA is working in partnership with LLWR to develop a LLW Strategy for the Nuclear Industry and has in parallel commissioned a number of studies by the National Nuclear Laboratory (NNL), looking at opportunities to share best practice. A National Strategy Group has been established to develop a working partnership between the Nuclear Decommissioning Authority, LLW Repository Ltd, Regulators, Stakeholders and LLW Consignors, promoting innovation, value for money, and robust implementation of the waste hierarchy (avoid-reduce-re-use-recycle). Additionally the LLWR supported by the NNL have undertaken a comprehensive strategic review of the UK's LLW management activities. Initial collaborative work has provided for the first time a detailed picture of the existing strategic baseline and identified significant national benefits from improving the way LLW is forecasted, characterised, segregated, and

SOLID WASTE INTEGRATED FORECAST TECHNICAL (SWIFT) REPORT FY2005 THRU FY2035 2005.0 VOLUME 2

Energy Technology Data Exchange (ETDEWEB)

BARCOT, R.A.

2005-08-17

This report provides up-to-date life cycle information about the radioactive solid waste expected to be managed by Hanford's Waste Management (WM) Project from onsite and offsite generators. It includes: (1) an overview of Hanford-wide solid waste to be managed by the WM Project; (2) multi-level and waste class-specific estimates; (3) background information on waste sources; and (4) comparisons to previous forecasts and other national data sources. The focus of this report is low-level waste (LLW), mixed low-level waste (MLLW), and transuranic waste, both non-mixed and mixed (TRU(M)). Some details on hazardous waste are also provided, however, this information is not considered comprehensive. This report includes data requested in December, 2004 with updates through March 31,2005. The data represent a life cycle forecast covering all reported activities from FY2005 through the end of each program's life cycle and are an update of the previous FY2004.1 data version.

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

International Nuclear Information System (INIS)

Birk, S.M.

1997-10-01

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

Safety analysis and inventory control of transuranic and low-level waste in common storage

International Nuclear Information System (INIS)

Porten, D.R.; Bonner, A.L.; Joyce, J.P.

1993-01-01

This paper describes a methodology developed For the inventory control of low-level waste (LLW) and transuranic (TRU) waste, when both are stored in the same location, and both contribute to an inventory constrained by safety considerations. Development of the method arose from the necessity to make safety analysis calculations for the addition of LLW, in quantities greater than existing inventory limits would allow when stored with TRU waste, in the Hanford Central Waste Complex (CWC)-Ensuring that the dose consequences of credible releases are maintained at low-hazard limits or less, was used to allow greater than Type A quantities of LLW into the CWC. Basically, what happens is the original limited amount of TRU allowed is reduced by some equivalent amount of LLW introduced. The total quantity of TRU, and LLW in excess of Type A quantities, must be administratively maintained via curie equivalency Factors to ensure operation as a low-hazard Facility. The ''equivalency'' between TRU and LLW proposed here is specific only to the CWC, but the methodology can be used for other specific applications, such as TRU and LLW storage or handling facilities where inventory limits must be enforced or where a simplified inventory system is required

Radioactive waste management

International Nuclear Information System (INIS)

Tsoulfanidis, N.

1991-01-01

The management of radioactive waste is a very important part of the nuclear industry. The future of the nuclear power industry depends to a large extent on the successful solution of the perceived or real problems associated with the disposal of both low-level waste (LLW) and high-level waste (HLW). All the activities surrounding the management of radioactive waste are reviewed. The federal government and the individual states are working toward the implementation of the Nuclear Waste Policy Act and the Low-Level Waste Policy Act. The two congressional acts are reviewed and progress made as of early 1990 is presented. Spent-fuel storage and transportation are discussed in detail as are the concepts of repositories for HLW. The status of state compacts for LLW is also discussed. Finally, activities related to the decommissioning of nuclear facilities are also described

VUJE experience with cementation of liquid and wet radioactive waste

International Nuclear Information System (INIS)

Kravarik, Kamil; Holicka, Zuzana; Pekar, Anton; Zatkulak, Milan

2011-01-01

Liquid and wet LLW generated during operation as well as decommissioning of NPPs is treated with different methods and fixed in a suitable fixation matrix so that a final product meets required criteria for its disposal in a final repository. Cementation is an important process used for fixation of liquid and wet radioactive waste such as concentrate, spent resins and sludge. Active cement grout is also used for fixation of low level solid radioactive waste loaded in final packing containers. VUJE Inc. has been engaged in research of cementation for long. The laboratory for analyzing radioactive waste properties, prescription of cementation formulation and estimation of final cement product properties has been established. Experimental, semi-production cementation plant has been built to optimize operation parameters of cementation. VUJE experience with cementation of liquid and wet LLW is described in the presented paper. VUJE has assisted in commissioning of Jaslovske Bohunice Treatment Centre. Cement formulations for treatment of concentrate, spent resins and sludge have been developed. Research studies on the stability of a final concrete packaging container for disposal in repository have been performed. Gained experience has been further utilized for design and manufacture of several cementation plants for treatment of various liquid and wet LLW. Their main technological and technical parameters as well as characterization of treated waste are described in the paper. Applications include the Mochovce Final Treatment Centre, Movable Cementation Facility utilizing in-drum mixing for treatment of sludge, Cementation Facility for treatment of tritiated water in Latvia and Cementation Facility for fixation of liquid and solid institutional radioactive waste in Bulgaria, which utilizes lost stirrer mixer. (author)

Greater-than-Class-C Low-Level Waste Data Base user's manual

International Nuclear Information System (INIS)

1992-07-01

The Greater-than-Class-C Low-level Waste (GTCC LLW) Data Base characterizes GTCC LLW using low, base, and high cases for three different scenarios: unpackaged, packaged, and concentration averages. The GTCC LLW Data Base can be used to project future volumes and radionuclide activities. This manual provides instructions for users of the GTCC LLW Data Base

Low-level waste certification plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility. Revision 1

International Nuclear Information System (INIS)

1995-01-01

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan is composed to meet the requirements found in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and follows the suggested outline provided by WHC in the letter of April 26, 1990, to Dr. R.H. Thomas, Occupational Health Division, LBL. LLW is to be transferred to the WHC Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington

Low-level waste certification plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility. Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-10

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan is composed to meet the requirements found in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and follows the suggested outline provided by WHC in the letter of April 26, 1990, to Dr. R.H. Thomas, Occupational Health Division, LBL. LLW is to be transferred to the WHC Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington.

Low-level radioactive waste source terms for the 1992 integrated data base

International Nuclear Information System (INIS)

Loghry, S.L.; Kibbey, A.H.; Godbee, H.W.; Icenhour, A.S.; DePaoli, S.M.

1995-01-01

This technical manual presents updated generic source terms (i.e., unitized amounts and radionuclide compositions) which have been developed for use in the Integrated Data Base (IDB) Program of the U.S. Department of Energy (DOE). These source terms were used in the IDB annual report, Integrated Data Base for 1992: Spent Fuel and Radioactive Waste Inventories, Projections, and Characteristics, DOE/RW-0006, Rev. 8, October 1992. They are useful as a basis for projecting future amounts (volume and radioactivity) of low-level radioactive waste (LLW) shipped for disposal at commercial burial grounds or sent for storage at DOE solid-waste sites. Commercial fuel cycle LLW categories include boiling-water reactor, pressurized-water reactor, fuel fabrication, and uranium hexafluoride (UF 6 ) conversion. Commercial nonfuel cycle LLW includes institutional/industrial (I/I) waste. The LLW from DOE operations is category as uranium/thorium fission product, induced activity, tritium, alpha, and open-quotes otherclose quotes. Fuel cycle commercial LLW source terms are normalized on the basis of net electrical output [MW(e)-year], except for UF 6 conversion, which is normalized on the basis of heavy metal requirement [metric tons of initial heavy metal ]. The nonfuel cycle commercial LLW source term is normalized on the basis of volume (cubic meters) and radioactivity (curies) for each subclass within the I/I category. The DOE LLW is normalized in a manner similar to that for commercial I/I waste. The revised source terms are based on the best available historical data through 1992

Robotics for mixed waste operations, demonstration description

International Nuclear Information System (INIS)

Ward, C.R.

1993-01-01

The Department of Energy (DOE) Office of Technology Development (OTD) is developing technology to aid in the cleanup of DOE sites. Included in the OTD program are the Robotics Technology Development Program and the Mixed Waste Integrated Program. These two programs are working together to provide technology for the cleanup of mixed waste, which is waste that has both radioactive and hazardous constituents. There are over 240,000 cubic meters of mixed low level waste accumulated at DOE sites and the cleanup is expected to generate about 900,000 cubic meters of mixed low level waste over the next five years. This waste must be monitored during storage and then treated and disposed of in a cost effective manner acceptable to regulators and the states involved. The Robotics Technology Development Program is developing robotics technology to make these tasks safer, better, faster and cheaper through the Mixed Waste Operations team. This technology will also apply to treatment of transuranic waste. The demonstration at the Savannah River Site on November 2-4, 1993, showed the progress of this technology by DOE, universities and industry over the previous year. Robotics technology for the handling, characterization and treatment of mixed waste as well robotics technology for monitoring of stored waste was demonstrated. It was shown that robotics technology can make future waste storage and waste treatment facilities better, faster, safer and cheaper

77 FR 38789 - Notice of Availability of Draft Waste Incidental to Reprocessing Evaluation for the Concentrator...

Science.gov (United States)

2012-06-29

... disposal facility, either the Area 5 Radioactive Waste Management Site at DOE's Nevada National Security... offsite LLW disposal facility, either the NNSS Area 5 Radioactive Waste Management Site or the Waste... radioactive waste (HLW) and may be managed and disposed of offsite as low-level waste (LLW). DOE prepared the...

Summary report, low-level radioactive waste management activities in the states and compacts. Vol. 4. No. 1

International Nuclear Information System (INIS)

1996-01-01

'Low-Level Radioactive Waste Management Activities in the States and Compacts' is a supplement to 'LLW Notes' and is distributed periodically by Afton Associates, Inc. to state, compact and federal officials that receive 'LLW Notes'. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

Summary report. Low-level radioactive waste management activities in the states and compacts. Volume 4, No. 2

International Nuclear Information System (INIS)

1996-08-01

'Low-Level Radioactive Waste Management Activities in the States and Compacts' is a supplement to 'LLW Notes' and is distributed periodically by Afton Associates, Inc. to state, compact and federal officials that receive 'LLW Notes'. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

Hanford Central Waste Complex: Radioactive mixed waste storage facility dangerous waste permit application

International Nuclear Information System (INIS)

1991-10-01

The Hanford Site is owned by the US Government and operated by the US Department of Energy Field Office, Richland. The Hanford Site manages and produces dangerous waste and mixed waste (containing both radioactive and dangerous components). The dangerous waste is regulated in accordance with the Resource Conversation and Recovery Act of 1976 and the State of Washington Hazardous Waste Management Act of 1976. The radioactive component of mixed waste is interpreted by the US Department of Energy to be regulated under the Atomic Energy Act of 1954; the nonradioactive dangerous component of mixed waste is interpreted to be regulated under the Resource Conservation and Recovery Act of 1976 and Washington Administrative Code 173--303. Westinghouse Hanford Company is a major contractor to the US Department of Energy Field Office, Richland and serves as co-operator of the Hanford Central Waste Complex. The Hanford Central Waste Complex is an existing and planned series of treatment, storage, and/or disposal units that will centralize the management of solid waste operations at a single location on the Hanford facility. The Hanford Central Waste Complex units include the Radioactive Mixed Waste Storage Facility, the unit addressed by this permit application, and the Waste Receiving and Processing Facility. The Waste Receiving and Processing Facility is covered in a separate permit application submittal

Sources, amounts, and characteristics of low-level radioactive solid wastes

International Nuclear Information System (INIS)

Kibbey, A.H.; Godbee, H.W.

1979-01-01

Low-level radioactive solid wastes (LLW) are generated in the nuclear fuel cycle, national defense programs, institutional (especially medical/biological) applications, and other research and development activities. The estimated total accumulation of defense LLW, approx. 50.8 x 10 6 ft 3 (approx. 1.4 x 10 6 m 3 ), is roughly three times that estimated for commercial LLW, mill tailings excepted. All nuclear fuel cycle steps generate some LLW, but power plants are the chief source. From 1975 through 1977, reactor process stream cleanup generated approx. 1 x 10 6 (approx. 2.8 x 10 4 m 3 ) annually. Spent fuel storage (or reprocessing) and facility decontamination and decommissioning will become important LLW generators as the nuclear power industry matures. The LLW contains dry contaminated trash, much of which is combustible and/or compactible; discarded tools and equipment; wet filter sludges and ion-exchange resins; disposable filter cartridges; and solidified or sorbed liquids, including some organics. A distinguishing characteristic of LLW is a long-lived alpha-emitting transuranic content of 5 ft 3 (approx. 2.1 x 10 4 m 3 )/y. The majority of these wastes, > 6 x 10 5 ft 3 (> 1.7 x 10 4 m 3 ), was medical and academic wastes which usually contained isotopes with induced activities of less than or equal to 60-day half-life, neglecting 3 H and 14 C

Integrated data base for 1993: US spent fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

Klein, J.A.; Storch, S.N.; Ashline, R.C.

1994-03-01

The Integrated Data Base (IDB) Program has compiled historic data on inventories and characteristics of both commercial and DOE spent fuel; also, commercial and U.S. government-owned radioactive wastes through December 31, 1992. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest U.S. Department of Energy/Energy Information Administration (DOE/EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste (HLW), transuranic (TRU), waste, low-level waste (LLW), commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) LLW. For most of these categories, current and projected inventories are given through the calendar-year (CY) 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal

U.S. policy and current practices for blending low-level radioactive waste for disposal

Energy Technology Data Exchange (ETDEWEB)

Kessel, David S.; Kim, Chang Lak [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2016-09-15

In the near future, many countries, including the Republic of Korea, will face a significant increase in low level radioactive waste (LLW) from nuclear power plant decommissioning. The purpose of this paper is to look at blending as a method for enhancing disposal options for low-level radioactive waste from the decommissioning of nuclear reactors. The 2007 U.S. Nuclear Regulatory Commission strategic assessment of the status of the U.S. LLW program identified the need to move to a risk-informed and performance-based regulatory approach for managing LLW. The strategic assessment identified blending waste of varying radionuclide concentrations as a potential means of enhancing options for LLW disposal. The NRC's position is that concentration averaging or blending can be performed in a way that does not diminish the overall safety of LLW disposal. The revised regulatory requirements for blending LLW are presented in the revised NRC Branch Technical Position for Concentration Averaging and Encapsulation (CA BTP 2015). The changes to the CA BTP that are the most significant for NPP operation, maintenance and decommissioning are reviewed in this paper and a potential application is identified for decommissioning waste in Korea. By far the largest volume of LLW from NPPs will come from decommissioning rather than operation. The large volumes in decommissioning present an opportunity for significant gains in disposal efficiency from blending and concentration averaging. The application of concentration averaging waste from a reactor bio-shield is also presented.

U.S. policy and current practices for blending low-level radioactive waste for disposal

International Nuclear Information System (INIS)

Kessel, David S.; Kim, Chang Lak

2016-01-01

In the near future, many countries, including the Republic of Korea, will face a significant increase in low level radioactive waste (LLW) from nuclear power plant decommissioning. The purpose of this paper is to look at blending as a method for enhancing disposal options for low-level radioactive waste from the decommissioning of nuclear reactors. The 2007 U.S. Nuclear Regulatory Commission strategic assessment of the status of the U.S. LLW program identified the need to move to a risk-informed and performance-based regulatory approach for managing LLW. The strategic assessment identified blending waste of varying radionuclide concentrations as a potential means of enhancing options for LLW disposal. The NRC's position is that concentration averaging or blending can be performed in a way that does not diminish the overall safety of LLW disposal. The revised regulatory requirements for blending LLW are presented in the revised NRC Branch Technical Position for Concentration Averaging and Encapsulation (CA BTP 2015). The changes to the CA BTP that are the most significant for NPP operation, maintenance and decommissioning are reviewed in this paper and a potential application is identified for decommissioning waste in Korea. By far the largest volume of LLW from NPPs will come from decommissioning rather than operation. The large volumes in decommissioning present an opportunity for significant gains in disposal efficiency from blending and concentration averaging. The application of concentration averaging waste from a reactor bio-shield is also presented

New trends in the low-level waste management in Italy

International Nuclear Information System (INIS)

Costa, A.; Donato, A.

1987-01-01

The low level radioactive waste production per year in Italy is evaluated to be at the origin of the order of about 2500 cu.m.. The LLW management scheme in the past was based on a double approach, depending on the waste origin. The LLW from nuclear activities were stored on site under the responsibility of the producers, which had no real possibility to dispose off the LLW in the lack of authorized disposal sites. The management of the LLW coming from other activities (hospitals, university etc.) was left mainly to the sense of responsibility of the same producers which, under the local authorities authorization released case by case, were permitted by the existing regulations to store and sometimes to discharge the wastes, after a suitable decay period. In this context, the government charged the ENEA (Italian Committee for Nuclear and Alternative Energies Development), in the frame of the national energy plan, to overview and organize the whole matter. This paper describes the new trends adopted by ENEA for the LLW management

Management of low- and intermediate level waste in Sweden

International Nuclear Information System (INIS)

Carlsson, Jan

1999-01-01

This presentation describes how the management of radioactive waste is organised in Sweden, where Swedish law places the responsibility for such management with the waste generators. The four nuclear utilities have formed a joint company, the Swedish Nuclear Fuel and Waste Management Co., SKB, to handle the nuclear waste. The Swedish waste management system includes a final repository for short-lived low level waste (LLW) and intermediate level waste (ILW) and an interim storage facility for spent nuclear fuel and long-lived waste. Some very low-level, short-lived waste is disposed of in shallow-land repositories at the nuclear power stations. The final repository is situated in underground rock caverns close to the Forsmark nuclear power plant. The rock caverns have been excavated to a depth of more than 50 m beneath the Baltic Sea floor. LLW is compacted into bales or packaged in metal drums or cases that can be transported in standard freight containers. Radioactive materials used in other sectors such as hospitals are collected and packaged at Studsvik and later deposited in the deep repository. ILW is mixed with cement or bitumen and cast in cement or steel boxes or metal drums. The final repository has different chambers for different kinds of waste. The environmental impact of the repository is negligible. Because Sweden's nuclear power plants and the SKB facilities all are located on the coast, all the waste transport can be conducted by sea. The costs of managing and disposing of Sweden's nuclear waste are small compared to the price of electricity

DOE regulatory reform initiative vitrified mixed waste

International Nuclear Information System (INIS)

Carroll, S.J.; Holtzscheiter, E.W.

1997-01-01

The US Department of Energy (DOE) is charged with responsibly managing the largest volume of mixed waste in the United States. This responsibility includes managing waste in compliance with all applicable Federal and State laws and regulations, and in a cost-effective, environmentally responsible manner. Managing certain treated mixed wastes in Resource Conservation and Recovery Act (RCRA) permitted storage and disposal units (specifically those mixed wastes that pose low risks from the hazardous component) is unlikely to provide additional protection to human health and the environment beyond that afforded by managing these wastes in storage and disposal units subject to requirements for radiological control. In October, 1995, the DOE submitted a regulatory reform proposal to the Environmental Protection Agency (EPA) relating to vitrified mixed waste forms. The technical proposal supports a regulatory strategy that would allow vitrified mixed waste forms treated through a permit or other environmental compliance mechanism to be granted an exemption from RCRA hazardous waste regulation, after treatment, based upon the inherent destruction and immobilization capabilities of vitrification technology. The vitrified waste form will meet, or exceed the performance criteria of the Environmental Assessment (EA) glass that has been accepted as an international standard for immobilizing radioactive waste components and the LDR treatment standards for inorganics and metals for controlling hazardous constituents. The proposal further provides that vitrified mixed waste would be responsibly managed under the Atomic Energy Act (AEA) while reducing overall costs. Full regulatory authority by the EPA or a State would be maintained until an acceptable vitrified mixed waste form, protective of human health and the environment, is produced

Development of DUST: A computer code that calculates release rates from a LLW disposal unit

International Nuclear Information System (INIS)

Sullivan, T.M.

1992-01-01

Performance assessment of a Low-Level Waste (LLW) disposal facility begins with an estimation of the rate at which radionuclides migrate out of the facility (i.e., the disposal unit source term). The major physical processes that influence the source term are water flow, container degradation, waste form leaching, and radionuclide transport. A computer code, DUST (Disposal Unit Source Term) has been developed which incorporates these processes in a unified manner. The DUST code improves upon existing codes as it has the capability to model multiple container failure times, multiple waste form release properties, and radionuclide specific transport properties. Verification studies performed on the code are discussed

Treatment of liquid radioactive waste: Evaporation

International Nuclear Information System (INIS)

Pfeiffer, R.

1982-01-01

About 10.000 m 3 of low active liquid waste (LLW) arise in the Nuclear Research Center Karlsruhe. Chemical contents of this liquid waste are generally not declared. Resulting from experiments carried out in the Center during the early sixties, the evaporator facility was built in 1968 for decontamination of LLW. The evaporators use vapor compression and concentrate recirculation in the evaporator sump by pumps. Since 1971 the medium active liquid waste (MLW) from the Karlsruhe Reprocessing Plant (WAK) was decontaminated in this evaporator facility, too. By this time the amount of low liquid waste (LLW) had been decontaminated without mentionable interruptions. Afterwards a lot of interruptions of operations occurred, mainly due to leakages of pumps, valves and pipes. There was also a very high radiation level for the operating personnel. As a consequence of this experience a new evaporator facility for decontamination of medium active liquid waste was built in 1974. This facility started operation in 1976. The evaporator has natural circulation and is heated by steam through a heat exchanger. (orig./RW)

Interim Storage Facility for LLW of Decommissioning Nuclear Research Facilities

Energy Technology Data Exchange (ETDEWEB)

Amato, S.; Ugolini, D.; Basile, F. [European Commission, Joint Research Centre, Nuclear Decommissioning and Facility Management Unit, TP 800, Via E. Fermi 2749, 21027 Ispra - VA (Italy)

2009-06-15

JRC-Ispra has initiated a Decommissioning and Waste Management (D and WM) Programme of all its nuclear facilities. In the frame of this programme, it has been decided to build an interim storage facility to host conditioned low level waste (LLW) that had been produced during the operation of JRC-Ispra nuclear research reactors and laboratories and that will be produced from their decommissioning. This paper presents the main characteristics of the facility. The storage ISFISF has a rectangular shape with uniform height and it is about 128 m long, 41 m wide and 9 m high. The entire surface affected by the facility, including screening area and access roads, is about 27.000 m{sup 2}. It is divided in three sectors, a central one, about 16 m long, for loading/unloading operations and operational services and two lateral sectors, each about 55 m long, for the conditioned LLW storage. Each storage sector is divided by a concrete wall in two transversal compartments. The ISFISF, whose operational lifetime is 50 years, is designed to host the conditioned LLW boxed in UNI CP-5.2 packages, 2,5 m long, 1.65 m wide, and 1,25 m high. The expected nominal inventory of waste is about 2100 packages, while the maximum storage is 2540 packages, thus a considerably large reserve capacity is available. The packages will be piled in stacks of maximum number of five. The LLW is going to be conditioned with a cement matrix. The maximum weight allowed for each package has been fixed at 16.000 kg. The total radioactivity inventory of waste to be hosted in the facility is about 30 TBq (mainly {beta}/{gamma} emitters). In order to satisfy the structural, seismic, and, most of all, radiological requirements, the external walls of the ISFISF are made of pre-fabricated panels, 32 cm thick, consisting of, from inside to outside, 20 cm of reinforced concrete, 7 cm of insulating material, and again 5 cm of reinforced concrete. For the same reason the roof is made with pre-fabricated panels in

Potential co-disposal of greater-than-class C low-level radioactive waste with Department of Energy special case waste - greater-than-class C low-level waste management program

International Nuclear Information System (INIS)

Allred, W.E.

1994-09-01

This document evaluates the feasibility of co-disposing of greater-than-Class C low-level radioactive waste (GTCC LLW) with U.S. Department of Energy (DOE) special case waste (SCW). This document: (1) Discusses and evaluates key issues concerning co-disposal of GTCC LLW with SCW. This includes examining these issues in terms of regulatory concerns, technical feasibility, and economics; (2) Examines advantages and disadvantages of such co-disposal; and (3) Makes recommendations. Research and analysis of the issues presented in this report indicate that it would be technically and economically feasible to co-dispose of GTCC LLW with DOE SCW. However, a dilemma will likely arise in the current division of regulatory responsibilities between the U.S. Nuclear Regulatory Commission and DOE (i.e., current requirement for disposal of GTCC LLW in a facility licensed by the Nuclear Regulatory Commission). DOE SCW is currently not subject to this licensing requirement

A59 waste repackaging database (AWARD)

International Nuclear Information System (INIS)

Keel, A.

1993-06-01

This paper sets out the requirements for AWARD (the A59 Waste Repackaging Database); a computer-based system to record LLW sorting and repacking information from the North Cave Line in A59. A solution will be developed on the basis of this document. AWARD will record and store details entered from waste sorting and LLW repackaging operations. This document will be used as the basis of the development of the host computer system. (Author)

Differential diagnosis of pulmonary emphysema using the CT index: LL%w

Energy Technology Data Exchange (ETDEWEB)

Kitahara, Yoshinari; Takamoto, Masahiro; Maruyama, Masao; Tanaka, Yasushi; Ishibashi, Tuneo; Shinoda, Atsushi [Ohmuta National Hospital, Fukuoka (Japan)

1989-06-01

We measured the computed tomography (CT) index, LL%w, in 81 patients of chronic obstructive pulmonary disease (COPD) and asthma. In this study we defined LL%w as the mean value of the proportion of the low density area under -950 Hounsfield units in the six lung fields: upper, middle and lower lung fields bilaterally, at deep expiration. To examine the usefulness of LL%w in differentiating pulmomary emphysema (PE) from bronchial asthma (BA) and chronic bronchitis (CB), we excluded the overlapped cases of each disease. Mean value (+- standard deviation) of LL%w in PE was 24.6+-20.2% (n=40), whereas it was 0.5+-0.8% (n=27) in BA and 0.2+-0.3% (n=14) in CB respectively. There were clear statistically differences in the values of LL%w between clinically diagnosed emphysema and others. We considered that the value of LL%w within 1% would be observed nonspecifically, because the frequent existence of low density areas originated in bronchial tangents and/or motion artifacts mainly in the left lower lung field. Thus we judged that cases with over 1% of LL%w had abnormal CT findings. The relationship between clinically diagnosed emphysema and CT abnormality (LL%w > 1%) was significant in the analysis of the four-fold table. The CT sensitivity for diagnosing PE was 100%, the CT specificity was 87.8%, and CT accuracy was 93.8%. When cases of LL%w > 1% were shown in BA or CB, it would be better to consider the existence of complicated emphysema or the presence of air trapping or air spaces of any origin. We compared three groups (A', E', C') selected from groups BA, PE and CB, respectively. The groups consisted of patients showing almost the same mean values of FEV{sub 1.0}/VC(%). The value of the LL%w of E', selected from PE, also showed a significantly higher value than those from BA or CB. (J.P.N).

Differential diagnosis of pulmonary emphysema using the CT index: LL%w

International Nuclear Information System (INIS)

Kitahara, Yoshinari; Takamoto, Masahiro; Maruyama, Masao; Tanaka, Yasushi; Ishibashi, Tuneo; Shinoda, Atsushi

1989-01-01

We measured the computed tomography (CT) index, LL%w, in 81 patients of chronic obstructive pulmonary disease (COPD) and asthma. In this study we defined LL%w as the mean value of the proportion of the low density area under -950 Hounsfield units in the six lung fields: upper, middle and lower lung fields bilaterally, at deep expiration. To examine the usefulness of LL%w in differentiating pulmomary emphysema (PE) from bronchial asthma (BA) and chronic bronchitis (CB), we excluded the overlapped cases of each disease. Mean value (± standard deviation) of LL%w in PE was 24.6±20.2% (n=40), whereas it was 0.5±0.8% (n=27) in BA and 0.2±0.3% (n=14) in CB respectively. There were clear statistically differences in the values of LL%w between clinically diagnosed emphysema and others. We considered that the value of LL%w within 1% would be observed nonspecifically, because the frequent existence of low density areas originated in bronchial tangents and/or motion artifacts mainly in the left lower lung field. Thus we judged that cases with over 1% of LL%w had abnormal CT findings. The relationship between clinically diagnosed emphysema and CT abnormality (LL%w > 1%) was significant in the analysis of the four-fold table. The CT sensitivity for diagnosing PE was 100%, the CT specificity was 87.8%, and CT accuracy was 93.8%. When cases of LL%w > 1% were shown in BA or CB, it would be better to consider the existence of complicated emphysema or the presence of air trapping or air spaces of any origin. We compared three groups (A', E', C') selected from groups BA, PE and CB, respectively. The groups consisted of patients showing almost the same mean values of FEV 1.0 /VC(%). The value of the LL%w of E', selected from PE, also showed a significantly higher value than those from BA or CB. (J.P.N)

Nevada National Security Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

2012-01-01

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept DOE non-radioactive classified waste, DOE non-radioactive hazardous classified waste, DOE low-level radioactive waste (LLW), DOE mixed low-level waste (MLLW), and U.S. Department of Defense (DOD) classified waste for permanent disposal. Classified waste is the only waste accepted for disposal that may be non-radioactive and will be required to meet the waste acceptance criteria for radioactive waste as specified in this document. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project (WMP) at (702) 295-7063, and your call will be directed to the appropriate contact.

Nevada National Security Site Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2012-02-28

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept DOE non-radioactive classified waste, DOE non-radioactive hazardous classified waste, DOE low-level radioactive waste (LLW), DOE mixed low-level waste (MLLW), and U.S. Department of Defense (DOD) classified waste for permanent disposal. Classified waste is the only waste accepted for disposal that may be non-radioactive and will be required to meet the waste acceptance criteria for radioactive waste as specified in this document. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project (WMP) at (702) 295-7063, and your call will be directed to the appropriate contact.

Experiences with treatment of mixed waste

International Nuclear Information System (INIS)

Dziewinski, J.; Marczak, S.; Smith, W.H.; Nuttall, E.

1996-01-01

During its many years of research activities involving toxic chemicals and radioactive materials, Los Alamos National Laboratory (Los Alamos) has generated considerable amounts of waste. Much of this waste includes chemically hazardous components and radioisotopes. Los Alamos chose to use an electrochemical process for the treatment of many mixed waste components. The electro-chemical process, which the authors are developing, can treat a great variety of waste using one type of equipment built at a moderate expense. Such a process can extract heavy metals, destroy cyanides, dissolve contamination from surfaces, oxidize toxic organic compounds, separate salts into acids and bases, and reduce the nitrates. All this can be accomplished using the equipment and one crew of trained operating personnel. Results of a treatability study of chosen mixed wastes from Los Alamos Mixed Waste Inventory are presented. Using electrochemical methods cyanide and heavy metals bearing wastes were treated to below disposal limits

Experiences with treatment of mixed waste

Energy Technology Data Exchange (ETDEWEB)

Dziewinski, J.; Marczak, S.; Smith, W.H. [Los Alamos National Lab., NM (United States); Nuttall, E. [Univ. of New Mexico, Albuquerque, NM (United States). Chemical and Nuclear Engineering Dept.

1996-04-10

During its many years of research activities involving toxic chemicals and radioactive materials, Los Alamos National Laboratory (Los Alamos) has generated considerable amounts of waste. Much of this waste includes chemically hazardous components and radioisotopes. Los Alamos chose to use an electrochemical process for the treatment of many mixed waste components. The electro-chemical process, which the authors are developing, can treat a great variety of waste using one type of equipment built at a moderate expense. Such a process can extract heavy metals, destroy cyanides, dissolve contamination from surfaces, oxidize toxic organic compounds, separate salts into acids and bases, and reduce the nitrates. All this can be accomplished using the equipment and one crew of trained operating personnel. Results of a treatability study of chosen mixed wastes from Los Alamos Mixed Waste Inventory are presented. Using electrochemical methods cyanide and heavy metals bearing wastes were treated to below disposal limits.

Waste segregation

International Nuclear Information System (INIS)

Clark, D.E.; Colombo, P.

1982-01-01

A scoping study has been undertaken to determine the state-of-the-art of waste segregation technology as applied to the management of low-level waste (LLW). Present-day waste segregation practices were surveyed through a review of the recent literature and by means of personal interviews with personnel at selected facilities. Among the nuclear establishments surveyed were Department of Energy (DOE) laboratories and plants, nuclear fuel cycle plants, public and private laboratories, institutions, industrial plants, and DOE and commercially operated shallow land burial sites. These survey data were used to analyze the relationship between waste segregation practices and waste treatment/disposal processes, to assess the developmental needs for improved segregation technology, and to evaluate the costs and benefits associated with the implementation of waste segregation controls. This task was planned for completion in FY 1981. It should be noted that LLW management practices are now undergoing rapid change such that the technology and requirements for waste segregation in the near future may differ significantly from those of the present day. 8 figures

Investigations of potential below regulatory concern (de minimus) wastes

International Nuclear Information System (INIS)

Gruhlke, J.M.; Galpin, F.L.

1983-01-01

Low-level radioactive waste (LLW) includes a wide variety of waste types. Many organizations are contemplating the merits of declaring certain LLW as de minimus. The concept of de minimus has considerable support, as evidenced by the comments on NRC's rulemaking for 10 CFR Part 61, Licensing Requirements for Land Disposal of Radioactive Waste. Practical and philosophical considerations lend weight to the further investigation of the de minimus concept for LLW. The Environmental Protection Agency (EPA) recognizes the interest and efforts in the concept of de minimus. Because the term de minimus may imply a lack of concern for the risks of disposal, we use the term Below Regulatory Concern (BRC). EPA has developed technical information, cost data, and a methodology for selecting promising candidate waste streams. The NRC's breakdown of LLW, as provided in the supporting documentation for 10 CFR Part 51, serves as a starting point for evaluating individual waste streams. Waste streams may then be ranked on the basis of individual dose, population health impact, and cost/benefit. A set of waste streams consistently ranks near the top in all categories and deserves further analysis. This screening is the initial step in an overall effort to develop a basis for determining the appropriateness and form of generic BRC criteria. 14 references, 8 tables

Feed Materials Production Center waste management plan (Revision to NLCO-1100, R.6)

International Nuclear Information System (INIS)

Watts, R.E.; Allen, T.; Castle, S.A.; Hopper, J.P.; Oelrich, R.L.

1986-01-01

In the process of producing uranium metal products used in Department of Energy (DOE) defense programs at other DOE facilities, various types of wastes are generated at the Feed Materials Production Center (FMPC). Process wastes, both generated and stored, are discussed in the Waste Management Plan and include low-level radioactive waste (LLW), mixed hazardous/radioactive waste, and sanitary/industrial waste. Scrap metal waste and wastes requiring special remediation are also addressed in the Plan. The Waste Management Plan identifies the comprehensive programs developed to address safe storage and disposition of all wastes from past, present, and future operations at the FMPC. Waste streams discussed in this Plan are representative of the wastes generated and waste types that concern worker and public health and safety. Budgets and schedules for implementation of waste disposition are also addressed. The waste streams receiving the largest amount of funding include LLW approved for shipment by DOE/ORO to the Nevada Test Site (NTS) (MgF 2 , slag leach filter cake, and neutralized raffinate); remedial action wastes (waste pits, K-65 silo waste); thorium; scrap metal (contaminated and noncontaminated ferrous and copper scrap); construction rubble and soil generated from decontamination and decommissioning of outdated facilities; and low-level wastes that will be handled through the Low-Level Waste Processing and Shipping System (LLWPSS). Waste Management milestones are also provided. The Waste Management Plan is divided into eight major sections: Introduction; Site Waste and Waste Generating Process; Strategy; Projects and Operations; Waste Stream Budgets; Milestones; Quality Assurance for Waste Management; and Environmental Monitoring Program

Permitting mixed waste treatment, storage and disposal facilities: A mixed bag

International Nuclear Information System (INIS)

Ranek, N.L.; Coalgate, J.L.

1995-01-01

The Federal Facility Compliance Act of 1992 (FFCAct) requires the U.S. Department of Energy (DOE) to make a comprehensive national inventory of its mixed wastes (i.e., wastes that contain both a hazardous component that meets the Resource Conservation and Recovery Act (RCRA) definition of hazardous waste and a radioactive component consisting of source, special nuclear, or byproduct material regulated under the Atomic Energy Act (AEA)), and of its mixed waste treatment technologies and facilities. It also requires each DOE facility that stores or generates mixed waste to develop a treatment plan that includes, in part, a schedule for constructing units to treat those wastes that can be treated using existing technologies. Inherent in constructing treatment units for mixed wastes is, of course, permitting. This paper identifies Federal regulatory program requirements that are likely to apply to new DOE mixed waste treatment units. The paper concentrates on showing how RCRA permitting requirements interrelate with the permitting or licensing requirements of such other laws as the Atomic Energy Act, the Clean Water Act, and the Clean Air Act. Documentation needed to support permit applications under these laws are compared with RCRA permit application documentation. National Environmental Policy Act (NEPA) documentation requirements are also addressed, and throughout the paper, suggestions are made for managing the permitting process

Commercial disposal options for Idaho National Engineering Laboratory low-level radioactive waste

International Nuclear Information System (INIS)

Porter, C.L.; Widmayer, D.A.

1995-09-01

The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE)-owned, contractor-operated site. Significant quantities of low-level radioactive waste (LLW) have been generated and disposed of onsite at the Radioactive Waste Management Complex (RWMC). The INEL expects to continue generating LLW while performing its mission and as aging facilities are decommissioned. An on-going Performance Assessment process for the RWMC underscores the potential for reduced or limited LLW disposal capacity at the existing onsite facility. In order to properly manage the anticipated amount of LLW, the INEL is investigating various disposal options. These options include building a new facility, disposing the LLW at other DOE sites, using commercial disposal facilities, or seeking a combination of options. This evaluation reports on the feasibility of using commercial disposal facilities

Integrated data base for 1993: US spent fuel and radioactive waste inventories, projections, and characteristics. Revision 9

Energy Technology Data Exchange (ETDEWEB)

Klein, J.A.; Storch, S.N.; Ashline, R.C. [and others

1994-03-01

The Integrated Data Base (IDB) Program has compiled historic data on inventories and characteristics of both commercial and DOE spent fuel; also, commercial and U.S. government-owned radioactive wastes through December 31, 1992. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest U.S. Department of Energy/Energy Information Administration (DOE/EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste (HLW), transuranic (TRU), waste, low-level waste (LLW), commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) LLW. For most of these categories, current and projected inventories are given through the calendar-year (CY) 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal.

Strategy for managing mixed waste at a plant site

International Nuclear Information System (INIS)

Fentiman, A.

1991-01-01

No waste disposal site is currently accepting mixed waste, but facilities across the country continue to generate it. The waste manager at each site is faced with two problems: how to manage the mixed waste already on-site and how to minimize the amount of new waste generated. A strategy has been developed to address each problem. A key element of the strategy is a building-by-building survey of the site. The survey provides information on how and where mixed waste is generated and stored. This paper describes a method for planning and conducting a site-wide mixed-waste survey. It then outlines approaches to managing existing mixed waste and to minimizing mixed-waste generation using information from the survey

Low-level tank waste simulant data base

International Nuclear Information System (INIS)

Lokken, R.O.

1996-04-01

The majority of defense wastes generated from reprocessing spent N- Reactor fuel at Hanford are stored in underground Double-shell Tanks (DST) and in older Single-Shell Tanks (SST) in the form of liquids, slurries, sludges, and salt cakes. The tank waste remediation System (TWRS) Program has the responsibility of safely managing and immobilizing these tank wastes for disposal. This report discusses three principle topics: the need for and basis for selecting target or reference LLW simulants, tanks waste analyses and simulants that have been defined, developed, and used for the GDP and activities in support of preparing and characterizing simulants for the current LLW vitrification project. The procedures and the data that were generated to characterized the LLW vitrification simulants were reported and are presented in this report. The final section of this report addresses the applicability of the data to the current program and presents recommendations for additional data needs including characterization and simulant compositional variability studies

Waste minimization handbook, Volume 1

Energy Technology Data Exchange (ETDEWEB)

Boing, L.E.; Coffey, M.J.

1995-12-01

This technical guide presents various methods used by industry to minimize low-level radioactive waste (LLW) generated during decommissioning and decontamination (D and D) activities. Such activities generate significant amounts of LLW during their operations. Waste minimization refers to any measure, procedure, or technique that reduces the amount of waste generated during a specific operation or project. Preventive waste minimization techniques implemented when a project is initiated can significantly reduce waste. Techniques implemented during decontamination activities reduce the cost of decommissioning. The application of waste minimization techniques is not limited to D and D activities; it is also useful during any phase of a facility`s life cycle. This compendium will be supplemented with a second volume of abstracts of hundreds of papers related to minimizing low-level nuclear waste. This second volume is expected to be released in late 1996.

Waste minimization handbook, Volume 1

International Nuclear Information System (INIS)

Boing, L.E.; Coffey, M.J.

1995-12-01

This technical guide presents various methods used by industry to minimize low-level radioactive waste (LLW) generated during decommissioning and decontamination (D and D) activities. Such activities generate significant amounts of LLW during their operations. Waste minimization refers to any measure, procedure, or technique that reduces the amount of waste generated during a specific operation or project. Preventive waste minimization techniques implemented when a project is initiated can significantly reduce waste. Techniques implemented during decontamination activities reduce the cost of decommissioning. The application of waste minimization techniques is not limited to D and D activities; it is also useful during any phase of a facility's life cycle. This compendium will be supplemented with a second volume of abstracts of hundreds of papers related to minimizing low-level nuclear waste. This second volume is expected to be released in late 1996

Assessment of waste characteristics and waste management practices for the Midwest compact region:

International Nuclear Information System (INIS)

Sutherland, A.A.

1986-01-01

To define that system and optimize its components, it is necessary to know various characteristics of the LLW generated in the Midwest Compact Region. It must have projections for the annual volumes from the states in the compact to determine the size and lifetimes of waste management facilities. Information on the different volumes of the region's LLW that fall into NRC waste classes will help determine volumes of waste that may need separate disposal. Eventually, licensing a LLW disposal facility will require source terms /emdash/ quantities and concentrations of nuclides placed in the facility /emdash/ in order to conduct performance assessments. To provide the information needed to make informed decisions about the nature and size of the Midwest region's low-level waste management system, information was gathered from a number of sources. The information was placed in a computer data base to preserve it and to facilitate extracton of combinations of data. This report describes how the information was assembled and the nature of the computerized data base. It also provides a baseline characterization of the low-level waste being generated and shipped for disposal from the Midwest region in the late 1980's. 10 refs., 7 figs., 13 tabs

Mixed Low-Level Radioactive Waste (MLLW) Primer

International Nuclear Information System (INIS)

Schwinkendorf, W.E.

1999-01-01

This document presents a general overview of mixed low-level waste, including the regulatory definitions and drivers, the manner in which the various kinds of mixed waste are regulated, and a discussion of the waste treatment options

Mixed Low-Level Radioactive Waste (MLLW) Primer

Energy Technology Data Exchange (ETDEWEB)

W. E. Schwinkendorf

1999-04-01

This document presents a general overview of mixed low-level waste, including the regulatory definitions and drivers, the manner in which the various kinds of mixed waste are regulated, and a discussion of the waste treatment options.

Integrated Data Base: Status and waste projections

International Nuclear Information System (INIS)

Klein, J.A.

1990-01-01

The Integrated Data Base (IDB) is the official US Department of Energy (DOE) data base for spent fuel and radioactive waste inventories and projections. DOE low-level waste (LLW) is just one of the many waste types that are documented with the IDB. Summary-level tables and figures are presented illustrating historical and projected volume changes of DOE LLW. This information is readily available through the annual IDB publication. Other presentation formats are also available to the DOE community through a request to the IDB Program. 4 refs., 6 figs., 5 tabs

Sulfur polymer cement for macroencapsulation of mixed waste debris

International Nuclear Information System (INIS)

Mattus, C.H.

1998-01-01

In FY 1997, the US DOE Mixed Waste Focus Area (MWFA) sponsored a demonstration of the macroencapsulation of mixed waste debris using sulfur polymer cement (SPC). Two mixed wastes were tested--a D006 waste comprised of sheets of cadmium and a D008/D009 waste comprised of lead pipes and joints contaminated with mercury. The demonstration was successful in rendering these wastes compliant with Land Disposal Restrictions (LDR), thereby eliminating one Mixed Waste Inventory Report (MWIR) waste stream from the national inventory

Application for approval to construct the Waste Receiving And Processing facility

International Nuclear Information System (INIS)

1993-02-01

The following Application For Approval Of Construction is being submitted by the US Department of Energy, Richland Field Office pursuant to 40 CFR 61.07, ''Application for Approval of Construction or Modification,'' for the Waste Receiving and Processing (WRAP) Module 1 facility (also referred to as WRAP 1). The WRAP 1 facility will be a new source of radioactive emissions to the atmosphere. The WRAP 1 facility will be housed in the new 2336-W Building, which will be located in the 200 West Area south of 23rd Street and west of Dayton Avenue. The 200 West Area is located within the boundary of the Hanford Site. The mission of the WRAP 1 facility is to examine, assay, characterize, treat, and repackage solid radioactive and mixed waste to enable permanent disposal of the waste in accordance with all applicable regulations. The solid wastes to be handled in the WRAP 1 facility include low-level waste (LLW), Transuranic (TRU) waste, TRU mixed waste, and low-level mixed waste (LLMW). The WRAP 1 facility will only accept contact handled (CH) waste containers. CH waste is a waste category whose external surface dose rate does not exceed 200 mrem/h. These containers have a surface dose rate of less than 200 mrem/h

Acceptance issues for large items and difficult waste

International Nuclear Information System (INIS)

Palmer, J.; Lock, Peter

2002-01-01

Peter Lock described some particular cases which had given rise to difficult acceptance issues at NIREX, ranging from large size items to the impacts of chemicals used during decontamination on the mobility of radionuclides in a disposal facility: The UK strategy for intermediate level and certain low level radioactive waste disposal is based on production of cementitious waste-forms packaged in a standard range of containers as follows: 500 litre Drum - the normal container for most operational ILW (0.8 m diameter x 1.2 m high); 3 m"3 Box - a larger container for solid wastes (1.72 m x 1.72 m plan x 1.2 m high); 3 m"3 Drum - a larger container for in-drum mixing and immobilisation of sludge waste-forms (1.72 m diameter x 1.2 m high); 4 m Box - for large items of waste, especially from decommissioning (4.0 m x 2.4 m plan x 2.2 m high); 2 m LLW Box - for higher-density wastes (2.0 m x 2.4 m plan x 2.2 m high). In addition the majority of LLW is packaged by supercompaction followed by grouting in modified ISO freight containers (6 m x 2.5 m x 2.5 m). Some wastes do not fit easily into this strategy. These wastes include: very large items, (too big for the 4 m box) which, if dealt with whole, pose transport and disposal problems. These items are discussed further in Section 2; waste whose characteristics make packaging difficult. Such wastes are described in more detail in Section 3

The incineration of low-level radioactive waste: A report for the Advisory Committee on Nuclear Waste

International Nuclear Information System (INIS)

Long, S.W.

1990-06-01

This report is a summary of the contemporary use of incineration technology as a method for volume reduction of LLW. It is intended primarily to serve as an overview of the technology for waste management professionals involved in the use or regulation of LLW incineration. It is also expected that organizations presently considering the use of incineration as part of their radioactive waste management programs will benefit by gaining a general knowledge of incinerator operating experience. Specific types of incineration technologies are addressed in this report, including designation of the kinds of wastes that can be processed, the magnitudes of volume reduction that are achievable in typical operation, and requirements for ash handling and off-gas filtering and scrubbing. A status listing of both US and foreign incinerators provides highlights of activities at government, industry, institutional, and commercial nuclear power plant sites. The Federal and State legislative structures for the regulation of LLW incineration are also described. 84 refs., 33 tabs

Mixed waste characterization reference document

International Nuclear Information System (INIS)

1997-09-01

Waste characterization and monitoring are major activities in the management of waste from generation through storage and treatment to disposal. Adequate waste characterization is necessary to ensure safe storage, selection of appropriate and effective treatment, and adherence to disposal standards. For some wastes characterization objectives can be difficult and costly to achieve. The purpose of this document is to evaluate costs of characterizing one such waste type, mixed (hazardous and radioactive) waste. For the purpose of this document, waste characterization includes treatment system monitoring, where monitoring is a supplement or substitute for waste characterization. This document establishes a cost baseline for mixed waste characterization and treatment system monitoring requirements from which to evaluate alternatives. The cost baseline established as part of this work includes costs for a thermal treatment technology (i.e., a rotary kiln incinerator), a nonthermal treatment process (i.e., waste sorting, macronencapsulation, and catalytic wet oxidation), and no treatment (i.e., disposal of waste at the Waste Isolation Pilot Plant (WIPP)). The analysis of improvement over the baseline includes assessment of promising areas for technology development in front-end waste characterization, process equipment, off gas controls, and monitoring. Based on this assessment, an ideal characterization and monitoring configuration is described that minimizes costs and optimizes resources required for waste characterization

Commercial mixed waste treatment and disposal

International Nuclear Information System (INIS)

Vance, J.K.

1994-01-01

At the South Clive, Utah, site, Envirocare of Utah, Inc., (Envirocare), currently operates a commercial low-activity, low-level radioactive waste facility, a mixed waste RCRA Part B storage and disposal facility, and an 11e.(2) disposal facility. Envirocare is also in the process of constructing a Mixed Waste Treatment Facility. As the nation's first and only commercial treatment and disposal facility for such waste, the information presented in this segment will provide insight into their current and prospective operations

Mixed Waste Focus Area program management plan

International Nuclear Information System (INIS)

Beitel, G.A.

1996-10-01

This plan describes the program management principles and functions to be implemented in the Mixed Waste Focus Area (MWFA). The mission of the MWFA is to provide acceptable technologies that enable implementation of mixed waste treatment systems developed in partnership with end-users, stakeholders, tribal governments and regulators. The MWFA will develop, demonstrate and deliver implementable technologies for treatment of mixed waste within the DOE Complex. Treatment refers to all post waste-generation activities including sampling and analysis, characterization, storage, processing, packaging, transportation and disposal

Research and development of treatment techniques for LLW from decommissioning: Decontamination and volume reduction techniques

International Nuclear Information System (INIS)

Hirabayashi, T.; Kameo, Y.; Nakashio, N.

2001-01-01

For the purpose of reducing the amount and/or volume of low-level radioactive waste (LLW) arising from decommissioning of nuclear reactor, the Japan Atomic Energy Research Institute (JAERI) has been developing four decontamination techniques. They are: (a) Gas-carrying abrasive method, (b) In-situ remote electropolishing method for pipe system before dismantling, (c) Bead reaction - thermal shock method, and (d) Laser induced chemical method for components after dismantling. JAERI in developing techniques are also carrying out melting tests of metal and non-metal. Melting was confirmed to be effective in reducing the volume, homogenizing, and furthermore stabilizing non-metallic wastes. (author)

Radioactive mixed waste disposal

International Nuclear Information System (INIS)

Jasen, W.G.; Erpenbeck, E.G.

1993-02-01

Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA), the Resource Conservation and Recovery Act of 1976 (RCRA), and the Hazardous and Solid Waste Amendments (HSWA) have led to the definition of radioactive mixed wastes (RMW). The radioactive and hazardous properties of these wastes have resulted in the initiation of special projects for the management of these wastes. Other solid wastes at the Hanford Site include low-level wastes, transuranic (TRU), and nonradioactive hazardous wastes. This paper describes a system for the treatment, storage, and disposal (TSD) of solid radioactive waste

Low-level wastes pathways at EDF

International Nuclear Information System (INIS)

Hilmoine, R.; Casseau, L.Ph.

1999-01-01

First, what are, for EDF, the main issues dealing with the future management of low level wastes (LLW) will be recalled; and followed by a description of what are the implications of implementing these management principles: areas zoning, set up of pathways, traceability of the wastes and associated controls. The origin of the wastes will then be described using both qualitative and quantitative approaches; the description will specifically address the spreading of wastes production in time. LLW management at EDF will then be envisaged: storage in a specific discharge, pathways for treatment and elimination of wastes with acceptable radiological impact and costs. The example of LLW oils will be developed: particularly as far as hypothesis and results concerning the radiological impacts are concerned. The choice of incineration will then be justified, however expected difficulties to implement it industrially will be pointed out. Other on going studies and their main results will be mentioned: the present time is a turning point on that issue between thought and action; to be on going dismantling must take into account the emerging principles and give rise to good communication. (author)

State compacts and low-level waste

International Nuclear Information System (INIS)

Brown, H.

1984-01-01

In 1979, for the first time, low-level waste (LLW) was brought to the attention of policy makers in most states. For several decades, technical personnel had regulated and managed LLW, but elected officials and their staff had been largely ignorant of the origins and destination of low-level radioactive materials. Events in the fall of 1979 set in motion a sequence of events that has compelled the continuing attention of policy makers in every state in the nation. In December 1979, the Executive Committee of the National Governors' Association appointed an eight-member task force, chaired by Governor Bruce Babbitt of Arizona, to review low-level waste management and to formulate state policy by July 1980. The principal findings were as follows: 1. LLW could be managed most efficiently, both technically and politically, at the state level. 2. Each state should take responsibility for its own waste. 3. The creation of a regional waste management system by means of interstate compacts offered the best promise of creating new disposal capacity. 4. Regions should be allowed to exclude waste generated outside their borders after a specified date

Gas generation from low-level radioactive waste: Concerns for disposal

International Nuclear Information System (INIS)

Siskind, B.

1992-01-01

The Advisory Committee on Nuclear Waste (ACNW) has urged the Nuclear Regulatory Commission (NRC) to reexamine the topic of hydrogen gas generation from low-level radioactive waste (LLW) in closed spaces to ensure that the slow buildup of hydrogen from water-bearing wastes in sealed containers does not become a problem for long-term safe disposal. Brookhaven National Laboratory (BNL) has prepared a report, summarized in this paper, for the NRC to respond to these concerns. The paper discusses the range of values for G(H 2 ) reported for materials of relevance to LLW disposal; most of these values are in the range of 0.1 to 0.6. Most studies of radiolytic hydrogen generation indicate a leveling off of pressurization, probably because of chemical kinetics involving, in many cases, the radiolysis of water within the waste. Even if no leveling off occurs, realistic gas leakage rates (indicating poor closure by gaskets on drums and liners) will result in adequate relief of pressure for radiolytic gas generation from the majority of commercial sector LLW packages. Biodegradative gas generation, however, could pose a pressurization hazard even at realistic gas leakage rates. Recommendations include passive vents on LLW containers (as already specified for high integrity containers) and upper limits to the G values and/or the specific activity of the LLW

Waste treatment

International Nuclear Information System (INIS)

Hutson, G.V.

1996-01-01

Numerous types of waste are produced by the nuclear industry ranging from high-level radioactive and heat-generating, HLW, to very low-level, LLW and usually very bulky wastes. These may be in solid, liquid or gaseous phases and require different treatments. Waste management practices have evolved within commercial and environmental constraints resulting in considerable reduction in discharges. (UK)

Development of LLW and VLLW disposal business cost estimation system

International Nuclear Information System (INIS)

Koibuchi, Hiroko; Ishiguro, Hideharu; Matsuda, Kenji

2004-01-01

In order to undertake the LLW and VLLW disposal business, various examinations are carried out in RANDEC. Since it is important in undertaking this business to secure funds, a disposal cost must be calculated by way of trial. However, at present, there are many unknown factors such as the amount of wastes, a disposal schedule, the location of a disposal site, and so on, and the cost cannot be determined. Meanwhile, the cost depends on complicated relations among these factors. Then, a 'LLW and VLLW disposal business cost estimation system' has been developed to calculate the disposal cost easily. This system can calculate an annual balance of payments by using a construction and operation cost of disposal facilities, considering economic parameters of tax, inflation rate, interest rate and so on. And the system can calculate internal reserves to assign to next-stage upkeep of the disposal facilities after the disposal operation. A model of disposal site was designed based on assumption of some preconditions and a study was carried out to make a trial calculation by using the system. Moreover, it will be required to reduce construction cost by rationalizing the facility and to make flat an annual business spending by examining the business schedule. (author)

Strategies, technologies, and economics for managing greater-than-class C waste

International Nuclear Information System (INIS)

Danna, J.G.; Baird, R.D.; Chau, T.K.

1994-01-01

The Low-Level Radioactive Waste Policy Amendments Act 0f 1985, Public Law 99-240, transferred responsibility for disposing of Greater-Than-Class C (GTCC) low-level radioactive waste (LLW) generated by commercial licensees from the states to the U.S. Department of Energy (DOE). Development of permanent disposal capacity for GTCC LLW requires the evaluation of potential disposal concepts in terms of technical feasibility, economics, and institutional concerns. Previous studies have identified 13 potential GTCC LLW disposal concepts and have characterized volumes and types of GTCC LLW. Data from these studies, along with newly developed data pertaining to concept designs and hypothetical sites, were used to evaluate each concept's technical feasibility. An evaluation of the cost effectiveness of the technically feasible disposal concepts was also conducted

Microbial degradation of low-level radioactive waste. Volume 2, Annual report for FY 1994

International Nuclear Information System (INIS)

Rogers, R.D.; Hamilton, M.A.; Veeh, R.H.; McConnell, J.W. Jr.

1995-08-01

The Nuclear Regulatory Commission stipulates in 10 CFR 61 that disposed low-level radioactive waste (LLW) be stabilized. To provide guidance to disposal vendors and nuclear station waste generators for implementing those requirements, the NRC developed the Technical Position on Waste Form, Revision 1. That document details a specified set of recommended testing procedures and criteria, including several tests for determining the biodegradation properties of waste forms. Cement has been widely used to solidify LLW; however, the resulting waste forms are sometimes susceptible to failure due to the actions of waste constituents, stress, and environment. The purpose of this research program is to develop modified microbial degradation test procedures that will be more appropriate than the existing procedures for evaluating the effects of microbiologically influenced chemical attack on cement-solidified LLW. Groups of microorganisms indigenous to LLW disposal sites are being employed that can metabolically convert organic and inorganic substrates into organic and mineral acids. Such acids aggressively react with cement and can ultimately lead to structural failure. Results over the past year on the application of mechanisms inherent in microbially influenced degradation of cement-based material are the focus of the annual report. Data-validated evidence of the potential for microbially influenced deterioration of cement-solidified LLW and subsequent release of radionuclides has been developed during this study

Transportable Vitrification System Demonstration on Mixed Waste

International Nuclear Information System (INIS)

Zamecnik, J.R.; Whitehouse, J.C.; Wilson, C.N.; Van Ryn, F.R.

1998-01-01

This paper describes preliminary results from the first demonstration of the Transportable Vitrification System (TVS) on actual mixed waste. The TVS is a fully integrated, transportable system for the treatment of mixed and low-level radioactive wastes. The demonstration was conducted at Oak Ridge's East Tennessee Technology Park (ETTP), formerly known as the K-25 site. The purpose of the demonstration was to show that mixed wastes could be vitrified safely on a 'field' scale using joule-heated melter technology and obtain information on system performance, waste form durability, air emissions, and costs

Hanford's Radioactive Mixed Waste Disposal Facility

International Nuclear Information System (INIS)

McKenney, D.E.

1995-01-01

The Radioactive Mixed Waste Disposal Facility, is located in the Hanford Site Low-Level Burial Grounds and is designated as Trench 31 in the 218-W-5 Burial Ground. Trench 31 is a Resource Conservation and Recovery Act compliant landfill and will receive wastes generated from both remediation and waste management activities. On December 30, 1994, Westinghouse Hanford Company declared readiness to operate Trench 31, which is the Hanford Site's (and the Department of Energy complex's) first facility for disposal of low-level radioactive mixed wastes

Assessment of LANL transuranic mixed waste management documentation

International Nuclear Information System (INIS)

Davis, K.D.; Hoevemeyer, S.S.; McCance, C.H.; Jennrich, E.A.; Lund, D.M.

1991-04-01

The objective of this report is to present findings from the evaluation of the Los Alamos National Laboratory (LANL) TRU Mixed Waste Acceptance Criteria to determine its compliance with applicable DOE requirements. The driving requirements for s TRU Mixed Waste Acceptance Criteria are essentially those contained in the ''TRU Waste Acceptance Criteria for the Waste Isolation Pilot Plant'' or WIPP WAC (DOE Report WIPP-DOE-069), 40 CFR 261-270, and DOE Order 5820.2A (Radioactive Waste Management), specifically Chapter II which is entitled ''Management of Transuranic Waste''. The primary purpose of the LANL WAC is the establishment of those criteria that must be met by generators of TRU mixed waste before such waste can be accepted by the Waste Management Group. An annotated outline of a genetic TRU mixed waste acceptance criteria document was prepared from those requirements contained in the WIPP WAC, 40 CFR 261-270, and 5820.2A, and is based solely upon those requirements

Low-level radioactive waste treatment systems in northern Europe

International Nuclear Information System (INIS)

Sjoeblom, R.

1987-08-01

In the United States, the use of low-level waste (LLW) treatment systems by low level waste generators can be expected to expand with increasing costs for disposal and continuing uncertainty over the availability of disposal space. This development increases the need for performance information and operational data and has prompted the US Department of Energy to commission several compilations of LLW systems experience. The present paper summarizes some of the know-how from Northern Europe where the incentive for LLW treatment and volume reduction is very high since deposition space has not been available for many years. 65 refs., 10 figs., 4 tabs

Low-level radioactive waste vitrification: effect of Cs partitioning

International Nuclear Information System (INIS)

Horton, W.S.; Ougouag, A.M.

1986-01-01

The traditional Low-Level Radioactive Waste (LLW) immobilization options are cementation or bituminization. Either of these options could be followed by shallow-land burial (SLB) or above-ground disposal. These rather simple LLW procedures appeared to be readily available, to meet regulatory requirements, and to satisfy cost constraints. The authorization of State Compacts, the forced closure of half of the six SLB disposal facilities of the nation, and the escalation of transportation/disposal fees diminish the viability of these options. The synergetic combination of these factors led to a reassessment of traditional methods and to an investigation of other techniques. This paper analyzes the traditional LLW immobilization options, reviews the impact of the LLW stream composition on Low-Level Waste Vitrification (LLWV), then proposes and briefly discusses several techniques to control the volatile radionuclides in a Process Improved LLWV system (PILLWV)

Development of low-level radioactive waste disposal capacity in the United States - progress or stalemate?

International Nuclear Information System (INIS)

Devgun, J.S.; Larson, G.S.

1995-01-01

It has been fifteen years since responsibility for the disposal of commercially generated low-level radioactive waste (LLW) was shifted to the states by the United States Congress through the Low-Level Radioactive Waste Policy Act of 1980 (LLRWPA). In December 1985, Congress revisited the issue and enacted the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA). No new disposal sites have opened yet, however, and it is now evident that disposal facility development is more complex, time-consuming, and controversial than originally anticipated. For a nation with a large nuclear power industry, the lack of availability of LLW disposal capacity coupled with a similar lack of high-level radioactive waste disposal capacity could adversely affect the future viability of the nuclear energy option. The U.S. nuclear power industry, with 109 operating reactors, generates about half of the LLW shipped to commercial disposal sites and faces dwindling access to waste disposal sites and escalating waste management costs. The other producers of LLW - industries, government (except the defense related research and production waste), academic institutions, and medical institutions that account for the remaining half of the commercial LLW - face the same storage and cost uncertainties. This paper will summarize the current status of U.S. low-level radioactive waste generation and the status of new disposal facility development efforts by the states. The paper will also examine the factors that have contributed to delays, the most frequently suggested alternatives, and the likelihood of change

Development of low-level radioactive waste disposal capacity in the United States -- Progress or stalemate?

International Nuclear Information System (INIS)

Devgun, J.S.

1995-01-01

It has been fifteen years since responsibility for the disposal of commercially generated low-level radioactive waste (LLW) was shifted to the states by the United States Congress through the Low-Level Radioactive Waste Policy Act of 1980 (LLRWPA). In December 1985, Congress revisited the issue and enacted the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA). No new disposal sites have opened yet, however, and it is now evident that disposal facility development is more complex, time-consuming, and controversial than originally anticipated. For a nation with a large nuclear power industry, the lack of availability of LLW disposal capacity coupled with a similar lack of high-level radioactive waste disposal capacity could adversely affect the future viability of the nuclear energy option. The US nuclear power industry, with 109 operating reactors, generates about half of the LLW shipped to commercial disposal sites and faces dwindling access to waste disposal sites and escalating waste management costs. The other producers of LLW -- industries, government (except the defense related research and production waste), academic institutions, and medical institutions that account for the remaining half of the commercial LLW -- face the same storage and cost uncertainties. This paper will summarize the current status of US low-level radioactive waste generation and the status of new disposal facility development efforts by the states. The paper will also examine the factors that have contributed to delays, the most frequently suggested alternatives, and the likelihood of change

Separation, Concentration, and Immobilization of Technetium and Iodine from Alkaline Supernate Waste

Energy Technology Data Exchange (ETDEWEB)

James Harvey; Michael Gula

1998-12-07

Development of remediation technologies for the characterization, retrieval, treatment, concentration, and final disposal of radioactive and chemical tank waste stored within the Department of Energy (DOE) complex represents an enormous scientific and technological challenge. A combined total of over 90 million gallons of high-level waste (HLW) and low-level waste (LLW) are stored in 335 underground storage tanks at four different DOE sites. Roughly 98% of this waste is highly alkaline in nature and contains high concentrations of nitrate and nitrite salts along with lesser concentrations of other salts. The primary waste forms are sludge, saltcake, and liquid supernatant with the bulk of the radioactivity contained in the sludge, making it the largest source of HLW. The saltcake (liquid waste with most of the water removed) and liquid supernatant consist mainly of sodium nitrate and sodium hydroxide salts. The main radioactive constituent in the alkaline supernatant is cesium-137, but strontium-90, technetium-99, and transuranic nuclides are also present in varying concentrations. Reduction of the radioactivity below Nuclear Regulatory Commission (NRC) limits would allow the bulk of the waste to be disposed of as LLW. Because of the long half-life of technetium-99 (2.1 x 10 5 y) and the mobility of the pertechnetate ion (TcO 4 - ) in the environment, it is expected that technetium will have to be removed from the Hanford wastes prior to disposal as LLW. Also, for some of the wastes, some level of technetium removal will be required to meet LLW criteria for radioactive content. Therefore, DOE has identified a need to develop technologies for the separation and concentration of technetium-99 from LLW streams. Eichrom has responded to this DOE-identified need by demonstrating a complete flowsheet for the separation, concentration, and immobilization of technetium (and iodine) from alkaline supernatant waste.

Mixed Waste Salt Encapsulation Using Polysiloxane - Final Report

International Nuclear Information System (INIS)

Miller, C.M.; Loomis, G.G.; Prewett, S.W.

1997-01-01

A proof-of-concept experimental study was performed to investigate the use of Orbit Technologies polysiloxane grouting material for encapsulation of U.S. Department of Energy mixed waste salts leading to a final waste form for disposal. Evaporator pond salt residues and other salt-like material contaminated with both radioactive isotopes and hazardous components are ubiquitous in the DOE complex and may exceed 250,000,000 kg of material. Current treatment involves mixing low waste percentages (less than 10% by mass salt) with cement or costly thermal treatment followed by cementation to the ash residue. The proposed technology involves simple mixing of the granular salt material (with relatively high waste loadings-greater than 50%) in a polysiloxane-based system that polymerizes to form a silicon-based polymer material. This study involved a mixing study to determine optimum waste loadings and compressive strengths of the resultant monoliths. Following the mixing study, durability testing was performed on promising waste forms. Leaching studies including the accelerated leach test and the toxicity characteristic leaching procedure were also performed on a high nitrate salt waste form. In addition to this testing, the waste form was examined by scanning electron microscope. Preliminary cost estimates for applying this technology to the DOE complex mixed waste salt problem is also given

Chemistry of application of calcination/dissolution to the Hanford tank waste inventory

International Nuclear Information System (INIS)

Delegard, C.H.; Elcan, T.D.; Hey, B.E.

1994-05-01

Approximately 330,000 metric tons of sodium-rich radioactive waste originating from separation of plutonium from irradiated uranium fuel are stored in underground tanks at the Hanford Site in Washington State. Fractionation of the waste into low-level waste (LLW) and high-level waste (HLW) streams is envisioned via partial water dissolution and limited radionuclide extraction operations. Under optimum conditions, LLW would contain most of the chemical bulk while HLW would contain virtually all of the transuranic and fission product activity. Calcination at around 850 C, followed by water dissolution, has been proposed as an alternative initial treatment of Hanford Site waste to improve waste dissolution and the envisioned LLW/HLW split. Results of literature and laboratory studies are reported on the application of calcination/dissolution (C/D) to the fractionation of the Hanford Site tank waste inventory. Both simulated and genuine Hanford Site waste materials were used in the lab tests. To evaluation confirmed that C/D processing reduced the amount of several components from the waste. The C/D dissolutions of aluminum and chromium allow redistribution of these waste components from the HLW to the LLW fraction. Comparisons of simple water-washing with C/D processing of genuine Hanford Site waste are also reported based on material (radionuclide and chemical) distributions to solution and solid residue phases. The lab results show that C/D processing yielded superior dissolution of aluminum and chromium sludges compared to simple water dissolution. 57 refs., 26 figs., 18 tabs

Chemistry of application of calcination/dissolution to the Hanford tank waste inventory

Energy Technology Data Exchange (ETDEWEB)

Delegard, C.H.; Elcan, T.D.; Hey, B.E.

1994-05-01

Approximately 330,000 metric tons of sodium-rich radioactive waste originating from separation of plutonium from irradiated uranium fuel are stored in underground tanks at the Hanford Site in Washington State. Fractionation of the waste into low-level waste (LLW) and high-level waste (HLW) streams is envisioned via partial water dissolution and limited radionuclide extraction operations. Under optimum conditions, LLW would contain most of the chemical bulk while HLW would contain virtually all of the transuranic and fission product activity. Calcination at around 850 C, followed by water dissolution, has been proposed as an alternative initial treatment of Hanford Site waste to improve waste dissolution and the envisioned LLW/HLW split. Results of literature and laboratory studies are reported on the application of calcination/dissolution (C/D) to the fractionation of the Hanford Site tank waste inventory. Both simulated and genuine Hanford Site waste materials were used in the lab tests. To evaluation confirmed that C/D processing reduced the amount of several components from the waste. The C/D dissolutions of aluminum and chromium allow redistribution of these waste components from the HLW to the LLW fraction. Comparisons of simple water-washing with C/D processing of genuine Hanford Site waste are also reported based on material (radionuclide and chemical) distributions to solution and solid residue phases. The lab results show that C/D processing yielded superior dissolution of aluminum and chromium sludges compared to simple water dissolution. 57 refs., 26 figs., 18 tabs.

Influence of non-technical policies on choices of waste solidification technologies

International Nuclear Information System (INIS)

Trubatch, S.L.

1987-01-01

This paper describes and discusses non-technical policy considerations which may improperly influence decisions on the solidification of low-level radioactive wastes (''LLW''). These policy considerations are contained principally in several State and Federal statutes which regulate various aspects of LLW disposal. One policy consideration in particular, the unqualified bias in favor of volume reduction, is shown to present a substantial potential for leading to technically suboptimal decisions on the appropriate processes for solidifying LLW. To avoid the unintended skewing of technical decisions by non-technical policy considerations, certain current policies may need to be revised to ensure that the choices of waste treatment, including decisions on solidification, are based primarily on reasonable assurance of adequate protection of public health and safety. This goal may be realized in part by basing any disposal fee structure on more than just LLW volume to include consideration of the waste's activity and its difficulty of confinement

Technical feasibility of retrieval within the UK repository concept for ILW/LLW

International Nuclear Information System (INIS)

McCall, A.; McKirdy, B.

2000-01-01

Nirex is developing a staged, reversible concept for the disposal of ILW and certain LLW in the UK. Within that concept, the retrievability strategy includes the option of keeping open the repository, for an extended period, after all waste has been emplaced. In examining the feasibility of such an approach, a number of key technical issues have been identified and options for addressing these issues have been established. This paper will describe the issues identified and the development of practical solutions for incorporating retrievability within the Nirex concept. (author)

Proceedings of the US Department of Energy Office of Environmental Restoration and Waste Management waste reduction workshop 4

International Nuclear Information System (INIS)

1990-03-01

The fourth of a series of waste minimization/reduction workshops was held at the Sheridan Grand Hotel in Tampa, Florida, on February 6--7, 1990. The workshops are held under the auspices of the Department of Energy's (DOE's) Office of Environmental Restoration and Waste Management. This workshop provided a forum for waste minimization/reduction planning, including waste minimization assessments. The workshops assist DOE waste-generating sites in implementing waste minimization/reduction programs, plans, and activities, thus providing for optimal waste reduction within the DOE complex. All wastes are considered within this discipline: liquid, solid, and airborne, within the categories of high-level, transuranic (TRU), low-level (LLW), hazardous, and mixed. Topics of discussion within workshops encompassed a wide range of subjects. Subjects included any method or technical activity from waste generation to disposal, such as process design or improvement, substitution of materials, waste segregation and recycling/reuse, waste treatment and processing, and administrative controls (procurement and waste awareness training). Consideration was also given to activities for remedial action and for decontamination and disposal. 1 tab

Melter system technology testing for Hanford Site low-level tank waste vitrification

International Nuclear Information System (INIS)

Wilson, C.N.

1996-01-01

Following revisions to the Tri-Party Agreement for Hanford Site cleanup, which specified vitrification for Complete melter feasibility and system operability immobilization of the low-level waste (LLW) tests, select reference melter(s), and establish reference derived from retrieval and pretreatment of the radioactive LLW glass formulation that meets complete systems defense wastes stored in 177 underground tanks, commercial requirements (June 1996). Available melter technologies were tested during 1994 to 1995 as part of a multiphase program to select reference Submit conceptual design and initiate definitive design technologies for the new LLW vitrification mission

Low-level waste drum staging building at Weapons Engineering Tritium Facility, TA-16, Los Alamos National Laboratory, Los Alamos, New Mexico. Environmental Assessment

International Nuclear Information System (INIS)

1994-08-01

The proposed action is to place a 3 meter (m) by 4.5 m (10 ft x 15 ft) prefabricated storage building (transportainer) adjacent to the existing Weapons Engineering Tritium Facility (WETF) at Technical Area (TA-) 16, Los Alamos National Laboratory (LANL), and to use the building as a staging site for sealed 55 galllon drums of noncompactible waste contaminated with low levels of tritium (LLW). Up to eight drums of waste would be accumulated before the waste is moved by LANL Waste Management personnel to the existing on-site LLW disposal area at TA-54. The drum staging building would be placed on a bermed asphalt pad, near other existing accumulation structures for office trash and compactible LLW. The no-action alternative is to continue storing drums of LLW in the WETF laboratories where they occupy valuable work space, hamper movement of personnel and equipment, and require waste management personnel to enter those laboratories in order to remove filled drums. No new waste would be generated by implementing the proposed action; no changes or increases in WETF operations or waste production rate are anticipated as a result of staging drums of LLW outside the main laboratory building. The site for the LLW drum staging building would not impact any sensitive areas. Tritium emissions from the drums of LLW were included within the source term for normal operations at the WETF; the cumulative impacts would not be increased

Reverse osmosis: experience of cold commissioning trials in waste immobilisation plant, Trombay

International Nuclear Information System (INIS)

Anand, G.; Bose, Aditi; Verma, B.B.

1999-01-01

Industrial scale reverse osmosis plant for low level radioactive waste put up in Waste Immobilisation Plant (WIP), Trombay is the first of its kind in India. The performance test with inactive simulated waste is meeting the desired performance. The preliminary treatment of LLW stream at W.I.P., Trombay is proposed to be carried out with reverse osmosis membrane separation process. The design, recovery and rejection ratio of LLW is described

Conversion of three mixed-waste streams

International Nuclear Information System (INIS)

Harmer, D.E.; Porter, D.L.; Conley, C.W.

1990-01-01

At the present time, commercial mixed waste (containing both radioactive and hazardous components) is not handled by any disposal site in this country. Thus, a generator of such material is faced with the prospect of separating or altering the nature of the waste components. A chemical or physical separation may be possible. However, if separation fails there remains the opportunity of chemically transforming the hazardous ingredients to non-hazardous substances, allowing disposal at an existing radioactive burial site. Finally, chemical or physical stabilization can be used as a tool to achieve an acceptable waste form lacking the characteristics of mixed waste. A practical application of these principles has been made in the case of certain mixed waste streams at Aerojet Ordnance Tennessee. Three different streams were involved: (1) lead and lead oxide contaminated with uranium, (2) mixed chloride salts including barium chloride, contaminated with uranium, and (3) bricks impregnated with the barium salt mixture. This paper summarizes the approach of this mixed-waste problem, the laboratory solutions found, and the intended field remediations to be followed. Mixture (1), above, was successfully converted to a vitreous insoluble form. Mixture (2) was separated into radioactive and non-radioactive streams, and the hazardous characteristics of the latter altered chemically. Mixture (3) was treated to an extraction process, after which the extractant could be treated by the methods of Mixture (2). Field application of these methods is scheduled in the near future

EPA/DOE joint efforts on mixed waste treatment

International Nuclear Information System (INIS)

Lee, C.C.; Huffman, G.L.; Nalesnik, R.P.

1995-01-01

Under the requirements of the Federal Facility Compliance Act (FFCA), the Department of Energy (DOE) is directed to develop treatment plans for their stockpile of wastes generated at their various sites. As a result, DOE is facing the monumental problem associated with the treatment and ultimate disposal of their mixed (radioactive and hazardous) waste. Meanwhile, the Environmental Protection Agency (EPA) issued a final open-quotes Hazardous Waste Combustion Strategyclose quotes in November 1994. Under the Combustion Strategy, EPA permit writers have been given the authority to use the Omnibus Provision of the Resource Conservation and Recovery Act (RCRA) to impose more stringent emission limits for waste combustors prior to the development of new regulations. EPA and DOE established a multi-year Interagency Agreement (IAG) in 1991. The main objective of the IAG (and of the second IAG that was added in 1993) is to conduct a research program on thermal technologies for treating mixed waste and to establish permit procedures for these technologies particularly under the new requirements of the above-mentioned EPA Combustion Strategy. The objective of this Paper is to summarize the results of the EPA/DOE joint efforts on mixed waste treatment since the establishment of the original Interagency Agreement. Specifically, this Paper will discuss six activities that have been underway; namely: (1) National Technical Workgroup (NTW) on Mixed Waste Treatment, (2) State-of-the-Art Assessment of APC (Air Pollution Control) and Monitoring Technologies for the Rocky Flats Fluidized Bed Unit, (3) Initial Study of Permit open-quotes Roadmapclose quotes Development for Mixed Waste Treatment, (4) Risk Assessment Approach for a Mixed Waste Thermal Treatment Facility, (5) Development and Application of Technology Selection Criteria for Mixed Waste Thermal Treatment, and (6) Performance Testing of Mixed Waste Incineration: In-Situ Chlorine Capture in a Fluidized Bed Unit

Development of threshold guidance: National Low-Level Radioactive Waste Management Program

International Nuclear Information System (INIS)

1986-09-01

The current study has been conducted to provide DOE with a technical basis for the development of threshold guidance. The objective of the study was to develop the necessary background information and recommendations to assist the DOE in implementing the threshold limit concept for the disposal of DOE wastes at DOE facilities. The nature of low-level radioactive waste (LLW) varies greatly in both form and radionuclide content. While some low-level waste streams can contain substantial quantities of radioactive constituents, a potentially significant fraction of low-level waste is contaminated either very slightly or not at all. There is a strong likelihood that managing wastes with extremely low levels of radioactivity as nonradioactive waste would pose no significant safety problems and could result in substantial cost savings relative to its handling as LLW. Since all materials, including waste products, contain some radioactivity, it is necessary to distinguish between those wastes that would require disposal as LLW and those that have sufficiently low levels of radiological content to be managed according to their nonradiological properties. 131 refs., 9 figs., 24 tabs

Technical Safety Requirements for the B695 Segment of the Decontamination and Waste Treatment Facility

International Nuclear Information System (INIS)

Larson, H L

2007-01-01

This document contains Technical Safety Requirements (TSRs) for the Radioactive and Hazardous Waste Management (RHWM) Division's B695 Segment of the Decontamination and Waste Treatment Facility (DWTF) at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the B695 Segment of the DWTF. The TSRs are derived from the Documented Safety Analysis (DSA) for the B695 Segment of the DWTF (LLNL 2004). The analysis presented there determined that the B695 Segment of the DWTF is a low-chemical hazard, Hazard Category 3, nonreactor nuclear facility. The TSRs consist primarily of inventory limits as well as controls to preserve the underlying assumptions in the hazard analyses. Furthermore, appropriate commitments to safety programs are presented in the administrative controls section of the TSRs. The B695 Segment of the DWTF (B695 and the west portion of B696) is a waste treatment and storage facility located in the northeast quadrant of the LLNL main site. The approximate area and boundary of the B695 Segment of the DWTF are shown in the B695 Segment of the DWTF DSA. Activities typically conducted in the B695 Segment of the DWTF include container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. B695 is used to store and treat radioactive, mixed, and hazardous waste, and it also contains equipment used in conjunction with waste processing operations to treat various liquid and solid wastes. The portion of the building called Building 696 Solid Waste Processing Area (SWPA), also referred to as B696S in this report, is used primarily to manage solid radioactive waste. Operations specific to the SWPA include sorting and segregating low-level waste (LLW) and transuranic (TRU) waste, lab-packing, sampling, and crushing empty drums that previously contained LLW. A permit modification for B696S was submitted to DTSC in January 2004 to store and treat hazardous and mixed

Assessment of LANL solid low-level mixed waste documentation

International Nuclear Information System (INIS)

Jennrich, E.A.; Lund, D.M.; Davis, K.D.; Hoevemeyer, S.S.

1991-04-01

DOE Order 5820.2A requires that a system performance assessment be conducted to assure efficient and compliant management of all radioactive waste. The objective of this report is to determine the present status of the Radioactive Waste Operations Section and the Chemical Waste Operations Section capabilities regarding preparation and maintenance of appropriate criteria, plans, and procedures. Additionally, a comparison is made which identifies areas where these documents are not presently in existence or being fully implemented. The documents being assessed in this report are: Solid Low-Level Mixed Waste Acceptance Criteria, Solid Low-Level Mixed Waste Characterization Plan, Solid Low-Level Mixed waste Certification Plan, Solid Low-Level Mixed Waste Acceptance Procedures, Solid Low-Level Mixed Waste characterization Procedures, Solid Low-Level Mixed Waste Certification Procedures, Solid Low-Level Mixed Waste Training Procedures, and Solid Low-Level Mixed Waste Recordkeeping Requirements. This report compares the current status of preparation and implementation, by the Radioactive Waste Operations Section and the Chemical Waste Operations Section, of these documents to the requirements of DOE 5820.2A,. 40 CFR 260 to 270, and to recommended practice. Chapters 2 through 9 of the report presents the results of the comparison in tabular form for each of the documents being assessed, followed by narrative discussion of all areas which are perceived to be unsatisfactory or out of compliance with respect to the availability and content of the documents. The final subpart of each of the following chapters provides recommendations where documentation practices may be improved to achieve compliance or to follow the recommended practice