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1

Idaho Waste Vitrification Facilities Project Vitrified Waste Interim Storage Facility  

SciTech Connect (OSTI)

This feasibility study report presents a draft design of the Vitrified Waste Interim Storage Facility (VWISF), which is one of three subprojects of the Idaho Waste Vitrification Facilities (IWVF) project. The primary goal of the IWVF project is to design and construct a treatment process system that will vitrify the sodium-bearing waste (SBW) to a final waste form. The project will consist of three subprojects that include the Waste Collection Tanks Facility, the Waste Vitrification Facility (WVF), and the VWISF. The Waste Collection Tanks Facility will provide for waste collection, feed mixing, and surge storage for SBW and newly generated liquid waste from ongoing operations at the Idaho Nuclear Technology and Engineering Center. The WVF will contain the vitrification process that will mix the waste with glass-forming chemicals or frit and turn the waste into glass. The VWISF will provide a shielded storage facility for the glass until the waste can be disposed at either the Waste Isolation Pilot Plant as mixed transuranic waste or at the future national geological repository as high-level waste glass, pending the outcome of a Waste Incidental to Reprocessing determination, which is currently in progress. A secondary goal is to provide a facility that can be easily modified later to accommodate storage of the vitrified high-level waste calcine. The objective of this study was to determine the feasibility of the VWISF, which would be constructed in compliance with applicable federal, state, and local laws. This project supports the Department of Energy’s Environmental Management missions of safely storing and treating radioactive wastes as well as meeting Federal Facility Compliance commitments made to the State of Idaho.

Bonnema, Bruce Edward

2001-09-01T23:59:59.000Z

2

Site Visit Report, Hanford Waste Encapsulation Storage Facility...  

Office of Environmental Management (EM)

Site Visit Report, Hanford Waste Encapsulation Storage Facility - January 2011 Site Visit Report, Hanford Waste Encapsulation Storage Facility - January 2011 January 2011 Hanford...

3

Hanford facility dangerous waste permit application, 616 Nonradioactive Dangerous Waste Storage Facility. Revision 2A  

SciTech Connect (OSTI)

This permit application for the 616 Nonradioactive Dangerous Waste Storage Facility consists for 15 chapters. Topics of discussion include the following: facility description and general provisions; waste characteristics; process information; personnel training; reporting and record keeping; and certification.

Bowman, R.C.

1994-04-01T23:59:59.000Z

4

The necessity for permanence : making a nuclear waste storage facility  

E-Print Network [OSTI]

The United States Department of Energy is proposing to build a nuclear waste storage facility in southern Nevada. This facility will be designed to last 10,000 years. It must prevent the waste from contaminating the ...

Stupay, Robert Irving

1991-01-01T23:59:59.000Z

5

Technical Safety Requirements for the Waste Storage Facilities  

SciTech Connect (OSTI)

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting of buildings, tents, other structures, and open areas as described in Chapter 2 of the DSA. Section 2.4 of the DSA provides an overview of the buildings, structures, and areas in the WASTE STORAGE FACILITIES, including construction details such as basic floor plans, equipment layout, construction materials, controlling dimensions, and dimensions significant to the hazard and accident analysis. Chapter 5 of the DSA documents the derivation of the TSRs and develops the operational limits that protect the safety envelope defined for the WASTE STORAGE FACILITIES. This TSR document is applicable to the handling, storage, and treatment of hazardous waste, TRU WASTE, LLW, mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste received or generated in the WASTE STORAGE FACILITIES. Section 5, Administrative Controls, contains those Administrative Controls necessary to ensure safe operation of the WASTE STORAGE FACILITIES. Programmatic Administrative Controls are in Section 5.6. This Introduction to the WASTE STORAGE FACILITIES TSRs is not part of the TSR limits or conditions and contains no requirements related to WASTE STORAGE FACILITIES operations or to the safety analyses of the DSA.

Larson, H L

2007-09-07T23:59:59.000Z

6

Documented Safety Analysis for the Waste Storage Facilities  

SciTech Connect (OSTI)

This documented safety analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements', and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

Laycak, D

2008-06-16T23:59:59.000Z

7

Documented Safety Analysis for the Waste Storage Facilities March 2010  

SciTech Connect (OSTI)

This Documented Safety Analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements,' and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

Laycak, D T

2010-03-05T23:59:59.000Z

8

Technical Safety Requirements for the Waste Storage Facilities  

SciTech Connect (OSTI)

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the 'Documented Safety Analysis for the Waste Storage Facilities' (DSA) (LLNL 2008). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting of buildings, tents, other structures, and open areas as described in Chapter 2 of the DSA. Section 2.4 of the DSA provides an overview of the buildings, structures, and areas in the WASTE STORAGE FACILITIES, including construction details such as basic floor plans, equipment layout, construction materials, controlling dimensions, and dimensions significant to the hazard and accident analysis. Chapter 5 of the DSA documents the derivation of the TSRs and develops the operational limits that protect the safety envelope defined for the WASTE STORAGE FACILITIES. This TSR document is applicable to the handling, storage, and treatment of hazardous waste, TRU WASTE, LLW, mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste received or generated in the WASTE STORAGE FACILITIES. Section 5, Administrative Controls, contains those Administrative Controls necessary to ensure safe operation of the WASTE STORAGE FACILITIES. Programmatic Administrative Controls are in Section 5.6.

Laycak, D T

2008-06-16T23:59:59.000Z

9

Safety analysis report for the Waste Storage Facility. Revision 2  

SciTech Connect (OSTI)

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

Bengston, S.J.

1994-05-01T23:59:59.000Z

10

Waste Encapsulation and Storage Facility (WESF) Hazards Assessment  

SciTech Connect (OSTI)

This report documents the hazards assessment for the Waste Encapsulation and Storage Facility (WESF) located on the U.S. Department of Energy (DOE) Hanford Site. This hazards assessment was conducted to provide the emergency planning technical basis for WESF. DOE Orders require an emergency planning hazards assessment for each facility that has the potential to reach or exceed the lowest level emergency classification.

COVEY, L.I.

2000-11-28T23:59:59.000Z

11

Waste Encapsulation and Storage Facility (WESF) Interim Status Closure Plan  

SciTech Connect (OSTI)

This document describes the planned activities and performance standards for closing the Waste Encapsulation and Storage Facility (WESF). WESF is located within the 225B Facility in the 200 East Area on the Hanford Facility. Although this document is prepared based on Title 40 Code of Federal Regulations (CFR), Part 265, Subpart G requirements, closure of the storage unit will comply with Washington Administrative Code (WAC) 173-303-610 regulations pursuant to Section 5.3 of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Action Plan (Ecology et al. 1996). Because the intention is to clean close WESF, postclosure activities are not applicable to this interim status closure plan. To clean close the storage unit, it will be demonstrated that dangerous waste has not been left onsite at levels above the closure performance standard for removal and decontamination. If it is determined that clean closure is not possible or environmentally is impracticable, the interim status closure plan will be modified to address required postclosure activities. WESF stores cesium and strontium encapsulated salts. The encapsulated salts are stored in the pool cells or process cells located within 225B Facility. The dangerous waste is contained within a double containment system to preclude spills to the environment. In the unlikely event that a waste spill does occur outside the capsules, operating methods and administrative controls require that waste spills be cleaned up promptly and completely, and a notation made in the operating record. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

SIMMONS, F.M.

2000-12-01T23:59:59.000Z

12

Hanford facility dangerous waste permit application, PUREX storage tunnels  

SciTech Connect (OSTI)

The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, operating treatment, storage, and/or disposal units, such as the PUREX Storage Tunnels (this document, DOE/RL-90-24). Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the US Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needs defined by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology alpha-numeric section identifiers from the permit application guidance documentation (Ecology 1996) follow, in brackets, the chapter headings and subheadings. A checklist indicating where information is contained in the PUREX Storage Tunnels permit application documentation, in relation to the Washington State Department of Ecology guidance, is located in the Contents Section. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Wherever appropriate, the PUREX Storage Tunnels permit application documentation makes cross-reference to the General Information Portion, rather than duplicating text. Information provided in this PUREX Storage Tunnels permit application documentation is current as of April 1997.

Price, S.M.

1997-09-08T23:59:59.000Z

13

EA-0820: Construction of Mixed Waste Storage RCRA Facilities, Buildings 7668 and 7669, Oak Ridge, Tennessee  

Broader source: Energy.gov [DOE]

This EA evaluates the environmental impacts of a proposal to construct and operate two mixed (both radioactive and hazardous) waste storage facilities (Buildings 7668 and 7669) in accordance with...

14

SWAMI: An Autonomous Mobile Robot for Inspection of Nuclear Waste Storage Facilities  

E-Print Network [OSTI]

SWAMI: An Autonomous Mobile Robot for Inspection of Nuclear Waste Storage Facilities Ron Fulbright Inspector (SWAMI) is a prototype mobile robot designed to perform autonomous inspection of nuclear waste user interface building tool called UIM/X. Introduction Safe disposal of nuclear waste is a difficult

Stephens, Larry M.

15

Mixed waste storage facility CDR review, Paducah Gaseous Diffusion Plant; Solid waste landfill CDR review, Paducah Gaseous Diffusion Plant  

SciTech Connect (OSTI)

This report consists of two papers reviewing the waste storage facility and the landfill projects proposed for the Paducah Gaseous Diffusion Plant complex. The first paper is a review of DOE`s conceptual design report for a mixed waste storage facility. This evaluation is to review the necessity of constructing a separate mixed waste storage facility. The structure is to be capable of receiving, weighing, sampling and the interim storage of wastes for a five year period beginning in 1996. The estimated cost is assessed at approximately $18 million. The review is to help comprehend and decide whether a new storage building is a feasible approach to the PGDP mixed waste storage problem or should some alternate approach be considered. The second paper reviews DOE`s conceptual design report for a solid waste landfill. This solid waste landfill evaluation is to compare costs and the necessity to provide a new landfill that would meet State of Kentucky regulations. The assessment considered funding for a ten year storage facility, but includes a review of other facility needs such as a radiation detection building, compactor/baler machinery, material handling equipment, along with other personnel and equipment storage buildings at a cost of approximately $4.1 million. The review is to help discern whether a landfill only or the addition of compaction equipment is prudent.

NONE

1998-08-01T23:59:59.000Z

16

Fast facility spent-fuel and waste assay instrument. [Fluorinel Dissolution and Fuel Storage (FAST) Facility  

SciTech Connect (OSTI)

A delayed-neutron assay instrument was installed in the Fluorinel Dissolution and Fuel Storage Facility at Idaho National Engineering Laboratory. The dual-assay instrument is designed to measure both spent fuel and waste solids that are produced from fuel processing. A set of waste standards, fabricated by Los Alamos using uranium supplied by Exxon Nuclear Idaho Company, was used to calibrate the small-sample assay region of the instrument. Performance testing was completed before installation of the instrument to determine the effects of uranium enrichment, hydrogenous materials, and neutron poisons on assays. The unit was designed to measure high-enriched uranium samples in the presence of large neutron backgrounds. Measurements indicate that the system can assay low-enriched uranium samples with moderate backgrounds if calibrated with proper standards.

Eccleston, G.W.; Johnson, S.S.; Menlove, H.O.; Van Lyssel, T.; Black, D.; Carlson, B.; Decker, L.; Echo, M.W.

1983-01-01T23:59:59.000Z

17

Progress and Status of the Ignalina Nuclear Power Plant's New Solid Waste Management and Storage Facilities  

SciTech Connect (OSTI)

A considerable amount of dry radioactive waste from former NPP operation has accumulated up to date and is presently stored at the Ignalina NPP site, Lithuania. Current storage capacities are nearly exhausted and more waste is to come from future decommissioning of the two RMBKtype reactors. Additionally, the existing storage facilities does not comply to the state-of-the-art technology for handling and storage of radioactive waste. In 2005, INPP faced this situation of a need for waste processing and subsequent interim storage of these wastes by contracting NUKEM with the design, construction, installation and commissioning of new waste management and storage facilities. The subject of this paper is to describe the scope and the status of the new solid waste management and storage facilities at the Ignalina Nuclear Power Plant. In summary: The turnkey contract for the design, supply and commission of the SWMSF was awarded in December 2005. The realisation of the project was initially planned within 48 month. The basic design was finished in August 2007 and the Technical Design Documentation and Preliminary Safety Analyses Report was provided to Authorities in October 2007. The construction license is expected in July 2008. The procurement phase was started in August 2007, start of onsite activities is expected in November 2007. The start of operation of the SWMSF is scheduled for end of 2009. (authors)

Rausch, J.; Henderson, R.W. [NUKEM Technologies GmbH, Alzenau (Germany); Penkov, V. [State Enterprise Ignalina Nuclear Power Plant, Visaginas (Lithuania)

2008-07-01T23:59:59.000Z

18

Environmental assessment for the construction and operation of waste storage facilities at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky  

SciTech Connect (OSTI)

DOE is proposing to construct and operate 3 waste storage facilities (one 42,000 ft{sup 2} waste storage facility for RCRA waste, one 42,000 ft{sup 2} waste storage facility for toxic waste (TSCA), and one 200,000 ft{sup 2} mixed (hazardous/radioactive) waste storage facility) at Paducah. This environmental assessment compares impacts of this proposed action with those of continuing present practices aof of using alternative locations. It is found that the construction, operation, and ultimate closure of the proposed waste storage facilities would not significantly affect the quality of the human environment within the meaning of NEPA; therefore an environmental impact statement is not required.

NONE

1994-06-01T23:59:59.000Z

19

Hanford facility dangerous waste permit application, 616 Nonradioactive dangerous waste storage facility  

SciTech Connect (OSTI)

This chapter provides information on the physical, chemical, and biological characteristics of the waste stored at the 616 NRDWSF. A waste analysis plan is included that describes the methodology used for determining waste types.

Price, S.M.

1997-04-30T23:59:59.000Z

20

Waste Encapsulation and Storage Facility (WESF) Quality Assurance Program Plan (QAPP)  

SciTech Connect (OSTI)

This Quality Assurance Plan describes how the Waste Encapsulation and Storage Facility (WESF) implements the quality assurance (QA) requirements of the Quality Assurance Program Description (QAPD) (HNF-Mp-599) for Project Hanford activities and products. This QAPP also describes the organizational structure necessary to successfully implement the program. The QAPP provides a road map of applicable Project Hanford Management System Procedures, and facility specific procedures, that may be utilized by WESF to implement the requirements of the QAPD.

ROBINSON, P.A.

2000-04-17T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Waste encapsulation storage facility (WESF) standards/requirements identification document (S/RIDS)  

SciTech Connect (OSTI)

This Standards/Requirements Identification Document (S/RID) sets forth the Environmental Safety and Health (ES{ampersand}H) standards/requirements for the Waste Encapsulation Storage Facility (WESF). This S/RID is applicable to the appropriate life cycle phases of design, construction, operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.

Maddox, B.S., Westinghouse Hanford

1996-07-29T23:59:59.000Z

22

Waste Encapsulation and Storage Facility (WESF) Basis for Interim Operation (BIO)  

SciTech Connect (OSTI)

The Waste Encapsulation and Storage Facility (WESF) is located in the 200 East Area adjacent to B Plant on the Hanford Site north of Richland, Washington. The current WESF mission is to receive and store the cesium and strontium capsules that were manufactured at WESF in a safe manner and in compliance with all applicable rules and regulations. The scope of WESF operations is currently limited to receipt, inspection, decontamination, storage, and surveillance of capsules in addition to facility maintenance activities. The capsules are expected to be stored at WESF until the year 2017, at which time they will have been transferred for ultimate disposition. The WESF facility was designed and constructed to process, encapsulate, and store the extracted long-lived radionuclides, {sup 90}Sr and {sup 137}Cs, from wastes generated during the chemical processing of defense fuel on the Hanford Site thus ensuring isolation of hazardous radioisotopes from the environment. The construction of WESF started in 1971 and was completed in 1973. Some of the {sup 137}Cs capsules were leased by private irradiators or transferred to other programs. All leased capsules have been returned to WESF. Capsules transferred to other programs will not be returned except for the seven powder and pellet Type W overpacks already stored at WESF.

COVEY, L.I.

2000-11-28T23:59:59.000Z

23

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

SciTech Connect (OSTI)

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

Not Available

1986-05-01T23:59:59.000Z

24

Waste Encapsulation and Storage Facility (WESF) Dangerous Waste Training Plan (DWTP)  

SciTech Connect (OSTI)

This training plan describes general requirements, worker categories, and provides course descriptions for operation of the WESF permitted miscellaneous storage units, and the < 90 day accumulation areas.

LEBARON, G.J.

1999-12-03T23:59:59.000Z

25

Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)  

SciTech Connect (OSTI)

The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

Burgard, K.C.

1998-04-09T23:59:59.000Z

26

Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)  

SciTech Connect (OSTI)

The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

Burgard, K.C.

1998-06-02T23:59:59.000Z

27

RH-TRU Waste Shipments from Battelle Columbus Laboratories to the Hanford Nuclear Facility for Interim Storage  

SciTech Connect (OSTI)

Battelle Columbus Laboratories (BCL), located in Columbus, Ohio, must complete decontamination and decommissioning (D&D) activities for nuclear research buildings and grounds by 2006, as directed by Congress. Most of the resulting waste (approximately 27 cubic meters [m3]) is remote-handled (RH) transuranic (TRU) waste destined for disposal at the Waste Isolation Pilot Plant (WIPP). The BCL, under a contract to the U.S. Department of Energy (DOE) Ohio Field Office, has initiated a plan to ship the TRU waste to the DOE Hanford Nuclear Facility (Hanford) for interim storage pending the authorization of WIPP for the permanent disposal of RH-TRU waste. The first of the BCL RH-TRU waste shipments was successfully completed on December 18, 2002. This BCL shipment of one fully loaded 10-160B Cask was the first shipment of RH-TRU waste in several years. Its successful completion required a complex effort entailing coordination between different contractors and federal agencies to establish necessary supporting agreements. This paper discusses the agreements and funding mechanisms used in support of the BCL shipments of TRU waste to Hanford for interim storage. In addition, this paper presents a summary of the efforts completed to demonstrate the effectiveness of the 10-160B Cask system. Lessons learned during this process are discussed and may be applicable to other TRU waste site shipment plans.

Eide, J.; Baillieul, T. A.; Biedscheid, J.; Forrester, T,; McMillan, B.; Shrader, T.; Richterich, L.

2003-02-26T23:59:59.000Z

28

CHARACTERIZING DOE HANFORD SITE WASTE ENCAPSULATION STORAGE FACILITY CELLS USING RADBALL  

SciTech Connect (OSTI)

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

Farfan, E.; Coleman, R.

2011-03-31T23:59:59.000Z

29

Analysis of accident sequences and source terms at treatment and storage facilities for waste generated by US Department of Energy waste management operations  

SciTech Connect (OSTI)

This report documents the methodology, computational framework, and results of facility accident analyses performed for the US Department of Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). The accident sequences potentially important to human health risk are specified, their frequencies assessed, and the resultant radiological and chemical source terms evaluated. A personal-computer-based computational framework and database have been developed that provide these results as input to the WM PEIS for the calculation of human health risk impacts. The WM PEIS addresses management of five waste streams in the DOE complex: low-level waste (LLW), hazardous waste (HW), high-level waste (HLW), low-level mixed waste (LLMW), and transuranic waste (TRUW). Currently projected waste generation rates, storage inventories, and treatment process throughputs have been calculated for each of the waste streams. This report summarizes the accident analyses and aggregates the key results for each of the waste streams. Source terms are estimated, and results are presented for each of the major DOE sites and facilities by WM PEIS alternative for each waste stream. Key assumptions in the development of the source terms are identified. The appendices identify the potential atmospheric release of each toxic chemical or radionuclide for each accident scenario studied. They also discuss specific accident analysis data and guidance used or consulted in this report.

Mueller, C.; Nabelssi, B.; Roglans-Ribas, J.; Folga, S.; Policastro, A.; Freeman, W.; Jackson, R.; Mishima, J.; Turner, S.

1996-12-01T23:59:59.000Z

30

PEGASUS, a European research project on the effects of gas in underground storage facilities for radioactive waste  

SciTech Connect (OSTI)

Whereas the subject of gas generation and possible gas release from radioactive waste repositories has gained in interest on the international scene, the Commission of the European Communities has increased its research efforts on this issue. In particular in the 4th five year R and D program on Management and Storage of Radioactive Waste (1990--1994), a framework has been set up in which research efforts on the subject of gas generation and migration, supported by the CEC, are brought together and coordinated. In this project, called PEGASUS, Project on the Effects of GAS in Underground Storage facilities for radioactive waste, about 20 organizations and research institutes from 7 European countries are involved. The project covers both experimental and theoretical studies of the processes of gas formation and possible gas release from the different waste types, LLW, ILW and HLW, under typical repository conditions in suitable geological formations as clay, salt and granite. In this paper an overview is given of the various studies undertaken in the project as well as some first results presented.

Haijtink, B.; McMenamin, T. [Commission of the European Communities, Brussels (Belgium)

1993-12-31T23:59:59.000Z

31

Calcined solids storage facility closure study  

SciTech Connect (OSTI)

The disposal of radioactive wastes now stored at the Idaho National Engineering and Environmental Laboratory is currently mandated under a {open_quotes}Settlement Agreement{close_quotes} (or {open_quotes}Batt Agreement{close_quotes}) between the Department of Energy and the State of Idaho. Under this agreement, all high-level waste must be treated as necessary to meet the disposal criteria and disposed of or made road ready to ship from the INEEL by 2035. In order to comply with this agreement, all calcined waste produced in the New Waste Calcining Facility and stored in the Calcined Solids Facility must be treated and disposed of by 2035. Several treatment options for the calcined waste have been studied in support of the High-Level Waste Environmental Impact Statement. Two treatment methods studied, referred to as the TRU Waste Separations Options, involve the separation of the high-level waste (calcine) into TRU waste and low-level waste (Class A or Class C). Following treatment, the TRU waste would be sent to the Waste Isolation Pilot Plant (WIPP) for final storage. It has been proposed that the low-level waste be disposed of in the Tank Farm Facility and/or the Calcined Solids Storage Facility following Resource Conservation and Recovery Act closure. In order to use the seven Bin Sets making up the Calcined Solids Storage Facility as a low-level waste landfill, the facility must first be closed to Resource Conservation and Recovery Act (RCRA) standards. This study identifies and discusses two basic methods available to close the Calcined Solids Storage Facility under the RCRA - Risk-Based Clean Closure and Closure to Landfill Standards. In addition to the closure methods, the regulatory requirements and issues associated with turning the Calcined Solids Storage Facility into an NRC low-level waste landfill or filling the bin voids with clean grout are discussed.

Dahlmeir, M.M.; Tuott, L.C.; Spaulding, B.C. [and others] [and others

1998-02-01T23:59:59.000Z

32

EA-0981: Solid Waste Retrieval Complex, Enhanced Radioactive and Mixed Waste Storage Facility, Infrastructure Upgrades, and Central Waste Support Complex, Hanford Site, Richland, Washington  

Broader source: Energy.gov [DOE]

This EA evaluates the environmental impacts of the proposal to retrieve transuranic waste (TRU), provide storage capacity for retrieved and newly generated TRU, Greater-than-Category 3, and mixed...

33

Nevada Nuclear Waste Storage Investigations: Exploratory Shaft Facility fluids and materials evaluation  

SciTech Connect (OSTI)

The objective of this study was to determine if any fluids or materials used in the Exploratory Shaft Facility (ESF) of Yucca Mountain will make the mountain unsuitable for future construction of a nuclear waste repository. Yucca Mountain, an area on and adjacent to the Nevada Test Site in southern Nevada, USA, is a candidate site for permanent disposal of high-level radioactive waste from commercial nuclear power and defense nuclear activities. To properly characterize Yucca Mountain, it will be necessary to construct an underground test facility, in which in situ site characterization tests can be conducted. The candidate repository horizon at Yucca Mountain, however, could potentially be compromised by fluids and materials used in the site characterization tests. To minimize this possibility, Los Alamos National Laboratory was directed to evaluate the kinds of fluids and materials that will be used and their potential impacts on the site. A secondary objective was to identify fluids and materials, if any, that should be prohibited from, or controlled in, the underground. 56 refs., 19 figs., 11 tabs.

West, K.A.

1988-11-01T23:59:59.000Z

34

Structural Integrity Program for INTEC Calcined Solids Storage Facilities  

SciTech Connect (OSTI)

This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, 'Radioactive Waste Management Manual'. Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities.

Jeffrey Bryant

2008-08-30T23:59:59.000Z

35

2727-S Nonradioactive Dangerous Waste Storage Facility clean closure evaluation report  

SciTech Connect (OSTI)

This report presents the analytical results of 2727-S NRDWS facility closure verification soil sampling and compares these results to clean closure criteria. The results of this comparison will determine if clean closure of the unit is regulatorily achievable. This report also serves to notify regulators that concentrations of some analytes at the site exceed sitewide background threshold levels (DOE-RL 1993b) and/or the limits of quantitation (LOQ). This report also presents a Model Toxics Control Act Cleanup (MTCA) (WAC 173-340) regulation health-based closure standard under which the unit can clean close in lieu of closure to background levels or LOQ in accordance with WAC 173-303-610. The health-based clean closure standard will be closure to MTCA Method B residential cleanup levels. This report reconciles all analyte concentrations reported above background or LOQ to this health-based cleanup standard. Regulator acceptance of the findings presented in this report will qualify the TSD unit for clean closure in accordance with WAC 173-303-610 without further TSD unit soil sampling, or soil removal and/or decontamination. Nondetected analytes require no further evaluation.

Luke, S.N.

1994-07-14T23:59:59.000Z

36

Waste Management Facilities Cost Information Report  

SciTech Connect (OSTI)

The Waste Management Facility Cost Information (WMFCI) Report, commissioned by the US Department of Energy (DOE), develops planning life-cycle cost (PLCC) estimates for treatment, storage, and disposal facilities. This report contains PLCC estimates versus capacity for 26 different facility cost modules. A procedure to guide DOE and its contractor personnel in the use of estimating data is also provided. Estimates in the report apply to five distinctive waste streams: low-level waste, low-level mixed waste, alpha contaminated low-level waste, alpha contaminated low-level mixed waste, and transuranic waste. The report addresses five different treatment types: incineration, metal/melting and recovery, shredder/compaction, solidification, and vitrification. Data in this report allows the user to develop PLCC estimates for various waste management options.

Feizollahi, F.; Shropshire, D.

1992-10-01T23:59:59.000Z

37

Supplemental analysis of accident sequences and source terms for waste treatment and storage operations and related facilities for the US Department of Energy waste management programmatic environmental impact statement  

SciTech Connect (OSTI)

This report presents supplemental information for the document Analysis of Accident Sequences and Source Terms at Waste Treatment, Storage, and Disposal Facilities for Waste Generated by US Department of Energy Waste Management Operations. Additional technical support information is supplied concerning treatment of transuranic waste by incineration and considering the Alternative Organic Treatment option for low-level mixed waste. The latest respirable airborne release fraction values published by the US Department of Energy for use in accident analysis have been used and are included as Appendix D, where respirable airborne release fraction is defined as the fraction of material exposed to accident stresses that could become airborne as a result of the accident. A set of dominant waste treatment processes and accident scenarios was selected for a screening-process analysis. A subset of results (release source terms) from this analysis is presented.

Folga, S.; Mueller, C.; Nabelssi, B.; Kohout, E.; Mishima, J.

1996-12-01T23:59:59.000Z

38

Hazardous Waste Facilities Siting (Connecticut)  

Broader source: Energy.gov [DOE]

These regulations describe the siting and permitting process for hazardous waste facilities and reference rules for construction, operation, closure, and post-closure of these facilities.

39

Solid Waste Facilities Regulations (Massachusetts)  

Broader source: Energy.gov [DOE]

This chapter of the Massachusetts General Laws governs the operation of solid waste facilities. It seeks to encourage sustainable waste management practices and to mitigate adverse effects, such as...

40

Update Direct-Strike Lightning Environment for Stockpile-to-Target Sequence: Supplement LLNL Subcontract #B568621 Lightning Protection at the Yucca Mountain Waste Storage Facility  

SciTech Connect (OSTI)

The University of Florida has surveyed all relevant publications reporting lightning damage to metals, metals which could be used as components of storage containers for nuclear waste materials. We show that even the most severe lightning could not penetrate the stainless steel thicknesses proposed for nuclear waste storage casks.

Uman, M A

2008-10-09T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Referenced-site environmental document for a Monitored Retrievable Storage facility: backup waste management option for handling 1800 MTU per year  

SciTech Connect (OSTI)

This environmental document includes a discussion of the purpose of a monitored retrievable storage facility, a description of two facility design concepts (sealed storage cask and field drywell), a description of three reference sites (arid, warm-wet, and cold-wet), and a discussion and comparison of the impacts associated with each of the six site/concept combinations. This analysis is based on a 15,000-MTU storage capacity and a throughput rate of up to 1800 MTU per year.

Silviera, D.J.; Aaberg, R.L.; Cushing, C.E.; Marshall, A.; Scott, M.J.; Sewart, G.H.; Strenge, D.L.

1985-06-01T23:59:59.000Z

42

New Waste Calcining Facility (NWCF) Waste Streams  

SciTech Connect (OSTI)

This report addresses the issues of conducting debris treatment in the New Waste Calcine Facility (NWCF) decontamination area and the methods currently being used to decontaminate material at the NWCF.

K. E. Archibald

1999-08-01T23:59:59.000Z

43

Hazardous Waste Facility Siting Program (Maryland)  

Broader source: Energy.gov [DOE]

The Hazardous Waste Facilities Siting Board is responsible for overseeing the siting of hazardous waste facilities in Maryland, and will treat hazardous waste facilities separately from low-level...

44

Rules and Regulations for Underground Storage Facilities Used for Petroleum Products and Hazardous Materials (Rhode Island)  

Broader source: Energy.gov [DOE]

These regulations apply to underground storage facilities for petroleum and hazardous waste, and seek to protect water resources from contamination. The regulations establish procedures for the...

45

Chapter 47 Solid Waste Facilities (Kentucky)  

Broader source: Energy.gov [DOE]

This chapter establishes the permitting standards for solid waste sites or facilities, the standards applicable to all solid waste sites or facilities, and the standards for certification of...

46

Independent Oversight Assessment, Salt Waste Processing Facility...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Salt Waste Processing Facility Project - January 2013 January 2013 Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project The U.S. Department...

47

Solid Waste Disposal Facilities (Massachusetts)  

Broader source: Energy.gov [DOE]

These sections articulate rules for the maintenance and operation of solid waste disposal facilities, as well as site assignment procedures. Applications for site assignment will be reviewed by the...

48

EA-0942: Return of Isotope Capsules to the Waste Encapsulation and Storage Facility, Hanford Site, Richland, Washington  

Broader source: Energy.gov [DOE]

This EA evaluates the environmental impacts of the proposal for the return of all leased cesium-137 and strontium-90 leased capsules to the U.S. Department of Energy's Waste Encapsulation and...

49

Development of biological and chemical methods for environmental monitoring of DOE waste disposal and storage facilities. Final report  

SciTech Connect (OSTI)

Hazardous chemicals in the environment have received ever increasing attention in recent years. In response to ongoing problems with hazardous waste management, Congress enacted the Resource Conservation and Recovery Act (RCRA) in 1976. In 1980, Congress adopted the Comprehensive Environmental Response Compensation, and Liability Act (CERCLA), commonly called Superfund to provide for emergency spill response and to clean up closed or inactive hazardous waste sites. Scientists and engineers have begun to respond to the hazardous waste challenge with research and development on treatment of waste streams as well as cleanup of polluted areas. The magnitude of the problem is just now beginning to be understood. The U.S. Environmental Protection Agency (USEPA) National Priorities List as of September 13 1985, contained 318 proposed sites and 541 final sites (USEPA, 1985). Estimates of up to 30,000 sites containing hazardous wastes (1,200 to 2,000 of which present a serious threat to public health) have been made (Public Law 96-150). In addition to the large number of sites, the costs of cleanup using available technology are phenomenal. For example, a 10-acre toxic waste site in Ohio is to be cleaned up by removing chemicals from the site and treating the contaminated groundwater. The federal government has already spent more than $7 million to remove the most hazardous wastes and the groundwater decontamination alone is expected to take at least 10 years and cost $12 million. Another example of cleanup costs comes from the State of California Commission for Economic Development which predicts a bright economic future for the state except for the potential outlay of $40 billion for hazardous waste cleanup mandated by federal and state laws.

NONE

1989-04-01T23:59:59.000Z

50

assembly storage facility: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Page Last Page Topic Index 1 Temporary (mobile) storage testing facilities Renewable Energy Websites Summary: Temporary (mobile) storage testing facilities Permanent storage...

51

High level waste facilities -- Continuing operation or orderly shutdown  

SciTech Connect (OSTI)

Two options for Environmental Impact Statement No action alternatives describe operation of the radioactive liquid waste facilities at the Idaho Chemical Processing Plant at the Idaho National Engineering and Environmental Laboratory. The first alternative describes continued operation of all facilities as planned and budgeted through 2020. Institutional control for 100 years would follow shutdown of operational facilities. Alternatively, the facilities would be shut down in an orderly fashion without completing planned activities. The facilities and associated operations are described. Remaining sodium bearing liquid waste will be converted to solid calcine in the New Waste Calcining Facility (NWCF) or will be left in the waste tanks. The calcine solids will be stored in the existing Calcine Solids Storage Facilities (CSSF). Regulatory and cost impacts are discussed.

Decker, L.A.

1998-04-01T23:59:59.000Z

52

Progress of the High Level Waste Program at the Defense Waste Processing Facility - 13178  

SciTech Connect (OSTI)

The Defense Waste Processing Facility at the Savannah River Site treats and immobilizes High Level Waste into a durable borosilicate glass for safe, permanent storage. The High Level Waste program significantly reduces environmental risks associated with the storage of radioactive waste from legacy efforts to separate fissionable nuclear material from irradiated targets and fuels. In an effort to support the disposition of radioactive waste and accelerate tank closure at the Savannah River Site, the Defense Waste Processing Facility recently implemented facility and flowsheet modifications to improve production by 25%. These improvements, while low in cost, translated to record facility production in fiscal years 2011 and 2012. In addition, significant progress has been accomplished on longer term projects aimed at simplifying and expanding the flexibility of the existing flowsheet in order to accommodate future processing needs and goals. (authors)

Bricker, Jonathan M.; Fellinger, Terri L.; Staub, Aaron V.; Ray, Jeff W.; Iaukea, John F. [Savannah River Remediation, Aiken, South Carolina, 29808 (United States)] [Savannah River Remediation, Aiken, South Carolina, 29808 (United States)

2013-07-01T23:59:59.000Z

53

The Hazardous Waste/Mixed Waste Disposal Facility  

SciTech Connect (OSTI)

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.

Bailey, L.L.

1991-01-01T23:59:59.000Z

54

The Hazardous Waste/Mixed Waste Disposal Facility  

SciTech Connect (OSTI)

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.

Bailey, L.L.

1991-12-31T23:59:59.000Z

55

303-K Storage Facility closure plan. Revision 2  

SciTech Connect (OSTI)

Recyclable scrap uranium with zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/zircaloy-2 alloy, and zircaloy-2 chips and fines were secured in concrete billets (7.5-gallon containers) in the 303-K Storage Facility, located in the 300 Area. The beryllium/zircaloy-2 alloy and zircaloy-2 chips and fines are designated as mixed waste with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 303-K Storage Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040. This closure plan presents a description of the 303-K Storage Facility, the history of materials and waste managed, and the procedures that will be followed to close the 303-K Storage Facility. The 303-K Storage Facility is located within the 300-FF-3 (source) and 300-FF-5 (groundwater) operable units, as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992). Contamination in the operable units 300-FF-3 and 300-FF-5 is scheduled to be addressed through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 remedial action process. Therefore, all soil remedial action at the 304 Facility will be conducted as part of the CERCLA remedial action of operable units 300-FF-3 and 300-FF-5.

Not Available

1993-12-15T23:59:59.000Z

56

Dismantlement and Radioactive Waste Management of DPRK Nuclear Facilities  

SciTech Connect (OSTI)

One critical aspect of any denuclearization of the Democratic People’s Republic of Korea (DPRK) involves dismantlement of its nuclear facilities and management of their associated radioactive wastes. The decommissioning problem for its two principal operational plutonium facilities at Yongbyun, the 5MWe nuclear reactor and the Radiochemical Laboratory reprocessing facility, alone present a formidable challenge. Dismantling those facilities will create radioactive waste in addition to existing inventories of spent fuel and reprocessing wastes. Negotiations with the DPRK, such as the Six Party Talks, need to appreciate the enormous scale of the radioactive waste management problem resulting from dismantlement. The two operating plutonium facilities, along with their legacy wastes, will result in anywhere from 50 to 100 metric tons of uranium spent fuel, as much as 500,000 liters of liquid high-level waste, as well as miscellaneous high-level waste sources from the Radiochemical Laboratory. A substantial quantity of intermediate-level waste will result from disposing 600 metric tons of graphite from the reactor, an undetermined quantity of chemical decladding liquid waste from reprocessing, and hundreds of tons of contaminated concrete and metal from facility dismantlement. Various facilities for dismantlement, decontamination, waste treatment and packaging, and storage will be needed. The shipment of spent fuel and liquid high level waste out of the DPRK is also likely to be required. Nuclear facility dismantlement and radioactive waste management in the DPRK are all the more difficult because of nuclear nonproliferation constraints, including the call by the United States for “complete, verifiable and irreversible dismantlement,” or “CVID.” It is desirable to accomplish dismantlement quickly, but many aspects of the radioactive waste management cannot be achieved without careful assessment, planning and preparation, sustained commitment, and long completion times. The radioactive waste management problem in fact offers a prospect for international participation to engage the DPRK constructively. DPRK nuclear dismantlement, when accompanied with a concerted effort for effective radioactive waste management, can be a mutually beneficial goal.

Jooho, W.; Baldwin, G. T.

2005-04-01T23:59:59.000Z

57

Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility  

SciTech Connect (OSTI)

The 200 Area Effluent Treatment Facility Dangerous Waste Permit Application documentation consists of both Part A and a Part B permit application documentation. An explanation of the Part A revisions associated with this treatment and storage unit, including the current revision, is provided at the beginning of the Part A section. Once the initial Hanford Facility Dangerous Waste Permit is issued, the following process will be used. As final, certified treatment, storage, and/or disposal unit-specific documents are developed, and completeness notifications are made by the US Environmental Protection Agency and the Washington State Department of Ecology, additional unit-specific permit conditions will be incorporated into the Hanford Facility Dangerous Waste Permit through the permit modification process. All treatment, storage, and/or disposal units that are included in the Hanford Facility Dangerous Waste Permit Application will operate under interim status until final status conditions for these units are incorporated into the Hanford Facility Dangerous Waste Permit. The Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility contains information current as of May 1, 1993.

Not Available

1993-08-01T23:59:59.000Z

58

President Reagan Calls for a National Spent Fuel Storage Facility...  

National Nuclear Security Administration (NNSA)

Spent Fuel Storage Facility Washington, DC The Reagan Administration announces a nuclear energy policy that anticipates the establishment of a facility for the storage of...

59

Optimal operating strategy for a storage facility  

E-Print Network [OSTI]

In the thesis, I derive the optimal operating strategy to maximize the value of a storage facility by exploiting the properties in the underlying natural gas spot price. To achieve the objective, I investigate the optimal ...

Zhai, Ning

2008-01-01T23:59:59.000Z

60

Transuranic waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement  

SciTech Connect (OSTI)

Transuranic waste (TRUW) loads and potential contaminant releases at and en route to treatment, storage, and disposal sites in the US Department of Energy (DOE) complex are important considerations in DOE`s Waste Management Programmatic Environmental Impact Statement (WM PEIS). Waste loads are determined in part by the level of treatment the waste has undergone and the complex-wide configuration of origination, treatment, storage, and disposal sites selected for TRUW management. Other elements that impact waste loads are treatment volumes, waste characteristics, and the unit operation parameters of the treatment technologies. Treatment levels and site configurations have been combined into six TRUW management alternatives for study in the WM PEIS. This supplemental report to the WM PEIS gives the projected waste loads and contaminant release profiles for DOE treatment sites under each of the six TRUW management alternatives. It gives TRUW characteristics and inventories for current DOE generation and storage sites, describes the treatment technologies for three proposed levels of TRUW treatment, and presents the representative unit operation parameters of the treatment technologies. The data presented are primary inputs to developing the costs, health risks, and socioeconomic and environmental impacts of treating, packaging, and shipping TRUW for disposal.

Hong, K.; Kotek, T.; Folga, S.; Koebnick, B.; Wang, Y.; Kaicher, C.

1996-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

340 waste handling facility interim safety basis  

SciTech Connect (OSTI)

This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people.

VAIL, T.S.

1999-04-01T23:59:59.000Z

62

340 Waste handling facility interim safety basis  

SciTech Connect (OSTI)

This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people.

Stordeur, R.T.

1996-10-04T23:59:59.000Z

63

Information related to low-level mixed waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement  

SciTech Connect (OSTI)

This report was prepared to support the analysis of risks and costs associated with the proposed treatment of low-level mixed waste (LLMW) under management of the US Department of Energy (DOE). The various waste management alternatives for treatment of LLMW have been defined in the DOE`s Office of Waste Management Programmatic Environmental Impact Statement. This technical memorandum estimates the waste material throughput expected at each proposed LLMW treatment facility and analyzes potential radiological and chemical releases at each DOE site resulting from treatment of these wastes. Models have been developed to generate site-dependent radiological profiles and waste-stream-dependent chemical profiles for these wastes. Current site-dependent inventories and estimates for future generation of LLMW have been obtained from DOE`s 1994 Mixed Waste Inventory Report (MWIR-2). Using treatment procedures developed by the Mixed Waste Treatment Project, the MWIR-2 database was analyzed to provide waste throughput and emission estimates for each of the different waste types assessed in this report. Uncertainties in the estimates at each site are discussed for waste material throughputs and radiological and chemical releases.

Wilkins, B.D.; Dolak, D.A.; Wang, Y.Y.; Meshkov, N.K.

1996-12-01T23:59:59.000Z

64

3718-F Alkali Metal Treatment and Storage Facility Closure Plan  

SciTech Connect (OSTI)

Since 1987, Westinghouse Hanford Company has been a major contractor to the U.S. Department of Energy-Richland Operations Office and has served as co-operator of the 3718-F Alkali Metal Treatment and Storage Facility, the waste management unit addressed in this closure plan. The closure plan consists of a Part A Dangerous waste Permit Application and a RCRA Closure Plan. An explanation of the Part A Revision (Revision 1) submitted with this document is provided at the beginning of the Part A section. The closure plan consists of 9 chapters and 5 appendices. The chapters cover: introduction; facility description; process information; waste characteristics; groundwater; closure strategy and performance standards; closure activities; postclosure; and references.

none,

1991-12-01T23:59:59.000Z

65

Waste Treatment and Immobilation Plant Pretreatment Facility  

Office of Environmental Management (EM)

7-DESIGN-047 Technology Readiness Assessment for the Waste Treatment and Immobilization Plant (WTP) Pretreatment Facility L. Holton D. Alexander M. Johnson H. Sutter August 2007...

66

Environmental Management Waste Management Facility (EMWMF) at...  

Office of Environmental Management (EM)

Technical Review Report: Oak Ridge Reservation Review of the Environmental Management Waste Management Facility (EMWMF) at Oak Ridge By Craig H. Benson, PhD, PE; William H....

67

Massachusetts Hazardous Waste Facility Siting Act (Massachusetts)  

Broader source: Energy.gov [DOE]

This Act establishes the means by which developers of proposed hazardous waste facilities will work with the community in which they wish to construct a facility. When the intent to construct,...

68

Waste Analysis Plan for the Waste Receiving and Processing (WRAP) Facility  

SciTech Connect (OSTI)

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for dangerous, mixed, and radioactive waste accepted for confirmation, nondestructive examination (NDE) and nondestructive assay (NDA), repackaging, certification, and/or storage at the Waste Receiving and Processing Facility (WRAP). Mixed and/or radioactive waste is treated at WRAP. WRAP is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

TRINER, G.C.

1999-11-01T23:59:59.000Z

69

Feasibility study: Assess the feasibility of siting a monitored retrievable storage facility. Phase 1  

SciTech Connect (OSTI)

The purpose of phase one of this study are: To understand the waste management system and a monitored retrievable storage facility; and to determine whether the applicant has real interest in pursuing the feasibility assessment process. Contents of this report are: Generating electric power; facts about exposure to radiation; handling storage, and transportation techniques; description of a proposed monitored retrievable storage facility; and benefits to be received by host jurisdiction.

King, J.W.

1993-08-01T23:59:59.000Z

70

Westinghouse Cementation Facility of Solid Waste Treatment System - 13503  

SciTech Connect (OSTI)

During NPP operation, several waste streams are generated, caused by different technical and physical processes. Besides others, liquid waste represents one of the major types of waste. Depending on national regulation for storage and disposal of radioactive waste, solidification can be one specific requirement. To accommodate the global request for waste treatment systems Westinghouse developed several specific treatment processes for the different types of waste. In the period of 2006 to 2008 Westinghouse awarded several contracts for the design and delivery of waste treatment systems related to the latest CPR-1000 nuclear power plants. One of these contracts contains the delivery of four Cementation Facilities for waste treatment, s.c. 'Follow on Cementations' dedicated to three locations, HongYanHe, NingDe and YangJiang, of new CPR-1000 nuclear power stations in the People's Republic of China. Previously, Westinghouse delivered a similar cementation facility to the CPR-1000 plant LingAo II, in Daya Bay, PR China. This plant already passed the hot functioning tests successfully in June 2012 and is now ready and released for regular operation. The 'Follow on plants' are designed to package three 'typical' kind of radioactive waste: evaporator concentrates, spent resins and filter cartridges. The purpose of this paper is to provide an overview on the Westinghouse experience to design and execution of cementation facilities. (authors)

Jacobs, Torsten; Aign, Joerg [Westinghouse Electric Germany GmbH, Global Waste Management, Tarpenring 6, D- 22419 Hamburg (Germany)] [Westinghouse Electric Germany GmbH, Global Waste Management, Tarpenring 6, D- 22419 Hamburg (Germany)

2013-07-01T23:59:59.000Z

71

Quality Services: Solid Wastes, Part 361: Siting of Industrial Hazardous Waste Facilities (New York)  

Broader source: Energy.gov [DOE]

These regulations describe the siting of new industrial hazardous waste facilities located wholly or partially within the State. Industrial hazardous waste facilities are defined as facilities used...

72

Solid Waste Operations Complex (SWOC) Facilities Sprinkler System Hydraulic Calculations  

SciTech Connect (OSTI)

The attached calculations demonstrate sprinkler system operational water requirements as determined by hydraulic analysis. Hydraulic calculations for the waste storage buildings of the Central Waste Complex (CWC), T Plant, and Waste Receiving and Packaging (WRAP) facility are based upon flow testing performed by Fire Protection Engineers from the Hanford Fire Marshal's office. The calculations received peer review and approval prior to release. The hydraulic analysis program HASS Computer Program' (under license number 1609051210) is used to perform all analyses contained in this document. Hydraulic calculations demonstrate sprinkler system operability based upon each individual system design and available water supply under the most restrictive conditions.

KERSTEN, J.K.

2003-07-11T23:59:59.000Z

73

Idaho Waste Treatment Facility Improves Worker Safety and Efficiency...  

Office of Environmental Management (EM)

Idaho Waste Treatment Facility Improves Worker Safety and Efficiency, Saves Taxpayer Dollars Idaho Waste Treatment Facility Improves Worker Safety and Efficiency, Saves Taxpayer...

74

Status of the Nevada Nuclear Waste Storage investigations  

SciTech Connect (OSTI)

The Nevada Nuclear Waste Storage Investigations (NNWSI) are part of the National Waste Terminal Storage (NWTS) program being conducted by the Department of Energy. Within the NWTS program, the NNWSI is the component that focuses on siting evaluations on and near the Nevada Test Site (NTS). The objectives of the Nevada project include evaluating the suitability of a Test and Evaluation Facility (TEF) site on or near the NTS, evaluating the suitability of a commercial nuclear waste repository site on or near the NTS, and supporting the NWTS program with research that is uniquely possible at NTS. Current engineering studies suggest that TEF and repository surface facilities would need to be located on gently sloping alluvium east of Yucca Mountain. Access from surface facilities to underground waste emplacement areas would be by vertical shafts and horizontal drifts, or possibly by inclined adits. The current NNWSI schedule includes an exploratory shaft location and horizon recommendation in 12/82, with a start of exploratory shaft drilling in 9/83. Because of the complexities of horizon selection, it is possible that the exploratory shaft depth or horizon recommendation may involve the exploration of more than one horizon. Phase I of the exploratory shaft, determination of TEF site suitability, is currently scheduled for 7/85. Phase II of the exploratory shaft, determination of repository site suitability, is currently scheduled for 3/87. This schedule is consistent with the current NWTS TEF and repository site selection schedules.

Lincoln, R. C.

1982-01-01T23:59:59.000Z

75

Calcine Waste Storage at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect (OSTI)

A potential option in the program for long-term management of high-level wastes at the Idaho Nuclear Technology and Engineering Center (INTEC), at the Idaho National Engineering and Environmental Laboratory, calls for retrieving calcine waste and converting it to a more stable and less dispersible form. An inventory of calcine produced during the period December 1963 to May 1999 has been prepared based on calciner run, solids storage facilities operating, and miscellaneous operational information, which gives the range of chemical compositions of calcine waste stored at INTEC. Information researched includes calciner startup data, waste solution analyses and volumes calcined, calciner operating schedules, solids storage bin capacities, calcine storage bin distributor systems, and solids storage bin design and temperature monitoring records. Unique information on calcine solids storage facilities design of potential interest to remote retrieval operators is given.

M. D. Staiger

1999-06-01T23:59:59.000Z

76

Supplemental design requirements document, Multifunction Waste Tank Facility, Project W-236A. Revision 1  

SciTech Connect (OSTI)

The Multi-Function Waste Tank Facility (MWTF) consists of four, nominal 1 million gallon, underground double-shell tanks, located in the 200-East area, and two tanks of the same capacity in the 200-West area. MWTF will provide environmentally safe storage capacity for wastes generated during remediation/retrieval activities of existing waste storage tanks. This document delineates in detail the information to be used for effective implementation of the Functional Design Criteria requirements.

Groth, B.D.

1995-01-11T23:59:59.000Z

77

Certification Plan, low-level waste Hazardous Waste Handling Facility  

SciTech Connect (OSTI)

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.

Albert, R.

1992-06-30T23:59:59.000Z

78

Transfer Lines to Connect Liquid Waste Facilities and Salt Waste...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

far will integrate SWPF with current liquid waste facilities, such as the DWPF and the tanks farms." EM is pleased with the spirit of integration. "A key objective for us over the...

79

Consolidated Storage Facilities: Camel's Nose or Shared Burden? - 13112  

SciTech Connect (OSTI)

The Blue Ribbon Commission (BRC) made a strong argument why the reformulated nuclear waste program should make prompt efforts to develop one or more consolidated storage facilities (CSFs), and recommended the amendment of NWPA Section 145(b) 2 (linking 'monitored retrievable storage' to repository development) as an essential means to that end. However, other than recommending that the siting of CSFs should be 'consent-based' and that spent nuclear fuel (SNF) at stranded sites should be first-in-line for removal, the Commission made few recommendations regarding how CSF development should proceed. Working with three other key Senators, Jeff Bingaman attempted in the 112. Congress to craft legislation (S. 3469) to put the BRC recommendations into legislative language. The key reason why the Nuclear Waste Administration Act of 2012 did not proceed was the inability of the four senators to agree on whether and how to amend NWPA Section 145(b). A brief review of efforts to site consolidated storage since the Nuclear Waste Policy Amendments Act of 1987 suggests a strong and consistent motivation to shift the burden to someone (anyone) else. This paper argues that modification of NWPA Section 145(b) should be accompanied by guidelines for regional development and operation of CSFs. After review of the BRC recommendations regarding CSFs, and the 'camel's nose' prospects if implementation is not accompanied by further guidelines, the paper outlines a proposal for implementation of CSFs on a regional basis, including priorities for removal from reactor sites and subsequently from CSFs to repositories. Rather than allowing repository siting to be prejudiced by the location of a single remote CSF, the regional approach limits transport for off-site acceptance and storage, increases the efficiency of removal operations, provides a useful basis for compensation to states and communities that accept CSFs, and gives states with shared circumstances a shared stake in storage and disposal in an integrated national program. (authors)

Williams, James M. [Western Interstate Energy Board, 1600 Broadway, Suite 1700, Denver CO 80202 (United States)] [Western Interstate Energy Board, 1600 Broadway, Suite 1700, Denver CO 80202 (United States)

2013-07-01T23:59:59.000Z

80

Design requirements document for project W-465, immobilized low activity waste interim storage  

SciTech Connect (OSTI)

The scope of this design requirements document is to identify the functions and associated requirements that must be performed to accept, transport, handle, and store immobilized low-activity waste produced by the privatized Tank Waste Remediation System treatment contractors. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized low-activity waste interim storage facility project and provides traceability from the program level requirements to the project design activity.

Burbank, D.A.

1997-01-27T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Hanford facility dangerous waste permit application, general information portion  

SciTech Connect (OSTI)

The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the U.S. Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needed by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in this report).

Hays, C.B.

1998-05-19T23:59:59.000Z

82

Characterization of 618-11 solid waste burial ground, disposed waste, and description of the waste generating facilities  

SciTech Connect (OSTI)

The 618-11 (Wye or 318-11) burial ground received transuranic (TRTJ) and mixed fission solid waste from March 9, 1962, through October 2, 1962. It was then closed for 11 months so additional burial facilities could be added. The burial ground was reopened on September 16, 1963, and continued operating until it was closed permanently on December 31, 1967. The burial ground received wastes from all of the 300 Area radioactive material handling facilities. The purpose of this document is to characterize the 618-11 solid waste burial ground by describing the site, burial practices, the disposed wastes, and the waste generating facilities. This document provides information showing that kilogram quantities of plutonium were disposed to the drum storage units and caissons, making them transuranic (TRU). Also, kilogram quantities of plutonium and other TRU wastes were disposed to the three trenches, which were previously thought to contain non-TRU wastes. The site burial facilities (trenches, caissons, and drum storage units) should be classified as TRU and the site plutonium inventory maintained at five kilograms. Other fissile wastes were also disposed to the site. Additionally, thousands of curies of mixed fission products were also disposed to the trenches, caissons, and drum storage units. Most of the fission products have decayed over several half-lives, and are at more tolerable levels. Of greater concern, because of their release potential, are TRU radionuclides, Pu-238, Pu-240, and Np-237. TRU radionuclides also included slightly enriched 0.95 and 1.25% U-231 from N-Reactor fuel, which add to the fissile content. The 618-11 burial ground is located approximately 100 meters due west of Washington Nuclear Plant No. 2. The burial ground consists of three trenches, approximately 900 feet long, 25 feet deep, and 50 feet wide, running east-west. The trenches constitute 75% of the site area. There are 50 drum storage units (five 55-gallon steel drums welded together) buried in three rows in the northeast comer. In addition, five eight-foot diameter caissons are located at the west end of the center row of the drum storage units. Initially, wastes disposed to the caissons and drum storage units were from the 325 and 327 building hot cells. Later, a small amount of remote-handled (RH) waste from the 309 building Plutonium Recycle Test Reactor (PRTR) cells, and the newly built 324 building hot cells, was disposed at the site.

Hladek, K.L.

1997-10-07T23:59:59.000Z

83

2401-W Waste storage building closure plan  

SciTech Connect (OSTI)

This plan describes the performance standards met and closure activities conducted to achieve clean closure of the 2401-W Waste Storage Building (2401-W) (Figure I). In August 1998, after the last waste container was removed from 2401-W, the U.S. Department of Energy, Richland Operations Office (DOE-RL) notified Washington State Department of Ecology (Ecology) in writing that the 2401-W would no longer receive waste and would be closed as a Resource Conservation and Recovery Act (RCRA) of 1976 treatment, storage, and/or disposal (TSD) unit (98-EAP-475). Pursuant to this notification, closure activities were conducted, as described in this plan, in accordance with Washington Administrative Code (WAC) 173-303-610 and completed on February 9, 1999. Ecology witnessed the closure activities. Consistent with clean closure, no postclosure activities will be necessary. Because 2401-W is a portion of the Central Waste Complex (CWC), these closure activities become the basis for removing this building from the CWC TSD unit boundary. The 2401-W is a pre-engineered steel building with a sealed concrete floor and a 15.2-centimeter concrete curb around the perimeter of the floor. This building operated from April 1988 until August 1998 storing non-liquid containerized mixed waste. All waste storage occurred indoors. No potential existed for 2401-W operations to have impacted soil. A review of operating records and interviews with cognizant operations personnel indicated that no waste spills occurred in this building (Appendix A). After all waste containers were removed, a radiation survey of the 2401-W floor for radiological release of the building was performed December 17, 1998, which identified no radiological contamination (Appendix B).

LUKE, S.M.

1999-07-15T23:59:59.000Z

84

RCRA Permit for a Hazardous Waste Management Facility, Permit Number NEV HW0101, Annual Summary/Waste Minimization Report  

SciTech Connect (OSTI)

This report summarizes the EPA identification number of each generator from which the Permittee received a waste stream, a description and quantity of each waste stream in tons and cubic feet received at the facility, the method of treatment, storage, and/or disposal for each waste stream, a description of the waste minimization efforts undertaken, a description of the changes in volume and toxicity of waste actually received, any unusual occurrences, and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101.

Arnold, Patrick [NSTec] [NSTec

2014-02-14T23:59:59.000Z

85

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

SciTech Connect (OSTI)

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

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

2003-02-26T23:59:59.000Z

86

Quality Services: Solid Wastes, Part 360: Solid Waste Management Facilities (New York)  

Broader source: Energy.gov [DOE]

These regulations apply to all solid wastes with the exception of hazardous or radioactive waste. Proposed solid waste processing facilities are required to obtain permits prior to construction,...

87

Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria  

SciTech Connect (OSTI)

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

W. Mahlon Heileson

2006-10-01T23:59:59.000Z

88

Hanford Facility dangerous waste permit application, general information. Revision 1  

SciTech Connect (OSTI)

The current Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (this document, number DOE/RL-91-28) and a treatment, storage, and/or disposal Unit-Specific Portion, which includes documentation for individual TSD units (e.g., document numbers DOE/RL-89-03 and DOE/RL-90-01). Both portions consist of a Part A division and a Part B division. The Part B division consists of 15 chapters that address the content of the Part B checklists prepared by the Washington State Department of Ecology (Ecology 1987) and the US Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information requirements mandated by the Hazardous and Solid Waste Amendments of 1984 and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology checklist section numbers, in brackets, follow the chapter headings and subheadings. Documentation contained in the General Information Portion (i.e., this document, number DOE/RL-91-28) is broader in nature and applies to all treatment, storage, and/or disposal units for which final status is sought. Because of its broad nature, the Part A division of the General Information Portion references the Hanford Facility Dangerous Waste Part A Permit Application (document number DOE/RL-88-21), a compilation of all Part A documentation for the Hanford Facility.

Not Available

1993-05-01T23:59:59.000Z

89

Los Alamos Transuranic Waste Size Reduction Facility  

SciTech Connect (OSTI)

The Los Alamos Transuranic (TRU) Waste Size Reduction Facility (SRF) is a production oriented prototype. The facility is operated to remotely cut and repackage TRU contaminated metallic wastes (e.g., glove boxes, ducting and pipes) for eventual disposal at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The resulting flat sections are packaged into a tested Department of Transportation Type 7A metal container. To date, the facility has successfully processed stainless steel glove boxes (with and without lead shielding construction) and retention tanks. We have found that used glove boxes generate more cutting fumes than do unused glove boxes or metal plates - possibly due to deeply embedded chemical residues from years of service. Water used as a secondary fluid with the plasma arc cutting system significantly reduces visible fume generation during the cutting of used glove boxes and lead-lined glove boxes. 2 figs., 1 tab.

Harper, J.; Warren, J.

1987-06-01T23:59:59.000Z

90

Hanford facility dangerous waste permit application, general information portion  

SciTech Connect (OSTI)

The `Hanford Facility Dangerous Waste Permit Application` is considered to be a single application organized into a General Information Portion (this document, DOE/RL-91-28) and a Unit- Specific Portion. The scope of the General Information Portion includes information that could be used to discuss operating units, units undergoing closure, or units being dispositioned through other options. Documentation included in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units. A checklist indicating where information is contained in the General Information Portion, in relation to the Washington State Department of Ecology guidance documentation, is located in the Contents Section. The intent of the General Information Portion is: (1) to provide an overview of the Hanford Facility; and (2) to assist in streamlining efforts associated with treatment, storage, and/or disposal unit-specific Part B permit application, preclosure work plan, closure work plan, closure plan, closure/postclosure plan, or postclosure permit application documentation development, and the `Hanford Facility Resource Conservation and Recovery Act Permit` modification process. Revision 2 of the General Information Portion of the `Hanford Facility Dangerous Waste Permit Application` contains information current as of May 1, 1996. This document is a complete submittal and supersedes Revision 1.

Price, S.M., Westinghouse Hanford

1996-07-29T23:59:59.000Z

91

Waste Examination Assay Facility operations: TRU waste certification  

SciTech Connect (OSTI)

The ORNL Waste Examination Assay Facility (WEAF) was established to nondestructively assay (NDA) transuranic (TRU) waste generated at Oak Ridge National Laboratory (ORNL). The present facility charter encompasses the NDA and nondestructive examination (NDE) of both TRU and low-level wastes (LLW). Presently, equipment includes a Neutron Assay System (NAS), a Segmented Gamma Scanner (SGS), a drum-sized Real-Time Radiography (RTR) system, and a Neutron Slab Detector (NSD). The first three instruments are computer interfaced. Approximately 2300 TRU waste drums have been assayed with the NAS and the SGS. Another 3000 TRU and LLW drums have been examined with the RTR unit. Computer data bases have been developed to collate the large amount of data generated during the assays and examinations. 6 refs., 1 tab.

Schultz, F.J.; Caylor, B.A.; Coffey, D.E.; Phoenix, L.B.

1987-01-01T23:59:59.000Z

92

Solid low level waste forms and extended storage  

SciTech Connect (OSTI)

This paper presents regulatory, technical, and economic aspects of selecting solid waste forms for the extended on-site storage of power plant low level wastes (LLW) in the United States. The author explains current uncertainties and disposal site shortages, defines power plant waste types, addresses regulatory requirements for disposal, discusses basic waste form storage considerations, outlines possible strategies for the management of individual waste types, and offers methodological steps for selecting a waste form for extended storage. Broader issues closely associated with waste form selection are also presented.

Kohout, R. [R. Kohout & Associates, Ltd., Toronto, Ontario (Canada)

1995-11-01T23:59:59.000Z

93

SLUDGE TREATMENT PROJECT PHASE 1 SLUDGE STORAGE OPTIONS ASSESSMENT OF T PLANT VERSUS ALTERNATE STORAGE FACILITY  

SciTech Connect (OSTI)

The CH2M HILL Plateau Remediation Company (CHPRC) has recommended to the U.S. Department of Energy (DOE) a two phase approach for removal and storage (Phase 1) and treatment and packaging for offsite shipment (Phase 2) of the sludge currently stored within the 105-K West Basin. This two phased strategy enables early removal of sludge from the 105-K West Basin by 2015, allowing remediation of historical unplanned releases of waste and closure of the 100-K Area. In Phase 1, the sludge currently stored in the Engineered Containers and Settler Tanks within the 105-K West Basin will be transferred into sludge transport and storage containers (STSCs). The STSCs will be transported to an interim storage facility. In Phase 2, sludge will be processed (treated) to meet shipping and disposal requirements and the sludge will be packaged for final disposal at a geologic repository. The purpose of this study is to evaluate two alternatives for interim Phase 1 storage of K Basin sludge. The cost, schedule, and risks for sludge storage at a newly-constructed Alternate Storage Facility (ASF) are compared to those at T Plant, which has been used previously for sludge storage. Based on the results of the assessment, T Plant is recommended for Phase 1 interim storage of sludge. Key elements that support this recommendation are the following: (1) T Plant has a proven process for storing sludge; (2) T Plant storage can be implemented at a lower incremental cost than the ASF; and (3) T Plant storage has a more favorable schedule profile, which provides more float, than the ASF. Underpinning the recommendation of T Plant for sludge storage is the assumption that T Plant has a durable, extended mission independent of the K Basin sludge interim storage mission. If this assumption cannot be validated and the operating costs of T Plant are borne by the Sludge Treatment Project, the conclusions and recommendations of this study would change. The following decision-making strategy, which is dependent on the confidence that DOE has in the long term mission for T Plant, is proposed: (1) If the confidence level in a durable, extended T Plant mission independent of sludge storage is high, then the Sludge Treatment Project (STP) would continue to implement the path forward previously described in the Alternatives Report (HNF-39744). Risks to the sludge project can be minimized through the establishment of an Interface Control Document (ICD) defining agreed upon responsibilities for both the STP and T Plant Operations regarding the transfer and storage of sludge and ensuring that the T Plant upgrade and operational schedule is well integrated with the sludge storage activities. (2) If the confidence level in a durable, extended T Plant mission independent of sludge storage is uncertain, then the ASF conceptual design should be pursued on a parallel path with preparation of T Plant for sludge storage until those uncertainties are resolved. (3) Finally, if the confidence level in a durable, extended T Plant mission independent of sludge storage is low, then the ASF design should be selected to provide independence from the T Plant mission risk.

RUTHERFORD WW; GEUTHER WJ; STRANKMAN MR; CONRAD EA; RHOADARMER DD; BLACK DM; POTTMEYER JA

2009-04-29T23:59:59.000Z

94

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  

SciTech Connect (OSTI)

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.

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

1996-12-01T23:59:59.000Z

95

Hanford facility dangerous waste permit application  

SciTech Connect (OSTI)

This document, Set 2, the Hanford Facility Dangerous Waste Part B Permit Application, consists of 15 chapters that address the content of the Part B checklists prepared by the Washington State Department of Ecology (Ecology 1987) and the US Environmental Protection Agency (40 CFR 270), with additional information requirements mandated by the Hazardous and Solid Waste Amendments of 1984 and revisions of WAC 173-303. For ease of reference, the Washington State Department of Ecology checklist section numbers, in brackets, follow the chapter headings and subheadings. This permit application contains umbrella- type'' documentation with overall application to the Hanford Facility. This documentation is broad in nature and applies to all TSD units that have final status under the Hanford Facility Permit.

none,

1991-09-18T23:59:59.000Z

96

3718-F Alkali Metal Treatment and Storage Facility Closure Plan. Revision 1  

SciTech Connect (OSTI)

The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, as well as for activities associated with nuclear energy development. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. The 3718-F Alkali Metal Treatment and Storage Facility (3718-F Facility), located in the 300 Area, was used to store and treat alkali metal wastes. Therefore, it is subject to the regulatory requirements for the storage and treatment of dangerous wastes. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610 (Ecology 1989) and 40 CFR 270.1. Closure also will satisfy the thermal treatment facility closure requirements of 40 CFR 265.381. This closure plan presents a description of the 3718-F Facility, the history of wastes managed, and the approach that will be followed to close the facility. Only hazardous constituents derived from 3718-F Facility operations will be addressed.

none,

1992-11-01T23:59:59.000Z

97

Radioactive waste shipments to Hanford Retrievable Storage from the General Electric Vallecitos Nuclear Center, Pleasanton, California  

SciTech Connect (OSTI)

During the next two decades the transuranic (TRU) wastes now stored in the burial trenches and storage facilities at the Hanford Site are to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant near Carlsbad, New Mexico for final disposal. Approximately 3.8% of the TRU waste to be retrieved for shipment to WIPP was generated at the General Electric (GE) Vallecitos Nuclear Center (VNC) in Pleasanton, California and shipped to the Hanford Site for storage. The purpose of this report is to characterize these radioactive solid wastes using process knowledge, existing records, and oral history interviews. The waste was generated almost exclusively from the activities, of the Plutonium Fuels Development Laboratory and the Plutonium Analytical Laboratory. Section 2.0 provides further details of the VNC physical plant, facility operations, facility history, and current status. The solid radioactive wastes were associated with two US Atomic Energy Commission/US Department of Energy reactor programs -- the Fast Ceramic Reactor (FCR) program, and the Fast Flux Test Reactor (FFTR) program. These programs involved the fabrication and testing of fuel assemblies that utilized plutonium in an oxide form. The types and estimated quantities of waste resulting from these programs are discussed in detail in Section 3.0. A detailed discussion of the packaging and handling procedures used for the VNC radioactive wastes shipped to the Hanford Site is provided in Section 4.0. Section 5.0 provides an in-depth look at this waste including the following: weight and volume of the waste, container types and numbers, physical description of the waste, radiological components, hazardous constituents, and current storage/disposal locations.

Vejvoda, E.J.; Pottmeyer, J.A.; DeLorenzo, D.S.; Weyns-Rollosson, M.I. [Los Alamos Technical Associates, Inc., NM (United States); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (United States)

1993-10-01T23:59:59.000Z

98

EIS-0212: Safe Interim Storage of Hanford Tank Wastes, Hanford Site, Richland, WA  

Broader source: Energy.gov [DOE]

This environmental impact statement asseses Department of Energy and Washington State Department of Ecology maintanence of safe storage of high-level radioactive wastes currently stored in the older single-shell tanks, the Watchlist Tank 101-SY, and future waste volumes associated with tank farm and other Hanford facility operations, including a need to provide a modern safe, reliable, and regulatory-compliant replacement cross-site transfer capability. The purpose of this action is to prevent uncontrolled releases to the environment by maintaining safe storage of high-level tank wastes.

99

Waste minimization at a plutonium processing facility  

SciTech Connect (OSTI)

As part of Los Alamos National Laboratory`s (LANL) mission to reduce the nuclear danger throughout the world, the plutonium processing facility at LANL maintains expertise and skills in nuclear weapons technologies as well as leadership in all peaceful applications of plutonium technologies, including fuel fabrication for terrestrial and space reactors and heat sources and thermoelectric generators for space missions. Another near-term challenge resulted from two safety assessments performed by the Defense Nuclear Facilities Safety Board and the U.S. Department of Energy during the past two years. These assessments have necessitated the processing and stabilization of plutonium contained in tons of residues so that they can be stored safely for an indefinite period. This report describes waste streams and approaches to waste reduction of plutonium management.

Pillay, K.K.S. [Los Alamos National Laboratory, NM (United States)

1995-12-31T23:59:59.000Z

100

Mixed Waste Management Facility Groundwater Monitoring Report  

SciTech Connect (OSTI)

During fourth quarter 1997, eleven constituents exceeded final Primary Drinking Water Standards (PDWS) in groundwater samples from downgradient monitoring wells at the Mixed Waste Management Facility. No constituents exceeded final PDWS in samples from upgradient monitoring wells. As in previous quarters, tritium and trichloroethylene were the most widespread elevated constituents. The groundwater flow directions and rates in the three hydrostratigraphic units were similar to those of previous quarters.

Chase, J.

1998-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Standard Guide for Preparing Waste Management Plans for Decommissioning Nuclear Facilities  

E-Print Network [OSTI]

1.1 This guide addresses the development of waste management plans for potential waste streams resulting from decommissioning activities at nuclear facilities, including identifying, categorizing, and handling the waste from generation to final disposal. 1.2 This guide is applicable to potential waste streams anticipated from decommissioning activities of nuclear facilities whose operations were governed by the Nuclear Regulatory Commission (NRC) or Agreement State license, under Department of Energy (DOE) Orders, or Department of Defense (DoD) regulations. 1.3 This guide provides a description of the key elements of waste management plans that if followed will successfully allow for the characterization, packaging, transportation, and off-site treatment or disposal, or both, of conventional, hazardous, and radioactive waste streams. 1.4 This guide does not address the on-site treatment, long term storage, or on-site disposal of these potential waste streams. 1.5 This standard does not purport to address ...

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

102

Solid Waste Regulation No. 8- Solid Waste Composting Facilities (Rhode Island)  

Broader source: Energy.gov [DOE]

Facilities which compost putrescible waste and/or leaf and yard waste are subject to these regulations. The regulations establish permitting, registration, and operational requirements for...

103

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

SciTech Connect (OSTI)

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

DEFFENBAUGH, M.L.

2000-08-01T23:59:59.000Z

104

COMPLETION OF THE FIRST INTEGRATED SPENT NUCLEAR FUEL TRANSSHIPMENT/INTERIM STORAGE FACILITY IN NW RUSSIA  

SciTech Connect (OSTI)

Northwest and Far East Russia contain large quantities of unsecured spent nuclear fuel (SNF) from decommissioned submarines that potentially threaten the fragile environments of the surrounding Arctic and North Pacific regions. The majority of the SNF from the Russian Navy, including that from decommissioned nuclear submarines, is currently stored in on-shore and floating storage facilities. Some of the SNF is damaged and stored in an unstable condition. Existing Russian transport infrastructure and reprocessing facilities cannot meet the requirements for moving and reprocessing this amount of fuel. Additional interim storage capacity is required. Most of the existing storage facilities being used in Northwest Russia do not meet health and safety, and physical security requirements. The United States and Norway are currently providing assistance to the Russian Federation (RF) in developing systems for managing these wastes. If these wastes are not properly managed, they could release significant concentrations of radioactivity to these sensitive environments and could become serious global environmental and physical security issues. There are currently three closely-linked trilateral cooperative projects: development of a prototype dual-purpose transport and storage cask for SNF, a cask transshipment interim storage facility, and a fuel drying and cask de-watering system. The prototype cask has been fabricated, successfully tested, and certified. Serial production is now underway in Russia. In addition, the U.S. and Russia are working together to improve the management strategy for nuclear submarine reactor compartments after SNF removal.

Dyer, R.S.; Barnes, E.; Snipes, R.L.; Hoeibraaten, S.; Gran, H.C.; Foshaug, E.; Godunov, V.

2003-02-27T23:59:59.000Z

105

Fire protection guide for solid waste metal drum storage  

SciTech Connect (OSTI)

This guide provides a method to assess potential fire development in drum storage facilities. The mechanism of fire propagation/spread through stored drum arrays is a complex process. It involves flame heat transfer, transient conduction,convection, and radiation between drums (stored in an array configuration). There are several phenomena which may occur when drums are exposed to fire. The most dramatic is violent lid failure which results in total lid removal. When a drum loses its lid due to fire exposure, some or all of the contents may be ejected from the drum, and both the ejected combustible material and the combustible contents remaining within the container will burn. The scope of this guide is limited to storage arrays of steel drums containing combustible (primarily Class A) and noncombustible contents. Class B combustibles may be included in small amounts as free liquid within the solid waste contents.Storage arrays, which are anticipated in this guide, include single or multi-tier palletized (steel or wood pallets) drums,high rack storage of drums, and stacked arrays of drums where plywood sheets are used between tiers. The purpose of this guide is to describe a simple methodology that estimates the consequences of a fire in drum storage arrays. The extent of fire development and the resulting heat release rates can be estimated. Release fractions applicable to this type of storage are not addressed, and the transport of contaminants away from the source is not addressed. However, such assessments require the amount of combustible material consumed and the surface area of this burning material. The methods included in this guide do provide this information.

Bucci, H.M.

1996-09-16T23:59:59.000Z

106

Supplemental design requirements document enhanced radioactive and mixed waste storage Phase V Project W-112  

SciTech Connect (OSTI)

This document provides additional and supplemental information to WHC-SD-W112-FDC-001, Project W-112 for radioactive and mixed waste storage. It provides additional requirements for the design and summarizes Westinghouse Hanford Company key design guidance and establishes the technical baseline agreements to be used for definitive design of the Project W-112 facilities.

Ocampo, V.P.; Boothe, G.F.; Greager, T.M.; Johnson, K.D.; Kooiker, S.L.; Martin, J.D.

1994-11-01T23:59:59.000Z

107

Waste Receiving and Processing Facility Module 2A: Advanced Conceptual Design Report. Volume 2  

SciTech Connect (OSTI)

This volume presents the Total Estimated Cost (TEC) for the WRAP (Waste Receiving and Processing) 2A facility. The TEC is $81.9 million, including an overall project contingency of 25% and escalation of 13%, based on a 1997 construction midpoint. (The mission of WRAP 2A is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities the Category 1 and 3 contact handled low-level radioactive mixed wastes that are currently in retrievable storage, and are forecast to be generated over the next 30 years by Hanford, and waste to be shipped to Hanford site from about 20 DOE sites.)

Not Available

1994-03-01T23:59:59.000Z

108

Performance assessment for continuing and future operations at solid waste storage area 6  

SciTech Connect (OSTI)

This revised performance assessment (PA) for the continued disposal operations at Solid Waste Storage Area (SWSA) 6 on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the performance objectives for low-level radioactive waste (LLW) disposal contained in the US Department of Energy (DOE) Order 5820.2A. This revised PA considers disposal operations conducted from September 26, 1988, through the projects lifetime of the disposal facility.

NONE

1997-09-01T23:59:59.000Z

109

WIPP Hazardous Waste Facility Permit Update  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit (HWFP) was issued on October 27, 1999 [1]. Since that time, the WIPP has sought modifications to clarify the permit language, provide alternative methods for meeting permit requirements and to update permit conditions. Significant advancements have been made in transuranic (TRU) waste management as the result of modifications to the HWFP. Among these advancements is a modification to obtain a drum age criteria (DAC) value to perform headspace gas sampling on drums to be super-compacted and placed in a 100-gallon overpack drum. In addition, the Section 311 permit modification request that would allow for more efficient waste characterization, and the modification to authorize the shipment and disposal of Remote-Handled (RH) TRU waste were merged together and submitted to the regulator as the Consolidated Permit Modification Request (PMR). The submittal of the Consolidated PMR came at the request of the regulator as part of responses to Notices of Deficiency (NODs) for the separate PMRs which had been submitted in previous years. Section 311 of the fiscal year 2004 Energy and Water Developments Appropriations Act (Public Law 108-137) [2] directs the Department of Energy to submit a permit modification that limits waste confirmation to radiography or visual examination of a statistical subpopulation of containers. Section 311 also specifically directs that disposal room performance standards be to be met by monitoring for volatile organic compounds in the underground disposal rooms. This statute translates into the elimination of other waste confirmation methods such as headspace gas sampling and analysis and solids sampling and analysis. These methods, as appropriate, will continue to be used by the generator sites during hazardous waste determinations or characterization activities. This modification is expected to reduce the overall cost of waste analysis by hundreds of millions of dollars [3]. Combining both the chap. 311 and RH TRU waste permit modification requests allows for both the regulator and DOE to expedite action on the modification requests. The Combined PMR reduces costs by having only one administrative process for both modification requests. (authors)

Kehrman, B.; Most, W. [Washington Regulatory and Environmental Services, 4021 National Parks Highway, Carlsbad, NM 88220 (United States)

2006-07-01T23:59:59.000Z

110

Advanced conceptual design report solid waste retrieval facility, phase I, project W-113  

SciTech Connect (OSTI)

Project W-113 will provide the equipment and facilities necessary to retrieve suspect transuranic (TRU) waste from Trench 04 of the 218W-4C burial ground. As part of the retrieval process, waste drums will be assayed, overpacked, vented, head-gas sampled, and x-rayed prior to shipment to the Phase V storage facility in preparation for receipt at the Waste Receiving and Processing Facility (WRAP). Advanced Conceptual Design (ACD) studies focused on project items warranting further definition prior to Title I design and areas where the potential for cost savings existed. This ACD Report documents the studies performed during FY93 to optimize the equipment and facilities provided in relation to other SWOC facilities and to provide additional design information for Definitive Design.

Smith, K.E.

1994-03-21T23:59:59.000Z

111

Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216  

SciTech Connect (OSTI)

Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the Iraqi Decommissioning Directorate (IDD) is responsible for decommissioning activities. The IDD and the RWTMD work together on decommissioning projects. The IDD has developed plans and has completed decommissioning of the GeoPilot Facility in Baghdad and the Active Metallurgical Testing Laboratory (LAMA) in Al-Tuwaitha. Given this experience, the IDD has initiated work on more dangerous facilities. Plans are being developed to characterize, decontaminate and decommission the Tamuz II Research Reactor. The Tammuz Reactor was destroyed by an Israeli air-strike in 1981 and the Tammuz II Reactor was destroyed during the First Gulf War in 1991. In addition to being responsible for managing the decommissioning wastes, the RWTMD is responsible for more than 950 disused sealed radioactive sources, contaminated debris from the first Gulf War and (approximately 900 tons) of naturally-occurring radioactive materials wastes from oil production in Iraq. The RWTMD has trained staff, rehabilitated the Building 39 Radioactive Waste Storage building, rehabilitated portions of the French-built Radioactive Waste Treatment Station, organized and secured thousands of drums of radioactive waste organized and secured the stores of disused sealed radioactive sources. Currently, the IDD and the RWTMD are finalizing plans for the decommissioning of the Tammuz II Research Reactor. (authors)

Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi [Ministry of Science and Technology (MoST), Al-Jadraya, P.O. Box 0765, Baghdad (Iraq)] [Ministry of Science and Technology (MoST), Al-Jadraya, P.O. Box 0765, Baghdad (Iraq); Cochran, John R. [Sandia National Laboratories1, New Mexico, Albuquerque New Mexico 87185 (United States)] [Sandia National Laboratories1, New Mexico, Albuquerque New Mexico 87185 (United States)

2013-07-01T23:59:59.000Z

112

Staging and storage facility feasibility study. Final report  

SciTech Connect (OSTI)

This study was performed to investigate the feasibility of adapting the design of the HWVP Canister Storage Building (CSB) to meet the needs of the WHC Spent Nuclear Fuel Project for Staging and Storage Facility (SSF), and to develop Rough Order of Magnitude (ROM) cost and schedule estimates.

Swenson, C.E. [Westinghouse Hanford Co., Richland, WA (United States)

1995-02-01T23:59:59.000Z

113

International low level waste disposal practices and facilities  

SciTech Connect (OSTI)

The safe management of nuclear waste arising from nuclear activities is an issue of great importance for the protection of human health and the environment now and in the future. The primary goal of this report is to identify the current situation and practices being utilized across the globe to manage and store low and intermediate level radioactive waste. The countries included in this report were selected based on their nuclear power capabilities and involvement in the nuclear fuel cycle. This report highlights the nuclear waste management laws and regulations, current disposal practices, and future plans for facilities of the selected international nuclear countries. For each country presented, background information and the history of nuclear facilities are also summarized to frame the country's nuclear activities and set stage for the management practices employed. The production of nuclear energy, including all the steps in the nuclear fuel cycle, results in the generation of radioactive waste. However, radioactive waste may also be generated by other activities such as medical, laboratory, research institution, or industrial use of radioisotopes and sealed radiation sources, defense and weapons programs, and processing (mostly large scale) of mineral ores or other materials containing naturally occurring radionuclides. Radioactive waste also arises from intervention activities, which are necessary after accidents or to remediate areas affected by past practices. The radioactive waste generated arises in a wide range of physical, chemical, and radiological forms. It may be solid, liquid, or gaseous. Levels of activity concentration can vary from extremely high, such as levels associated with spent fuel and residues from fuel reprocessing, to very low, for instance those associated with radioisotope applications. Equally broad is the spectrum of half-lives of the radionuclides contained in the waste. These differences result in an equally wide variety of options for the management of radioactive waste. There is a variety of alternatives for processing waste and for short term or long term storage prior to disposal. Likewise, there are various alternatives currently in use across the globe for the safe disposal of waste, ranging from near surface to geological disposal, depending on the specific classification of the waste. At present, there appears to be a clear and unequivocal understanding that each country is ethically and legally responsible for its own wastes, in accordance with the provisions of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. Therefore the default position is that all nuclear wastes will be disposed of in each of the 40 or so countries concerned with nuclear power generation or part of the fuel cycle. To illustrate the global distribution of radioactive waste now and in the near future, Table 1 provides the regional breakdown, based on the UN classification of the world in regions illustrated in Figure 1, of nuclear power reactors in operation and under construction worldwide. In summary, 31 countries operate 433 plants, with a total capacity of more than 365 gigawatts of electrical energy (GW[e]). A further 65 units, totaling nearly 63 GW(e), are under construction across 15 of these nations. In addition, 65 countries are expressing new interest in, considering, or actively planning for nuclear power to help address growing energy demands to fuel economic growth and development, climate change concerns, and volatile fossil fuel prices. Of these 65 new countries, 21 are in Asia and the Pacific region, 21 are from the Africa region, 12 are in Europe (mostly Eastern Europe), and 11 in Central and South America. However, 31 of these 65 are not currently planning to build reactors, and 17 of those 31 have grids of less than 5 GW, which is said to be too small to accommodate most of the reactor designs available. For the remaining 34 countries actively planning reactors, as of September 2010: 14 indicate a strong intention to precede w

Nutt, W.M. (Nuclear Engineering Division)

2011-12-19T23:59:59.000Z

114

Waste Encapsulation and Storage Facility - Hanford Site  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption byAbout Printable Version BookmarkHanfordProjects &

115

Thermal Storage Applications for Commercial/Industrial Facilities  

E-Print Network [OSTI]

THERMAL STORAGE APPLICATIONS FOR COMMERCIAL/INDUSTRIAL FACILITIES Roger 1. Knipp, PE. Dallas Power & Light Company Dallas, Texas ABSTRACT Texas Utilities Electric Company has been actively encouraging installations of thermal storage... since 1981. Financial incentives and advantageous rates can make thermal storage an attractive cooling concept in Texas Utilities Electric Company service area. Currently, 14 million square feet of commercial building space in Dallas is either...

Knipp, R. L.

116

Simple Waste Solutions for Complex Facilities - 12433  

SciTech Connect (OSTI)

The buildings in the 300 Area, including several Category 3 nuclear facilities are undergoing deactivation, decommissioning, decontamination and demolition (D4) by Washington Closure Hanford (WCH) as part of the River Corridor Closure Contract (RCCC). The D4 process has generated a wide variety of low-level radioactive and low-level radioactive mixed waste as well as TRU. The Hanford Site-wide Transportation Safety Document (TSD) has been successfully utilized to transport waste streams that otherwise would not be able to be shipped. The TSD accomplished this by establishing a comprehensive set of onsite transportation and packaging performance standards and risk-based standards. The requirements and standards presented are equivalent to DOT and NRC standards (10 CFR 71). (authors)

King, Terry I. [Washington Closure Hanford, Richland, Washington 99352 (United States); Stephan, Clifford J. [Lucas Engineering and Management Services, Richland Washington 99352 (United States)

2012-07-01T23:59:59.000Z

117

RADIOACTIVE WASTE STORAGE IN MINED CAVERNS IN CRYSTALLINE ROCK-RESULTS OF FIELD INVESTIGATIONS AT STRIPA, SWEDEN  

E-Print Network [OSTI]

Waste Storage in Mined Caverns—Program Summary. LawrenceWASTE STORAGE IN MINED CAVERNS IN CRYSTALLINE ROCK- BESULTS

Witherspoon, P.A.

2010-01-01T23:59:59.000Z

118

Cool Storage Economic Feasibility Analysis for a Large Industrial Facility  

E-Print Network [OSTI]

The analysis of economic feasibility for adding a cool storage facility to shift electric demand to off-peak hours for a large industrial facility is presented. DOE-2 is used to generate the necessary cooling load profiles for the analysis...

Fazzolari, R.; Mascorro, J. A.; Ballard, R. H.

1988-01-01T23:59:59.000Z

119

Los Alamos National Laboratory opens new waste repackaging facility  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

to increase its capability to process nuclear waste for permanent disposal. March 7, 2013 A view of the new box line facility where transuranic waste will be repackaged at Los...

120

Waste receiving and processing facility module 1 auditable safetyanalysis  

SciTech Connect (OSTI)

The Waste Receiving and Processing Facility Module 1 Auditable Safety Analysis analyzes postulated accidents and determines controls to prevent the accidents or mitigate the consequences.

Bottenus, R.J.

1997-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Method of preparing nuclear wastes for tansportation and interim storage  

DOE Patents [OSTI]

Nuclear waste is formed into a substantially water-insoluble solid for temporary storage and transportation by mixing the calcined waste with at least 10 weight percent powdered anhydrous sodium silicate to form a mixture and subjecting the mixture to a high humidity environment for a period of time sufficient to form cementitious bonds by chemical reaction. The method is suitable for preparing an interim waste form from dried high level radioactive wastes.

Bandyopadhyay, Gautam (Naperville, IL); Galvin, Thomas M. (Darien, IL)

1984-01-01T23:59:59.000Z

122

IMPACT OF THE SMALL COLUMN ION EXCHANGE PROCESS ON THE DEFENSE WASTE PROCESSING FACILITY - 12112  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is investigating the deployment of a parallel technology to the Salt Waste Processing Facility (SWPF, presently under construction) to accelerate high activity salt waste processing. The proposed technology combines large waste tank strikes of monosodium titanate (MST) to sorb strontium and actinides with two ion exchange columns packed with crystalline silicotitanate (CST) resin to sorb cesium. The new process was designated Small Column Ion Exchange (SCIX), since the ion exchange columns were sized to fit within a waste storage tank riser. Loaded resins are to be combined with high activity sludge waste and fed to the Defense Waste Processing Facility (DWPF) for incorporation into the current glass waste form. Decontaminated salt solution produced by SCIX will be fed to the SRS Saltstone Facility for on-site immobilization as a grout waste form. Determining the potential impact of SCIX resins on DWPF processing was the basis for this study. Accelerated salt waste treatment is projected to produce a significant savings in the overall life cycle cost of waste treatment at SRS.

Koopman, D.; Lambert, D.; Fox, K.; Stone, M.

2011-11-07T23:59:59.000Z

123

RCRA Permit for a Hazardous Waste Management Facility Permit Number NEV HW0101 Annual Summary/Waste Minimization Report Calendar Year 2012, Nevada National Security Site, Nevada  

SciTech Connect (OSTI)

This report summarizes the U.S. Environmental Protection Agency (EPA) identification number of each generator from which the Permittee received a waste stream, a description and quantity of each waste stream in tons and cubic feet received at the facility, the method of treatment, storage, and/or disposal for each waste stream, a description of the waste minimization efforts undertaken, a description of the changes in volume and toxicity of waste actually received, any unusual occurrences, and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101, issued 10/17/10.

,

2013-02-21T23:59:59.000Z

124

RCRA Permit for a Hazardous Waste Management Facility Permit Number NEV HW0101 Annual Summary/Waste Minimization Report Calendar Year 2011  

SciTech Connect (OSTI)

This report summarizes the U.S. Environmental Protection Agency (EPA) identification number of each generator from which the Permittee received a waste stream; a description and quantity of each waste stream in tons and cubic feet received at the facility; the method of treatment, storage, and/or disposal for each waste stream; a description of the waste minimization efforts undertaken; a description of the changes in volume and toxicity of waste actually received; any unusual occurrences; and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101.

NSTec Environmental Restoration

2012-02-16T23:59:59.000Z

125

General Heat Transfer Characterization and Empirical Models of Material Storage Temperatures for the Los Alamos Nuclear Materials Storage Facility  

SciTech Connect (OSTI)

The Los Alamos National Laboratory's Nuclear Materials Storage Facility (NMSF) is being renovated for long-term storage of canisters designed to hold heat-generating nuclear materials. A fully passive cooling scheme, relying on the transfer of heat by conduction, free convection, and radiation has been proposed as a reliable means of maintaining material at acceptable storage temperatures. The storage concept involves placing radioactive materials, with a net heat-generation rate of 10 W to 20 W, inside a set of nested steel canisters. The canisters are, in placed in holding fixtures and positioned vertically within a steel storage pipe. Several hundred drywells are arranged in a linear array within a large bay and dissipate the waste heat to the surrounding air, thus creating a buoyancy driven airflow pattern that draws cool air into the storage facility and exhausts heated air through an outlet stack. In this study, an experimental apparatus was designed to investigate the thermal characteristics of simulated nuclear materials placed inside two nested steel canisters positioned vertically on an aluminum fixture plate and placed inside a section of steel pipe. The heat-generating nuclear materials were simulated with a solid aluminum cylinder containing .an embedded electrical resistance heater. Calibrated type T thermocouples (accurate to ~ O.1 C) were used to monitor temperatures at 20 different locations within the apparatus. The purposes of this study were to observe the heat dissipation characteristics of the proposed `canister/fixture plate storage configuration, to investigate how the storage system responds to changes in various parameters, and to develop and validate empirical correlations to predict material temperatures under various operating conditions

J. D. Bernardin; W. S. Gregory

1998-10-01T23:59:59.000Z

126

Thirty-year solid waste generation forecast for facilities at SRS  

SciTech Connect (OSTI)

The information supplied by this 30-year solid waste forecast has been compiled as a source document to the Waste Management Environmental Impact Statement (WMEIS). The WMEIS will help to select a sitewide strategic approach to managing present and future Savannah River Site (SRS) waste generated from ongoing operations, environmental restoration (ER) activities, transition from nuclear production to other missions, and decontamination and decommissioning (D&D) programs. The EIS will support project-level decisions on the operation of specific treatment, storage, and disposal facilities within the near term (10 years or less). In addition, the EIS will provide a baseline for analysis of future waste management activities and a basis for the evaluation of the specific waste management alternatives. This 30-year solid waste forecast will be used as the initial basis for the EIS decision-making process. The Site generates and manages many types and categories of waste. With a few exceptions, waste types are divided into two broad groups-high-level waste and solid waste. High-level waste consists primarily of liquid radioactive waste, which is addressed in a separate forecast and is not discussed further in this document. The waste types discussed in this solid waste forecast are sanitary waste, hazardous waste, low-level mixed waste, low-level radioactive waste, and transuranic waste. As activities at SRS change from primarily production to primarily decontamination and decommissioning and environmental restoration, the volume of each waste s being managed will change significantly. This report acknowledges the changes in Site Missions when developing the 30-year solid waste forecast.

Not Available

1994-07-01T23:59:59.000Z

127

Monitored retrievable storage submission to Congress: Volume 2, Environmental assessment for a monitored retrievable storage facility. [Contains glossary  

SciTech Connect (OSTI)

This Environmental Assessment (EA) supports the DOE proposal to Congress to construct and operate a facility for monitored retrievable storage (MRS) of spent fuel at a site on the Clinch River in the Roane County portion of Oak Ridge, Tennessee. The first part of this document is an assessment of the value of, need for, and feasibility of an MRS facility as an integral component of the waste management system. The second part is an assessment and comparison of the potential environmental impacts projected for each of six site-design combinations. The MRS facility would be centrally located with respect to existing reactors, and would receive and canister spent fuel in preparation for shipment to and disposal in a geologic repository. 207 refs., 57 figs., 132 tabs.

none,

1986-02-01T23:59:59.000Z

128

Central Facilities Area Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect (OSTI)

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Central Facilities Area facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facilityspecific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-11-01T23:59:59.000Z

129

The WIPP Hazardous Waste Facility Permit Improvements--2007 Update  

SciTech Connect (OSTI)

The most significant changes to the Waste Isolation Pilot Plant Hazardous Waste Facility Permit to date were completed during the past year with the implementation of significant revisions to the Waste Analysis Plan and the authorization to dispose of remote-handled transuranic waste. The modified Permit removes the requirement for reporting headspace gas sampling and analysis results for every container of transuranic mixed waste and provides for the use of radiography and visual examination to confirm a statistically representative subpopulation of the waste stream in each waste shipment as well as other changes that streamline the analytical data management process. Implementation began on November 17, 2006. (authors)

Kehrman, R.; Most, W. [Washington Regulatory and Environmental Services, Carlsbad, NM (United States)

2007-07-01T23:59:59.000Z

130

High Purity Germanium Gamma-PHA Assay of Uranium Storage Pigs for 321-M Facility  

SciTech Connect (OSTI)

The Analytical Development Section of SRTC was requested by the Facilities Disposition Division (FDD) to determine the holdup of enriched uranium in the 321-M facility as part of an overall deactivation project of the facility. The 321-M facility was used to fabricate enriched uranium fuel assemblies, lithium-aluminum target tubes, neptunium assemblies, and miscellaneous components for the production reactors. The facility also includes the 324-M storage building and the passageway connecting it to 321-M. The results of the holdup assays are essential for determining compliance with the Solid Waste's Waste Acceptance Criteria, Material Control and Accountability, and to meet criticality safety controls. This report describes and documents the use of a portable HPGe detector and EG and G Dart system that contains a high voltage power supply, signal processing electronics, a personal computer with Gamma-Vision software, and space to store and manipulate multiple 4096-channel g-ray spectra to assay for 235U content in 268 uranium shipping and storage pigs. This report includes a description of three efficiency calibration configurations and also the results of the assay. A description of the quality control checks is included as well.

Dewberry, R.A.

2001-09-18T23:59:59.000Z

131

SWEDISH-AMERICAN COOPERATIVE PROGRAM ON RADIOACTIVE WASTE STORAGE IN MINED CAVERNS. PROGRAM SUMMARY  

E-Print Network [OSTI]

WASTE STORAGE IN MINED CAVERNS by P. A. Witherspoon LawrenceWASTE STORAGE IN MINED CAVERNS INTRODUCTION Final and safeon the possibility of using mined caverns in salt as waste

Witherspoon, P.A.

2011-01-01T23:59:59.000Z

132

Fuel Storage Facility Final Safety Analysis Report. Revision 1  

SciTech Connect (OSTI)

The Fuel Storage Facility (FSF) is an integral part of the Fast Flux Test Facility. Its purpose is to provide long-term storage (20-year design life) for spent fuel core elements used to provide the fast flux environment in FFTF, and for test fuel pins, components and subassemblies that have been irradiated in the fast flux environment. This Final Safety Analysis Report (FSAR) and its supporting documentation provides a complete description and safety evaluation of the site, the plant design, operations, and potential accidents.

Linderoth, C.E.

1984-03-01T23:59:59.000Z

133

EIS-0082: Defense Waste Processing Facility, Savannah River Plant  

Broader source: Energy.gov [DOE]

The Office of Defense Waste and Byproducts Management developed this EIS to provide environmental input into both the selection of an appropriate strategy for the permanent disposal of the high-level radioactive waste currently stored at the Savannah River Plant (SRP) and the subsequent decision to construct and operate a Defense Waste Processing Facility at the SRP site.

134

An Underwater Robotic Network for Monitoring Nuclear Waste Storage Pools  

E-Print Network [OSTI]

An Underwater Robotic Network for Monitoring Nuclear Waste Storage Pools Sarfraz Nawaz1 , Muzammil Manchester M60 1QD simon.watson@postgrad.manchester.ac.uk peter.n.green@manchester.ac.uk Abstract. Nuclear to build maps of their internal structure which can then be used for waste removal and pool decommissioning

Jeavons, Peter

135

Technological options for management of hazardous wastes from US Department of Energy facilities  

SciTech Connect (OSTI)

This report provides comprehensive information on the technological options for management of hazardous wastes generated at facilities owned or operated by the US Department of Energy (DOE). These facilities annually generate a large quantity of wastes that could be deemed hazardous under the Resource Conservation and Recovery Act (RCRA). Included in these wastes are liquids or solids containing polychlorinated biphenyls, pesticides, heavy metals, waste oils, spent solvents, acids, bases, carcinogens, and numerous other pollutants. Some of these wastes consist of nonnuclear hazardous chemicals; others are mixed wastes containing radioactive materials and hazardous chemicals. Nearly 20 unit processes and disposal methods are presented in this report. They were selected on the basis of their proven utility in waste management and potential applicability at DOE sites. These technological options fall into five categories: physical processes, chemical processes, waste exchange, fixation, and ultimate disposal. The options can be employed for either resource recovery, waste detoxification, volume reduction, or perpetual storage. Detailed descriptions of each technological option are presented, including information on process performance, cost, energy and environmental considerations, waste management of applications, and potential applications at DOE sites. 131 references, 25 figures, 23 tables.

Chiu, S.; Newsom, D.; Barisas, S.; Humphrey, J.; Fradkin, L.; Surles, T.

1982-08-01T23:59:59.000Z

136

Aluminum phosphate ceramics for waste storage  

SciTech Connect (OSTI)

The present disclosure describes solid waste forms and methods of processing waste. In one particular implementation, the invention provides a method of processing waste that may be particularly suitable for processing hazardous waste. In this method, a waste component is combined with an aluminum oxide and an acidic phosphate component in a slurry. A molar ratio of aluminum to phosphorus in the slurry is greater than one. Water in the slurry may be evaporated while mixing the slurry at a temperature of about 140-200.degree. C. The mixed slurry may be allowed to cure into a solid waste form. This solid waste form includes an anhydrous aluminum phosphate with at least a residual portion of the waste component bound therein.

Wagh, Arun; Maloney, Martin D

2014-06-03T23:59:59.000Z

137

LABORATORY CHEMICAL WASTE DISPOSAL POSTER (Post Near Chemical Waste Storage Area)  

E-Print Network [OSTI]

WSTPS.rtf LABORATORY CHEMICAL WASTE DISPOSAL POSTER (Post Near Chemical Waste Storage Area) Excess Chemicals and Chemical Wastes · Toxic and Flammable Chemicals - These cannot go down the drain. Call Environmental Health and Safety (EHSO) at x-2723 for collection. · Corrosive Chemicals (Acids & Bases) - When

Oliver, Douglas L.

138

Mixed waste disposal facilities at the Savannah River Site  

SciTech Connect (OSTI)

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

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

1991-01-01T23:59:59.000Z

139

Mixed waste disposal facilities at the Savannah River Site  

SciTech Connect (OSTI)

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

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

1991-12-31T23:59:59.000Z

140

Hanford facility dangerous waste permit application, general information portion. Revision 3  

SciTech Connect (OSTI)

For purposes of the Hanford facility dangerous waste permit application, the US Department of Energy`s contractors are identified as ``co-operators`` and sign in that capacity (refer to Condition I.A.2. of the Dangerous Waste Portion of the Hanford Facility Resource Conservation and Recovery Act Permit). Any identification of these contractors as an ``operator`` elsewhere in the application is not meant to conflict with the contractors` designation as co-operators but rather is based on the contractors` contractual status with the U.S. Department of Energy, Richland Operations Office. The Dangerous Waste Portion of the initial Hanford Facility Resource Conservation and Recovery Act Permit, which incorporated five treatment, storage, and/or disposal units, was based on information submitted in the Hanford Facility Dangerous Waste Permit Application and in closure plan and closure/postclosure plan documentation. During 1995, the Dangerous Waste Portion was modified twice to incorporate another eight treatment, storage, and/or disposal units; during 1996, the Dangerous Waste Portion was modified once to incorporate another five treatment, storage, and/or disposal units. The permit modification process will be used at least annually to incorporate additional treatment, storage, and/or disposal units as permitting documentation for these units is finalized. The units to be included in annual modifications are specified in a schedule contained in the Dangerous Waste Portion of the Hanford Facility Resource Conservation and Recovery Act Permit. Treatment, storage, and/or disposal units will remain in interim status until incorporated into the Permit. The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (this document, DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to individual operating treatment, storage, and/or disposal units for which Part B permit application documentation has been, or is anticipated to be, submitted. Documentation for treatment, storage, and/or disposal units undergoing closure, or for units that are, or are anticipated to be, dispositioned through other options, will continue to be submitted by the Permittees in accordance with the provisions of the Hanford Federal Facility Agreement and Consent Order. However, the scope of the General Information Portion includes information that could be used to discuss operating units, units undergoing closure, or units being dispositioned through other options. Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the contents of the Part B permit application guidance documentation prepared by the Washington State Department of Ecology and the U.S. Environmental Protection Agency, with additional information needs defined by revisions of Washington Administrative Code 173-303 and by the Hazardous and Solid Waste Amendments. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (i.e., either operating units, units undergoing closure, or units being dispositioned through other options).

Sonnichsen, J.C.

1997-08-21T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect (OSTI)

This comprehensive report provides definitive volume, mass, and composition (chemical and radioactivity) of calcined waste stored at the Idaho Nuclear Technology and Engineering Center. Calcine composition data are required for regulatory compliance (such as permitting and waste disposal), future treatment of the caline, and shipping the calcine to an off-Site-facility (such as a geologic repository). This report also contains a description of the calcine storage bins. The Calcined Solids Storage Facilities (CSSFs) were designed by different architectural engineering firms and built at different times. Each CSSF has a unique design, reflecting varying design criteria and lessons learned from historical CSSF operation. The varying CSSF design will affect future calcine retrieval processes and equipment. Revision 4 of this report presents refinements and enhancements of calculations concerning the composition, volume, mass, chemical content, and radioactivity of calcined waste produced and stored within the CSSFs. The historical calcine samples are insufficient in number and scope of analysis to fully characterize the entire inventory of calcine in the CSSFs. Sample data exist for all the liquid wastes that were calcined. This report provides calcine composition data based on liquid waste sample analyses, volume of liquid waste calcined, calciner operating data, and CSSF operating data using several large Microsoft Excel (Microsoft 2003) databases and spreadsheets that are collectively called the Historical Processing Model. The calcine composition determined by this method compares favorably with historical calcine sample data.

Staiger, M. Daniel, Swenson, Michael C.

2011-09-01T23:59:59.000Z

142

EIS-0287: Idaho High-Level Waste and Facilities Disposition Final...  

Office of Environmental Management (EM)

: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) EIS-0287: Idaho High-Level Waste and Facilities Disposition...

143

Commercial experience with facility deactivation to safe storage  

SciTech Connect (OSTI)

The Department of Energy (DOE) has shutdown many production reactors; the Department has begun a major effort to also shutdown a wide variety of other nuclear facilities. Because so many facilities are being closed, it is necessary to place many of them into a safe- storage status, i.e., deactivation, before conducting decommissioning- for perhaps as long as 20 years. The challenge is to achieve this safe-storage condition in a cost-effective manner while remaining in compliance with applicable regulations. The DOE Office of Environmental Management, Office of Transition and Management, commissioned a lessons-learned study of commercial experience with safe storage and decommissioning. Although the majority of the commercial experience has been with reactors, many of the lessons learned presented in this document can provide insight into transitioning challenges that Will be faced by the DOE weapons complex.

Sype, T.T. [Sandia National Labs., Albuquerque, NM (United States); Fischer, S.R. [Los Alamos National Lab., NM (United States); Lee, J.H. Jr.; Sanchez, L.C.; Ottinger, C.A.; Pirtle, G.J. [Sandia National Labs., Albuquerque, NM (United States)

1995-09-01T23:59:59.000Z

144

Management of a complex cavern storage facility for natural gas  

SciTech Connect (OSTI)

The Epe cavern storage facility operated by Ruhrgas AG has developed into one of the largest gas cavern storage facilities in the world. Currently, there are 32 caverns and 18 more are planned in the future. Working gas volume will increase from approximately 1.5 {times} 10{sup 9} to 2 {times} 10{sup 9} m{sup 3}. The stratified salt deposit containing the caverns has a surface area of approximately 7 km{sup 2} and is 250 m thick at the edge and 400 m thick in the center. Caverns are leached by a company that uses the recovered brine in the chlorine industry. Cavern dimensions are determined before leaching. The behavior of each cavern, as well as the thermodynamic properties of natural gas must be considered in cavern management. The full-length paper presents the components of a complex management system covering the design, construction, and operation of the Epe gas-storage caverns.

NONE

1998-04-01T23:59:59.000Z

145

Survey of computer codes applicable to waste facility performance evaluations  

SciTech Connect (OSTI)

This study is an effort to review existing information that is useful to develop an integrated model for predicting the performance of a radioactive waste facility. A summary description of 162 computer codes is given. The identified computer programs address the performance of waste packages, waste transport and equilibrium geochemistry, hydrological processes in unsaturated and saturated zones, and general waste facility performance assessment. Some programs also deal with thermal analysis, structural analysis, and special purposes. A number of these computer programs are being used by the US Department of Energy, the US Nuclear Regulatory Commission, and their contractors to analyze various aspects of waste package performance. Fifty-five of these codes were identified as being potentially useful on the analysis of low-level radioactive waste facilities located above the water table. The code summaries include authors, identification data, model types, and pertinent references. 14 refs., 5 tabs.

Alsharif, M.; Pung, D.L.; Rivera, A.L.; Dole, L.R.

1988-01-01T23:59:59.000Z

146

Waste Receiving and Processing Facility Module 2A: Advanced Conceptual Design Report. Volume 1  

SciTech Connect (OSTI)

This ACDR was performed following completed of the Conceptual Design Report in July 1992; the work encompassed August 1992 to January 1994. Mission of the WRAP Module 2A facility is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities the Category 1 and 3 contact handled low-level radioactive mixed wastes that are currently in retrievable storage at Hanford and are forecast to be generated over the next 30 years by Hanford, and waste to be shipped to Hanford from about DOE sites. This volume provides an introduction to the ACDR process and the scope of the task along with a project summary of the facility, treatment technologies, cost, and schedule. Major areas of departure from the CDR are highlighted. Descriptions of the facility layout and operations are included.

Not Available

1994-03-01T23:59:59.000Z

147

State waste discharge permit application for the 200 Area Effluent Treatment Facility and the State-Approved Land Disposal Site  

SciTech Connect (OSTI)

Application is being made for a permit pursuant to Chapter 173--216 of the Washington Administrative Code (WAC), to discharge treated waste water and cooling tower blowdown from the 200 Area Effluent Treatment Facility (ETF) to land at the State-Approved Land Disposal Site (SALDS). The ETF is located in the 200 East Area and the SALDS is located north of the 200 West Area. The ETF is an industrial waste water treatment plant that will initially receive waste water from the following two sources, both located in the 200 Area on the Hanford Site: (1) the Liquid Effluent Retention Facility (LERF) and (2) the 242-A Evaporator. The waste water discharged from these two facilities is process condensate (PC), a by-product of the concentration of waste from DSTs that is performed in the 242-A Evaporator. Because the ETF is designed as a flexible treatment system, other aqueous waste streams generated at the Hanford Site may be considered for treatment at the ETF. The origin of the waste currently contained in the DSTs is explained in Section 2.0. An overview of the concentration of these waste in the 242-A Evaporator is provided in Section 3.0. Section 4.0 describes the LERF, a storage facility for process condensate. Attachment A responds to Section B of the permit application and provides an overview of the processes that generated the wastes, storage of the wastes in double-shell tanks (DST), preliminary treatment in the 242-A Evaporator, and storage at the LERF. Attachment B addresses waste water treatment at the ETF (under construction) and the addition of cooling tower blowdown to the treated waste water prior to disposal at SALDS. Attachment C describes treated waste water disposal at the proposed SALDS.

Not Available

1993-08-01T23:59:59.000Z

148

SCFA lead lab technical assistance at Oak Ridge Y-12 nationalsecurity complex: Evaluation of treatment and characterizationalternatives of mixed waste soil and debris at disposal area remedialaction DARA solids storage facility (SSF)  

SciTech Connect (OSTI)

On July 17-18, 2002, a technical assistance team from the U.S. Department of Energy (DOE) Subsurface Contaminants Focus Area (SCFA) met with the Bechtel Jacobs Company Disposal Area Remedial Action (DARA) environmental project leader to review treatment and characterization options for the baseline for the DARA Solids Storage Facility (SSF). The technical assistance request sought suggestions from SCFA's team of technical experts with experience and expertise in soil treatment and characterization to identify and evaluate (1) alternative treatment technologies for DARA soils and debris, and (2) options for analysis of organic constituents in soil with matrix interference. Based on the recommendations, the site may also require assistance in identifying and evaluating appropriate commercial vendors.

Hazen, Terry

2002-08-26T23:59:59.000Z

149

Assessment of the Electrical Power Requirements for Continued Safe Storage and Waste Feed Delivery Phase 1  

SciTech Connect (OSTI)

This study evaluated the ability of the electrical distribution system to support safe storage as well as the first phase of the Waste Feed Delivery. Several recommendations are made to improve the electrical system. The ability to assure adequate Waste Feed Delivery (WFD) to the Privatization Contractor's vitrification facility is a key element in the overall Hanford cleanup schedule. An important aspect of this WFD is the availability of sufficient and appropriate electrical power in the single- and double-shell tank farms. The methodology for performing this review and the results are described.

MAY, T.H.

2000-04-07T23:59:59.000Z

150

Flood Assessment at the Area 5 Radioactive Waste Management Site and the Proposed Hazardous Waste Storage Unit, DOE/Nevada Test Site, Nye County, Nevada  

SciTech Connect (OSTI)

A flood assessment at the Radioactive Waste Management Site (RWMS) and the proposed Hazardous Waste Storage Unit (HWSU) in Area 5 of the Nevada Test Site (NTS) was performed to determine the 100-year flood hazard at these facilities. The study was conducted to determine whether the RWMS and HWSU are located within a 100-year flood hazard as defined by the Federal Emergency Management Agency, and to provide discharges for the design of flood protection.

Schmeltzer, J. S., Millier, J. J., Gustafson, D. L.

1993-01-01T23:59:59.000Z

151

EA-0688: Hazardous Waste Staging Facility, Pantex Plant, Amarillo, Texas  

Broader source: Energy.gov [DOE]

This EA evaluates the environmental impacts of a proposal to construct the Hazardous Waste Staging Facility that would help to alleviate capacity problems as well as provide a single compliant...

152

Low-Level Radioactive Waste Disposal Regional Facility Act (Pennsylvania)  

Broader source: Energy.gov [DOE]

This act establishes a low-level radioactive waste disposal regional facility siting fund that requires nuclear power reactor constructors and operators to pay to the Department of Environmental...

153

TRU waste certification compliance requirements for contact-handled wastes retrieved from storage for shipment to the WIPP  

SciTech Connect (OSTI)

Compliance requirements are presented for certifying that unclassified, contact-handled (CH) transuranic (TRU) solid wastes retrieved from storage at DOE sites meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). All applicable DOE Orders must continue to be met. The compliance requirements for certified waste retrieved from certified storage are addressed in another document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste.

Not Available

1982-09-01T23:59:59.000Z

154

The Advantages of Fixed Facilities in Characterizing TRU Wastes  

SciTech Connect (OSTI)

In May 1998 the Hanford Site started developing a program for characterization of transuranic (TRU) waste for shipment to the Waste Isolation Pilot Plant (WIPP) in New Mexico. After less than two years, Hanford will have a program certified by the Carlsbad Area Office (CAO). By picking a simple waste stream, taking advantage of lessons learned at the other sites, as well as communicating effectively with the CAO, Hanford was able to achieve certification in record time. This effort was further simplified by having a centralized program centered on the Waste Receiving and Processing (WRAP) Facility that contains most of the equipment required to characterize TRU waste. The use of fixed facilities for the characterization of TRU waste at sites with a long-term clean-up mission can be cost effective for several reasons. These include the ability to control the environment in which sensitive instrumentation is required to operate and ensuring that calibrations and maintenance activities are scheduled and performed as an operating routine. Other factors contributing to cost effectiveness include providing approved procedures and facilities for handling hazardous materials and anticipated contingencies and performing essential evolutions, and regulating and smoothing the work load and environmental conditions to provide maximal efficiency and productivity. Another advantage is the ability to efficiently provide characterization services to other sites in the Department of Energy (DOE) Complex that do not have the same capabilities. The Waste Receiving and Processing (WRAP) Facility is a state-of-the-art facility designed to consolidate the operations necessary to inspect, process and ship waste to facilitate verification of contents for certification to established waste acceptance criteria. The WRAP facility inspects, characterizes, treats, and certifies transuranic (TRU), low-level and mixed waste at the Hanford Site in Washington state. Fluor Hanford operates the $89 million facility under the Project Hanford Management Contract. This paper describes the operating experiences and results obtained during the first year of full operations at WRAP. Interested audiences include personnel involved in TRU waste characterization activities, TRU waste treatment and disposal facilities and TRU waste certification. The conclusions of this paper are that WRAP has proven itself to be a valuable asset for low-level and TRU waste management.

FRENCH, M.S.

2000-02-08T23:59:59.000Z

155

Stress evaluation of the primary tank of a double-shell underground storage tank facility  

SciTech Connect (OSTI)

A facility called the Multi-Function Waste Tank Facility (MWTF) is being designed at the Department of Energy`s Hanford site. The MWTF is expected to be completed in 1998 and will consist of six underground double-shell waste storage tanks and associated systems. These tanks will provide safe and environmentally acceptable storage capacity to handle waste generated during single-shell and double-shell tank safety mitigation and remediation activities. This paper summarizes the analysis and qualification of the primary tank structure of the MWTF, as performed by ICF Kaiser Hanford during the latter phase of Title 1 (Preliminary) design. Both computer finite element analysis (FEA) and hand calculations methods based on the so-called Tank Seismic Experts Panel (TSEP) Guidelines were used to perform the analysis and evaluation. Based on the evaluations summarized in this paper, it is concluded that the primary tank structure of the MWTF satisfies the project design requirements. In addition, the hand calculations performed using the methodologies provided in the TSEP Guidelines demonstrate that, except for slosh height, the capacities exceed the demand. The design accounts for the adverse effect of the excessive slosh height demand, i.e., inadequate freeboard, by increasing the hydrodynamic wall and roof pressures appropriately, and designing the tank for such increased pressures.

Atalay, M.B. [ICF Kaiser Engineers, Inc., Oakland, CA (United States); Stine, M.D. [ICF Kaiser Hanford Co., Richland, WA (United States); Farnworth, S.K. [Westinghouse Hanford Co., Richland, WA (United States)

1994-12-01T23:59:59.000Z

156

United States National Waste Terminal Storage argillaceous rock studies  

SciTech Connect (OSTI)

The past and present argillaceous rock studies for the US National Waste Terminal Storage Program consist of: (1) evaluation of the geological characteristics of several widespread argillaceous formations in the United States; (2) laboratory studies of the physical and chemical properties of selected argillaceous rock samples; and (3) two full-scale in situ surface heater experiments that simulate the emplacement of heat-generating radioactive waste in argillaceous rock.

Brunton, G.D.

1981-01-01T23:59:59.000Z

157

Joint Assessment of Renewable Energy and Water Desalination Research Center (REWDC) Program Capabilities and Facilities In Radioactive Waste Management  

SciTech Connect (OSTI)

The primary goal of this visit was to perform a joint assessment of the Renewable Energy and Water Desalination Center's (REWDC) program in radioactive waste management. The visit represented the fourth technical and scientific interaction with Libya under the DOE/NNSA Sister Laboratory Arrangement. Specific topics addressed during the visit focused on Action Sheet P-05-5, ''Radioactive Waste Management''. The Team, comprised of Mo Bissani (Team Lead), Robert Fischer, Scott Kidd, and Jim Merrigan, consulted with REWDC management and staff. The team collected information, discussed particulars of the technical collaboration and toured the Tajura facility. The tour included the waste treatment facility, waste storage/disposal facility, research reactor facility, hot cells and analytical labs. The assessment team conducted the first phase of Task A for Action Sheet 5, which involved a joint assessment of the Radioactive Waste Management Program. The assessment included review of the facilities dedicated to the management of radioactive waste at the Tourja site, the waste management practices, proposed projects for the facility and potential impacts on waste generation and management.

Bissani, M; Fischer, R; Kidd, S; Merrigan, J

2006-04-03T23:59:59.000Z

158

Hanford facility dangerous waste permit application, 325 hazardous waste treatment units. Revision 1  

SciTech Connect (OSTI)

This report contains the Hanford Facility Dangerous Waste Permit Application for the 325 Hazardous Waste Treatment Units (325 HWTUs) which consist of the Shielded Analytical Laboratory, the 325 Building, and the 325 Collection/Loadout Station Tank. The 325 HWTUs receive, store, and treat dangerous waste generated by Hanford Facility programs. Routine dangerous and/or mixed waste treatment that will be conducted in the 325 HWTUs will include pH adjustment, ion exchange, carbon absorption, oxidation, reduction, waste concentration by evaporation, precipitation, filtration, solvent extraction, solids washing, phase separation, catalytic destruction, and solidification/stabilization.

NONE

1997-07-01T23:59:59.000Z

159

Fissile material storage in the Oak Ridge Radiochemical Development Facility  

SciTech Connect (OSTI)

As a part of a Department of Energy review of Oak Ridge National Laboratory facilities, nuclear safety documentation for the Radiochemical Development Facility (Building 3019) was found to be inadequate. While calculations existed which established safe limits for the storage of fissile material, these calculations were not performed with verified/validated software nor were the results reported in the manner prescribed by applicable DOE orders and ORNL procedures. To address this deficiency, the operations conducted in Building 3019 were reviewed and conditions were compared to available critical experiment data. Applicable critical experiments were selected and multiplication factors were calculated. Subcritical limits were derived for each of three fissile materials (U-233, U-235, and Pu-239). One application of these limits was to certify the safety of a storage array which could contain any or all of the above nuclides at varying degrees of moderation. The studies presented are believed to fulfill most of the applicable regulatory requirements.

Primm, R.T. III

1993-08-01T23:59:59.000Z

160

Recommendations on the proposed Monitored Retrievable Storage Facility  

SciTech Connect (OSTI)

Following the Department of Energy's announcement in April 1985 that three Tennessee sites were to be considered for the Monitored Retrievable Storage facility, Governor Lamar Alexander initiated a review of the proposal to be coordinated by his Safe Growth Team. Roane County and the City of Oak Ridge, the local governments sharing jurisdiction over DOE's primary and secondary sites, were invited to participate in the state's review of the MRS proposal. Many issues related to the proposed MRS are being considered by the Governor's Safe Growth Team. The primary objective of the Clinch River MRS Task Force has been to determine whether the proposed Monitored Retrievable Storage facility should be accepted by the local governments, and if so, under what conditions. The Clinch River MRS Task Force is organized into an Executive Committee cochaired by the Roane County Executive and Mayor of Oak Ridge and three Study Groups focusing on environmental (including health and safety), socioeconomic, and transportation issues.

Not Available

1985-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Waste-heat recovery in batch processes using heat storage  

SciTech Connect (OSTI)

The waste-heat recovery in batch processes has been studied using the pinch-point method. The aim of the work has been to investigate theoretical and practical approaches to the design of heat-exchanger networks, including heat storage, for waste-heat recovery in batch processes. The study is limited to the incorporation of energy-storage systems based on fixed-temperature variable-mass stores. The background for preferring this to the alternatives (variable-temperature fixed-mass and constant-mass constant-temperature (latent-heat) stores) is given. It is shown that the maximum energy-saving targets as calculated by the pinch-point method (time average model, TAM) can be achieved by locating energy stores at either end of each process stream. This theoretically large number of heat-storage tanks (twice the number of process streams) can be reduced to just a few tanks. A simple procedure for determining a number of heat-storage tanks sufficient to achieve the maximum energy-saving targets as calculated by the pinch-point method is described. This procedure relies on combinatorial considerations, and could therefore be labeled the combinatorial method for incorporation of heat storage in heat-exchanger networks. Qualitative arguments justifying the procedure are presented. For simple systems, waste-heat recovery systems with only three heat-storage temperatures (a hot storage, a cold storage, and a heat store at the pinch temperature) often can achieve the maximum energy-saving targets. Through case studies, six of which are presented, it is found that a theoretically large number of heat-storage tanks (twice the number of process streams) can be reduced to just a few tanks. The description of these six cases is intended to be sufficiently detailed to serve as benchmark cases for development of alternative methods.

Stoltze, S.; Mikkelsen, J.; Lorentzen, B.; Petersen, P.M.; Qvale, B. [Technical Univ. of Denmark, Lyngby (Denmark). Lab. for Energetics

1995-06-01T23:59:59.000Z

162

Waste Heat Recovery from Refrigeration in a Meat Processing Facility  

E-Print Network [OSTI]

A case study is reviewed on a heat recovery system installed in a meat processing facility to preheat water for the plant hot water supply. The system utilizes waste superheat from the facility's 1,350-ton ammonia refrigeration system. The heat...

Murphy, W. T.; Woods, B. E.; Gerdes, J. E.

1980-01-01T23:59:59.000Z

163

Characterization of decontamination and decommissioning wastes expected from the major processing facilities in the 200 Areas  

SciTech Connect (OSTI)

This study was intended to characterize and estimate the amounts of equipment and other materials that are candidates for removal and subsequent processing in a solid waste facility when the major processing and handling facilities in the 200 Areas of the Hanford Site are decontaminated and decommissioned. The facilities in this study were selected based on processing history and on the magnitude of the estimated decommissioning cost cited in the Surplus Facilities Program Plan; Fiscal Year 1993 (Winship and Hughes 1992). The facilities chosen for this study include B Plant (221-B), T Plant (221-T), U Plant (221-U), the Uranium Trioxide (UO{sub 3}) Plant (224-U and 224-UA), the Reduction Oxidation (REDOX) or S Plant (202-S), the Plutonium Concentration Facility for B Plant (224-B), and the Concentration Facility for the Plutonium Finishing Plant (PFP) and REDOX (233-S). This information is required to support planning activities for current and future solid waste treatment, storage, and disposal operations and facilities.

Amato, L.C.; Franklin, J.D.; Hyre, R.A.; Lowy, R.M.; Millar, J.S.; Pottmeyer, J.A. [Los Alamos Technical Associates, Kennewick, WA (United States); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (United States)

1994-08-01T23:59:59.000Z

164

Occupational dose estimates for a monitored retrievable storage facility  

SciTech Connect (OSTI)

Occupational doses were estimated for radiation workers at the monitored retrievable storage (MRS) facility. This study provides an estimate of the occupational dose based on the current MRS facility design, examines the extent that various design parameters and assumptions affect the dose estimates, and identifies the areas and activities where exposures can be reduced most effectively. Occupational doses were estimated for both the primary storage concept and the alternate storage concept. The dose estimates indicate the annual dose to all radiation workers will be below the 5 rem/yr federal dose equivalent limit. However, the estimated dose to most of the receiving and storage crew (the workers responsible for the receipt, storage, and surveillance of the spent fuel and its subsequent retrieval), to the crane maintenance technicians, and to the cold and remote maintenance technicians is above the design objective of 1 rem/yr. The highest annual dose is received by the riggers (4.7 rem) in the receiving and storage crew. An indication of the extent to which various design parameters and assumptions affect the dose estimates was obtained by changing various design-based assumptions such as work procedures, background dose rates in radiation zones, and the amount of fuel received and stored annually. The study indicated that a combination of remote operations, increased shielding, and additional personnel (for specific jobs) or changes in operating procedures will be necessary to reduce worker doses below 1.0 rem/yr. Operations that could be made at least partially remote include the removal and replacement of the tiedowns, impact limiters, and personnel barriers from the shipping casks and the removal or installation of the inner closure bolts. Reductions of the background dose rates in the receiving/shipping and the transfer/discharge areas may be accomplished with additional shielding.

Harty, R.; Stoetzel, G.A.

1986-06-01T23:59:59.000Z

165

Industrial Solid Waste Landfill Facilities (Ohio)  

Broader source: Energy.gov [DOE]

This chapter of the law establishes that the Ohio Environmental Protection Agency provides rules and guidelines for landfills, including those that treat waste to generate electricity. The law...

166

Technical evaluation of proposed Ukrainian Central Radioactive Waste Processing Facility  

SciTech Connect (OSTI)

This technical report is a comprehensive evaluation of the proposal by the Ukrainian State Committee on Nuclear Power Utilization to create a central facility for radioactive waste (not spent fuel) processing. The central facility is intended to process liquid and solid radioactive wastes generated from all of the Ukrainian nuclear power plants and the waste generated as a result of Chernobyl 1, 2 and 3 decommissioning efforts. In addition, this report provides general information on the quantity and total activity of radioactive waste in the 30-km Zone and the Sarcophagus from the Chernobyl accident. Processing options are described that may ultimately be used in the long-term disposal of selected 30-km Zone and Sarcophagus wastes. A detailed report on the issues concerning the construction of a Ukrainian Central Radioactive Waste Processing Facility (CRWPF) from the Ukrainian Scientific Research and Design institute for Industrial Technology was obtained and incorporated into this report. This report outlines various processing options, their associated costs and construction schedules, which can be applied to solving the operating and decommissioning radioactive waste management problems in Ukraine. The costs and schedules are best estimates based upon the most current US industry practice and vendor information. This report focuses primarily on the handling and processing of what is defined in the US as low-level radioactive wastes.

Gates, R.; Glukhov, A.; Markowski, F.

1996-06-01T23:59:59.000Z

167

Device Assembly Facility (DAF) Glovebox Radioactive Waste Characterization  

SciTech Connect (OSTI)

The Device Assembly Facility (DAF) at the Nevada Test Site (NTS) provides programmatic support to the Joint Actinide Shock Physics Experimental Research (JASPER) Facility in the form of target assembly. The target assembly activities are performed in a glovebox at DAF and include Special Nuclear Material (SNM). Currently, only activities with transuranic SNM are anticipated. Preliminary discussions with facility personnel indicate that primarily two distributions of SNM will be used: Weapons Grade Plutonium (WG-Pu), and Pu-238 enhanced WG-Pu. Nominal radionuclide distributions for the two material types are included in attachment 1. Wastes generated inside glove boxes is expected to be Transuranic (TRU) Waste which will eventually be disposed of at the Waste Isolation Pilot Plant (WIPP). Wastes generated in the Radioactive Material Area (RMA), outside of the glove box is presumed to be low level waste (LLW) which is destined for disposal at the NTS. The process knowledge quantification methods identified herein may be applied to waste generated anywhere within or around the DAF and possibly JASPER as long as the fundamental waste stream boundaries are adhered to as outlined below. The method is suitable for quantification of waste which can be directly surveyed with the Blue Alpha meter or swiped. An additional quantification methodology which requires the use of a high resolution gamma spectroscopy unit is also included and relies on the predetermined radionuclide distribution and utilizes scaling to measured nuclides for quantification.

Dominick, J L

2001-12-18T23:59:59.000Z

168

Seismic modeling and analysis of a prototype heated nuclear waste storage tunnel, Yucca Mountain, Nevada  

E-Print Network [OSTI]

Seismic modeling and analysis of a prototype heated nuclear waste storage tunnel, Yucca Mountain was heated to replicate the effects of long-term storage of decaying nuclear waste and to study the effects for the long- term storage of high-level nuclear waste from reactors and decom- missioned atomic weapons

Snieder, Roel

169

Texas facility treats, recycles refinery, petrochemical wastes  

SciTech Connect (OSTI)

A US Gulf Coast environmental services company is treating refinery and petrochemical plant wastes to universal treatment standards (UTS). DuraTherm Inc.`s recycling center uses thermal desorption to treat a variety of refinery wastes and other hazardous materials. The plant is located in San Leon, Tex., near the major Houston/Texas City refining and petrochemical center. DuraTherm`s customers include major US refining companies, plus petrochemical, terminal, pipeline, transportation, and remediation companies. Examples of typical contaminant concentrations and treatment levels for refinery wastes are shown. The paper discusses thermal desorption, the process description and testing.

NONE

1996-09-16T23:59:59.000Z

170

Biohazardous Waste Disposal GuidelinesDescriptionStorage& LabelingTreatmentDisposal  

E-Print Network [OSTI]

Waste Sharps Waste Solid Lab Waste Liquid Waste Any of these devices if contaminated with biohazardousBiohazardous Waste Disposal GuidelinesDescriptionStorage& packaging LabelingTreatmentDisposal Mixed container. Container must be leakproof, ridgid, puncture resistant, clearly marked for biohazardous waste

Wikswo, John

171

Avoca, New York Salt Cavern Gas Storage Facility  

SciTech Connect (OSTI)

The first salt cavern natural gas storage facility in the northeastern United States designed to serve the interstate gas market is being developed by J Makowski Associates and partners at Avoca in Steuben County, New York. Multiple caverns will be leached at a depth of about 3800 ft from an approximately 100 ft interval of salt within the F unit of the Syracuse Formation of the Upper Silurian Salina Group. The facility is designed to provide 5 Bcf of working gas capacity and 500 MMcfd of deliverability within an operating cavern pressure range between 760 psi and 2850 psi. Fresh water for leaching will be obtained from the Cohocton River aquifer at a maximum rate of 3 million gallons per day and produced brine will be injected into deep permeable Cambrian age sandstones and dolostones. Gas storage service is anticipated to commence in the Fall of 1997 with 2 Bcf of working gas capacity and the full 5 Bcf or storage service is scheduled to be available in the Fall of 1999.

Morrill, D.C. [J. Makowski and Associates, Boston, MA (United States)

1995-09-01T23:59:59.000Z

172

Structural Integrity Program for the 300,000-Gallon Radioactive Liquid Waste Storage Tanks at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect (OSTI)

This report provides a record of the Structural Integrity Program for the 300,000-gal liquid waste storage tanks and associated equipment at the Idaho Nuclear Technology and Engineering Center, as required by U.S. Department of Energy M 435.1-1, ''Radioactive Waste Management Manual.'' This equipment is known collectively as the Tank Farm Facility. The conclusion of this report is that the Tank Farm Facility tanks, vaults, and transfer systems that remain in service for storage are structurally adequate, and are expected to remain structurally adequate over the remainder of their planned service life through 2012. Recommendations are provided for continued monitoring of the Tank Farm Facility.

Bryant, J.W.; Nenni, J.A.; Yoder, T.S.

2003-04-22T23:59:59.000Z

173

Foreign programs for the storage of spent nuclear power plant fuels, high-level waste canisters and transuranic wastes  

SciTech Connect (OSTI)

The various national programs for developing and applying technology for the interim storage of spent fuel, high-level radioactive waste, and TRU wastes are summarized. Primary emphasis of the report is on dry storage techniques for uranium dioxide fuels, but data are also provided concerning pool storage.

Harmon, K.M.; Johnson, A.B. Jr.

1984-04-01T23:59:59.000Z

174

Low-level radioactive waste disposal facility closure  

SciTech Connect (OSTI)

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

White, G.J.; Ferns, T.W.; Otis, M.D.; Marts, S.T.; DeHaan, M.S.; Schwaller, R.G.; White, G.J. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

1990-11-01T23:59:59.000Z

175

West Valley facility spent fuel handling, storage, and shipping experience  

SciTech Connect (OSTI)

The result of a study on handling and shipping experience with spent fuel are described in this report. The study was performed by Pacific Northwest Laboratory (PNL) and was jointly sponsored by the US Department of Energy (DOE) and the Electric Power Research Institute (EPRI). The purpose of the study was to document the experience with handling and shipping of relatively old light-water reactor (LWR) fuel that has been in pool storage at the West Valley facility, which is at the Western New York Nuclear Service Center at West Valley, New York and operated by DOE. A subject of particular interest in the study was the behavior of corrosion product deposits (i.e., crud) deposits on spent LWR fuel after long-term pool storage; some evidence of crud loosening has been observed with fuel that was stored for extended periods at the West Valley facility and at other sites. Conclusions associated with the experience to date with old spent fuel that has been stored at the West Valley facility are presented. The conclusions are drawn from these subject areas: a general overview of the West Valley experience, handling of spent fuel, storing of spent fuel, rod consolidation, shipping of spent fuel, crud loosening, and visual inspection. A list of recommendations is provided. 61 refs., 4 figs., 5 tabs.

Bailey, W.J.

1990-11-01T23:59:59.000Z

176

Design requirements document for Project W-465, immobilized low-activity waste interim storage  

SciTech Connect (OSTI)

The scope of this Design Requirements Document (DRD) is to identify the functions and associated requirements that must be performed to accept, transport, handle, and store immobilized low-activity waste (ILAW) produced by the privatized Tank Waste Remediation System (TWRS) treatment contractors. The functional and performance requirements in this document provide the basis for the conceptual design of the TWRS ILAW Interim Storage facility project and provides traceability from the program level requirements to the project design activity. Technical and programmatic risk associated with the TWRS planning basis are discussed in the Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The design requirements provided in this document will be augmented by additional detailed design data documented by the project.

Burbank, D.A.

1998-05-19T23:59:59.000Z

177

324 Facility special-case waste assessment in support of 324 closure (TPA milestone M-89-05)  

SciTech Connect (OSTI)

Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement Milestone M-89-05, requires US Department of Energy, Richland Operations Office to complete a 324 Facility Special-Case Waste Assessment in Support of 324 Closure. This document, HNF-1270, has been prepared with the intent of meeting this regulatory commitment. Alternatives for the special-case wastes located in the 324 Building were defined and analyzed. Based on the criteria of safety, environmental, complexity of interfaces, risk, cost, schedule, and long-term operability and maintainability, the best alternative was chosen. Waste packaging and transportation options are also included in the recommendations. The waste disposition recommendations for the B-Cell dispersibles/tank heels and High-Level Vault packaged residuals are to direct them to the Plutonium Uranium Extraction Facility (PUREX) Number 2 storage tunnel.

Hobart, R.L.

1998-06-25T23:59:59.000Z

178

Viability of Existing INL Facilities for Dry Storage Cask Handling  

SciTech Connect (OSTI)

This report evaluates existing capabilities at the INL to determine if a practical and cost effective method could be developed for opening and handling full-sized dry storage casks. The Idaho Nuclear Technology and Engineering Center (INTEC) CPP-603, Irradiated Spent Fuel Storage Facility, provides the infrastructure to support handling and examining casks and their contents. Based on a reasonable set of assumptions, it is possible to receive, open, inspect, remove samples, close, and reseal large bolted-lid dry storage casks at the INL. The capability can also be used to open and inspect casks that were last examined at the TAN Hot Shop over ten years ago. The Castor V/21 and REA-2023 casks can provide additional confirmatory information regarding the extended performance of low-burnup (<45 GWD/MTU) used nuclear fuel. Once a dry storage cask is opened inside CPP-603, used fuel retrieved from the cask can be packaged in a shipping cask, and sent to a laboratory for testing. Testing at the INL’s Materials and Fuels Complex (MFC) can occur starting with shipment of samples from CPP-603 over an on-site road, avoiding the need to use public highways. This reduces cost and reduces the risk to the public. The full suite of characterization methods needed to establish the condition of the fuel exists and MFC. Many other testing capabilities also exist at MFC, but when those capabilities are not adequate, samples can be prepared and shipped to other laboratories for testing. This report discusses how the casks would be handled, what work needs to be done to ready the facilities/capabilities, and what the work will cost.

Randy Bohachek; Charles Park; Bruce Wallace; Phil Winston; Steve Marschman

2013-04-01T23:59:59.000Z

179

Permeability of consolidated incinerator facility wastes stabilized with portland cement  

SciTech Connect (OSTI)

The Consolidated Incinerator Facility (CIF) at the Savannah River Site (SRS) burns low-level radioactive wastes and mixed wastes as a method of treatment and volume reduction. The CIF generates secondary waste, which consists of ash and offgas scrubber solution. Currently the ash is stabilized/solidified in the Ashcrete process. The scrubber solution (blowdown) is sent to the SRS Effluent Treatment Facility (ETF) for treatment as wastewater. In the past, the scrubber solution was also stabilized/solidified in the Ashcrete process as blowcrete, and will continue to be treated this way for listed waste burns and scrubber solutions that do not meet the ETF Waste Acceptance Criteria (WAC). The disposal plan for Ashcrete and special case blowcrete is to bury these containerized waste forms in shallow unlined trenches in E-Area. The WAC for intimately mixed, cement-based wasteforms intended for direct disposal specifies limits on compressive strength and permeability. Simulated waste and actual CIF ash and scrubber solution were mixed in the laboratory and cast into wasteforms for testing. Test results and related waste disposal consequences are given in this report.

Walker, B.W.

2000-04-19T23:59:59.000Z

180

Integral Monitored Retrievable Storage (MRS) Facility conceptual design report  

SciTech Connect (OSTI)

In April 1985, the Department of Energy (DOE) selected the Clinch River site as its preferred site for the construction and operation of the monitored retrievable storage (MRS) facility (USDOE, 1985). In support of the DOE MRS conceptual design activity, available data describing the site have been gathered and analyzed. A composite geotechnical description of the Clinch River site has been developed and is presented herein. This report presents Clinch River site description data in the following sections: general site description, surface hydrologic characteristics, groundwater characteristics, geologic characteristics, vibratory ground motion, surface faulting, stability of subsurface materials, slope stability, and references. 48 refs., 35 figs., 6 tabs.

None

1985-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Field Survey of Cactus Crater Storage Facility (Runit Dome)  

SciTech Connect (OSTI)

The US Department of Energy, Office of Health and Safety (DOE/HS-10), requested that National Security Technologies, LLC, Environmental Management directorate (NSTec/EM) perform a field survey of the Cactus Crater Storage Facility (Runit Dome), similar to past surveys conducted at their request. This field survey was conducted in conjunction with a Lawrence Livermore National Laboratory (LLNL) mission on Runit Island in the Enewetak Atoll in the Republic of the Marshall Islands (RMI). The survey was strictly a visual survey, backed up by digital photos and a written description of the current condition.

Douglas Miller, Terence Holland

2008-10-31T23:59:59.000Z

182

WIPP Facility Work Plan for Solid Waste Management Units  

SciTech Connect (OSTI)

This 2001 Facility Work Plan (FWP) has been prepared as required by Module VII, Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a), and incorporates comments from the New Mexico Environment Department (NMED) received on December 6, 2000 (NMED, 2000a). This February 2001 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. The permittees are evaluating data from previous investigations of the SWMUs and AOCs against the newest guidance proposed by the NMED. Based on these data, the permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility’s Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit.

Washington TRU Solutions LLC

2001-02-25T23:59:59.000Z

183

Pipe overpack container for trasuranic waste storage and shipment  

DOE Patents [OSTI]

A Pipe Overpack Container for transuranic waste storage and shipment. The system consists of a vented pipe component which is positioned in a vented, insulated 55 gallon steel drum. Both the vented pipe component and the insulated drum are capable of being secured to prevent the contents from leaving the vessel. The vented pipe component is constructed of 1/4 inch stainless steel to provide radiation shielding. Thus, allowing shipment having high Americium-241 content. Several Pipe Overpack Containers are then positioned in a type B, Nuclear Regulatory Commission (NRC) approved, container. In the current embodiment, a TRUPACT-II container was employed and a maximum of fourteen Pipe Overpack Containers were placed in the TRUPACT-II. The combination received NRC approval for the shipment and storage of transuranic waste.

Geinitz, Richard R. (Arvada, CO); Thorp, Donald T. (Broomfield, CO); Rivera, Michael A. (Boulder, CO)

1999-01-01T23:59:59.000Z

184

Hanford Site annual dangerous waste report: Volume 4, Waste Management Facility report, Radioactive mixed waste  

SciTech Connect (OSTI)

This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling method and containment vessel, waste number, waste designation and amount of waste.

NONE

1994-12-31T23:59:59.000Z

185

SCFA lead lab technical assistance at Oak Ridge Y-12 national security complex: Evaluation of treatment and characterization alternatives of mixed waste soil and debris at disposal area remedial action DARA solids storage facility (SSF)  

E-Print Network [OSTI]

allowing the use of macroencapsulation technologies. SCFADemonstration of Macroencapsulation of Mixed Waste Debrisoff-site for treatment. Macroencapsulation will meet the LDR

Hazen, Terry

2002-01-01T23:59:59.000Z

186

Recommendations on the proposed Monitored Retrievable Storage Facility  

SciTech Connect (OSTI)

Following the Department of Energy`s announcement in April 1985 that three Tennessee sites were to be considered for the Monitored Retrievable Storage facility, Governor Lamar Alexander initiated a review of the proposal to be coordinated by his Safe Growth Team. Roane County and the City of Oak Ridge, the local governments sharing jurisdiction over DOE`s primary and secondary sites, were invited to participate in the state`s review of the MRS proposal. Many issues related to the proposed MRS are being considered by the Governor`s Safe Growth Team. The primary objective of the Clinch River MRS Task Force has been to determine whether the proposed Monitored Retrievable Storage facility should be accepted by the local governments, and if so, under what conditions. The Clinch River MRS Task Force is organized into an Executive Committee cochaired by the Roane County Executive and Mayor of Oak Ridge and three Study Groups focusing on environmental (including health and safety), socioeconomic, and transportation issues.

Not Available

1985-10-01T23:59:59.000Z

187

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

SciTech Connect (OSTI)

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.

Not Available

1993-06-01T23:59:59.000Z

188

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

SciTech Connect (OSTI)

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

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

1997-04-01T23:59:59.000Z

189

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

SciTech Connect (OSTI)

The U.S. Department of Energy, National Security Administration Nevada Site Office (NNSA/NSO) is planning to close the 92-Acre Area of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS), which is about 65 miles northwest of Las Vegas, Nevada. Closure planning for this facility must take into account the regulatory requirements for a diversity of waste streams, disposal and storage configurations, disposal history, and site conditions. This paper provides a brief background of the Area 5 RWMS, identifies key closure issues, and presents the closure strategy. Disposals have been made in 25 shallow excavated pits and trenches and 13 Greater Confinement Disposal (GCD) boreholes at the 92-Acre Area since 1961. The pits and trenches have been used to dispose unclassified low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform waste, and to store classified low-level and low-level mixed materials. The GCD boreholes are intermediate-depth disposal units about 10 feet (ft) in diameter and 120 ft deep. Classified and unclassified high-specific activity LLW, transuranic (TRU), and mixed TRU are disposed in the GCD boreholes. TRU waste was also disposed inadvertently in trench T-04C. Except for three disposal units that are active, all pits and trenches are operationally covered with 8-ft thick alluvium. The 92-Acre Area also includes a Mixed Waste Disposal Unit (MWDU) operating under Resource Conservation and Recovery Act (RCRA) Interim Status, and an asbestiform waste unit operating under a state of Nevada Solid Waste Disposal Site Permit. A single final closure cover is envisioned over the 92-Acre Area. The cover is the evapotranspirative-type cover that has been successfully employed at the NTS. Closure, post-closure care, and monitoring must meet the requirements of the following regulations: U.S. Department of Energy Order 435.1, Title 40 Code of Federal Regulations (CFR) Part 191, Title 40 CFR Part 265, Nevada Administrative Code (NAC) 444.743, RCRA requirements as incorporated into NAC 444.8632, and the Federal Facility Agreement and Consent Order (FFACO). A grouping of waste disposal units according to waste type, location, and similarity in regulatory requirements identified six closure units: LLW Unit, Corrective Action Unit (CAU) 111 under FFACO, Asbestiform LLW Unit, Pit 3 MWDU, TRU GCD Borehole Unit, and TRU Trench Unit. The closure schedule of all units is tied to the closure schedule of the Pit 3 MWDU under RCRA.

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

2008-03-01T23:59:59.000Z

190

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

SciTech Connect (OSTI)

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

Denney, R.D.

1995-10-01T23:59:59.000Z

191

Screening Level Risk Assessment for the New Waste Calcining Facility  

SciTech Connect (OSTI)

This screening level risk assessment evaluates potential adverse human health and ecological impacts resulting from continued operations of the calciner at the New Waste Calcining Facility (NWCF) at the Idaho Nuclear Technology and Engineering Center (INTEC), Idaho National Engineering and Environmental Laboratory (INEEL). The assessment was conducted in accordance with the Environmental Protection Agency (EPA) report, Guidance for Performing Screening Level Risk Analyses at Combustion Facilities Burning Hazardous Waste. This screening guidance is intended to give a conservative estimate of the potential risks to determine whether a more refined assessment is warranted. The NWCF uses a fluidized-bed combustor to solidify (calcine) liquid radioactive mixed waste from the INTEC Tank Farm facility. Calciner off volatilized metal species, trace organic compounds, and low-levels of radionuclides. Conservative stack emission rates were calculated based on maximum waste solution feed samples, conservative assumptions for off gas partitioning of metals and organics, stack gas sampling for mercury, and conservative measurements of contaminant removal (decontamination factors) in the off gas treatment system. Stack emissions were modeled using the ISC3 air dispersion model to predict maximum particulate and vapor air concentrations and ground deposition rates. Results demonstrate that NWCF emissions calculated from best-available process knowledge would result in maximum onsite and offsite health and ecological impacts that are less then EPA-established criteria for operation of a combustion facility.

M. L. Abbott; K. N. Keck; R. E. Schindler; R. L. VanHorn; N. L. Hampton; M. B. Heiser

1999-05-01T23:59:59.000Z

192

Hazardous Waste Facility Permit Public Comments to Community...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

1 SECTION COMMENT POST? 2.0 & 4.0 1. Fix broken links on pages 3 and 4 for the HWA permit. Yes 2.0 2. Revise a sentence on page 4 to: "Limits on LANL waste facilities may be...

193

Geosynthetic Clay Liner applications in waste disposal facilities  

SciTech Connect (OSTI)

Geosynthetic Clay Liners (GCLs) are becoming a popular alternative to compacted clay barrier layers, and represent the state of the art in waste disposal facility design. They possess many of the same qualities of compacted clay barrier layers while occupying only a small fraction of the airspace. This is a very attractive feature to waste disposal facility owners and operators. There are many manufacturers of GCLs in the marketplace, providing numerous products that can be used in a wide variety of applications. Designing for the constructing with a GCL an be a challenging task; stability issues must be evaluated, selecting the appropriate product should be considered, comprehensive specifications are needed to ensure proper product selection and installation, and steps must be taken during installation to prevent damage to the GCL. Perhaps most importantly, state regulatory agencies must be convinced that GCLs will provide long-term protection equivalent to a clay barrier layer. This paper will discuss design considerations, specification guidelines, installation criteria, construction quality assurance guidelines and regulatory issues pertaining to GCL. The paper will also present three brief case histories of relevant GCL applications in waste disposal facility design and construction. The purpose of the paper is to demonstrate that GCLs are a viable alternative to compacted clay barrier layers and to provide useful information in designing, specifying and installing them in waste disposal facilities.

McGrath, L.T.; Creamer, P.D. [RMT, Inc., Madison, WI (United States)

1995-12-31T23:59:59.000Z

194

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

SciTech Connect (OSTI)

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

Jordan, J.; Flach, G.

2012-03-29T23:59:59.000Z

195

EA-1848: Fulcrum Sierra Waste-to-Ethanol Facility in McCarran...  

Broader source: Energy.gov (indexed) [DOE]

8: Fulcrum Sierra Waste-to-Ethanol Facility in McCarran, Storey County, NV EA-1848: Fulcrum Sierra Waste-to-Ethanol Facility in McCarran, Storey County, NV June 1, 2011 EA-1848:...

196

Waste Receiving and Processing Facility - Hanford Site  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption byAbout Printable VersionProtective ActionsWaste

197

Waste Sampling and Characterization Facility - Hanford Site  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption byAbout Printable VersionProtective ActionsWasteSampling and

198

Proposed rulemaking on the storage and disposal of nuclear waste. Cross-statement of the United States Department of Energy  

SciTech Connect (OSTI)

The US DOE cross-statement in the matter of proposed rulemaking in the storage and disposal of nuclear wastes is presented. It is concluded from evidence contained in the document that: (1) spent fuel can be disposed of in a manner that is safe and environmentally acceptable; (2) present plans for establishing geological repositories are an effective and reasonable means of disposal; (3) spent nuclear fuel from licensed facilities can be stored in a safe and environmentally acceptable manner on-site or off-site until disposal facilities are ready; (4) sufficient additional storage capacity for spent fuel will be established; and (5) the disposal and interim storage systems for spent nuclear fuel will be integrated into an acceptable operating system. It was recommended that the commission should promulgate a rule providing that the safety and environmental implications of spent nuclear fuel remaining on site after the anticipated expiration of the facility licenses involved need not be considered in individual facility licensing proceedings. A prompt finding of confidence in the nuclear waste disposal and storage area by the commission is also recommeded. (DMC)

None

1980-09-05T23:59:59.000Z

199

US Department of Energy Storage of Spent Fuel and High Level Waste  

SciTech Connect (OSTI)

ABSTRACT This paper provides an overview of the Department of Energy's (DOE) spent nuclear fuel (SNF) and high level waste (HLW) storage management. Like commercial reactor fuel, DOE's SNF and HLW were destined for the Yucca Mountain repository. In March 2010, the DOE filed a motion with the Nuclear Regulatory Commission (NRC) to withdraw the license application for the repository at Yucca Mountain. A new repository is now decades away. The default for the commercial and DOE research reactor fuel and HLW is on-site storage for the foreseeable future. Though the motion to withdraw the license application and delay opening of a repository signals extended storage, DOE's immediate plans for management of its SNF and HLW remain the same as before Yucca Mountain was designated as the repository, though it has expanded its research and development efforts to ensure safe extended storage. This paper outlines some of the proposed research that DOE is conducting and will use to enhance its storage systems and facilities.

Sandra M Birk

2010-10-01T23:59:59.000Z

200

Materials evaluation programs at the Defense Waste Processing Facility  

SciTech Connect (OSTI)

The Savannah River Site (SRS) has been operating a nuclear fuel cycle since the 1950s to produce nuclear materials in support of the national defense effort. About 83 million gallons of high-level waste produced since operations began has been consolidated by evaporation into 33 million gallons at the waste tank farm. The Department of Energy authorized the construction of the Defense Waste Processing Facility (DWPF), the function of which is to immobilize the waste as a durable borosilicate glass contained in stainless steel canisters prior to the placement of the canisters in a federal repository. The DWPF is now mechanically complete and is undergoing commissioning and run-in activities. A brief description of the DWPF process is provided.

Gee, J.T.; Iverson, D.C.; Bickford, D.F.

1992-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Materials evaluation programs at the Defense Waste Processing Facility  

SciTech Connect (OSTI)

The Savannah River Site (SRS) has been operating a nuclear fuel cycle since the 1950s to produce nuclear materials in support of the national defense effort. About 83 million gallons of high-level waste produced since operations began has been consolidated by evaporation into 33 million gallons at the waste tank farm. The Department of Energy authorized the construction of the Defense Waste Processing Facility (DWPF), the function of which is to immobilize the waste as a durable borosilicate glass contained in stainless steel canisters prior to the placement of the canisters in a federal repository. The DWPF is now mechanically complete and is undergoing commissioning and run-in activities. A brief description of the DWPF process is provided.

Gee, J.T.; Iverson, D.C.; Bickford, D.F.

1992-12-31T23:59:59.000Z

202

Waste to energy facilities. (Latest citations from the NTIS database). Published Search  

SciTech Connect (OSTI)

The bibliography contains citations concerning technical, economic, and environmental evaluations of facilities that convert waste to energy. Solid waste and municipal waste conversion facilities are highlighted. Feasibility studies, technical design, emissions studies, and markets for the resulting energy are discussed. Heat and electrical generation facilities are emphasized. (Contains 250 citations and includes a subject term index and title list.)

Not Available

1993-05-01T23:59:59.000Z

203

Waste to energy facilities. (Latest citations from the NTIS bibliographic database). Published Search  

SciTech Connect (OSTI)

The bibliography contains citations concerning technical, economic, and environmental evaluations of facilities that convert waste to energy. Solid waste and municipal waste conversion facilities are highlighted. Feasibility studies, technical design, emissions studies, and markets for the resulting energy are discussed. Heat and electrical generation facilities are emphasized. (Contains 250 citations and includes a subject term index and title list.)

Not Available

1994-04-01T23:59:59.000Z

204

Waste to energy facilities. (Latest citations from the NTIS bibliographic database). Published Search  

SciTech Connect (OSTI)

The bibliography contains citations concerning technical, economic, and environmental evaluations of facilities that convert waste to energy. Solid waste and municipal waste conversion facilities are highlighted. Feasibility studies, technical design, emissions studies, and markets for the resulting energy are discussed. Heat and electrical generation facilities are emphasized. (Contains 250 citations and includes a subject term index and title list.)

NONE

1995-01-01T23:59:59.000Z

205

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

SciTech Connect (OSTI)

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

Not Available

1994-02-01T23:59:59.000Z

206

Assessing the Feasibility of Interrogating Nuclear Waste Storage Silos using Cosmic-ray Muons  

E-Print Network [OSTI]

Muon radiography is a fast growing field in applied scientific research. In recent years, many detector technologies and imaging techniques using the Coulomb scattering and absorption properties of cosmic-ray muons have been developed for the non-destructive assay of various structures across a wide range of applications. This work presents the first results that assess the feasibility of using muons to interrogate waste silos within the UK Nuclear Industry. Two such approaches, using different techniques that exploit each of these properties, have previously been published, and show promising results from both simulation and experimental data for the detection of shielded high-Z materials and density variations from volcanic assay. Both detector systems are based on scintillator and photomultiplier technologies. Results from dedicated simulation studies using both these technologies and image reconstruction techniques are presented for an intermediate-sized nuclear waste storage facility filled with concrete...

Ambrosino, F; Cimmino, L; D'Alessandro, R; Ireland, D G; Kaiser, R; Mahon, D F; Mori, N; Noli, P; Saracino, G; Shearer, C; Viliani, L; Yang, G

2014-01-01T23:59:59.000Z

207

EA-0995: Drum Storage Facility for Interim Storage of Materials Generated by Environmental Restoration Operations, Golden, Colorado  

Broader source: Energy.gov [DOE]

This EA evaluates the environmental impacts of the proposal to construct and operate a drum storage facility at the U.S. Department of Energy's Rocky Flats Environmental Technology Site in Golden,...

208

Nevada Nuclear-Waste-Storage Investigations. Quarterly report, April-June 1982  

SciTech Connect (OSTI)

The Nevada Nuclear Waste Storage Investigations (NNWSI) are studying the Nevada Test Site (NTS) area to establish whether it would qualify as a licensable location for a commercial nuclear waste repository; determining whether specific underground rock masses in the NTS area are technically acceptable for permanently disposing of highly radioactive solid wastes; and developing and demonstrating the capability to safely handle and store commercial spent reactor fuel and high-level waste. Progress reports for the following eight tasks are presented: systems; waste package; site; repository; regulatory and institutional; test facilities; land acquisition; and program management. Some of the highlights are: A code library was established to provide a central location for documentation of repository performance assessment codes. A two-dimensional finite element code, SAGUARO, was developed for modeling saturated/unsaturated groundwater flow. The results of an initial experiment to determine canister penetration rates due to corrosion indicate the expected strong effect of toxic environmental conditions on the corrosion rate of carbon steel in tuff-conditioned water. Wells USW-H3 and USW-H4 at Yucca Mountain have been sampled for groundwater analysis. A summary characterizing and relating the mineralogy and petrology of Yucca Mountain tuffs was compiled from the findings of studies of core samples from five drill holes.

None

1982-09-01T23:59:59.000Z

209

RCRA, superfund and EPCRA hotline training module. Introduction to: RCRA treatment, storage, and disposal facilities (40 cfr parts 264/265, subparts a-e) updated July 1996  

SciTech Connect (OSTI)

The management of hazardous waste at treatment, storage, and disposal facilities (TSDFs) plays a large and critical role in the Resource Conservation and Recovery Act (RCRA) regulatory scheme. The training module presents an overview of the general TSDF standards found in 40 CFR Parts 264/265, Subparts A through E.

NONE

1996-07-01T23:59:59.000Z

210

Overview of hazardous-waste regulation at federal facilities  

SciTech Connect (OSTI)

This report is organized in a fashion that is intended to explain the legal duties imposed on officials responsible for hazardous waste at each stage of its existence. Section 2 describes federal hazardous waste laws, explaining the legal meaning of hazardous waste and the protective measures that are required to be taken by its generators, transporters, and storers. In addition, penalties for violation of the standards are summarized, and a special discussion is presented of so-called imminent hazard provisions for handling hazardous waste that immediately threatens public health and safety. Although the focus of Sec. 2 is on RCRA, which is the principal federal law regulating hazardous waste, other federal statutes are discussed as appropriate. Section 3 covers state regulation of hazardous waste. First, Sec. 3 explains the system of state enforcement of the federal RCRA requirements on hazardous waste within their borders. Second, Sec. 3 discusses two peculiar provisions of RCRA that appear to permit states to regulate federal facilities more strictly than RCRA otherwise would require.

Tanzman, E.; LaBrie, B.; Lerner, K.

1982-05-01T23:59:59.000Z

211

WIPP Remote Handled Waste Facility: Performance Dry Run Operations  

SciTech Connect (OSTI)

The Remote Handled (RH) TRU Waste Handling Facility at the Waste Isolation Pilot Plant (WIPP) was recently upgraded and modified in preparation for handling and disposal of RH Transuranic (TRU) waste. This modification will allow processing of RH-TRU waste arriving at the WIPP site in two different types of shielded road casks, the RH-TRU 72B and the CNS 10-160B. Washington TRU Solutions (WTS), the WIPP Management and Operation Contractor (MOC), conducted a performance dry run (PDR), beginning August 19, 2002 and successfully completed it on August 24, 2002. The PDR demonstrated that the RHTRU waste handling system works as designed and demonstrated the handling process for each cask, including underground disposal. The purpose of the PDR was to develop and implement a plan that would define in general terms how the WIPP RH-TRU waste handling process would be conducted and evaluated. The PDR demonstrated WIPP operations and support activities required to dispose of RH-TRU waste in the WIPP underground.

Burrington, T. P.; Britain, R. M.; Cassingham, S. T.

2003-02-24T23:59:59.000Z

212

Solid Waste Operations Complex W-113, Detail Design Report (Title II). Volume 2: Solid waste retrieval facilities -- Phase 1, detail design drawings  

SciTech Connect (OSTI)

The Solid Waste Retrieval Facility--Phase 1 (Project W113) will provide the infrastructure and the facility required to retrieve from Trench 04, Burial ground 4C, contact handled (CH) drums and boxes at a rate that supports all retrieved TRU waste batching, treatment, storage, and disposal plans. This includes (1) operations related equipment and facilities, viz., a weather enclosure for the trench, retrieval equipment, weighing, venting, obtaining gas samples, overpacking, NDE, NDA, shipment of waste and (2) operations support related facilities, viz., a general office building, a retrieval staff change facility, and infrastructure upgrades such as supply and routing of water, sewer, electrical power, fire protection, roads, and telecommunication. Title I design for the operations related equipment and facilities was performed by Raytheon/BNFL, and that for the operations support related facilities including infrastructure upgrade was performed by KEH. These two scopes were combined into an integrated W113 Title II scope that was performed by Raytheon/BNFL. Volume 2 provides the complete set of the Detail Design drawings along with a listing of the drawings. Once approved by WHC, these drawings will be issued and baselined for the Title 3 construction effort.

NONE

1995-09-01T23:59:59.000Z

213

Environmental assessment, finding of no significant impact, and response to comments. Radioactive waste storage  

SciTech Connect (OSTI)

The Department of Energy`s (DOE) Rocky Flats Environmental Technology Site (the Site), formerly known as the Rocky Flats Plant, has generated radioactive, hazardous, and mixed waste (waste with both radioactive and hazardous constituents) since it began operations in 1952. Such wastes were the byproducts of the Site`s original mission to produce nuclear weapons components. Since 1989, when weapons component production ceased, waste has been generated as a result of the Site`s new mission of environmental restoration and deactivation, decontamination and decommissioning (D&D) of buildings. It is anticipated that the existing onsite waste storage capacity, which meets the criteria for low-level waste (LL), low-level mixed waste (LLM), transuranic (TRU) waste, and TRU mixed waste (TRUM) would be completely filled in early 1997. At that time, either waste generating activities must cease, waste must be shipped offsite, or new waste storage capacity must be developed.

NONE

1996-04-01T23:59:59.000Z

214

Waste immobilization demonstration program for the Hanford Site`s Mixed Waste Facility  

SciTech Connect (OSTI)

This paper presents an overview of the Waste Receiving and Processing facility, Module 2A> waste immobilization demonstration program, focusing on the cooperation between Hanford Site, commercial, and international participants. Important highlights of the development and demonstration activities is discussed from the standpoint of findings that have had significant from the standpoint of findings that have had significant impact on the evolution of the facility design. A brief description of the future direction of the program is presented, with emphasis on the key aspects of the technologies that call for further detailed investigation.

Burbank, D.A.; Weingardt, K.M.

1994-05-01T23:59:59.000Z

215

SECONDARY WASTE/ETF (EFFLUENT TREATMENT FACILITY) PRELIMINARY PRE-CONCEPTUAL ENGINEERING STUDY  

SciTech Connect (OSTI)

This pre-conceptual engineering study is intended to assist in supporting the critical decision (CD) 0 milestone by providing a basis for the justification of mission need (JMN) for the handling and disposal of liquid effluents. The ETF baseline strategy, to accommodate (WTP) requirements, calls for a solidification treatment unit (STU) to be added to the ETF to provide the needed additional processing capability. This STU is to process the ETF evaporator concentrate into a cement-based waste form. The cementitious waste will be cast into blocks for curing, storage, and disposal. Tis pre-conceptual engineering study explores this baseline strategy, in addition to other potential alternatives, for meeting the ETF future mission needs. Within each reviewed case study, a technical and facility description is outlined, along with a preliminary cost analysis and the associated risks and benefits.

MAY TH; GEHNER PD; STEGEN GARY; HYMAS JAY; PAJUNEN AL; SEXTON RICH; RAMSEY AMY

2009-12-28T23:59:59.000Z

216

Mixed Waste Management Facility groundwater monitoring report, First quarter 1994  

SciTech Connect (OSTI)

During first quarter 1994, nine constituents exceeded final Primary Drinking Water Standards in groundwater samples from downgradient monitoring wells at the Mixed Waste Management Facility, the Old Burial Ground, the E-Area Vaults, the proposed Hazardous Waste/Mixed Waste Disposal Vaults, and the F-Area Sewage Sludge Application Site. As in previous quarters, tritium and trichloroethylene were the most widespread elevated constituents. Chloroethene (vinyl chloride), copper, 1,1-dichloroethylene, lead, mercury, nonvolatile beta, or tetrachloroethylene also exceeded standards in one or more wells. Elevated constituents were found in numerous Aquifer Zone IIB{sub 2} (Water Table) and Aquifer Zone IIB{sub 1}, (Barnwell/McBean) wells and in one Aquifer Unit IIA (Congaree) well. The groundwater flow directions and rates in the three hydrostratigraphic units were similar to those of previous quarters.

Not Available

1994-06-01T23:59:59.000Z

217

Mixed and low-level waste treatment facility project  

SciTech Connect (OSTI)

The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies.

Not Available

1992-04-01T23:59:59.000Z

218

High efficiency waste to energy facility -- Pilot plant design  

SciTech Connect (OSTI)

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

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

1998-07-01T23:59:59.000Z

219

WIPP Facility Work Plan for Solid Waste Management Units  

SciTech Connect (OSTI)

This 2002 Facility Work Plan (FWP) has been prepared as required by Module VII, Permit Condition VII.U.3 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit) (New Mexico Environment Department [NMED], 1999a), and incorporates comments from the NMED received on December 6, 2000 (NMED, 2000a). This February 2002 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMU) and Areas of Concern (AOC) specified in the Permit. The Permittees are evaluating data from previous investigations of the SWMUs and AOCs against the most recent guidance proposed by the NMED. Based on these data, and completion of the August 2001 sampling requested by the NMED, the Permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a facility to exit the schedule of compliance contained in the facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA processcan be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit. The NMED accepted that the Permittees are using the ACAA in a letter dated April 20, 2000.

Washington TRU Solutions LLC

2002-02-14T23:59:59.000Z

220

WIPP Facility Work Plan for Solid Waste Management Units  

SciTech Connect (OSTI)

This Facility Work Plan (FWP) has been prepared as required by Module VII,Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a). This work plan describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current New Mexico Environment Department (NMED) guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility’s Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to NMED’s guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit. The scope of work for the RFI Work Plan or SAP is being developed by the Permittees. The final content of the RFI Work Plan or SAP will be coordinated with the NMED for submittal on May 24, 2000. Specific project-related planning information will be included in the RFI Work Plan or SAP. The SWMU program at WIPP began in 1994 under U.S. Environmental Protection Agency (EPA) regulatory authority. NMED subsequently received regulatory authority from EPA. A Phase I RFI was completed at WIPP as part of a Voluntary Release Assessment (VRA). The risk-based decision criteria recommended by EPA for the VRA were contained in a proposed Corrective Action rule for SWMUs (EPA, 1990). EPA Region VI has issued new risk-based screening criteria applicable to the WIPP SWMUs and AOCs.

Washington TRU Solutions LLC

2000-02-25T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

REVIEW OF FAST FLUX TEST FACILITY (FFTF) FUEL EXPERIMENTS FOR STORAGE IN INTERIM STORAGE CASKS (ISC)  

SciTech Connect (OSTI)

Appendix H, Section H.3.3.10.11 of the Final Safety Analysis Report (FSAR), provides the limits to be observed for fueled components authorized for storage in the Fast Flux Test Facility (FFTF) spent fuel storage system. Currently, the authorization basis allows standard driver fuel assemblies (DFA), as described in the FSAR Chapter 17, Section 17.5.3.1, to be stored provided decay power per assembly is {le} 250 watts, post-irradiation time is four years minimum, average assembly burn-up is 150,000 MWD/MTHM maximum and the pre-irradiation enrichment is 29.3% maximum (per H.3.3.10.11). In addition, driver evaluation (DE), core characterizer assemblies (CCA), and run-to-cladding-breach (RTCB) assemblies are included based on their similarities to a standard DFA. Ident-69 pin containers with fuel pins from these DFAs can also be stored. Section H.3.3.10.11 states that fuel types outside the specification criteria above will be addressed on a case-by-case basis. There are many different types of fuel and blanket experiments that were irradiated in the FFTF which now require offload to the spent fuel storage system. Two reviews were completed for a portion of these special type fuel components to determine if placement into the Core Component Container (CCC)/Interim Storage Cask (ISC) would require any special considerations or changes to the authorization basis. Project mission priorities coupled with availability of resources and analysts prevented these evaluations from being completed as a single effort. Areas of review have included radiological accident release consequences, radiological shielding adequacy, criticality safety, thermal limits, confinement, and stress. The results of these reviews are available in WHC-SD-FF-RPT-005, Rev. 0 and 1, ''Review of FFTF Fuel Experiments for Storage at ISA'', (Reference I), which subsequently allowed a large portion of these components to be included in the authorization basis (Table H.3.3-21). The report also identified additional components and actions in Section 3.0 and Table 3 that require further evaluation. The purpose of this report is to evaluate another portion of the remaining inventory (i.e., delayed neutron signal fuel, blanket assemblies, highly enriched assemblies, newly loaded Ident-69 pin containers, and returned fuel) to ensure it can be safely off loaded to the FFTF spent fuel storage system.

CHASTAIN, S.A.

2005-10-24T23:59:59.000Z

222

Oil field waste disposal costs at commercial disposal facilities  

SciTech Connect (OSTI)

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

Veil, J.A.

1997-10-01T23:59:59.000Z

223

Measurement of Atmospheric Sea Salt Concentration in the Dry Storage Facility of the Spent Nuclear Fuel  

SciTech Connect (OSTI)

Spent nuclear fuel coming from a Japanese nuclear power plant is stored in the interim storage facility before reprocessing. There are two types of the storage methods which are wet and dry type. In Japan, it is anticipated that the dry storage facility will increase compared with the wet type facility. The dry interim storage facility using the metal cask has been operated in Japan. In another dry storage technology, there is a concrete overpack. Especially in USA, a lot of concrete overpacks are used for the dry interim storage. In Japan, for the concrete cask, the codes of the Japan Society of Mechanical Engineers and the governmental technical guidelines are prepared for the realization of the interim storage as well as the code for the metal cask. But the interim storage using the concrete overpack has not been in progress because the evaluation on the stress corrosion cracking (SCC) of the canister is not sufficient. Japanese interim storage facilities would be constructed near the seashore. The metal casks and concrete overpacks are stored in the storage building in Japan. On the other hand, in USA they are stored outside. It is necessary to remove the decay heat of the spent nuclear fuel in the cask from the storage building. Generally, the heat is removed by natural cooling in the dry storage facility. Air including the sea salt particles goes into the dry storage facility. Concerning the concrete overpack, air goes into the cask body and cools the canister. Air goes along the canister surface and is in contact with the surface directly. In this case, the sea salt in the air attaches to the surface and then there is the concern about the occurrence of the SCC. For the concrete overpack, the canister including the spent fuel is sealed by the welding. The loss of sealability caused by the SCC has to be avoided. To evaluate the SCC for the canister, it is necessary to make clear the amount of the sea salt particles coming into the storage building and the concentration on the canister. In present, the evaluation on that point is not sufficient. In this study, the concentration of the sea salt particles in the air and on the surface of the storage facility are measured inside and outside of the building. For the measurement, two sites of the dry storage facility using the metal cask are chosen. This data is applicable for the evaluation on the SCC of the canister to realize the interim storage using the concrete overpack. (authors)

Masumi Wataru; Hisashi Kato; Satoshi Kudo; Naoko Oshima; Koji Wada [Central Research Institute of Electric Power Industry - CRIEPI (Japan); Hirofumi Narutaki [Electric Power Engineering Systems Co. Ltd. (Japan)

2006-07-01T23:59:59.000Z

224

Identifying suitable "piercement" salt domes for nuclear waste storage sites  

SciTech Connect (OSTI)

Piercement salt domes of the northern interior salt basins of the Gulf of Mexico are being considered as permanent storage sites for both nuclear and chemically toxic wastes. The suitable domes are stable and inactive, having reached their final evolutionary configuration at least 30 million years ago. They are buried to depths far below the level to which erosion will penetrate during the prescribed storage period and are not subject to possible future reactivation. The salt cores of these domes are themselves impermeable, permitting neither the entry nor exit of ground water or other unwanted materials. In part, a stable dome may be recognized by its present geometric configuration, but conclusive proof depends on establishing its evolutionary state. The evolutionary state of a dome is obtained by reconstructing the growth history of the dome as revealed by the configuration of sedimentary strata in a large area (commonly 3,000 square miles or more) surrounding the dome. A high quality, multifold CDP reflection seismic profile across a candidate dome will provide much of the necessary information when integrated with available subsurface control. Additional seismic profiles may be required to confirm an apparent configuration of the surrounding strata and an interpreted evolutionary history. High frequency seismic data collected in the near vicinity of a dome are also needed as a supplement to the CDP data to permit accurate depiction of the configuration of shallow strata. Such data must be tied to shallow drill hole control to confirm the geologic age at which dome growth ceased. If it is determined that a dome reached a terminal configuration many millions of years ago, such a dome is incapable of reactivation and thus constitutes a stable storage site for nuclear wastes.

Kehle, R.

1980-08-01T23:59:59.000Z

225

Waste characterization for the F/H Effluent Treatment Facility in support of waste certification  

SciTech Connect (OSTI)

The Waste Acceptance Criteria (WAC) procedures define the rules concerning packages of solid Low Level Waste (LLW) that are sent to the E-area vaults (EAV). The WACs tabulate the quantities of 22 radionuclides that require manifesting in waste packages destined for each type of vault. These quantities are called the Package Administrative Criteria (PAC). If a waste package exceeds the PAC for any radionuclide in a given vault, then specific permission is needed to send to that vault. To avoid reporting insignificant quantities of the 22 listed radionuclides, the WAC defines the Minimum Reportable Quantity (MRQ) of each radionuclide as 1/1000th of the PAC. If a waste package contains less than the MRQ of a particular radionuclide, then the package`s manifest will list that radionuclide as zero. At least one radionuclide has to be reported, even if all are below the MRQ. The WAC requires that the waste no be ``hazardous`` as defined by SCDHEC/EPA regulations and also lists several miscellaneous physical/chemical requirements for the packages. This report evaluates the solid wastes generated within the F/H Effluent Treatment Facility (ETF) for potential impacts on waste certification.

Brown, D.F.

1994-10-17T23:59:59.000Z

226

Research and Education Campus Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect (OSTI)

U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory Research and Education Campus facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool to develop the radioactive waste management basis.

L. Harvego; Brion Bennett

2011-11-01T23:59:59.000Z

227

Materials and Security Consolidation Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect (OSTI)

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Security Consolidation Center facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Not Listed

2011-09-01T23:59:59.000Z

228

Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect (OSTI)

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-09-01T23:59:59.000Z

229

Life-cycle cost analysis 200-West Weather Enclosure: Multi-function Waste Tank Facility  

SciTech Connect (OSTI)

The Multi-Function Waste Tank Facility (MWTF)will provide environmentally safe and acceptable storage capacity for handling wastes resulting from the remediation of existing single-shell and double-shell tanks on the Hanford Site. The MWTF will construct two tank farm facilities at two separate locations. A four-tank complex will be constructed in the 200-East Area of the Hanford Site; a two-tank complex will be constructed in the 200-West Area. This report documents the results of a life-cycle cost analysis performed by ICF Kaiser Hanford Company (ICF KH) for the Weather Enclosure proposed to be constructed over the 200-West tanks. Currently, all tank farm operations on the Hanford Site are conducted in an open environment, with weather often affecting tank farm maintenance activities. The Weather Enclosure is being proposed to allow year-round tank farm operation and maintenance activities unconstrained by weather conditions. Elimination of weather-related delays at the MWTF and associated facilities will reduce operational costs. The life-cycle cost analysis contained in this report analyzes potential cost savings based on historical weather information, operational and maintenance costs, construction cost estimates, and other various assumptions.

Umphrey, M.R. [Westinghouse Hanford Co., Richland, WA (United States)

1995-01-16T23:59:59.000Z

230

Final report on the public involvement process phase 1, Monitored Retrievable Storage Facility Feasibility Study  

SciTech Connect (OSTI)

This report summarizes the pubic involvement component of Phase 1 of the Monitored Retrievable Storage Facility (NM) Feasibility Study in San Juan County, Utah. Part of this summary includes background information on the federal effort to locate a voluntary site for temporary storage of nuclear waste, how San Juan County came to be involved, and a profile of the county. The heart of the report, however, summarizes the activities within the public involvement process, and the issues raised in those various forums. The authors have made every effort to reflect accurately and thoroughly all the concerns and suggestions expressed to us during the five month process. We hope that this report itself is a successful model of partnership with the citizens of the county -- the same kind of partnership the county is seeking to develop with its constituents. Finally, this report offers some suggestions to both county officials and residents alike. These suggestions concern how decision-making about the county's future can be done by a partnership of informed citizens and listening decision-makers. In the Appendix are materials relating to the public involvement process in San Juan County.

Moore, L.; Shanteau, C.

1992-12-01T23:59:59.000Z

231

Final report on the public involvement process phase 1, Monitored Retrievable Storage Facility Feasibility Study  

SciTech Connect (OSTI)

This report summarizes the pubic involvement component of Phase 1 of the Monitored Retrievable Storage Facility (NM) Feasibility Study in San Juan County, Utah. Part of this summary includes background information on the federal effort to locate a voluntary site for temporary storage of nuclear waste, how San Juan County came to be involved, and a profile of the county. The heart of the report, however, summarizes the activities within the public involvement process, and the issues raised in those various forums. The authors have made every effort to reflect accurately and thoroughly all the concerns and suggestions expressed to us during the five month process. We hope that this report itself is a successful model of partnership with the citizens of the county -- the same kind of partnership the county is seeking to develop with its constituents. Finally, this report offers some suggestions to both county officials and residents alike. These suggestions concern how decision-making about the county`s future can be done by a partnership of informed citizens and listening decision-makers. In the Appendix are materials relating to the public involvement process in San Juan County.

Moore, L.; Shanteau, C.

1992-12-01T23:59:59.000Z

232

TRU waste certification compliance requirements for acceptance of contact-handled wastes retrieved from storage to be shipped to the WIPP. Revision 1  

SciTech Connect (OSTI)

Compliance requirements are presented for certifying that unclassified, contact-handled (CH) transuranic (TRU) solid defense wastes retrieved from storage at DOE sites meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). All applicable DOE orders must continue to be met. The compliance requirements for certified waste retrieved from certified storage are addressed in another document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste. 2 refs., 1 fig.

Not Available

1985-09-01T23:59:59.000Z

233

Environmental Restoration and Waste Management Site-Specific Plan for the Oak Ridge Reservation. [Appendix contains accromyms list and maps of waste management facilities  

SciTech Connect (OSTI)

The United States Department of Energy (DOE) is committed to achieving and maintaining environmental regulatory compliance at its waste sites and facilities, while responding to public concerns and emphasizing waste minimization. DOE publishes the Environmental Restoration and Waste Management Five-Year Plan (FYP) annually to document its progress towards these goals. The purpose of this Site-Specific Plan (SSP) is to describe the activities, planned and completed, undertaken to implement these FYP goals at the DOE Field Office-Oak Ridge (DOE/OR) installations and programs; specifically, for the Oak Ridge Reservation (ORR), Oak Ridge Associated Universities (ORAU), and Hazardous Waste Remedial Action Program (HAZWRAP). Activities described in this SSP address hazardous, radioactive, mixed, and sanitary wastes, along with treatment, storage, and disposal of current production waste and legacy waste from past operation. The SSP is presented in sections emphasizing Corrective Activities (A), Environmental Restoration (ER), Waste Management (WM), Technology Development (TD), and Transportation; and includes descriptions of activities, resources, and milestones by installation or program. 87 tabs.

Not Available

1991-09-01T23:59:59.000Z

234

Waste Management facilities fault tree databank 1995 status report  

SciTech Connect (OSTI)

The Safety Information Management and Analysis Group (SIMA) of the Safety Engineering Department (SED) maintains compilations of incidents that have occurred in the Separations and Process Control, Waste Management, Fuel Fabrication, Tritium and SRTC facilities. This report records the status of the Waste Management (WM) Databank at the end of CY-1994. The WM Databank contains more than 35,000 entries ranging from minor equipment malfunctions to incidents with significant potential for injury or contamination of personnel. This report documents the status of the WM Databank including the availability, training, sources of data, search options, Quality Assurance, and usage to which these data have been applied. Periodic updates to this memorandum are planned as additional data or applications are acquired.

Minnick, W.V.; Wellmaker, K.A.

1995-08-16T23:59:59.000Z

235

Criticality Safety Evaluation of Hanford Site High Level Waste Storage Tanks  

SciTech Connect (OSTI)

This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions.

ROGERS, C.A.

2000-02-17T23:59:59.000Z

236

Soil load above Hanford waste storage tanks (2 volumes)  

SciTech Connect (OSTI)

This document is a compilation of work performed as part of the Dome Load Control Project in 1994. Section 2 contains the calculations of the weight of the soil over the tank dome for each of the 75-feet-diameter waste-storage tanks located at the Hanford Site. The chosen soil specific weight and soil depth measured at the apex of the dome crown are the same as those used in the primary analysis that qualified the design. Section 3 provides reference dimensions for each of the tank farm sites. The reference dimensions spatially orient the tanks and provide an outer diameter for each tank. Section 4 summarizes the available soil surface elevation data. It also provides examples of the calculations performed to establish the present soil elevation estimates. The survey data and other data sources from which the elevation data has been obtained are printed separately in Volume 2 of this Supporting Document. Section 5 contains tables that provide an overall summary of the present status of dome loads. Tables summarizing the load state corresponding to the soil depth and soil specific weight for the original qualification analysis, the gravity load requalification for soil depth and soil specific weight greater than the expected actual values, and a best estimate condition of soil depth and specific weight are presented for the Double-Shell Tanks. For the Single-Shell Tanks, only the original qualification analysis is available; thus, the tabulated results are for this case only. Section 6 provides a brief overview of past analysis and testing results that given an indication of the load capacity of the waste storage tanks that corresponds to a condition approaching ultimate failure of the tank. 31 refs.

Pianka, E.W. [Advent Engineering Services, Inc., San Ramon, CA (United States)

1995-01-25T23:59:59.000Z

237

Waste Sampling and Characterization Facility (WSCF). Maintenance Implementation Plan  

SciTech Connect (OSTI)

This Maintenance Implementation Plan has been developed for maintenance functions associated with the Waste Sampling and Characterization Facility (WSCF). This plan is developed from the guidelines presented by Department of Energy (DOE) Order 4330.4A, Maintenance Management Program (DOE 1990), Chapter II. The objective of this plan is to provide baseline information for establishing and identifying WHC conformance programs and policies applicable to implementation of DOE order 4330.4A guidelines. In addition, this maintenance plan identifies the actions necessary to develop a cost-effective and efficient maintenance program at WSCF.

Bozich, J.L.

1993-07-01T23:59:59.000Z

238

Idaho Waste Treatment Facility Startup Testing Suspended To Evaluate System  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun withconfinementEtching. | EMSLtheIndustry |MentoringFacilityIdaho Waste

239

Low-Level Waste Disposal Facility Federal Review Group Manual  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG | DepartmentEnergy InvitationLegaltoLizLow- LEVEL WASTE DISPOSAL FACILITY

240

Design and construction of the defense waste processing facility project at the Savannah River Plant  

SciTech Connect (OSTI)

The Du Pont Company is building for the Department of Energy a facility to vitrify high-level radioactive waste at the Savannah River Plant (SRP) near Aiken, South Carolina. The Defense Waste Processing Facility (DWPF) will solidify existing and future radioactive wastes by immobilizing the waste in Processing Facility (DWPF) will solidify existing and future radioactives wastes by immobilizing the waste in borosilicate glass contained in stainless steel canisters. The canisters will be sealed, decontaminated and stored, prior to emplacement in a federal repository. At the present time, engineering and design is 90% complete, construction is 25% complete, and radioactive processing in the $870 million facility is expected to begin by late 1989. This paper describes the SRP waste characteristics, the DWPF processing, building and equipment features, and construction progress of the facility.

Baxter, R G

1986-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Criticality Safety Evaluations on the Use of 200-gram Pu Mass Limit for RHWM Waste Storage Operations  

SciTech Connect (OSTI)

This work establishes the criticality safety technical basis to increase the fissile mass limit from 120 grams to 200 grams for Type A 55-gallon drums and their equivalents. Current RHWM fissile mass limit is 120 grams Pu for Type A 55-gallon containers and their equivalent. In order to increase the Type A 55-gallon drum limit to 200 grams, a few additional criticality safety control requirements are needed on moderators, reflectors, and array controls to ensure that the 200-gram Pu drums remain criticality safe with inadvertent criticality remains incredible. The purpose of this work is to analyze the use of 200-gram Pu drum mass limit for waste storage operations in Radioactive and Hazardous Waste Management (RHWM) Facilities. In this evaluation, the criticality safety controls associated with the 200-gram Pu drums are established for the RHWM waste storage operations. With the implementation of these criticality safety controls, the 200-gram Pu waste drum storage operations are demonstrated to be criticality safe and meet the double-contingency-principle requirement per DOE O 420.1.

Chou, P

2011-12-14T23:59:59.000Z

242

Guidelines for development of structural integrity programs for DOE high-level waste storage tanks  

SciTech Connect (OSTI)

Guidelines are provided for developing programs to promote the structural integrity of high-level waste storage tanks and transfer lines at the facilities of the Department of Energy. Elements of the program plan include a leak-detection system, definition of appropriate loads, collection of data for possible material and geometric changes, assessment of the tank structure, and non-destructive examination. Possible aging degradation mechanisms are explored for both steel and concrete components of the tanks, and evaluated to screen out nonsignificant aging mechanisms and to indicate methods of controlling the significant aging mechanisms. Specific guidelines for assessing structural adequacy will be provided in companion documents. Site-specific structural integrity programs can be developed drawing on the relevant portions of the material in this document.

Bandyopadhyay, K.; Bush, S.; Kassir, M.; Mather, B.; Shewmon, P.; Streicher, M.; Thompson, B.; Rooyen, D. van; Weeks, J.

1997-01-01T23:59:59.000Z

243

Think inside the box : an analysis of converting commercial property into self storage facilities  

E-Print Network [OSTI]

The modern self storage facility is a multi-tenant operating business that reflects the needs of residential and commercial customers. The industry has evolved from a transition asset to a property type that adheres to ...

McKinley, Sean Jeffrey

2006-01-01T23:59:59.000Z

244

Mixed Waste Management Facility Preliminary Safety Analysis Report. Chapters 1 to 20  

SciTech Connect (OSTI)

This document provides information on waste management practices, occupational safety, and a site characterization of the Lawrence Livermore National Laboratory. A facility description, safety engineering analysis, mixed waste processing techniques, and auxiliary support systems are included.

Not Available

1994-09-01T23:59:59.000Z

245

Chemical Waste Guide for Facilities Services UW Environmental Health and Safety  

E-Print Network [OSTI]

CChemmical Fa Was aciliti Au te G ies S ugust uide Servic t 24, 2 for ces 2011 #12;Chemical Waste Guide for Facilities Services UW Environmental Health and Safety Page 2 Chemical Waste Guide ........................................................................................................... 3 Chemical Hazards

Wilcock, William

246

Assessment of degradation concerns for spent fuel, high-level wastes, and transuranic wastes in monitored retrievalbe storage  

SciTech Connect (OSTI)

It has been concluded that there are no significant degradation mechanisms that could prevent the design, construction, and safe operation of monitored retrievable storage (MRS) facilities. However, there are some long-term degradation mechanisms that could affect the ability to maintain or readily retrieve spent fuel (SF), high-level wastes (HLW), and transuranic wastes (TRUW) several decades after emplacement. Although catastrophic failures are not anticipated, long-term degradation mechanisms have been identified that could, under certain conditions, cause failure of the SF cladding and/or failure of TRUW storage containers. Stress rupture limits for Zircaloy-clad SF in MRS range from 300 to 440/sup 0/C, based on limited data. Additional tests on irradiated Zircaloy (3- to 5-year duration) are needed to narrow this uncertainty. Cladding defect sizes could increase in air as a result of fuel density decreases due to oxidation. Oxidation tests (3- to 5-year duration) on SF are also needed to verify oxidation rates in air and to determine temperatures below which monitoring of an inert cover gas would not be required. Few, if any, changes in the physical state of HLW glass or canisters or their performance would occur under projected MRS conditions. The major uncertainty for HLW is in the heat transfer through cracked glass and glass devitrification above 500/sup 0/C. Additional study of TRUW is required. Some fraction of present TRUW containers would probably fail within the first 100 years of MRS, and some TRUW would be highly degraded upon retrieval, even in unfailed containers. One possible solution is the design of a 100-year container. 93 references, 28 figures, 17 tables.

Guenther, R.J.; Gilbert, E.R.; Slate, S.C.; Partain, W.L.; Divine, J.R.; Kreid, D.K.

1984-01-01T23:59:59.000Z

247

Waste to energy facilities. (Latest citations from the NTIS bibliographic database). Published Search  

SciTech Connect (OSTI)

The bibliography contains citations concerning technical, economic, and environmental evaluations of facilities that convert waste to energy. Solid waste and municipal waste conversion facilities are highlighted. Feasibility studies, technical design, emissions studies, and markets for the resulting energy are discussed. Heat and electrical generation facilities are emphasized. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

NONE

1996-04-01T23:59:59.000Z

248

Waste to energy facilities. (Latest citations from the NTIS bibliographic database). Published Search  

SciTech Connect (OSTI)

The bibliography contains citations concerning technical, economic, and environmental evaluations of facilities that convert waste to energy. Solid waste and municipal waste conversion facilities are highlighted. Feasibility studies, technical design, emissions studies, and markets for the resulting energy are discussed. Heat and electrical generation facilities are emphasized. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

NONE

1997-02-01T23:59:59.000Z

249

A Short History of Hanford Waste Generation, Storage, and Release  

SciTech Connect (OSTI)

Nine nuclear reactors and four reprocessing plants at Hanford produced nearly two-thirds of the plutonium used in the United States for government purposes . These site operations also created large volumes of radioactive and chemical waste. Some contaminants were released into the environment, exposing people who lived downwind and downstream. Other contaminants were stored. The last reactor was shut down in 1987, and the last reprocessing plant closed in 1990. Most of the human-made radioactivity and about half of the chemicals remaining onsite are kept in underground tanks and surface facilities. The rest exists in the soil, groundwater, and burial grounds. Hanford contains about 40% of all the radioactivity that exists across the nuclear weapons complex. Today, environmental restoration activities are under way.

Gephart, Roy E.

2003-10-01T23:59:59.000Z

250

Voluntary Protection Program Onsite Review, Waste Sampling and Characterization Facility- May 2007  

Broader source: Energy.gov [DOE]

Evaluation of Waste Sampling and Characterization Facility to make the final decision regarding the company’s continued participation in DOE-VPP as a Star site.

251

Voluntary Protection Program Onsite Review, Salt Waste Processing Facility Construction Project- February 2013  

Broader source: Energy.gov [DOE]

Evaluation to determine whether Salt Waste Processing Facility Construction Project is continuing to perform at a level deserving DOE-VPP Star recognition.

252

EIS-0063: Waste Management Operations, Double-Shell Tanks for Defense High Level Radioactive Waste Storage, Hanford Site, Richland, Washington  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy developed this statement to evaluate the existing tank design and consider additional specific design and safety feature alternatives for the thirteen tanks being constructed for storage of defense high-level radioactive liquid waste at the Hanford Site in Richland, Washington. This statement supplements ERDA-1538, "Final Environmental Statement on Waste Management Operation."

253

SORPTION OF URANIUM, PLUTONIUM AND NEPTUNIUM ONTO SOLIDS PRESENT IN HIGH CAUSTIC NUCLEAR WASTE STORAGE TANKS  

SciTech Connect (OSTI)

Solids such as granular activated carbon, hematite and sodium phosphates, if present as sludge components in nuclear waste storage tanks, have been found to be capable of precipitating/sorbing actinides like plutonium, neptunium and uranium from nuclear waste storage tank supernatant liqueur. Thus, the potential may exists for the accumulation of fissile materials in such nuclear waste storage tanks during lengthy nuclear waste storage and processing. To evaluate the nuclear criticality safety in a typical nuclear waste storage tank, a study was initiated to measure the affinity of granular activated carbon, hematite and anhydrous sodium phosphate to sorb plutonium, neptunium and uranium from alkaline salt solutions. Tests with simulated and actual nuclear waste solutions established the affinity of the solids for plutonium, neptunium and uranium upon contact of the solutions with each of the solids. The removal of plutonium and neptunium from the synthetic salt solution by nuclear waste storage tank solids may be due largely to the presence of the granular activated carbon and transition metal oxides in these storage tank solids or sludge. Granular activated carbon and hematite also showed measurable affinity for both plutonium and neptunium. Sodium phosphate, used here as a reference sorbent for uranium, as expected, exhibited high affinity for uranium and neptunium, but did not show any measurable affinity for plutonium.

Oji, L; Bill Wilmarth, B; David Hobbs, D

2008-05-30T23:59:59.000Z

254

Mercury Reduction and Removal from High Level Waste at the Defense Waste Processing Facility - 12511  

SciTech Connect (OSTI)

The Defense Waste Processing Facility processes legacy nuclear waste generated at the Savannah River Site during production of enriched uranium and plutonium required by the Cold War. The nuclear waste is first treated via a complex sequence of controlled chemical reactions and then vitrified into a borosilicate glass form and poured into stainless steel canisters. Converting the nuclear waste into borosilicate glass is a safe, effective way to reduce the volume of the waste and stabilize the radionuclides. One of the constituents in the nuclear waste is mercury, which is present because it served as a catalyst in the dissolution of uranium-aluminum alloy fuel rods. At high temperatures mercury is corrosive to off-gas equipment, this poses a major challenge to the overall vitrification process in separating mercury from the waste stream prior to feeding the high temperature melter. Mercury is currently removed during the chemical process via formic acid reduction followed by steam stripping, which allows elemental mercury to be evaporated with the water vapor generated during boiling. The vapors are then condensed and sent to a hold tank where mercury coalesces and is recovered in the tank's sump via gravity settling. Next, mercury is transferred from the tank sump to a purification cell where it is washed with water and nitric acid and removed from the facility. Throughout the chemical processing cell, compounds of mercury exist in the sludge, condensate, and off-gas; all of which present unique challenges. Mercury removal from sludge waste being fed to the DWPF melter is required to avoid exhausting it to the environment or any negative impacts to the Melter Off-Gas system. The mercury concentration must be reduced to a level of 0.8 wt% or less before being introduced to the melter. Even though this is being successfully accomplished, the material balances accounting for incoming and collected mercury are not equal. In addition, mercury has not been effectively purified and collected in the Mercury Purification Cell (MPC) since 2008. A significant cleaning campaign aims to bring the MPC back up to facility housekeeping standards. Two significant investigations are being undertaken to restore mercury collection. The SMECT mercury pump has been removed from the tank and will be functionally tested. Also, research is being conducted by the Savannah River National Laboratory to determine the effects of antifoam addition on the behavior of mercury. These path forward items will help us better understand what is occurring in the mercury collection system and ultimately lead to an improved DWPF production rate and mercury recovery rate. (authors)

Behrouzi, Aria [Savannah River Remediation, LLC (United States); Zamecnik, Jack [Savannah River National Laboratory, Aiken, South Carolina, 29808 (United States)

2012-07-01T23:59:59.000Z

255

Mixed and low-level waste treatment facility project. Volume 3, Waste treatment technologies (Draft)  

SciTech Connect (OSTI)

The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies.

Not Available

1992-04-01T23:59:59.000Z

256

Defense Waste Processing Facility wasteform and canister description: Revision 2  

SciTech Connect (OSTI)

This document describes the reference wasteform and canister for the Defense Waste Processing Facility (DWPF). The principal changes include revised feed and glass product compositions, an estimate of glass product characteristics as a function of time after the start of vitrification, and additional data on glass leaching performance. The feed and glass product composition data are identical to that described in the DWPF Basic Data Report, Revision 90/91. The DWPF facility is located at the Savannah River Plant in Aiken, SC, and it is scheduled for construction completion during December 1989. The wasteform is borosilicate glass containing approximately 28 wt % sludge oxides, with the balance consisting of glass-forming chemicals, primarily glass frit. Borosilicate glass was chosen because of its stability toward reaction with potential repository groundwaters, its relatively high ability to incorporate nuclides found in the sludge into the solid matrix, and its reasonably low melting temperature. The glass frit contains approximately 71% SiO/sub 2/, 12% B/sub 2/O/sub 3/, and 10% Na/sub 2/O. Tests to quantify the stability of DWPF waste glass have been performed under a wide variety of conditions, including simulations of potential repository environments. Based on these tests, DWPF waste glass should easily meet repository criteria. The canister is filled with about 3700 lb of glass which occupies 85% of the free canister volume. The filled canister will generate approximately 690 watts when filled with oxides from 5-year-old sludge and precipitate from 15-year-old supernate. The radionuclide activity of the canister is about 233,000 curies, with an estimated radiation level of 5600 rad/hour at the canister surface. 14 figs., 28 tabs.

Baxter, R.G.

1988-12-01T23:59:59.000Z

257

PUREX facility preclosure work plan  

SciTech Connect (OSTI)

This preclosure work plan presents a description of the PUREX Facility, the history of the waste managed, and addresses transition phase activities that position the PUREX Facility into a safe and environmentally secure configuration. For purposes of this documentation, the PUREX Facility does not include the PUREX Storage Tunnels (DOE/RL-90/24). Information concerning solid waste management units is discussed in the Hanford Facility Dangerous Waste Permit Application, General Information Portion (DOE/RL-91-28, Appendix 2D).

Engelmann, R.H.

1997-04-24T23:59:59.000Z

258

TRU (transuranic) waste certification compliance requirements for acceptance of contact-handled wastes retrieved from storage to be shipped to the Waste Isolation Pilot Plant: Revision 2  

SciTech Connect (OSTI)

Compliance requirements are presented for certifying that unclassified, contact-handled (CH) transuranic (TRU) solid defense wastes retrieved from storage at DOE sites meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). All applicable Department of Energy (DOE) orders must continue to be met. The compliance requirements for acceptance of newly generated CH waste to be shipped to the WIPP are addressed in another document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste. 10 refs., 1 fig.

Not Available

1989-01-01T23:59:59.000Z

259

Structural Integrity Program for the 300,000-Gallon Radioactive Liquid Waste Storage Tanks at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect (OSTI)

This report provides a record of the Structural Integrity Program for the 300,000-gal liquid waste storage tanks and associated equipment at the Idaho Nuclear Technology and Engineering Center, as required by U.S. Department of Energy M 435.1-1, “Radioactive Waste Management Manual.” This equipment is known collectively as the Tank Farm Facility. This report is an update, and replaces the previous report by the same title issued April 2003. The conclusion of this report is that the Tank Farm Facility tanks, vaults, and transfer systems that remain in service for storage are structurally adequate, and are expected to remain structurally adequate over the remainder of their planned service life through 2012. Recommendations are provided for continued monitoring of the Tank Farm Facility.

Bryant, Jeffrey W.

2010-08-12T23:59:59.000Z

260

Accident Fault Trees for Defense Waste Processing Facility  

SciTech Connect (OSTI)

The purpose of this report is to document fault tree analyses which have been completed for the Defense Waste Processing Facility (DWPF) safety analysis. Logic models for equipment failures and human error combinations that could lead to flammable gas explosions in various process tanks, or failure of critical support systems were developed for internal initiating events and for earthquakes. These fault trees provide frequency estimates for support systems failures and accidents that could lead to radioactive and hazardous chemical releases both on-site and off-site. Top event frequency results from these fault trees will be used in further APET analyses to calculate accident risk associated with DWPF facility operations. This report lists and explains important underlying assumptions, provides references for failure data sources, and briefly describes the fault tree method used. Specific commitments from DWPF to provide new procedural/administrative controls or system design changes are listed in the ''Facility Commitments'' section. The purpose of the ''Assumptions'' section is to clarify the basis for fault tree modeling, and is not necessarily a list of items required to be protected by Technical Safety Requirements (TSRs).

Sarrack, A.G.

1999-06-22T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Coupled Operation of a Wind Farm and Pumped Storage Facility: Techno-Economic Modelling and Stochastic Optimization  

E-Print Network [OSTI]

Coupled Operation of a Wind Farm and Pumped Storage Facility: Techno-Economic Modelling Operation of a Wind Farm and Pumped Storage Facility: Techno-Economic Modelling and Stochastic Optimization a stochastic programming approach to the techno-economic analysis of a wind farm coupled with a pumped storage

Victoria, University of

262

Preliminary assessment of radiological doses in alternative waste management systems without an MRS facility  

SciTech Connect (OSTI)

This report presents generic analyses of radiological dose impacts of nine hypothetical changes in the operation of a waste management system without a monitored retrievable storage (MRS) facility. The waste management activities examined in this study include those for handling commercial spent fuel at nuclear power reactors and at the surface facilities of a deep geologic repository, and the transportation of spent fuel by rail and truck between the reactors and the repository. In the reference study system, the radiological doses to the public and to the occupational workers are low, about 170 person-rem/1000 metric ton of uranium (MTU) handled with 70% of the fuel transported by rail and 30% by truck. The radiological doses to the public are almost entirely from transportation, whereas the doses to the occupational workers are highest at the reactors and the repository. Operating alternatives examined included using larger transportation casks, marshaling rail cars into multicar dedicated trains, consolidating spent fuel at the reactors, and wet or dry transfer options of spent fuel from dry storage casks. The largest contribution to radiological doses per unit of spent fuel for both the public and occupational workers would result from use of truck transportation casks, which are smaller than rail casks. Thus, reducing the number of shipments by increasing cask sizes and capacities (which also would reduce the number of casks to be handled at the terminals) would reduce the radiological doses in all cases. Consolidating spent fuel at the reactors would reduce the radiological doses to the public but would increase the doses to the occupational workers at the reactors.

Schneider, K.J.; Pelto, P.J.; Daling, P.M.; Lavender, J.C.; Fecht, B.A.

1986-06-01T23:59:59.000Z

263

Engineering evaluation of alternatives for the disposition of Niagara Falls Storage Site, its residues and wastes  

SciTech Connect (OSTI)

The final disposition scenarios selected by DOE for assessment in this document are consistent with those stated in the Notice of Intent to prepare an Environmental Impact Statement (EIS) for the Niagara Falls Storage Site (NFSS) (DOE, 1983d) and the modifications to the alternatives resulting from the public scoping process. The scenarios are: take no action beyond interim remedial measures other than maintenance and surveillance of the NFSS; retain and manage the NFSS as a long-term waste management facility for the wastes and residues on the site; decontaminate, certify, and release the NFSS for other use, with long-term management of the wastes and residues at other DOE sites; and partially decontaminate the NFSS by removal and transport off site of only the more radioactive residues, and upgrade containment of the remaining wastes and residues on site. The objective of this document is to present to DOE the conceptual engineering, occupational radiation exposure, construction schedule, maintenance and surveillance requirements, and cost information relevant to design and implementation of each of the four scenarios. The specific alternatives within each scenario used as the basis for discussion in this document were evaluated on the bases of engineering considerations, technical feasibility, and regulatory requirements. Selected alternatives determined to be acceptable for each of the four final disposition scenarios for the NFSS were approved by DOE to be assessed and costed in this document. These alternatives are also the subject of the EIS for the NFSS currently being prepared by Argonne National Laboratory (ANL). 40 figures, 38 tables.

Not Available

1984-01-01T23:59:59.000Z

264

Site Visit Report, Hanford Waste Encapsulation Storage Facility - January  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartment of Energyof the Americas |DOE FormerEnergy DataPlan Guidance2011 | Department

265

Hazardous Waste Treatment, Storage and Disposal Facilities (TSDF) Guidance  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy Resources Jump to: navigation,Ohio:Greer CountyCorridorPart A Permit Application Jump to: navigation,|

266

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

SciTech Connect (OSTI)

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

Timothy Solack; Carol Mason

2012-03-01T23:59:59.000Z

267

Composite analysis for solid waste storage area 6  

SciTech Connect (OSTI)

The composite analysis (CA) provides an estimate of the potential cumulative impacts to a hypothetical future member of the public from the Solid Waste Storage Area 6 (SWSA 6) disposal operations and all of the other sources of radioactive material in the ground on the ORR that may interact with contamination originating in SWSA 6.The projected annual dose to hypothetical future member of the public from all contributing sources is compared to the primary dose limit of 100 mrem per year and a dose constraint of 30 mrem per year. Consistent with the CA guidance, dose estimates for the first 1000 years after disposal are emphasized for comparison with the primary dose limit and dose constraint.The current land use plan for the ORR is being revised, and may include a reduction in the land currently controlled by DOE on the ORR. The possibility of changes in the land use boundary is considered in the CA as part of the sensitivity and uncertainty analysis of the results, the interpretation of results, and the conclusions.

Lee, D.W.

1997-09-01T23:59:59.000Z

268

PLUTONIUM FINISHING PLANT (PFP) 241-Z LIQUID WASTE TREATMENT FACILITY DEACTIVATION AND DEMOLITION  

SciTech Connect (OSTI)

Fluor Hanford, Inc. (FH) is proud to submit the Plutonium Finishing Plant (PFP) 241-Z liquid Waste Treatment Facility Deactivation and Demolition (D&D) Project for consideration by the Project Management Institute as Project of the Year for 2008. The decommissioning of the 241-Z Facility presented numerous challenges, many of which were unique with in the Department of Energy (DOE) Complex. The majority of the project budget and schedule was allocated for cleaning out five below-grade tank vaults. These highly contaminated, confined spaces also presented significant industrial safety hazards that presented some of the most hazardous work environments on the Hanford Site. The 241-Z D&D Project encompassed diverse tasks: cleaning out and stabilizing five below-grade tank vaults (also called cells), manually size-reducing and removing over three tons of process piping from the vaults, permanently isolating service utilities, removing a large contaminated chemical supply tank, stabilizing and removing plutonium-contaminated ventilation ducts, demolishing three structures to grade, and installing an environmental barrier on the demolition site . All of this work was performed safely, on schedule, and under budget. During the deactivation phase of the project between November 2005 and February 2007, workers entered the highly contaminated confined-space tank vaults 428 times. Each entry (or 'dive') involved an average of three workers, thus equaling approximately 1,300 individual confined -space entries. Over the course of the entire deactivation and demolition period, there were no recordable injuries and only one minor reportable skin contamination. The 241-Z D&D Project was decommissioned under the provisions of the 'Hanford Federal Facility Agreement and Consent Order' (the Tri-Party Agreement or TPA), the 'Resource Conservation and Recovery Act of 1976' (RCRA), and the 'Comprehensive Environmental Response, Compensation, and Liability Act of 1980' (CERCLA). The project completed TPA Milestone M-083-032 to 'Complete those activities required by the 241-Z Treatment and Storage Unit's RCRA Closure Plan' four years and seven months ahead of this legally enforceable milestone. In addition, the project completed TPA Milestone M-083-042 to 'Complete transition and dismantlement of the 241-2 Waste Treatment Facility' four years and four months ahead of schedule. The project used an innovative approach in developing the project-specific RCRA closure plan to assure clear integration between the 241-Z RCRA closure activities and ongoing and future CERCLA actions at PFP. This approach provided a regulatory mechanism within the RCRA closure plan to place segments of the closure that were not practical to address at this time into future actions under CERCLA. Lessons learned from th is approach can be applied to other closure projects within the DOE Complex to control scope creep and mitigate risk. A paper on this topic, entitled 'Integration of the 241-Z Building D and D Under CERCLA with RCRA Closure at the PFP', was presented at the 2007 Waste Management Conference in Tucson, Arizona. In addition, techniques developed by the 241-Z D&D Project to control airborne contamination, clean the interior of the waste tanks, don and doff protective equipment, size-reduce plutonium-contaminated process piping, and mitigate thermal stress for the workers can be applied to other cleanup activities. The project-management team developed a strategy utilizing early characterization, targeted cleanup, and close coordination with PFP Criticality Engineering to significantly streamline the waste- handling costs associated with the project . The project schedule was structured to support an early transition to a criticality 'incredible' status for the 241-Z Facility. The cleanup work was sequenced and coordinated with project-specific criticality analysis to allow the fissile material waste being generated to be managed in a bulk fashion, instead of individual waste packages. This approach negated the need for real-time assay of individ

JOHNSTON GA

2008-01-15T23:59:59.000Z

269

Transuranic (Tru) waste volume reduction operations at a plutonium facility  

SciTech Connect (OSTI)

Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA 55) involve working with various amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne contamination, and excursions of contaminants into the operator's breathing zone are prevented through use of a variety of gloveboxes (the glovebox, coupled with an adequate negative pressure gradient, provides primary confinement). Size-reduction operations on glovebox equipment are a common activity when a process has been discontinued and the room is being modified to support a new customer. The Actin ide Processing Group at TA-55 uses one-meter-long glass columns to process plutonium. Disposal of used columns is a challenge, since they must be size-reduced to get them out of the glovebox. The task is a high-risk operation because the glass shards that are generated can puncture the bag-out bags, leather protectors, glovebox gloves, and the worker's skin when completing the task. One of the Lessons Learned from these operations is that Laboratory management should critically evaluate each hazard and provide more effective measures to prevent personnel injury. A bag made of puncture-resistant material was one of these enhanced controls. We have investigated the effectiveness of these bags and have found that they safely and effectively permit glass objects to be reduced to small pieces with a plastic or rubber mallet; the waste can then be easily poured into a container for removal from the glove box as non-compactable transuranic (TRU) waste. This size-reduction operation reduces solid TRU waste generation by almost 2% times. Replacing one-time-use bag-out bags with multiple-use glass crushing bags also contributes to reducing generated waste. In addition, significant costs from contamination, cleanup, and preparation of incident documentation are avoided. This effort contributes to the Los Alamos National Laboratory Continuous Improvement Program by improving the efficiency, cost-effectiveness, and formality of glovebox operations. In this report, the technical issues, associated with implementing this process improvement are addressed, the results discussed, effectiveness of Lessons Learned evaluated, and waste savings presented.

Cournoyer, Michael E [Los Alamos National Laboratory; Nixon, Archie E [Los Alamos National Laboratory; Dodge, Robert L [Los Alamos National Laboratory; Fife, Keith W [Los Alamos National Laboratory; Sandoval, Arnold M [Los Alamos National Laboratory; Garcia, Vincent E [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

270

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

SciTech Connect (OSTI)

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.

Not Available

1992-04-01T23:59:59.000Z

271

ENVIRONMENTALLY SOUND DISPOSAL OF RADIOACTIVE MATERIALS AT A RCRA HAZARDOUS WASTE DISPOSAL FACILITY  

SciTech Connect (OSTI)

The use of hazardous waste disposal facilities permitted under the Resource Conservation and Recovery Act (''RCRA'') to dispose of low concentration and exempt radioactive materials is a cost-effective option for government and industry waste generators. The hazardous and PCB waste disposal facility operated by US Ecology Idaho, Inc. near Grand View, Idaho provides environmentally sound disposal services to both government and private industry waste generators. The Idaho facility is a major recipient of U.S. Army Corps of Engineers FUSRAP program waste and received permit approval to receive an expanded range of radioactive materials in 2001. The site has disposed of more than 300,000 tons of radioactive materials from the federal government during the past five years. This paper presents the capabilities of the Grand View, Idaho hazardous waste facility to accept radioactive materials, site-specific acceptance criteria and performance assessment, radiological safety and environmental monitoring program information.

Romano, Stephen; Welling, Steven; Bell, Simon

2003-02-27T23:59:59.000Z

272

TWRS retrieval and disposal mission, immobilized high-level waste storage plan  

SciTech Connect (OSTI)

This project plan has a two fold purpose. First, it provides a plan specific to the Hanford Tank Waste Remediation System (TWRS) Immobilized High-Level Waste (EMW) Storage Subproject for the Washington State Department of Ecology (Ecology) that meets the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) milestone M-90-01 (Ecology et al. 1996) and is consistent with the project plan content guidelines found in Section 11.5 of the Tri-Party Agreement action plan. Second, it provides an upper tier document that can be used as the basis for future subproject line item construction management plans. The planning elements for the construction management plans are derived from applicable U.S. Department of Energy (DOE) planning guidance documents (DOE Orders 4700.1 (DOE 1992a) and 430.1 (DOE 1995)). The format and content of this project plan are designed to accommodate the plan`s dual purpose. A cross-check matrix is provided in Appendix A to explain where in the plan project planning elements required by Section 11.5 of the Tri-Party Agreement are addressed.

Calmus, R.B.

1998-01-07T23:59:59.000Z

273

Turning the Corner on Hanford Tank Waste Cleanup-From Safe Storage to Closure  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE), Office of River Protection (ORP) is leading the River Protection Project (RPP) which is responsible for the disposition of 204,000 cubic meters (54 million gallons) of high-level radioactive waste that have accumulated in large underground tanks at the Hanford Site since 1944. ORP continues to make good progress on improving the capability to treat Hanford tank waste. Design of the waste vitrification facilities is proceeding well and construction will begin within the next year. Progress is also being made in reducing risk to the worker and the environment from the waste currently stored in the tank farms. Removal of liquids from single-shell tanks (SSTs) is on schedule and we will begin removing solids (salt cake) from a tank (241-U-107) in 2002. There is a sound technical foundation for the waste vitrification facilities. These initial facilities will be capable of treating (vitrifying) the bulk of Hanford tank waste and are the corners tone of the clean-up strategy. ORP recognizes that as the near-term work is performed, it is vital that there be an equally strong and defensible plan for completing the mission. ORP is proceeding on a three-pronged approach for moving the mission forward. First, ORP will continue to work aggressively to complete the waste vitrification facilities. ORP intends to provide the most capable and robust facilities to maximize the amount of waste treated by these initial facilities by 2028 (regulatory commitment for completion of waste treatment). Second, and in parallel with completing the waste vitrification facilities, ORP is beginning to consider how best to match the hazard of the waste to the disposal strategy. The final piece of our strategy is to continue to move forward with actions to reduce risk in the tank farms and complete cleanup.

Boston, H. L.; Cruz, E. J.; Coleman, S. J.

2002-02-25T23:59:59.000Z

274

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

SciTech Connect (OSTI)

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

B. C. Rogers; P. L. Walter (Rogers and Associates Engineering Corporation); R. D. Baird

1999-08-01T23:59:59.000Z

275

Documentation of acceptable knowledge for Los Alamos National Laboratory Plutonium Facility TRU waste stream  

SciTech Connect (OSTI)

Characterization of transuranic waste from the LANL Plutonium Facility for certification and transportation to WIPP includes the use of acceptable knowledge as specified in the WIPP Quality Assurance Program Plan. In accordance with a site specific procedure, documentation of acceptable knowledge for retrievably stored and currently generated transuranic waste streams is in progress at LANL. A summary overview of the TRU waste inventory is complete and documented in the Sampling Plan. This document also includes projected waste generation, facility missions, waste generation processes, flow diagrams, times, and material inputs. The second part of acceptable knowledge documentation consists of assembling more detailed acceptable knowledge information into auditable records and is expected to require several years to complete. These records for each waste stream must support final assignment of waste matrix parameters, EPA hazardous waste numbers, and radionuclide characterization. They must also include a determination whether waste streams are defense waste streams for compliance with the WIPP Land Withdrawal Act. The LANL Plutonium Facility`s mission is primarily plutonium processing in basic special nuclear material (SNM) research activities to support national defense and energy programs. It currently has about 100 processes ranging from SNM recovery from residues to development of plutonium 238 heat sources for space applications. Its challenge is to characterize and certify waste streams from such diverse and dynamic operations using acceptable knowledge. This paper reports the progress on the certification of the first of these waste streams to the WIPP WAC.

Montoya, A.J.; Gruetzmacher, K.M.; Foxx, C.L.; Rogers, P.Z.

1998-03-01T23:59:59.000Z

276

Documentation of acceptable knowledge for LANL Plutonium Facility transuranic waste streams  

SciTech Connect (OSTI)

Characterization of transuranic waste from the LANL Plutonium Facility for certification and transportation to WIPP includes the use of acceptable knowledge as specified in the WIPP Quality Assurance Program Plan. In accordance with a site-specific procedure, documentation of acceptable knowledge for retrievably stored and currently generated transuranic waste streams is in progress at LANL. A summary overview of the transuranic waste inventory is complete and documented in the Sampling Plan. This document also includes projected waste generation, facility missions, waste generation processes, flow diagrams, times, and material inputs. The second part of acceptable knowledge documentation consists of assembling more detailed acceptable knowledge information into auditable records and is expected to require several years to complete. These records for each waste stream must support final assignment of waste matrix parameters, EPA hazardous waste numbers, and radionuclide characterization. They must also include a determination whether waste streams are defense waste streams for compliance with the WIPP Land Withdrawal Act. The LANL Plutonium Facility`s mission is primarily plutonium processing in basic special nuclear material (SNM) research activities to support national defense and energy programs. It currently has about 100 processes ranging from SNM recovery from residues to development of plutonium 238 heat sources for space applications. Its challenge is to characterize and certify waste streams from such diverse and dynamic operations using acceptable knowledge. This paper reports the progress on the certification of the first of these waste streams to the WIPP WAC.

Montoya, A.J.; Gruetzmacher, K.; Foxx, C.; Rogers, P.S.Z.

1998-07-01T23:59:59.000Z

277

Upgrades to meet LANL SF, 121-2011, hazardous waste facility permit requirements  

SciTech Connect (OSTI)

Members of San IIdefonso have requested information from LANL regarding implementation of the revision to LANL's Hazardous Waste Facility Permit (the RCRA Permit). On January 26, 2011, LANL staff from the Waste Disposition Project and the Environmental Protection Division will provide a status update to Pueblo members at the offices of the San IIdefonso Department of Environmental and Cultural Preservation. The Waste Disposition Project presentation will focus on upgrades and improvements to LANL waste management facilities at TA-50 and TA-54. The New Mexico Environment Department issued LANL's revised Hazardous Waste Facility permit on November 30, 2010 with a 30-day implementation period. The Waste Disposition Project manages and operates four of LANL's permitted facilities; the Waste Characterization, Reduction and Repackaging Facility (WCRRF) at TA-SO, and Area G, Area L and the Radioassay and Nondestructive Testing facility (RANT) at TA-54. By implementing a combination of permanent corrective action activities and shorter-term compensatory measures, WDP was able to achieve functional compliance on December 30, 2010 with new Permit requirements at each of our facilities. One component of WOP's mission at LANL is centralized management and disposition of the Laboratory's hazardous and mixed waste. To support this mission objective, WOP has undertaken a project to upgrade our facilities and equipment to achieve fully compliant and efficient waste management operations. Upgrades to processes, equipment and facilities are being designed to provide defense-in-depth beyond the minimum, regulatory requirements where worker safety and protection of the public and the environment are concerned. Upgrades and improvements to enduring waste management facilities and operations are being designed so as not to conflict with future closure activities at Material Disposal Area G and Material Disposal Area L.

French, Sean B [Los Alamos National Laboratory; Johns - Hughes, Kathryn W [Los Alamos National Laboratory

2011-01-21T23:59:59.000Z

278

Pre-title I safety evaluation for the retrieval operations of transuranic waste drums in the Solid Waste Disposal Facility. Revision 2  

SciTech Connect (OSTI)

Phase I of the Transuranic (TRU) Waste Facility Line Item Project includes the retrieval and safe storage of the pad drums that are stored on TRU pads 2-6 in the Solid Waste Disposal Facility (SWDF). Drums containing TRU waste were placed on these pads as early as 1974. The pads, once filled, were mounded with soil. The retrieval activities will include the excavation of the soil, retrieval of the pad drums, placing the drums in overpacks (if necessary) and venting and purging the retrieved drums. Once the drums have been vented and purged, they will be transported to other pads within the SWDF or in a designated area until they are eventually treated as necessary for ultimate shipment to the Waste Isolation Pilot Plant in Carlsbad, New Mexico. This safety evaluation provides a bounding assessment of the radiological risk involved with the drum retrieval activities to the maximally exposed offsite individual and the co-located worker. The results of the analysis indicate that the risk to the maximally exposed offsite individual and the co-located worker using maximum frequencies and maximum consequences are within the acceptance criteria defined in WSRC Procedural Manual 9Q. The purpose of this evaluation is to demonstrate the incremental risk from the SWDF due to the retrieval activities for use as design input only. As design information becomes available, this evaluation can be revised to satisfy the safety analysis requirements of DOE Orders 4700 and 5480.23.

Rabin, M.S.

1992-08-01T23:59:59.000Z

279

Permitted Mercury Storage Facility Notifications | Department of Energy  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) " ,"ClickPipelinesProvedDecemberInitiativesNationalNuclearRockyServices » Waste Management » Waste

280

Cooling Semiconductor Manufacturing Facilities with Chilled Water Storage  

E-Print Network [OSTI]

This paper examines the 5.2 million gallon chilled water storage system installed at TI's Expressway manufacturing complex in Dallas, Texas. During the peak cooling season ending September 30, 1994, it provided 3,750 tons of additional peak cooling...

Fiorino, D. P.

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect (OSTI)

This report provides a quantitative inventory and composition (chemical and radioactivity) of calcined waste stored at the Idaho Nuclear Technology and Engineering Center. From December 1963 through May 2000, liquid radioactive wastes generated by spent nuclear fuel reprocessing were converted into a solid, granular form called calcine. This report also contains a description of the calcine storage bins.

M. D. Staiger

2007-06-01T23:59:59.000Z

282

ivestock and poultry operations frequently use anaerobic lagoons as liquid waste storage and  

E-Print Network [OSTI]

L ivestock and poultry operations frequently use anaerobic lagoons as liquid waste storage and treatment structures. In a lagoon, organic waste is diluted with water and bacteria decompose the organic as fertilizer. Effluent also can be recycled for manure handling in a flush system. Efficiency To be efficient

Mukhtar, Saqib

283

Municipal solid waste combustion: Waste-to-energy technologies, regulations, and modern facilities in USEPA Region V  

SciTech Connect (OSTI)

Table of Contents: Incinerator operations (Waste preprocessing, combustion, emissions characterization and emission control, process monitoring, heat recovery, and residual ash management); Waste-to-energy regulations (Permitting requirements and operating regulations on both state and Federal levels); Case studies of EPA Region V waste-to-energy facilities (Polk County, Minnesota; Jackson County, Michigan; La Crosse, Wisconsin; Kent County, Michigan; Elk River, Minnesota; Indianapolis, Indiana); Evaluation; and Conclusions.

Sullivan, P.M.; Hallenbeck, W.H.; Brenniman, G.R.

1993-08-01T23:59:59.000Z

284

Summary engineering description of underwater fuel storage facility for foreign research reactor spent nuclear fuel  

SciTech Connect (OSTI)

This document is a summary description for an Underwater Fuel Storage Facility (UFSF) for foreign research reactor (FRR) spent nuclear fuel (SNF). A FRR SNF environmental Impact Statement (EIS) is being prepared and will include both wet and dry storage facilities as storage alternatives. For the UFSF presented in this document, a specific site is not chosen. This facility can be sited at any one of the five locations under consideration in the EIS. These locations are the Idaho National Engineering Laboratory, Savannah River Site, Hanford, Oak Ridge National Laboratory, and Nevada Test Site. Generic facility environmental impacts and emissions are provided in this report. A baseline fuel element is defined in Section 2.2, and the results of a fission product analysis are presented. Requirements for a storage facility have been researched and are summarized in Section 3. Section 4 describes three facility options: (1) the Centralized-UFSF, which would store the entire fuel element quantity in a single facility at a single location, (2) the Regionalized Large-UFSF, which would store 75% of the fuel element quantity in some region of the country, and (3) the Regionalized Small-UFSF, which would store 25% of the fuel element quantity, with the possibility of a number of these facilities in various regions throughout the country. The operational philosophy is presented in Section 5, and Section 6 contains a description of the equipment. Section 7 defines the utilities required for the facility. Cost estimates are discussed in Section 8, and detailed cost estimates are included. Impacts to worker safety, public safety, and the environment are discussed in Section 9. Accidental releases are presented in Section 10. Standard Environmental Impact Forms are included in Section 11.

Dahlke, H.J.; Johnson, D.A.; Rawlins, J.K.; Searle, D.K.; Wachs, G.W.

1994-10-01T23:59:59.000Z

285

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

SciTech Connect (OSTI)

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

NSTec Environmental Management

2009-01-31T23:59:59.000Z

286

Economic comparison of centralizing or decentralizing processing facilities for defense transuranic waste  

SciTech Connect (OSTI)

This study is part of a set of analyses under direction of the Transuranic Waste Management Program designed to provide comprehensive, systematic methodology and support necessary to better understand options for national long-term management of transuranic (TRU) waste. The report summarizes activities to evaluate the economics of possible alternatives in locating facilities to process DOE-managed transuranic waste. The options considered are: (1) Facilities located at all major DOE TRU waste generating sites. (2) Two or three regional facilities. (3) Central processing facility at only one DOE site. The study concludes that processing at only one facility is the lowest cost option, followed, in order of cost, by regional then individual site processing.

Brown, C M

1980-07-01T23:59:59.000Z

287

METHODOLOGY & CALCULATIONS FOR THE ASSIGNMENT OF WASTE FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE  

SciTech Connect (OSTI)

Waste stored within tank farm double-shell tanks (DST) and single-shell tanks (SST) generates flammable gas (principally hydrogen) to varying degrees depending on the type, amount, geometry, and condition of the waste. The waste generates hydrogen through the radiolysis of water and organic compounds, thermolytic decomposition of organic compounds, and corrosion of a tank's carbon steel walls. Radiolysis and thermolytic decomposition also generates ammonia. Nonflammable gases, which act as dilutents (such as nitrous oxide), are also produced. Additional flammable gases (e.g., methane) are generated by chemical reactions between various degradation products of organic chemicals present in the tanks. Volatile and semi-volatile organic chemicals in tanks also produce organic vapors. The generated gases in tank waste are either released continuously to the tank headspace or are retained in the waste matrix. Retained gas may be released in a spontaneous or induced gas release event (GRE) that can significantly increase the flammable gas concentration in the tank headspace as described in RPP-7771, Flammable Gas Safety Isme Resolution. Appendices A through I provide supporting information. The document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste and characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 6 is the annual update of the flammable gas Waste Groups for DSTs and SSTs.

TU, T.A.

2007-01-04T23:59:59.000Z

288

METHODOLOGY & CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE  

SciTech Connect (OSTI)

Waste stored within tank farm double-shell tanks (DST) and single-shell tanks (SST) generates flammable gas (principally hydrogen) to varying degrees depending on the type, amount, geometry, and condition of the waste. The waste generates hydrogen through the radiolysis of water and organic compounds, thermolytic decomposition of organic compounds, and corrosion of a tank's carbon steel walls. Radiolysis and thermolytic decomposition also generates ammonia. Nonflammable gases, which act as dilutents (such as nitrous oxide), are also produced. Additional flammable gases (e.g., methane) are generated by chemical reactions between various degradation products of organic chemicals present in the tanks. Volatile and semi-volatile organic chemicals in tanks also produce organic vapors. The generated gases in tank waste are either released continuously to the tank headspace or are retained in the waste matrix. Retained gas may be released in a spontaneous or induced gas release event (GRE) that can significantly increase the flammable gas concentration in the tank headspace as described in RPP-7771. The document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 5 is the annual update of the methodology and calculations of the flammable gas Waste Groups for DSTs and SSTs.

BARKER, S.A.

2006-07-27T23:59:59.000Z

289

Technology Potential of Thermal Energy Storage (TES) Systems in Federal Facilities  

SciTech Connect (OSTI)

This document presents the findings of a technology market assessment for thermal energy storage (TES) in space cooling applications. The potential impact of TES in Federal facilities is modeled using the Federal building inventory with the appropriate climatic and energy cost data. In addition, this assessment identified acceptance issues and major obstacles through interviews with energy services companies (ESCOs), TES manufacturers, and Federal facility staff.

Chvala, William D.

2001-07-31T23:59:59.000Z

290

Criticality Safety Evaluation for TRU Waste In Storage at the RWMC  

SciTech Connect (OSTI)

Stored containers (drums, boxes, and bins) of transuranic waste at the Radioactive Waste Management Complex (RWMC) facility located at the Idaho National Engineering Laboratory (INEL) were evaluated based on inherent neutron absorption characteristics of the waste materials. It was demonstrated that these properties are sufficient to preclude a criticality accident at the actual fissile levels present in the waste stored at the RWMC. Based on the database information available, the results reported herein confirm that the waste drums, boxes, and bins currently stored at the RWMC will remain safely subcritical if rearranged, restacked, or otherwise handled. Acceptance criteria for receiving future drum shipments were established based on fully infinite systems.

M. E. Shaw; J. B. Briggs; C. A. Atkinson; G. J. Briscoe

1994-04-01T23:59:59.000Z

291

Reevaluation Of Vitrified High-Level Waste Form Criteria For Potential Cost Savings At The Defense Waste Processing Facility  

SciTech Connect (OSTI)

At the Savannah River Site (SRS) the Defense Waste Processing Facility (DWPF) has been immobilizing SRS's radioactive high level waste (HLW) sludge into a durable borosilicate glass since 1996. Currently the DWPF has poured over 3,500 canisters, all of which are compliant with the U. S. Department of Energy's (DOE) Waste Acceptance Product Specifications for Vitrified High-Level Waste Forms (WAPS) and therefore ready to be shipped to a federal geologic repository for permanent disposal. Due to DOE petitioning to withdraw the Yucca Mountain License Application (LA) from the Nuclear Regulatory Commission (NRC) in 2010 and thus no clear disposal path for SRS canistered waste forms, there are opportunities for cost savings with future canister production at DWPF and other DOE producer sites by reevaluating high-level waste form requirements and compliance strategies and reducing/eliminating those that will not negatively impact the quality of the canistered waste form.

Ray, J. W.; Marra, S. L.; Herman, C. C.

2013-01-09T23:59:59.000Z

292

Reevaluation of Vitrified High-Level Waste Form Criteria for Potential Cost Savings at the Defense Waste Processing Facility - 13598  

SciTech Connect (OSTI)

At the Savannah River Site (SRS) the Defense Waste Processing Facility (DWPF) has been immobilizing SRS's radioactive high level waste (HLW) sludge into a durable borosilicate glass since 1996. Currently the DWPF has poured over 3,500 canisters, all of which are compliant with the U. S. Department of Energy's (DOE) Waste Acceptance Product Specifications for Vitrified High-Level Waste Forms (WAPS) and therefore ready to be shipped to a federal geologic repository for permanent disposal. Due to DOE petitioning to withdraw the Yucca Mountain License Application (LA) from the Nuclear Regulatory Commission (NRC) in 2010 and thus no clear disposal path for SRS canistered waste forms, there are opportunities for cost savings with future canister production at DWPF and other DOE producer sites by reevaluating high-level waste form requirements and compliance strategies and reducing/eliminating those that will not negatively impact the quality of the canistered waste form. (authors)

Ray, J.W. [Savannah River Remediation (United States)] [Savannah River Remediation (United States); Marra, S.L.; Herman, C.C. [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States)] [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

293

Biological Information Document, Radioactive Liquid Waste Treatment Facility  

SciTech Connect (OSTI)

This document is intended to act as a baseline source material for risk assessments which can be used in Environmental Assessments and Environmental Impact Statements. The current Radioactive Liquid Waste Treatment Facility (RLWTF) does not meet current General Design Criteria for Non-reactor Nuclear Facilities and could be shut down affecting several DOE programs. This Biological Information Document summarizes various biological studies that have been conducted in the vicinity of new Proposed RLWTF site and an Alternative site. The Proposed site is located on Mesita del Buey, a mess top, and the Alternative site is located in Mortandad Canyon. The Proposed Site is devoid of overstory species due to previous disturbance and is dominated by a mixture of grasses, forbs, and scattered low-growing shrubs. Vegetation immediately adjacent to the site is a pinyon-juniper woodland. The Mortandad canyon bottom overstory is dominated by ponderosa pine, willow, and rush. The south-facing slope was dominated by ponderosa pine, mountain mahogany, oak, and muhly. The north-facing slope is dominated by Douglas fir, ponderosa pine, and oak. Studies on wildlife species are limited in the vicinity of the proposed project and further studies will be necessary to accurately identify wildlife populations and to what extent they utilize the project area. Some information is provided on invertebrates, amphibians and reptiles, and small mammals. Additional species information from other nearby locations is discussed in detail. Habitat requirements exist in the project area for one federally threatened wildlife species, the peregrine falcon, and one federal candidate species, the spotted bat. However, based on surveys outside of the project area but in similar habitats, these species are not expected to occur in either the Proposed or Alternative RLWTF sites. Habitat Evaluation Procedures were used to evaluate ecological functioning in the project area.

Biggs, J.

1995-12-31T23:59:59.000Z

294

High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 7  

SciTech Connect (OSTI)

This Requirements Identification Document (RID) describes an Occupational Health and Safety Program as defined through the Relevant DOE Orders, regulations, industry codes/standards, industry guidance documents and, as appropriate, good industry practice. The definition of an Occupational Health and Safety Program as specified by this document is intended to address Defense Nuclear Facilities Safety Board Recommendations 90-2 and 91-1, which call for the strengthening of DOE complex activities through the identification and application of relevant standards which supplement or exceed requirements mandated by DOE Orders. This RID applies to the activities, personnel, structures, systems, components, and programs involved in maintaining the facility and executing the mission of the High-Level Waste Storage Tank Farms.

Not Available

1994-04-01T23:59:59.000Z

295

Interim storage study report  

SciTech Connect (OSTI)

High-level radioactive waste (HLW) stored at the Idaho Chemical Processing Plant (ICPP) in the form of calcine and liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the waste to be transported to a permanent repository. Because a permanent repository will not be available when the waste is processed, the waste must be stored at ICPP in an Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options under consideration.

Rawlins, J.K.

1998-02-01T23:59:59.000Z

296

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

SciTech Connect (OSTI)

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.

NONE

1995-01-10T23:59:59.000Z

297

Radioactive Liquid Waste Treatment Facility Discharges in 2011  

SciTech Connect (OSTI)

This report documents radioactive discharges from the TA50 Radioactive Liquid Waste Treatment Facilities (RLWTF) during calendar 2011. During 2011, three pathways were available for the discharge of treated water to the environment: discharge as water through NPDES Outfall 051 into Mortandad Canyon, evaporation via the TA50 cooling towers, and evaporation using the newly-installed natural-gas effluent evaporator at TA50. Only one of these pathways was used; all treated water (3,352,890 liters) was fed to the effluent evaporator. The quality of treated water was established by collecting a weekly grab sample of water being fed to the effluent evaporator. Forty weekly samples were collected; each was analyzed for gross alpha, gross beta, and tritium. Weekly samples were also composited at the end of each month. These flow-weighted composite samples were then analyzed for 37 radioisotopes: nine alpha-emitting isotopes, 27 beta emitters, and tritium. These monthly analyses were used to estimate the radioactive content of treated water fed to the effluent evaporator. Table 1 summarizes this information. The concentrations and quantities of radioactivity in Table 1 are for treated water fed to the evaporator. Amounts of radioactivity discharged to the environment through the evaporator stack were likely smaller since only entrained materials would exit via the evaporator stack.

Del Signore, John C. [Los Alamos National Laboratory

2012-05-16T23:59:59.000Z

298

Mixed Waste Management Facility groundwater monitoring report: Third quarter 1994  

SciTech Connect (OSTI)

Currently, 125 wells monitor groundwater quality in the uppermost aquifer beneath the Mixed Waste Management Facility (MWMF) at the Savannah River Site. Samples from the wells are analyzed for selected heavy metals, herbicides/pesticides, indicator parameters, radionuclides, volatile organic compounds, and other constituents. As in previous quarters, tritium and trichloroethylene were the most widespread elevated constituents during third quarter 1994. Sixty-four (51%) of the 125 monitoring wells contained elevated tritium activities. Trichloroethylene concentrations exceeded the final PDWS in 22 (18%) wells. Chloroethene, 1,1-dichloroethylene, and tetrachloroethylene, elevated in one or more wells during third quarter 1994, also occurred in elevated levels during second quarter 1994. These constituents generally were elevated in the same wells during both quarters. Gross alpha, which was elevated in only one well during second quarter 1994, was elevated again during third quarter. Mercury, which was elevated during first quarter 1994, was elevated again in one well. Dichloromethane was elevated in two wells for the first time in several quarters.

Not Available

1994-12-01T23:59:59.000Z

299

Mixed Waste Management Facility groundwater monitoring report. Second quarter 1994  

SciTech Connect (OSTI)

Currently, 125 wells monitor groundwater quality in the uppermost aquifer beneath the Mixed Waste Management Facility (MWMF) at the Savannah River Site. Samples from the wells are analyzed for selected heavy metals, indicator parameters, radionuclides, volatile organic compounds, and other constituents. During second quarter 1994, chloroethene (vinyl chloride), 1,1-dichloroethylene, gross alpha, lead, tetrachloroethylene, trichloroethylene, or tritium exceeded final Primary Drinking Water Standards (PDWS) in approximately half of the downgradient wells at the MWMF. Consistent with historical trends, elevated constituent levels were found primarily in Aquifer Zone. As in previous quarters, tritium and trichloroethylene were the most widespread elevated constituents during second quarter 1994. Sixty-two of the 125 monitoring wells contained elevated tritium activities. Trichloroethylene concentrations exceeded the final PDWS in 23 wells. Chloroethene, 1,1-dichloroethylene, lead, and tetrachloroethylene, elevated in one or more wells during second quarter 1994, also occurred in elevated levels during first quarter 1994. These constituents generally were elevated in the same wells during both quarters. Gross alpha, which was not elevated in any well during first quarter 1994, was elevated in one well during second quarter. Copper, mercury, and nonvolatile beta were elevated during first quarter 1994 but not during second quarter.

Chase, J.A.

1994-09-01T23:59:59.000Z

300

US Army facility for the consolidation of low-level radioactive waste  

SciTech Connect (OSTI)

A preliminary study of a waste consolidation facility for the Department of the Army's low-level radioactive waste was carried out to determine a possible site and perform a cost-benefit analysis. Four sites were assessed as possible locations for such a facility, using predetermined site selection criteria. To assist in the selection of a site, an evaluation of environmental issues was included as part of each site review. In addition, a preliminary design for a waste consolidation facility was developed, and facilities at each site were reviewed for their availability and suitability for this purpose. Currently available processes for volume reduction, as well as processes still under development, were then investigated, and the support and handling equipment and the staff needed for the safe operation of a waste consolidation facility were studied. Using current costs for the transportation and burial of low-level waste, a cost comparison was then made between waste disposal with and without the utilization of volume reduction. Finally, regulations that could affect the operation of a waste consolidation facility were identified and their impact was assessed. 11 references, 5 figures, 16 tables.

Stein, S.L.; Tanner, J.E.; Murphy, B.L.; Gillings, J.C.; Hadley, R.T.; Lyso, O.M.; Gilchrist, R.L.; Murphy, D.W.

1983-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Probabilistic risk analysis for Test Area North Hot Shop Storage Pool Facility  

SciTech Connect (OSTI)

A storage pool facility used for storing spent fuel and radioactive debris from the Three Mile Island (TMI) accident was evaluated to determine the risk associated with its normal operations. Several hazards were identified and examined to determine if any any credible accident scenarios existed. Expected annual occurrence frequencies were calculated for hazards for which accident scenarios were identified through use of fault trees modeling techniques. Fault tree models were developed for two hazards: (1) increased radiation field and (2) spread of contamination. The models incorporated facets of the operations within the facility as well as the facility itself. 6 refs.

Meale, B.M.; Satterwhite, D.G.

1990-01-01T23:59:59.000Z

302

Benchmarking the Remote-Handled Waste Facility at the West Valley Demonstration Project  

SciTech Connect (OSTI)

ABSTRACT Facility decontamination activities at the West Valley Demonstration Project (WVDP), the site of a former commercial nuclear spent fuel reprocessing facility near Buffalo, New York, have resulted in the removal of radioactive waste. Due to high dose and/or high contamination levels of this waste, it needs to be handled remotely for processing and repackaging into transport/disposal-ready containers. An initial conceptual design for a Remote-Handled Waste Facility (RHWF), completed in June 1998, was estimated to cost $55 million and take 11 years to process the waste. Benchmarking the RHWF with other facilities around the world, completed in November 1998, identified unique facility design features and innovative waste pro-cessing methods. Incorporation of the benchmarking effort has led to a smaller yet fully functional, $31 million facility. To distinguish it from the June 1998 version, the revised design is called the Rescoped Remote-Handled Waste Facility (RRHWF) in this topical report. The conceptual design for the RRHWF was completed in June 1999. A design-build contract was approved by the Department of Energy in September 1999.

O. P. Mendiratta; D. K. Ploetz

2000-02-29T23:59:59.000Z

303

Handling Radioactive Waste from the Proton Accelerator Facility at the Paul Scherrer Institut (PSI) - Always Surprising? - 13320  

SciTech Connect (OSTI)

The Paul Scherrer Institut (PSI) is the largest national research centre in Switzerland. Its multidisciplinary research is dedicated to a wide field in natural science and technology as well as particle physics. In this context, PSI is operating, amongst others, a large proton accelerator facility since more than 30 years. In two cyclotrons, protons are accelerated to high speeds and then guided along roughly 100 m of beam line to three different target stations to produce secondary particles like mesons and neutrons for experiments and a separately beam line for UCN. The protons induce spallation processes in the target materials, and also at other beam loss points along the way, with emission of protons, neutrons, hydrogen, tritium, helium, heavier fragments and fission processes. In particular the produced neutrons, due to their large penetration depth, will then interact also with the surrounding materials. These interactions of radiation with matter lead to activation and partly to contamination of machine components and the surrounding infrastructures. Maintenance, operation and decommissioning of installations generate inevitably substantial amounts of radioactive operational and dismantling waste like targets, magnets, collimators, shielding (concrete, steel) and of course secondary waste. To achieve an optimal waste management strategy for interim storage or final disposal, radioactive waste has to be characterized, sorted and treated. This strategy is based on radiation protection demands, raw waste properties (size, material, etc.), and requirements to reduce the volume of waste, mainly for legal and economical reasons. In addition, the radiological limitations for transportation of the waste packages to a future disposal site have to be taken into account, as well as special regulatory demands. The characterization is a task of the waste producer. The conditioning processes and quality checks for radioactive waste packages are part of an accredited waste management process of PSI, especially of the Section Dismantling and Waste Management. Strictly proven and accepted methods needed to be developed and enhanced for safe treatment, transport, conditioning and storage. But in the field of waste from research activities, individual and new solutions have to be found in an increasingly growing administrative environment. Furthermore, a wide variety of components, with a really large inventory of radioactive nuclides, has to be handled. And there are always surprising challenges concerning the unusual materials or the nuclide inventory. In case of the operational and dismantling radioactive accelerator waste, the existing conditioning methods are in the process of a continuous enhancement - technically and administratively. The existing authorized specifications of conditioning processes have to be extended to optimize and fully describe the treatment of the inevitably occurring radioactive waste from the accelerator facility. Additional challenges are the changes with time concerning the legal and regulatory requirements - or do we have to consider it as business as usual? This paper gives an overview of the current practices in radioactive waste management and decommissioning of the existing operational accelerator waste. (authors)

Mueth, Joachim [Paul Scherrer Institute, CH-5232 Villigen (Switzerland)] [Paul Scherrer Institute, CH-5232 Villigen (Switzerland)

2013-07-01T23:59:59.000Z

304

Data Storage and Access Policy for C-CAMP facilities Experimental Data  

E-Print Network [OSTI]

Data Storage and Access Policy for C-CAMP facilities Experimental Data At the conclusion of a project, data given to clients will NOT include raw data files. a) In the case of Genomics, base call) In the case of Proteomics, LC spectra and *.raw files will NOT be provided. Only processed data files (in

Udgaonkar, Jayant B.

305

EIS-0035: Use of VLCCs and VLCCs as Floating Storage Facilities  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy prepared this environmental impact statement to assess the potential environmental and socioeconomic impacts associated with the proposed use of tankers as floating storage facilities. This statement is a draft supplement to the programmatic environmental impact statement for the Strategic Petroleum Reserve.

306

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

SciTech Connect (OSTI)

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

Sutherland, A.A.; Miner, G.L.; Grahn, K.F.; Pollard, C.G. [Rogers and Associates Engineering Corp., Salt Lake City, UT (United States)

1993-10-01T23:59:59.000Z

307

al mixed waste: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

and characterization alternatives of mixed waste soil and debris at disposal area remedial action DARA solids storage facility (SSF) University of California eScholarship...

308

Advanced Test Reactor Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect (OSTI)

U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Advanced Test Reactor Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. U.S. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool to develop the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-11-01T23:59:59.000Z

309

Mixed Waste Management Facility Groundwater Monitoring Report, Fourth Quarter 1998 and 1998 Summary  

SciTech Connect (OSTI)

During fourth quarter 1998, ten constituents exceeded final Primary Drinking Water Standards (PDWS) in groundwater samples from downgradient monitoring wells at the Mixed Waste Management Facility. No constituents exceeded final PDWS in samples from the upgradient monitoring wells.

Chase, J.

1999-04-29T23:59:59.000Z

310

Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth...  

Office of Environmental Management (EM)

of Environmental Management (DOE-EM) External Technical Review of the Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth Gaseous Diffusion Plant Why DOE-EM Did...

311

Vit Plant receives and sets key air filtration equipment for Low Activity Waste Facility  

Broader source: Energy.gov [DOE]

WTP lifted a nearly 100-ton carbon bed absorber into the Low-Activity Waste Facility. This key piece of air-filtration equipment will remove mercury and acidic gases before air is channeled through...

312

Construction and operation of replacement hazardous waste handling facility at Lawrence Berkeley Laboratory. Environmental Assessment  

SciTech Connect (OSTI)

The US Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0423, for the construction and operation of a replacement hazardous waste handling facility (HWHF) and decontamination of the existing HWHF at Lawrence Berkeley Laboratory (LBL), Berkeley, California. The proposed facility would replace several older buildings and cargo containers currently being used for waste handling activities and consolidate the LBL`s existing waste handling activities in one location. The nature of the waste handling activities and the waste volume and characteristics would not change as a result of construction of the new facility. Based on the analysis in the EA, DOE has determined that the proposed action would not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969, 42 USC. 4321 et seq. Therefore, an environmental impact statement is not required.

Not Available

1992-09-01T23:59:59.000Z

313

Conceptual design report: Nuclear materials storage facility renovation. Part 7, Estimate data  

SciTech Connect (OSTI)

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This report is organized according to the sections and subsections outlined by Attachment III-2 of DOE Document AL 4700.1, Project Management System. It is organized into seven parts. This document, Part VII - Estimate Data, contains the project cost estimate information.

NONE

1995-07-14T23:59:59.000Z

314

Conceptual design report: Nuclear materials storage facility renovation. Part 3, Supplemental information  

SciTech Connect (OSTI)

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. It is organized into seven parts. Part I - Design Concept describes the selected solution. Part III - Supplemental Information contains calculations for the various disciplines as well as other supporting information and analyses.

NONE

1995-07-14T23:59:59.000Z

315

Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management  

SciTech Connect (OSTI)

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system.

NONE

1995-07-14T23:59:59.000Z

316

Statement of position of the United States Department of Energy in the matter of proposed rulemaking on the storage and disposal of nuclear waste (waste confidence rulemaking)  

SciTech Connect (OSTI)

Purpose of this proceeding is to assess generically the degree of assurance that the radioactive waste can be safely disposed of, to determine when such disposal or off-site storage will be available, and to determine whether wastes can be safely stored on-site past license expiration until off-site disposal/storage is available. (DLC)

None

1980-04-15T23:59:59.000Z

317

Facility design philosophy: Tank Waste Remediation System Process support and infrastructure definition  

SciTech Connect (OSTI)

This report documents the current facility design philosophy for the Tank Waste Remediation System (TWRS) process support and infrastructure definition. The Tank Waste Remediation System Facility Configuration Study (FCS) initially documented the identification and definition of support functions and infrastructure essential to the TWRS processing mission. Since the issuance of the FCS, the Westinghouse Hanford Company (WHC) has proceeded to develop information and requirements essential for the technical definition of the TWRS treatment processing programs.

Leach, C.E.; Galbraith, J.D. [Westinghouse Hanford Co., Richland, WA (United States); Grant, P.R.; Francuz, D.J.; Schroeder, P.J. [Fluor Daniel, Inc., Richland, WA (United States)

1995-11-01T23:59:59.000Z

318

Preliminary technical data summary No. 3 for the Defense Waste Processing Facility  

SciTech Connect (OSTI)

This document presents an update on the best information presently available for the purpose of establishing the basis for the design of a Defense Waste Processing Facility. Objective of this project is to provide a facility to fix the radionuclides present in Savannah River Plant (SRP) high-level liquid waste in a high-integrity form (glass). Flowsheets and material balances reflect the alternate CAB case including the incorporation of low-level supernate in concrete. (DLC)

Landon, L.F. (comp.)

1980-05-01T23:59:59.000Z

319

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

SciTech Connect (OSTI)

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

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

2010-10-01T23:59:59.000Z

320

The Mixed Waste Management Facility, monthly report, February 1995  

SciTech Connect (OSTI)

Technical progress continued in general accordance with the Mixed Waste Management Facility (MWMF) FY95 Plan. Engineering development and design continued in support of preliminary design of MWMF major subsystems. Peer reviews have begun in preparation for system preliminary design reviews. Procurements in support of engineering design/development have continued to increase. Significant effort to provide technical and cost trade-off information for the Project Baseline Revision 1.2 (PB1.2) and FY97 Validation was completed. Management focus during February centered upon addressing the rebaseline for MWMF for the FY97 Validation in March, and upon completing the permitting strategy. We completed a consistent baseline plan for Validation that satisfied the DOE constraints of integration with DWTF, schedule stretchout, overall Project cost, and FY cost profiles. The revised permitting strategy was completed and reviewed by a number of stakeholders (LLNL, DOE, State). The proposed strategy involves no RCRA RD&D permit, since all technology demonstrations can be done with surrogates and using limited treatability studies. The expenses for February continue to run somewhat below the plan due to the limited new hiring. This is a result of uncertain DOE funding and guidance to keep personnel to a minimum. However, the spending rate is picking up due to initiation of procurements for engineering development and a minimum of essential new hires. A significant imbalance in the OPEX/CENRTC funding split for FY95 exists (about $2.1M); DOE/OAK began to seek resolution this month. Critical-path items are DWTF construction, NEPA, and permitting (for both MWMF and DWTF). Contractual issues have delayed award of the A&E contract for DWTF, but work-arounds are in progress to avoid schedule impact. NEPA and permitting issues are discussed below. Progress on preliminary design for MWMF is close to schedule.

Streit, R.D.

1995-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

EIS-0133: Decontamination and Waste Treatment Facility for the Lawrence Livermore National Laboratory Livermore, California  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy’s San Francisco Operations Office developed this statement to analyze the potential environmental and socioeconomic impacts of alternatives for constructing and operating a Decontamination and Waste Treatment Facility for nonradioactive (hazardous and nonhazardous) mixed and radioactive wastes at Lawrence Livermore National Laboratory.

322

M-Area hazardous waste management facility groundwater monitoring report -- first quarter 1994. Volume 1  

SciTech Connect (OSTI)

This report describes the groundwater monitoring and corrective action program at the M-Area Hazardous Waste Management Facility (HWMF) at the Savannah River Site (SRS) during first quarter 1994 as required by South Carolina Hazardous Waste Permit SC1-890-008-989 and section 264.100(g) of the South Carolina Hazardous Waste Management Regulations. During first quarter 1994, 42 point-of-compliance (POC) wells at the M-Area HWMF were sampled for drinking water parameters.

Evans, C.S.; Washburn, F.; Jordan, J.; Van Pelt, R.

1994-05-01T23:59:59.000Z

323

Mixed Waste Management Facility FSS Well Data Groundwater Monitoring Report. Fourth Quarter 1994 and 1994 summary  

SciTech Connect (OSTI)

During fourth quarter 1994, ten constituents exceeded final Primary Drinking Water Standards (PDWS) in groundwater samples from downgradient monitoring wells at the Mixed Waste Management Facility, the Old Burial Ground, the E-Area Vaults, the proposed Hazardous Waste/Mixed Waste Disposal Vaults, and the F-Area Sewage Sludge Application Site. No constituent exceeded final PDWS in samples from the upgradient monitoring wells. The groundwater flow directions and rates in the three hydrostratigraphic units were similar to those of previous quarters.

Chase, J.A.

1995-03-01T23:59:59.000Z

324

340 Waste handling Facility Hazard Categorization and Safety Analysis  

SciTech Connect (OSTI)

The analysis presented in this document provides the basis for categorizing the facility as less than Hazard Category 3.

T. J. Rodovsky

2010-10-25T23:59:59.000Z

325

The Mixed Waste Management Facility monthly report, December 1994  

SciTech Connect (OSTI)

This report contains cost and planning schedules, and detailed information on project management at the LLNL facility.

Streit, R.

1995-01-01T23:59:59.000Z

326

CRAD, Conduct of Operations- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Conduct of Operations Program portion of an Operational Readiness Review at the Los Alamos National Laboratory, Waste Characterization, Reduction, and Repackaging Facility.

327

CRAD, Occupational Safety & Health- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Occupational and Industrial Safety and Hygiene Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

328

CRAD, Engineering- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Engineering Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

329

CRAD, Environmental Protection- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Environmental Compliance Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

330

EIS-0084: Incineration Facility for Radioactively Contaminated PCBs and Other Wastes, Oak Ridge, Tennessee  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy Office of Uranium Enrichment and Assessment prepared this statement to assess the environmental impacts of the construction and operation of the proposed Oak Ridge Gaseous Diffusion Plant, an incineration facility to dispose of radioactively contaminated polychlorinated biophenyls, as well as combustible waste from the Paducah, Portsmouth and Oak Ridge facilities.

331

CRAD, Radiological Controls- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Radiation Protection Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

332

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

SciTech Connect (OSTI)

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

BURBANK, D.A.

2000-08-31T23:59:59.000Z

333

CRAD, Fire Protection- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Fire Protection Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

334

CRAD, Management- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Management portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

335

CRAD, DOE Oversight- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Conduct of Operations Program portion of an Operational Readiness Review at the Los Alamos National Laboratory, Waste Characterization, Reduction, and Repackaging Facility.

336

CRAD, Emergency Management- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Emergency Management Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

337

CRAD, Quality Assurance- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Quality Assurance Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

338

Covanta Announces Contracts for Lee County, Florida Waste-to-Energy Facility Wednesday February 8, 3:51 pm ET  

E-Print Network [OSTI]

Covanta Announces Contracts for Lee County, Florida Waste-to-Energy Facility Expansion Wednesday the construction of a 636 TPD (ton per day) capacity expansion to Lee County's 1,200 TPD waste-to-energy facility includes recycling, composting, waste-to- energy and landfilling. Covanta's service agreement, which

Columbia University

339

Waste-Lithium-Liquid (WLL) Flow Battery for Stationary Energy Storage Applications Youngsik Kim* and Nina MahootcheianAsl  

E-Print Network [OSTI]

Waste-Lithium-Liquid (WLL) Flow Battery for Stationary Energy Storage Applications Youngsik Kim in a Waste-Lithium-Liquid (WLL) flow battery that can be used in a stationary energy storage application. Li* and Nina MahootcheianAsl Richard Lugar Center for Renewable Energy, Department of Mechanical Engineering

Zhou, Yaoqi

340

METHODOLOGY AND CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE  

SciTech Connect (OSTI)

The Hanford Site contains 177 large underground radioactive waste storage tanks (28 double-shell tanks and 149 single-shell tanks). These tanks are categorized into one of three waste groups (A, B, and C) based on their waste and tank characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement gas release event. Assignments of waste groups to the 177 double-shell tanks and single-shell tanks, as reported in this document, are based on a Monte Carlo analysis of three criteria. The first criterion is the headspace flammable gas concentration following release of retained gas. This criterion determines whether the tank contains sufficient retained gas such that the well-mixed headspace flammable gas concentration would reach 100% of the lower flammability limit if the entire tank's retained gas were released. If the volume of retained gas is not sufficient to reach 100% of the lower flammability limit, then flammable conditions cannot be reached and the tank is classified as a waste group C tank independent of the method the gas is released. The second criterion is the energy ratio and considers whether there is sufficient supernatant on top of the saturated solids such that gas-bearing solids have the potential energy required to break up the material and release gas. Tanks that are not waste group C tanks and that have an energy ratio < 3.0 do not have sufficient potential energy to break up material and release gas and are assigned to waste group B. These tanks are considered to represent a potential induced flammable gas release hazard, but no spontaneous buoyant displacement flammable gas release hazard. Tanks that are not waste group C tanks and have an energy ratio {ge} 3.0, but that pass the third criterion (buoyancy ratio < 1.0, see below) are also assigned to waste group B. Even though the designation as a waste group B (or A) tank identifies the potential for an induced flammable gas release hazard, the hazard only exists for specific operations that can release the retained gas in the tank at a rate and quantity that results in reaching 100% of the lower flammability limit in the tank headspace. The identification and evaluation of tank farm operations that could cause an induced flammable gas release hazard in a waste group B (or A) tank are included in other documents. The third criterion is the buoyancy ratio. This criterion addresses tanks that are not waste group C double-shell tanks and have an energy ratio {ge} 3.0. For these double-shell tanks, the buoyancy ratio considers whether the saturated solids can retain sufficient gas to exceed neutral buoyancy relative to the supernatant layer and therefore have buoyant displacement gas release events. If the buoyancy ratio is {ge} 1.0, that double-shell tank is assigned to waste group A. These tanks are considered to have a potential spontaneous buoyant displacement flammable gas release hazard in addition to a potential induced flammable gas release hazard. This document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 8 is the annual update of the calculations of the flammable gas Waste Groups for DSTs and SSTs.

WEBER RA

2009-01-16T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

METHODOLOGY AND CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE  

SciTech Connect (OSTI)

This document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 7 is the annual update of the calculations of the flammable gas Waste Groups for DSTs and SSTs. The Hanford Site contains 177 large underground radioactive waste storage tanks (28 double-shell tanks and 149 single-shell tanks). These tanks are categorized into one of three waste groups (A, B, and C) based on their waste and tank characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement gas release event. Assignments of waste groups to the 177 double-shell tanks and single-shell tanks, as reported in this document, are based on a Monte Carlo analysis of three criteria. The first criterion is the headspace flammable gas concentration following release of retained gas. This criterion determines whether the tank contains sufficient retained gas such that the well-mixed headspace flammable gas concentration would reach 100% of the lower flammability limit if the entire tank's retained gas were released. If the volume of retained gas is not sufficient to reach 100% of the lower flammability limit, then flammable conditions cannot be reached and the tank is classified as a waste group C tank independent of the method the gas is released. The second criterion is the energy ratio and considers whether there is sufficient supernatant on top of the saturated solids such that gas-bearing solids have the potential energy required to break up the material and release gas. Tanks that are not waste group C tanks and that have an energy ratio < 3.0 do not have sufficient potential energy to break up material and release gas and are assigned to waste group B. These tanks are considered to represent a potential induced flammable gas release hazard, but no spontaneous buoyant displacement flammable gas release hazard. Tanks that are not waste group C tanks and have an energy ratio {ge} 3.0, but that pass the third criterion (buoyancy ratio < 1.0, see below) are also assigned to waste group B. Even though the designation as a waste group B (or A) tank identifies the potential for an induced flammable gas release hazard, the hazard only exists for specific operations that can release the retained gas in the tank at a rate and quantity that results in reaching 100% of the lower flammability limit in the tank headspace. The identification and evaluation of tank farm operations that could cause an induced flammable gas release hazard in a waste group B (or A) tank are included in other documents. The third criterion is the buoyancy ratio. This criterion addresses tanks that are not waste group C double-shell tanks and have an energy ratio {ge} 3.0. For these double-shell tanks, the buoyancy ratio considers whether the saturated solids can retain sufficient gas to exceed neutral buoyancy relative to the supernatant layer and therefore have buoyant displacement gas release events. If the buoyancy ratio is {ge} 1.0, that double-shell tank is assigned to waste group A. These tanks are considered to have a potential spontaneous buoyant displacement flammable gas release hazard in addition to a potential induced flammable gas release hazard.

FOWLER KD

2007-12-27T23:59:59.000Z

342

Solid Waste Disposal Resource Recovery Facilities Act (South Carolina)  

Broader source: Energy.gov [DOE]

This legislation authorizes local governing bodies to form joint agencies to advance the collection, transfer, processing of solid waste, recovery of resources, and sales of recovered resources in...

343

Design of the Waste Receiving and Processing Module 2A Facility  

SciTech Connect (OSTI)

Westinghouse Hanford Company has determined that a facility is required for the treatment of mixed low-level waste at the Hanford Site. The mission of that facility will be to receive, process/treat, package, certify, and ship the contact-handled, mixed low-level waste that must be handled by Hanford Site to permanent disposal. Preconceptual and conceptual design studies were performed by United Engineers and Constructors, and a conceptual design report was issued. This report presents a summary of the conceptual design for a facility that will meet the mission established.

Lamberd, D.L.

1993-03-01T23:59:59.000Z

344

Waste Receiving and Processing (WRAP) Facility Final Safety Analysis Report (FSAR)  

SciTech Connect (OSTI)

The Waste Receiving and Processing Facility (WRAP), 2336W Building, on the Hanford Site is designed to receive, confirm, repackage, certify, treat, store, and ship contact-handled transuranic and low-level radioactive waste from past and present U.S. Department of Energy activities. The WRAP facility is comprised of three buildings: 2336W, the main processing facility (also referred to generically as WRAP); 2740W, an administrative support building; and 2620W, a maintenance support building. The support buildings are subject to the normal hazards associated with industrial buildings (no radiological materials are handled) and are not part of this analysis except as they are impacted by operations in the processing building, 2336W. WRAP is designed to provide safer, more efficient methods of handling the waste than currently exist on the Hanford Site and contributes to the achievement of as low as reasonably achievable goals for Hanford Site waste management.

TOMASZEWSKI, T.A.

2000-04-25T23:59:59.000Z

345

Thermoeconomic optimization of sensible heat thermal storage for cogenerated waste-to-energy recovery  

SciTech Connect (OSTI)

This paper investigates the feasibility of employing thermal storage for cogenerated waste-to-energy recovery such as using mass-burning water-wall incinerators and topping steam turbines. Sensible thermal storage is considered in rectangular cross-sectioned channels through which is passed unused process steam at 1,307 kPa/250 C (175 psig/482 F) during the storage period and feedwater at 1,307 kPa/102 C (175 psig/216 F) during the recovery period. In determining the optimum storage configuration, it is found that the economic feasibility is a function of mass and specific heat of the material and surface area of the channel as well as cost of material and fabrication. Economic considerations included typical cash flows of capital charges, energy revenues, operation and maintenance, and income taxes. Cast concrete is determined to be a potentially attractive storage medium.

Abdul-Razzak, H.A. [Texas A and M Univ., Kingsville, TX (United States). Dept. of Mechanical and Industrial Engineering; Porter, R.W. [Illinois Inst. of Tech., chicago, IL (United States). Dept. of Mechanical and Aerospace Engineering

1995-10-01T23:59:59.000Z

346

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

SciTech Connect (OSTI)

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

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

2012-11-21T23:59:59.000Z

347

Cryograb: A Novel Approach to the Retrieval of Waste from Underground Storage Tanks - 13501  

SciTech Connect (OSTI)

The UK's National Nuclear Laboratory (NNL) is investigating the use of cryogenic technology for the recovery of nuclear waste. Cryograb, freezing the waste on a 'cryo-head' and then retrieves it as a single mass which can then be treated or stabilized as necessary. The technology has a number of benefits over other retrieval approaches in that it minimizes sludge disturbance thereby reducing effluent arising and it can be used to de-water, and thereby reduce the volume of waste. The technology has been successfully deployed for a variety of nuclear and non-nuclear waste recovery operations. The application of Cryograb for the recovery of waste from US underground storage tanks is being explored through a US DOE International Technology Transfer and Demonstration programme. A sample deployment being considered involves the recovery of residual mounds of sludge material from waste storage tanks at Savannah River. Operational constraints and success criteria were agreed prior to the completion of a process down selection exercise which specified the preferred configuration of the cryo-head and supporting plant. Subsequent process modeling identified retrieval rates and temperature gradients through the waste and tank infrastructure. The work, which has been delivered in partnership with US DOE, SRNL, NuVision Engineering and Frigeo AB has demonstrated the technical feasibility of the approach (to TRL 2) and has resulted in the allocation of additional funding from DOE to take the programme to bench and cold pilot-scale trials. (authors)

O'Brien, Luke; Baker, Stephen; Bowen, Bob [UK National Nuclear Laboratory, Chadwick House, Warrington (United Kingdom)] [UK National Nuclear Laboratory, Chadwick House, Warrington (United Kingdom); Mallick, Pramod; Smith, Gary [US Department of Energy (United States)] [US Department of Energy (United States); King, Bill [Savannah River National Laboratory (United States)] [Savannah River National Laboratory (United States); Judd, Laurie [NuVision Engineering (United States)] [NuVision Engineering (United States)

2013-07-01T23:59:59.000Z

348

Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee)  

Broader source: Energy.gov [DOE]

The Solid Waste Disposal Laws and Regulations are found in Tenn. Code 68-211. These rules are enforced and subject to change by the Public Waste Board (PWB), which is established by the Division...

349

Disposal of radioactive waste from nuclear research facilities  

E-Print Network [OSTI]

Swiss radioactive wastes originate from nuclear power plants (NPP) and from medicine (e.g. radiation sources), industry (e.g. fire detectors) and research (e.g. CERN, PSI). Their conditioning, characterisation and documentation has to meet the demands given by the Swiss regulatory authorities including all information needed for a safe disposal in future repositories. For NPP wastes, arisings as well as the processes responsible for the buildup of short and long lived radionuclides are well known, and the conditioning procedures are established. The radiological inventories are determined on a routinely basis using a combined system of measurements and calculational programs. For waste from research, the situation is more complicated. The wide spectrum of different installations combined with a poorly known history of primary and secondary radiation results in heterogeneous waste sorts with radiological inventories quite different from NPP waste and difficult to measure long lived radionuclides. In order to c...

Maxeiner, H; Kolbe, E

2003-01-01T23:59:59.000Z

350

Borehole Miner - Extendible Nozzle Development for Radioactive Waste Dislodging and Retrieval from Underground Storage Tanks  

SciTech Connect (OSTI)

This report summarizes development of borehole-miner extendible-nozzle water-jetting technology for dislodging and retrieving salt cake, sludge} and supernate to remediate underground storage tanks full of radioactive waste. The extendible-nozzle development was based on commercial borehole-miner technology.

CW Enderlin; DG Alberts; JA Bamberger; M White

1998-09-25T23:59:59.000Z

351

The development of a management strategy for interim storage and final disposal of nuclear wastes  

SciTech Connect (OSTI)

The overall waste management strategy for alternative routes from reactor to final disposal, including dry interim storage, is discussed. Within the framework of a preliminary structure plan possible technical solutions must be investigated, and with sufficient relevant information available the future progress of the project, can be addressed on the base of a decision analysis.

Engelmann, H.J.; Popp, F.W. [Deutsche Gesellschaft zum Bau and Betrieb von Endglagern fuer Abfallostofe mbH, Peine (Germany); Arntzen, P.; Botzem, W. [NUKEM GmbH, Alzenau (Germany); Soucek, B. [Czech Power Board, Prague (Czech Republic)

1993-12-31T23:59:59.000Z

352

Thermal Energy Storage/Waste Heat Recovery Applications in the Cement Industry  

E-Print Network [OSTI]

, and the Portland Cement Association have studied the potential benefits of using waste heat recovery methods and thermal energy storage systems in the cement manufacturing process. This work was performed under DOE Contract No. EC-77-C-01-50S4. The study has been...

Beshore, D. G.; Jaeger, F. A.; Gartner, E. M.

1979-01-01T23:59:59.000Z

353

EIS-0110: Central Waste Disposal Facility for Low-Level Radioactive Waste, Oak Ridge Reservation, Oak Ridge, Tennessee  

Broader source: Energy.gov [DOE]

This EIS assesses the environmental impacts of alternatives for the disposal of low-level waste and by-product materials generated by the three major plants on the Oak Ridge Reservation (ORR). In addition to the no-action alternative, two classes of alternatives are evaluated: facility design alternatives and siting alternatives.

354

Preservation of artifacts in salt mines as a natural analog for the storage of transuranic wastes at the WIPP repository  

SciTech Connect (OSTI)

Use of nature`s laboratory for scientific analysis of complex systems is a largely untapped resource for understanding long-term disposal of hazardous materials. The Waste Isolation Pilot Plant (WIPP) in the US is a facility designed and approved for storage of transuranic waste in a salt medium. Isolation from the biosphere must be ensured for 10,000 years. Natural analogs provide a means to interpret the evolution of the underground disposal setting. Investigations of ancient sites where manmade materials have experienced mechanical and chemical processes over millennia provide scientific information unattainable by conventional laboratory methods. This paper presents examples of these pertinent natural analogs, provides examples of features relating to the WIPP application, and identifies potential avenues of future investigations. This paper cites examples of analogical information pertaining to the Hallstatt salt mine in Austria and Wieliczka salt mine in Poland. This paper intends to develop an appreciation for the applicability of natural analogs to the science and engineering of a long-term disposal facility in geomedia.

Martell, M.A.; Hansen, F.; Weiner, R.

1998-10-01T23:59:59.000Z

355

Technical Aspects Regarding the Management of Radioactive Waste from Decommissioning of Nuclear Facilities  

SciTech Connect (OSTI)

The proper application of the nuclear techniques and technologies in Romania started in 1957, once with the commissioning of the Research Reactor VVR-S from IFIN-HH-Magurele. During the last 45 years, appear thousands of nuclear application units with extremely diverse profiles (research, biology, medicine, education, agriculture, transport, all types of industry) which used different nuclear facilities containing radioactive sources and generating a great variety of radioactive waste during the decommissioning after the operation lifetime is accomplished. A new aspect appears by the planning of VVR-S Research Reactor decommissioning which will be a new source of radioactive waste generated by decontamination, disassembling and demolition activities. By construction and exploitation of the Radioactive Waste Treatment Plant (STDR)--Magurele and the National Repository for Low and Intermediate Radioactive Waste (DNDR)--Baita, Bihor county, in Romania was solved the management of radioactive wastes arising from operation and decommissioning of small nuclear facilities, being assured the protection of the people and environment. The present paper makes a review of the present technical status of the Romanian waste management facilities, especially raising on treatment capabilities of ''problem'' wastes such as Ra-266, Pu-238, Am-241 Co-60, Co-57, Sr-90, Cs-137 sealed sources from industrial, research and medical applications. Also, contain a preliminary estimation of quantities and types of wastes, which would result during the decommissioning project of the VVR-S Research Reactor from IFIN-HH giving attention to some special category of wastes like aluminum, graphite and equipment, components and structures that became radioactive through neutron activation. After analyzing the technical and scientific potential of STDR and DNDR to handle big amounts of wastes resulting from the decommissioning of VVR-S Research Reactor and small nuclear facilities, the necessity of up-gradation of these nuclear objectives before starting the decommissioning plan is revealed. A short presentation of the up-grading needs is also presented.

Dragolici, F.; Turcanu, C. N.; Rotarescu, G.; Paunica, I.

2003-02-25T23:59:59.000Z

356

Idaho High-Level Waste & Facilities Disposition, Final Environmental Impact Statement  

SciTech Connect (OSTI)

This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. After considering comments on the Draft EIS (DOE/EIS-0287D), as well as information on available treatment technologies, DOE and the State of Idaho have identified separate preferred alternatives for waste treatment. DOE's preferred alternative for waste treatment is performance based with the focus on placing the wastes in forms suitable for disposal. Technologies available to meet the performance objectives may be chosen from the action alternatives analyzed in this EIS. The State of Idaho's Preferred Alternative for treating mixed transuranic waste/SBW and calcine is vitrification, with or without calcine separations. Under both the DOE and State of Idaho preferred alternatives, newly generated liquid waste would be segregated after 2005, stored or treated directly and disposed of as low-level, mixed low-level, or transuranic waste depending on its characteristics. The objective of each preferred alternative is to enable compliance with the legal requirement to have INEEL HLW road ready by a target date of 2035. Both DOE and the State of Idaho have identified the same preferred alternative for facilities disposition, which is to use performance-based closure methods for existing facilities and to design new facilities consistent with clean closure methods.

N /A

2002-10-11T23:59:59.000Z

357

Spent fuel storage and waste management fuel cycle optimization using CAFCA  

SciTech Connect (OSTI)

Spent fuel storage modeling is at the intersection of nuclear fuel cycle system dynamics and waste management policy. A model that captures the economic parameters affecting used nuclear fuel storage location options, which complements fuel cycle economic assessment has been created using CAFCA (Code for Advanced Fuel Cycles Assessment) of MIT. Research has also expanded to the study on dependency of used nuclear fuel storage economics, environmental impact, and proliferation risk. Three options of local, regional, and national storage were studied. The preliminary product of this research is the creation of a system dynamics tool known as the Waste Management Module which provides an easy to use interface for education on fuel cycle waste management economic impacts. Storage options costs can be compared to literature values with simple variation available for sensitivity study. Additionally, a first of a kind optimization scheme for the nuclear fuel cycle analysis is proposed and the applications of such an optimization are discussed. The main tradeoff for fuel cycle optimization was found to be between economics and most of the other identified metrics. (authors)

Brinton, S.; Kazimi, M. [Massachusetts Institute of Technology, 77 Massachusetts Avenue, Cambridge MA 02139 (United States)

2013-07-01T23:59:59.000Z

358

EA-1106: Explosive Waste Treatment Facility at Site 300, Lawrence Livermore National Laboratory, San Joaquin County, California  

Broader source: Energy.gov [DOE]

This EA evaluates the environmental impacts of the proposal to build, permit, and operate the Explosive Waste Treatment Facility to treat explosive waste at the U.S. Department of Energy's Lawrence...

359

ASME AG-1 REQUIREMENT EXEMPTION JUSTIFICATIONS FOR VENTILATION SYSTEMS AT NUCLEAR WASTE STORAGE TANKS AT THE HANFORD SITE  

SciTech Connect (OSTI)

Washington State Department of Health regulations require compliance with the American Society of Mechanical Engineers (ASME) AG-1, ''Code on Nuclear Air and Gas Treatment,'' for all new radioactive air emission units. As a result, these requirements have been applied to systems that ventilate the radioactive waste storage tanks in the tank farm facilities on the U.S. Department of Energy's Hanford Site. ASME AG-1 is applied as a regulatory constraint to waste tank ventilation systems at the Hanford Site, even though the code was not intended for these systems. An assessment was performed to identify which requirements should be exempted for waste tank ventilation systems. The technical justifications for requirement exemptions were prepared and presented to the regulator. The technical justifications were documented so that select requirement exemptions for specific projects and systems can be sought through the regulator's permitting process. This paper presents the rationale for attempting to receive requirement exemption and presents examples of the technical justifications that form the basis for these exemptions.

GUSTAVSON, R.D.

2004-09-03T23:59:59.000Z

360

Nondestructive examination of DOE high-level waste storage tanks  

SciTech Connect (OSTI)

A number of DOE sites have buried tanks containing high-level waste. Tanks of particular interest am double-shell inside concrete cylinders. A program has been developed for the inservice inspection of the primary tank containing high-level waste (HLW), for testing of transfer lines and for the inspection of the concrete containment where possible. Emphasis is placed on the ultrasonic examination of selected areas of the primary tank, coupled with a leak-detection system capable of detecting small leaks through the wall of the primary tank. The NDE program is modelled after ASME Section XI in many respects, particularly with respects to the sampling protocol. Selected testing of concrete is planned to determine if there has been any significant degradation. The most probable failure mechanisms are corrosion-related so that the examination program gives major emphasis to possible locations for corrosion attack.

Bush, S.; Bandyopadhyay, K.; Kassir, M.; Mather, B.; Shewmon, P.; Streicher, M.; Thompson, B.; van Rooyen, D.; Weeks, J.

1995-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Waste treatment facility passes federal inspection, completes final  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched FerromagnetismWaste and Materials Disposition Information Waste and

362

CSER 94-004: Criticality safety of double-shell waste storage tanks  

SciTech Connect (OSTI)

This criticality safety evaluation covers double-shell waste storage tanks (DSTs), double-contained receiver tanks (DCRTs), vault tanks, and the 242-A Evaporator located in the High Level Waste (HLW) Tank Farms on the Hanford Site. Limits and controls are specified and the basis for ensuring criticality safety is discussed. A minimum limit of 1,000 is placed upon the solids/plutonium mass ratio in incoming waste. The average solids/Pu mass ratio over all waste in tank farms is estimated to be about 74,500, about 150 times larger than required to assure subcriticality in homogeneous waste. PFP waste in Tank-102-SY has an estimated solids/Pu mass ratio of 10,000. Subcriticality is assured whenever the plutonium concentration is less than 2.6 g. The median reported plutonium concentration for 200 samples of waste solids is about 0.01 g (0.038 g/gal). A surveillance program is proposed to increase the knowledge of the waste and provide added assurance of the high degree of subcriticality.

Rogers, C.A.

1994-09-22T23:59:59.000Z

363

Bubblers Speed Nuclear Waste Processing at SRS  

SciTech Connect (OSTI)

At the Department of Energy's Savannah River Site, American Recovery and Reinvestment Act funding has supported installation of bubbler technology and related enhancements in the Defense Waste Processing Facility (DWPF). The improvements will accelerate the processing of radioactive waste into a safe, stable form for storage and permit expedited closure of underground waste tanks holding 37 million gallons of liquid nuclear waste.

None

2010-11-14T23:59:59.000Z

364

Bubblers Speed Nuclear Waste Processing at SRS  

ScienceCinema (OSTI)

At the Department of Energy's Savannah River Site, American Recovery and Reinvestment Act funding has supported installation of bubbler technology and related enhancements in the Defense Waste Processing Facility (DWPF). The improvements will accelerate the processing of radioactive waste into a safe, stable form for storage and permit expedited closure of underground waste tanks holding 37 million gallons of liquid nuclear waste.

None

2014-08-06T23:59:59.000Z

365

Working with SRNL - Our Facilities- Waste Treatment Laboratories  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched FerromagnetismWaste and MaterialsWenjun1 Table 1.14WorkingPrimaryWaste Treatment

366

Decommissioning and waste disposal methods for an uranium mill facility in Spain  

SciTech Connect (OSTI)

In the south of Spain on the outskirts of the town of Andujar an inactive uranium mill tailings pile is being stabilized in place. Mill equipment, buildings and process facilities have been dismantled and demolished and the resulting metal wastes and debris will be placed in the pile. The tailings mass is being reshaped by flattening the sideslopes and a cover system will be placed over the pile. This paper describes the technical procedures used for the remediation and closure of the Andujar mill site and in particular discusses the approaches used for the dismantling and demolition of the processing facilities and the disposal of the metal wastes and demolition debris.

Santiago, J.L. [ENRESA, Madrid (Spain); Sanchez, M. [INITEC, Madrid (Spain)

1993-12-31T23:59:59.000Z

367

The Mixed Waste Management Facility. Design basis integrated operations plan (Title I design)  

SciTech Connect (OSTI)

The Mixed Waste Management Facility (MWMF) will be a fully integrated, pilotscale facility for the demonstration of low-level, organic-matrix mixed waste treatment technologies. It will provide the bridge from bench-scale demonstrated technologies to the deployment and operation of full-scale treatment facilities. The MWMF is a key element in reducing the risk in deployment of effective and environmentally acceptable treatment processes for organic mixed-waste streams. The MWMF will provide the engineering test data, formal evaluation, and operating experience that will be required for these demonstration systems to become accepted by EPA and deployable in waste treatment facilities. The deployment will also demonstrate how to approach the permitting process with the regulatory agencies and how to operate and maintain the processes in a safe manner. This document describes, at a high level, how the facility will be designed and operated to achieve this mission. It frequently refers the reader to additional documentation that provides more detail in specific areas. Effective evaluation of a technology consists of a variety of informal and formal demonstrations involving individual technology systems or subsystems, integrated technology system combinations, or complete integrated treatment trains. Informal demonstrations will typically be used to gather general operating information and to establish a basis for development of formal demonstration plans. Formal demonstrations consist of a specific series of tests that are used to rigorously demonstrate the operation or performance of a specific system configuration.

NONE

1994-12-01T23:59:59.000Z

368

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

SciTech Connect (OSTI)

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

Lisa Harvego; Mike Lehto

2010-05-01T23:59:59.000Z

369

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

SciTech Connect (OSTI)

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

Lisa Harvego; Mike Lehto

2010-02-01T23:59:59.000Z

370

Mobile Pit verification system design based on passive special nuclear material verification in weapons storage facilities  

SciTech Connect (OSTI)

A mobile 'drive by' passive radiation detection system to be applied in special nuclear materials (SNM) storage facilities for validation and compliance purposes has been designed through the use of computational modeling and new radiation detection methods. This project was the result of work over a 1 year period to create optimal design specifications to include creation of 3D models using both Monte Carlo and deterministic codes to characterize the gamma and neutron leakage out each surface of SNM-bearing canisters. Results were compared and agreement was demonstrated between both models. Container leakages were then used to determine the expected reaction rates using transport theory in the detectors when placed at varying distances from the can. A 'typical' background signature was incorporated to determine the minimum signatures versus the probability of detection to evaluate moving source protocols with collimation. This established the criteria for verification of source presence and time gating at a given vehicle speed. New methods for the passive detection of SNM were employed and shown to give reliable identification of age and material for highly enriched uranium (HEU) and weapons grade plutonium (WGPu). The finalized 'Mobile Pit Verification System' (MPVS) design demonstrated that a 'drive-by' detection system, collimated and operating at nominally 2 mph, is capable of rapidly verifying each and every weapon pit stored in regularly spaced, shelved storage containers, using completely passive gamma and neutron signatures for HEU and WGPu. This system is ready for real evaluation to demonstrate passive total material accountability in storage facilities. (authors)

Paul, J. N.; Chin, M. R.; Sjoden, G. E. [Nuclear and Radiological Engineering Program, George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, 770 State St, Atlanta, GA 30332-0745 (United States)

2013-07-01T23:59:59.000Z

371

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

SciTech Connect (OSTI)

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

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

2012-05-01T23:59:59.000Z

372

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

SciTech Connect (OSTI)

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.

Not Available

1993-03-01T23:59:59.000Z

373

Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington  

SciTech Connect (OSTI)

This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ``Safety Measures for Waste Tanks at Hanford Nuclear Reservation,`` of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues.

Not Available

1994-07-01T23:59:59.000Z

374

Steam reforming as a method to treat Hanford underground storage tank (UST) wastes  

SciTech Connect (OSTI)

This report summarizes a Sandia program that included partnerships with Lawrence Livermore National Laboratory and Synthetica Technologies, Inc. to design and test a steam reforming system for treating Hanford underground storage tank (UST) wastes. The benefits of steam reforming the wastes include the resolution of tank safety issues and improved radionuclide separations. Steam reforming destroys organic materials by first gasifying, then reacting them with high temperature steam. Tests indicate that up to 99% of the organics could be removed from the UST wastes by steam exposure. In addition, it was shown that nitrates in the wastes could be destroyed by steam exposure if they were first distributed as a thin layer on a surface. High purity alumina and nickel alloys were shown to be good candidates for materials to be used in the severe environment associated with steam reforming the highly alkaline, high nitrate content wastes. Work was performed on designing, building, and demonstrating components of a 0.5 gallon per minute (gpm) system suitable for radioactive waste treatment. Scale-up of the unit to 20 gpm was also considered and is feasible. Finally, process demonstrations conducted on non-radioactive waste surrogates were carried out, including a successful demonstration of the technology at the 0.1 gpm scale.

Miller, J.E.; Kuehne, P.B. [eds.] [and others

1995-07-01T23:59:59.000Z

375

Mixed Waste Management Facility (MWMF) groundwater monitoring report. Second quarter 1993  

SciTech Connect (OSTI)

Groundwater monitoring continued at the Savannah River Plant. During second quarter 1993, nine constituents exceeded final Primary Drinking Water Standards in groundwater samples from downgradient monitoring wells at the Mixed Waste Management Facility, the Old Burial Ground, the E-Area Vaults, and the proposed Hazardous Waste/Mixed Waste Disposal Vaults. As in previous quarters, tritium and trichloroethylene were the most widespread constituents. Chloroethene (vinyl chloride), dichloromethane (methylene chloride), 1,1-dichloroethylene, gross alpha, lead, nonvolatile beta, or tetrachloroethylene also exceeded standards in one or more wells. The groundwater flow directions and rates in the three hydrostratigraphic units were similar to those of previous quarters.

Not Available

1993-09-01T23:59:59.000Z

376

RESULTS OF THE EXTRACTION-SCRUB-STRIP TESTING USING AN IMPROVED SOLVENT FORMULATION AND SALT WASTE PROCESSING FACILITY SIMULATED WASTE  

SciTech Connect (OSTI)

The Office of Waste Processing, within the Office of Technology Innovation and Development, is funding the development of an enhanced solvent - also known as the next generation solvent (NGS) - for deployment at the Savannah River Site to remove cesium from High Level Waste. The technical effort is a collaborative effort between Oak Ridge National Laboratory (ORNL) and Savannah River National Laboratory (SRNL). As part of the program, the Savannah River National Laboratory (SRNL) has performed a number of Extraction-Scrub-Strip (ESS) tests. These batch contact tests serve as first indicators of the cesium mass transfer solvent performance with actual or simulated waste. The test detailed in this report used simulated Tank 49H material, with the addition of extra potassium. The potassium was added at 1677 mg/L, the maximum projected (i.e., a worst case feed scenario) value for the Salt Waste Processing Facility (SWPF). The results of the test gave favorable results given that the potassium concentration was elevated (1677 mg/L compared to the current 513 mg/L). The cesium distribution value, DCs, for extraction was 57.1. As a comparison, a typical D{sub Cs} in an ESS test, using the baseline solvent formulation and the typical waste feed, is {approx}15. The Modular Caustic Side Solvent Extraction Unit (MCU) uses the Caustic-Side Solvent Extraction (CSSX) process to remove cesium (Cs) from alkaline waste. This process involves the use of an organic extractant, BoBCalixC6, in an organic matrix to selectively remove cesium from the caustic waste. The organic solvent mixture flows counter-current to the caustic aqueous waste stream within centrifugal contactors. After extracting the cesium, the loaded solvent is stripped of cesium by contact with dilute nitric acid and the cesium concentrate is transferred to the Defense Waste Processing Facility (DWPF), while the organic solvent is cleaned and recycled for further use. The Salt Waste Processing Facility (SWPF), under construction, will use the same process chemistry. The Office of Waste Processing (EM-31) expressed an interest in investigating the further optimization of the organic solvent by replacing the BoBCalixC6 extractant with a more efficient extractant. This replacement should yield dividends in improving cesium removal from the caustic waste stream, and in the rate at which the caustic waste can be processed. To that end, EM-31 provided funding for both the Savannah River National Laboratory (SRNL) and the Oak Ridge National Laboratory (ORNL). SRNL wrote a Task Technical Quality and Assurance Plan for this work. As part of the envisioned testing regime, it was decided to perform an ESS test using a simulated waste that simulated a typical envisioned SWPF feed, but with added potassium to make the waste more challenging. Potassium interferes in the cesium removal, and its concentration is limited in the feed to <1950 mg/L. The feed to MCU has typically contained <500 mg/L of potassium.

Peters, T.; Washington, A.; Fink, S.

2012-01-09T23:59:59.000Z

377

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

SciTech Connect (OSTI)

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

Boyd D. Christensen

2010-02-01T23:59:59.000Z

378

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

SciTech Connect (OSTI)

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

Boyd D. Christensen

2010-05-01T23:59:59.000Z

379

Quality Assurance Program Plan (QAPP) Waste Management Project  

SciTech Connect (OSTI)

This document is the Quality Assurance Program Plan (QAPP) for Waste Management Federal Services of Hanford, Inc. (WMH), that implements the requirements of the Project Hanford Management Contract (PHMC), HNF-MP-599, Project Hanford Quality Assurance Program Description (QAPD) document, and the Hanford Federal Facility Agreement with Consent Order (Tri-Party Agreement), Sections 6.5 and 7.8. WHM is responsible for the treatment, storage, and disposal of liquid and solid wastes generated at the Hanford Site as well as those wastes received from other US Department of Energy (DOE) and non-DOE sites. WMH operations include the Low-Level Burial Grounds, Central Waste Complex (a mixed-waste storage complex), a nonradioactive dangerous waste storage facility, the Transuranic Storage Facility, T Plant, Waste Receiving and Processing Facility, 200 Area Liquid Effluent Facility, 200 Area Treated Effluent Disposal Facility, the Liquid Effluent Retention Facility, the 242-A Evaporator, 300 Area Treatment Effluent Disposal Facility, the 340 Facility (a radioactive liquid waste handling facility), 222-S Laboratory, the Waste Sampling and Characterization Facility, and the Hanford TRU Waste Program.

VOLKMAN, D.D.

1999-10-27T23:59:59.000Z

380

Water-related environmental control requirements at municipal solid waste-to-energy conversion facilities  

SciTech Connect (OSTI)

Water use and waste water production, water pollution control technology requirements, and water-related limitations to their design and commercialization are identified at municipal solid waste-to-energy conversion systems. In Part I, a summary of conclusions and recommendations provides concise statements of findings relative to water management and waste water treatment of each of four municipal solid waste-to-energy conversion categories investigated. These include: mass burning, with direct production of steam for use as a supplemental energy source; mechanical processing to produce a refuse-derived fuel (RDF) for co-firing in gas, coal or oil-fired power plants; pyrolysis for production of a burnable oil or gas; and biological conversion of organic wastes to methane. Part II contains a brief description of each waste-to-energy facility visited during the subject survey showing points of water use and wastewater production. One or more facilities of each type were selected for sampling of waste waters and follow-up tests to determine requirements for water-related environmental controls. A comprehensive summary of the results are presented. (MCW)

Young, J C; Johnson, L D

1980-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

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

SciTech Connect (OSTI)

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

Smith, M.; Iverson, D.

2010-12-08T23:59:59.000Z

382

Total Measurement Uncertainty (TMU) for Nondestructive Assay of Transuranic (TRU) Waste at the WRAP Facility  

SciTech Connect (OSTI)

At the WRAP facility, there are two identical imaging passive/active neutron (IPAN) assay systems and two identical gamma energy assay (GEA) systems. Currently, only the GEA systems are used to characterize waste, therefore, only the GEA systems are addressed in this document. This document contains the limiting factors relating to the waste drum analysis for shipments destined for WIPP. The TMU document provides the uncertainty basis in the NDA analysis of waste containers at the WRAP facility. The defined limitations for the current analysis scheme are as follows: (1) The WRAP waste stream debris is from the Hanford Plutonium Finishing Plant's process lines, primarily combustible materials. (2) Plutonium analysis range is from the minimum detectable concentration (MDC), Reference 6, to 200 grams (g). (3) The GEA system calibration density ranges from 0.013 g/cc to 1.6 g/cc. (4) PDP Plutonium drum densities were evaluated from 0.065 g/cc to 0.305 g/cc. (5) PDP Plutonium source weights ranged from 0.030 g to 318 g, in both empty and combustibles matrix drums. (6) The GEA system design density correction mass absorption coefficient table (MAC) is Lucite, a material representative of combustible waste. (7) Drums with material not fitting the debris waste criteria are targeted for additional calculations, reviews, and potential re-analysis using a calibration suited for the waste type.

CANTALOUB, M.G.

2000-10-20T23:59:59.000Z

383

Total Measurement Uncertainty (TMU) for Nondestructive Assay of Transuranic (TRU) Waste at the WRAP Facility  

SciTech Connect (OSTI)

At the WRAP facility, there are two identical imaging passive/active neutron (IPAN) assay systems and two identical gamma energy assay (GEA) systems. Currently, only the GEA systems are used to characterize waste, therefore, only the GEA systems are addressed in this document. This document contains the limiting factors relating to the waste drum analysis for shipments destined for WIPP. The TMU document provides the uncertainty basis in the NDA analysis of waste containers at the WRAP facility. The defined limitations for the current analysis scheme are as follows: The WRAP waste stream debris is from the Hanford Plutonium Finishing Plant's process lines, primarily combustible materials. Plutonium analysis range is from the minimum detectable concentration (MDC), Reference 6, to 160 grams (8). The GEA system calibration density ranges from 0.013 g/cc to 1.6 g/cc. PDP Plutonium drum densities were evaluated from 0.065 g/cc to 0.305 gkc. PDP Plutonium source weights ranged from 0.030 g to 3 18 g, in both empty and combustibles matrix drums. The GEA system design density correction macroscopic absorption cross section table (MAC) is Lucite, a material representative of combustible waste. Drums with material not fitting the debris waste criteria are targeted for additional calculations, reviews, and potential re-analysis using a calibration suited for the waste type.

CANTALOUB, M.G.

2000-05-22T23:59:59.000Z

384

Central Waste Complex (CWC) Waste Analysis Plan  

SciTech Connect (OSTI)

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for waste accepted for storage at the Central Waste Complex (CWC), which is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include the source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

ELLEFSON, M.D.

1999-12-01T23:59:59.000Z

385

RECENT PROCESS AND EQUIPMENT IMPROVEMENTS TO INCREASE HIGH LEVEL WASTE THROUGHPUT AT THE DEFENSE WASTE PROCESSING FACILITY  

SciTech Connect (OSTI)

The Savannah River Site's (SRS) Defense Waste Processing Facility (DWPF) began stabilizing high level waste (HLW) in a glass matrix in 1996. Over the past few years, there have been several process and equipment improvements at the DWPF to increase the rate at which the high level waste can be stabilized. These improvements have either directly increased waste processing rates or have desensitized the process to upsets, thereby minimizing downtime and increasing production. Improvements due to optimization of waste throughput with increased HLW loading of the glass resulted in a 6% waste throughput increase based upon operational efficiencies. Improvements in canister production include the pour spout heated bellows liner (5%), glass surge (siphon) protection software (2%), melter feed pump software logic change to prevent spurious interlocks of the feed pump with subsequent dilution of feed stock (2%) and optimization of the steam atomized scrubber (SAS) operation to minimize downtime (3%) for a total increase in canister production of 12%. A number of process recovery efforts have allowed continued operation. These include the off gas system pluggage and restoration, slurry mix evaporator (SME) tank repair and replacement, remote cleaning of melter top head center nozzle, remote melter internal inspection, SAS pump J-Tube recovery, inadvertent pour scenario resolutions, dome heater transformer bus bar cooling water leak repair and new Infra-red camera for determination of glass height in the canister are discussed.

Odriscoll, R; Allan Barnes, A; Jim Coleman, J; Timothy Glover, T; Robert Hopkins, R; Dan Iverson, D; Jeff Leita, J

2008-01-15T23:59:59.000Z

386

A ground-coupled storage heat pump system with waste heat recovery  

SciTech Connect (OSTI)

This paper reports on an experimental single-family residence that was constructed to demonstrate integration of waste heat recovery and seasonal energy storage using both a ventilating and a ground-coupled heat pump. Called the Idaho energy Conservation Technology House, it combines superinsulated home construction with a ventilating hot water heater and a ground coupled water-to-water heat pump system. The ground heat exchangers are designed to economically promote seasonal and waste heat storage. Construction of the house was completed in the spring of 1989. Located in Moscow, Idaho, the house is occupied by a family of three. The 3,500 ft{sup 2} (325 m{sup 2}) two-story house combines several unique sub-systems that all interact to minimize energy consumption for space heating and cooling, and domestic hot water.

Drown, D.C.; Braven, K.R.D. (Univ. of Idaho, ID (US)); Kast, T.P. (Thermal Dynamic Towers, Boulder, CO (US))

1992-02-01T23:59:59.000Z

387

Establishment of a facility for intrusive characterization of transuranic waste at the Nevada Test Site  

SciTech Connect (OSTI)

This paper describes design and construction, project management, and testing results associated with the Waste Examination Facility (WEF) recently constructed at the Nevada Test Site (NTS). The WEF and associated systems were designed, procured, and constructed on an extremely tight budget and within a fast track schedule. Part 1 of this paper focuses on design and construction activities, Part 2 discusses project management of WEF design and construction activities, and Part 3 describes the results of the transuranic (TRU) waste examination pilot project conducted at the WEF. In Part 1, the waste examination process is described within the context of Waste Isolation Pilot Plant (WIPP) characterization requirements. Design criteria are described from operational and radiological protection considerations. The WEF engineered systems are described. These systems include isolation barriers using a glove box and secondary containment structure, high efficiency particulate air (HEPA) filtration and ventilation systems, differential pressure monitoring systems, and fire protection systems. In Part 2, the project management techniques used for ensuring that stringent cost/schedule requirements were met are described. The critical attributes of these management systems are described with an emphasis on team work. In Part 3, the results of a pilot project directed at performing intrusive characterization (i.e., examination) of TRU waste at the WEF are described. Project activities included cold and hot operations. Cold operations included operator training, facility systems walk down, and operational procedures validation. Hot operations included working with plutonium contaminated TRU waste and consisted of waste container breaching, waste examination, waste segregation, data collection, and waste repackaging.

Foster, B.D.; Musick, R.G.; Pedalino, J.P.; Cowley, J.L. [Bechtel Nevada Corp., Las Vegas, NV (United States); Karney, C.C. [Dept. of Energy, Las Vegas, NV (United States); Kremer, J.L.

1998-01-01T23:59:59.000Z

388

Savannah River Site Salt Waste Processing Facility Technology Readiness  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartment of Energy fromCommentsRevolving STATEMENT OFSanEnergyWasteSeniorAssessment

389

Weidlinger-Navarro selected for waste staging facility design support  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched FerromagnetismWaste and Materials Disposition3February 2015

390

Power Hardware-in-the-Loop (PHIL) Testing Facility for Distributed Energy Storage (Poster)  

SciTech Connect (OSTI)

The growing deployment of distributed, variable generation and evolving end-user load profiles presents a unique set of challenges to grid operators responsible for providing reliable and high quality electrical service. Mass deployment of distributed energy storage systems (DESS) has the potential to solve many of the associated integration issues while offering reliability and energy security benefits other solutions cannot. However, tools to develop, optimize, and validate DESS control strategies and hardware are in short supply. To fill this gap, NREL has constructed a power hardware-in-the-loop (PHIL) test facility that connects DESS, grid simulator, and load bank hardware to a distribution feeder simulation.

Neubauer.J.; Lundstrom, B.; Simpson, M.; Pratt, A.

2014-06-01T23:59:59.000Z

391

Oak Ridge National Laboratory Old Hydrofracture Facility Waste Remediation Using the Borehole-Miner Extendible-Nozzle Sluicer  

SciTech Connect (OSTI)

A borehole-miner extendible-nozzle sluicing system was designed, constructed, and deployed at Oak Ridge National Laboratory to remediate five horizontal underground storage tanks containing sludge and supernate at the ORNL Old Hydrofracture Facility site. The tanks were remediated in fiscal year 1998 to remove {approx}98% of the waste, {approx}3% greater than the target removal of >95% of the waste. The tanks contained up to 18 in. of sludge covered by supernate. The 42,000 gal of low level liquid waste were estimated to contain 30,000 Ci, with 97% of this total located in the sludge. The retrieval was successful. At the completion of the remediation, the State of Tennessee Department of Environment and Conservation agreed that the tanks were cleaned to the maximum extent practicable using pumping technology. This deployment was the first radioactive demonstration of the borehole-miner extendible-nozzle water-jetting system. The extendible nozzle is based on existing bore hole-miner technology used to fracture and dislodge ore deposits in mines. Typically borehole-miner technology includes both dislodging and retrieval capabilities. Both dislodging, using the extendible-nozzle water-jetting system, and retrieval, using a jet pump located at the base of the mast, are deployed as an integrated system through one borehole or riser. Note that the extendible-nozzle system for Oak Ridge remediation only incorporated the dislodging capability; the retrieval pump was deployed through a separate riser. The borehole-miner development and deployment is part of the Retrieval Process Development and Enhancements project under the direction of the US Department of Energy's EM-50 Tanks Focus Area. This development and deployment was conducted as a partnership between RPD and E and the Oak Ridge National Laboratory's US DOE EM040 Old Hydrofracture Facility remediation project team.

Bamberger, J.A.; Boris, G.F.

1999-10-07T23:59:59.000Z

392

Analysis of long-term impacts of TRU waste remaining at generator/storage sites for No Action Alternative 2  

SciTech Connect (OSTI)

This report is a supplement to the Waste Isolation Pilot Plant Disposal-Phase Final Supplemental Environmental Impact Statement (SEIS-II). Described herein are the underlying information, data, and assumptions used to estimate the long-term human-health impacts from exposure to radionuclides and hazardous chemicals in transuranic (TRU) waste remaining at major generator/storage sites after loss of institutional control under No Action Alternative 2. Under No Action Alternative 2, TRU wastes would not be emplaced at the Waste Isolation Pilot Plant (WIPP) but would remain at generator/storage sites in surface or near-surface storage. Waste generated at smaller sites would be consolidated at the major generator/storage sites. Current TRU waste management practices would continue, but newly generated waste would be treated to meet the WIPP waste acceptance criteria. For this alternative, institutional control was assumed to be lost 100 years after the end of the waste generation period, with exposure to radionuclides and hazardous chemicals in the TRU waste possible from direct intrusion and release to the surrounding environment. The potential human-health impacts from exposure to radionuclides and hazardous chemicals in TRU waste were analyzed for two different types of scenarios. Both analyses estimated site-specific, human-health impacts at seven major generator/storage sites: the Hanford Site (Hanford), Idaho National Engineering and Environmental Laboratory (INEEL), Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Rocky Flats Environmental Technology Site (RFETS), and Savannah River Site (SRS). The analysis focused on these seven sites because 99 % of the estimated TRU waste volume and inventory would remain there under the assumptions of No Action Alternative 2.

Buck, J.W.; Bagaasen, L.M.; Bergeron, M.P.; Streile, G.P. [and others

1997-09-01T23:59:59.000Z

393

Mixed Waste Management Facility (MWMF) closure, Savannah River Plant: Clay cap test section construction report  

SciTech Connect (OSTI)

This report contains appendices 3 through 6 for the Clay Cap Test Section Construction Report for the Mixed Waste Management Facility (MWMF) closure at the Savannah River Plant. The Clay Cap Test Program was conducted to evaluate the source, lab. permeability, in-situ permeability, and compaction characteristics, representative of kaolin clays from the Aiken, South Carolina vicinity. (KJD)

Not Available

1988-02-26T23:59:59.000Z

394

Closure Plan for the E-Area Low-Level Waste Facility  

SciTech Connect (OSTI)

A closure plan has been developed to comply with the applicable requirements of the U.S. Department of Energy Order 435.2 Manual and Guidance. The plan is organized according to the specifications of the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans.

Cook, J.R.

2000-10-30T23:59:59.000Z

395

METHODS FOR DETERMINING AGITATOR MIXING REQUIREMENTS FOR A MIXING & SAMPLING FACILITY TO FEED WTP (WASTE TREATMENT PLANT)  

SciTech Connect (OSTI)

The following report is a summary of work conducted to evaluate the ability of existing correlative techniques and alternative methods to accurately estimate impeller speed and power requirements for mechanical mixers proposed for use in a mixing and sampling facility (MSF). The proposed facility would accept high level waste sludges from Hanford double-shell tanks and feed uniformly mixed high level waste to the Waste Treatment Plant. Numerous methods are evaluated and discussed, and resulting recommendations provided.

GRIFFIN PW

2009-08-27T23:59:59.000Z

396

A New Concept: Use of Negotiations in the Hazardous Waste Facility Permitting Process in New Mexico  

SciTech Connect (OSTI)

This paper describes a unique negotiation process leading to authorization of the U.S. Department of Energy (DOE) to manage and dispose remote-handled (RH) transuranic (TRU) mixed wastes at the Waste Isolation Pilot Plant (WIPP). The negotiation process involved multiple entities and individuals brought together under authority of the New Mexico Environment Department (NMED) to discuss and resolve technical and facility operational issues flowing from an NMED-issued hazardous waste facility Draft Permit. The novel negotiation process resulted in numerous substantive changes to the Draft Permit, which were ultimately memorialised in a 'Draft Permit as Changed'. This paper discusses various aspects of the negotiation process, including events leading to the negotiations, regulatory basis for the negotiations, negotiation participants, and benefits of the process. (authors)

Johnson, G.J. [Washington TRU Solutions, LLC, Waste Isolation Pilot Plant, New Mexico (United States); Rose, W.M. [U.S. Department of Energy, Carlsbad Field Office, Waste Isolation Pilot Plant, New Mexico (United States); Domenici, P.V.; Hollingsworth, L. [Domenici Law Firm PC, Albuquerque, New Mexico (United States)

2007-07-01T23:59:59.000Z

397

Closure of hazardous and mixed radioactive waste management units at DOE facilities. [Contains glossary  

SciTech Connect (OSTI)

This is document addresses the Federal regulations governing the closure of hazardous and mixed waste units subject to Resource Conservation and Recovery Act (RCRA) requirements. It provides a brief overview of the RCRA permitting program and the extensive RCRA facility design and operating standards. It provides detailed guidance on the procedural requirements for closure and post-closure care of hazardous and mixed waste management units, including guidance on the preparation of closure and post-closure plans that must be submitted with facility permit applications. This document also provides guidance on technical activities that must be conducted both during and after closure of each of the following hazardous waste management units regulated under RCRA.

Not Available

1990-06-01T23:59:59.000Z

398

Facility effluent monitoring plan for the Waste Receiving and Processing Facility Module 1  

SciTech Connect (OSTI)

A facility effluent monitoring plan is required by the US Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal state, and local requirements. This facility effluent monitoring plan shall ensure lonq-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years.

Lewis, C.J.

1995-10-01T23:59:59.000Z

399

Independent Oversight Assessment, Salt Waste Processing Facility Project -  

Broader source: Energy.gov (indexed) [DOE]

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400

Hazardous Waste Facility Permit Public Comments to Community Relations Plan  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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401

Hazardous Waste Facility Permit Public Comments to Community Relations Plan  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpgcommunity200cell 9Harvey Brooks, 1960OptionsHazardous Waste

402

Comparative assessment of status and opportunities for carbon Dioxide Capture and storage and Radioactive Waste Disposal In North America  

SciTech Connect (OSTI)

Aside from the target storage regions being underground, geologic carbon sequestration (GCS) and radioactive waste disposal (RWD) share little in common in North America. The large volume of carbon dioxide (CO{sub 2}) needed to be sequestered along with its relatively benign health effects present a sharp contrast to the limited volumes and hazardous nature of high-level radioactive waste (RW). There is well-documented capacity in North America for 100 years or more of sequestration of CO{sub 2} from coal-fired power plants. Aside from economics, the challenges of GCS include lack of fully established legal and regulatory framework for ownership of injected CO{sub 2}, the need for an expanded pipeline infrastructure, and public acceptance of the technology. As for RW, the USA had proposed the unsaturated tuffs of Yucca Mountain, Nevada, as the region's first high-level RWD site before removing it from consideration in early 2009. The Canadian RW program is currently evolving with options that range from geologic disposal to both decentralized and centralized permanent storage in surface facilities. Both the USA and Canada have established legal and regulatory frameworks for RWD. The most challenging technical issue for RWD is the need to predict repository performance on extremely long time scales (10{sup 4}-10{sup 6} years). While attitudes toward nuclear power are rapidly changing as fossil-fuel costs soar and changes in climate occur, public perception remains the most serious challenge to opening RW repositories. Because of the many significant differences between RWD and GCS, there is little that can be shared between them from regulatory, legal, transportation, or economic perspectives. As for public perception, there is currently an opportunity to engage the public on the benefits and risks of both GCS and RWD as they learn more about the urgent energy-climate crisis created by greenhouse gas emissions from current fossil-fuel combustion practices.

Oldenburg, C.; Birkholzer, J.T.

2011-07-22T23:59:59.000Z

403

Radioactive Waste Management at the New Conversion Facility of 'TVEL'{sup R} Fuel Company - 13474  

SciTech Connect (OSTI)

The project on the new conversion facility construction is being implemented by Joint Stock Company (JSC) 'Siberian Group of Chemical Enterprises' (SGChE) within TVEL{sup R} Fuel Company. The objective is to construct the up-to-date facility ensuring the industrial and environmental safety with the reduced impact on the community and environment in compliance with the Russian new regulatory framework on radioactive waste (RW) management. The history of the SGChE development, as well as the concepts and approaches to RW management implemented by now are shown. The SGChE future image is outlined, together with its objectives and concept on RW management in compliance with the new act 'On radioactive waste management' adopted in Russia in 2011. Possible areas of cooperation with international companies are discussed in the field of RW management with the purpose of deploying the best Russian and world practices on RW management at the new conversion facility. (authors)

Indyk, S.I.; Volodenko, A.V. [JSC 'TVEL', Russia, Moscow, 49 Kashirskoye Shosse, 115409 (Russian Federation)] [JSC 'TVEL', Russia, Moscow, 49 Kashirskoye Shosse, 115409 (Russian Federation); Tvilenev, K.A.; Tinin, V.V.; Fateeva, E.V. [JSC 'Siberian Group of Chemical Enterprises', Russia, Seversk, 1 Kurchatov Street, 636000 (Russian Federation)] [JSC 'Siberian Group of Chemical Enterprises', Russia, Seversk, 1 Kurchatov Street, 636000 (Russian Federation)

2013-07-01T23:59:59.000Z

404

Maximization of revenues for power sales from a solid waste resources recovery facility  

SciTech Connect (OSTI)

The report discusses the actual implementation of the best alternative in selling electrical power generated by an existing waste-to-energy facility, the Metro-Dade County Resources Recovery Plant. After the plant processes and extracts various products out of the municipal solid waste, it burns it to produce electrical power. The price for buying power to satisfy the internal needs of our Resources Recovery Facility (RRF) is substantially higher than the power price for selling electricity to any other entity. Therefore, without any further analysis, it was decided to first satisfy those internal needs and then export the excess power. Various alternatives were thoroughly explored as to what to do with the excess power. Selling power to the power utilities or utilizing the power in other facilities were the primary options.

Not Available

1991-12-01T23:59:59.000Z

405

E AREA LOW LEVEL WASTE FACILITY DOE 435.1 PERFORMANCE ASSESSMENT  

SciTech Connect (OSTI)

This Performance Assessment for the Savannah River Site E-Area Low-Level Waste Facility was prepared to meet requirements of Chapter IV of the Department of Energy Order 435.1-1. The Order specifies that a Performance Assessment should provide reasonable assurance that a low-level waste disposal facility will comply with the performance objectives of the Order. The Order also requires assessments of impacts to water resources and to hypothetical inadvertent intruders for purposes of establishing limits on radionuclides that may be disposed near-surface. According to the Order, calculations of potential doses and releases from the facility should address a 1,000-year period after facility closure. The point of compliance for the performance measures relevant to the all pathways and air pathway performance objective, as well as to the impact on water resources assessment requirement, must correspond to the point of highest projected dose or concentration beyond a 100-m buffer zone surrounding the disposed waste following the assumed end of active institutional controls 100 years after facility closure. During the operational and institutional control periods, the point of compliance for the all pathways and air pathway performance measures is the SRS boundary. However, for the water resources impact assessment, the point of compliance remains the point of highest projected dose or concentration beyond a 100-m buffer zone surrounding the disposed waste during the operational and institutional control periods. For performance measures relevant to radon and inadvertent intruders, the points of compliance are the disposal facility surface for all time periods and the disposal facility after the assumed loss of active institutional controls 100 years after facility closure, respectively. The E-Area Low-Level Waste Facility is located in the central region of the SRS known as the General Separations Area. It is an elbow-shaped, cleared area, which curves to the northwest, situated immediately north of the Mixed Waste Management Facility. The E-Area Low-Level Waste Facility is comprised of 200 acres for waste disposal and a surrounding buffer zone that extends out to the 100-m point of compliance. Disposal units within the footprint of the low-level waste facilities include the Slit Trenches, Engineered Trenches, Component-in-Grout Trenches, the Low-Activity Waste Vault, the Intermediate-Level Vault, and the Naval Reactor Component Disposal Area. Radiological waste disposal operations at the E-Area Low-Level Waste Facility began in 1994. E-Area Low-Level Waste Facility closure will be conducted in three phases: operational closure, interim closure, and final closure. Operational closure will be conducted during the 25-year operation period (30-year period for Slit and Engineered Trenches) as disposal units are filled; interim closure measures will be taken for some units. Interim closure will take place following the end of operations and will consist of an area-wide runoff cover along with additional grading over the trench units. Final closure of all disposal units in the E-Area Low-Level Waste Facility will take place at the end of the 100-year institutional control period and will consist of the installation of an integrated closure system designed to minimize moisture contact with the waste and to serve as a deterrent to intruders. Radiological dose to human receptors is analyzed in this PA in the all-pathways analysis, the inadvertent intruder analysis and the air pathway analysis, and the results are compared to the relevant performance measures. For the all-pathways analysis, the performance measure of relevance is a 25-mrem/yr EDE to representative members of the public, excluding dose from radon and its progeny in air. For the inadvertent intruder, the applicable performance measures are 100-mrem/yr EDE and 500 mrem/yr EDE for chronic and exposure scenarios, respectively. The relevant performance measure for the air pathway is 10-mrem/yr EDE via the air pathway, excluding dose from radon and its progeny in air. Protecti

Wilhite, E

2008-03-31T23:59:59.000Z

406

High level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 6  

SciTech Connect (OSTI)

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 6) outlines the standards and requirements for the sections on: Environmental Restoration and Waste Management, Research and Development and Experimental Activities, and Nuclear Safety.

Not Available

1994-04-01T23:59:59.000Z

407

EIS-0109: Long-Term Management of the Existing Radioactive Wastes and Residues at the Niagara Falls Storage Site  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy developed this statement to evaluate the environmental impacts of several alternatives for management and control of the radioactive wastes and residues at the Niagara Falls Storage Site, including a no action alternative, an alternative to manage wastes on-site, and two off-site management alternatives.

408

RCRA/UST, superfund, and EPCRA hotline training module. Introduction to: Treatment, storage, and disposal facilities (40 CFR parts 264/265, subparts A-E) updated as of July 1995  

SciTech Connect (OSTI)

The module presents an overview of the general treatment, storage, and disposal facility (TSDF) standards found in 40 CFR parts 264/265, subparts A through E. It identifies and explains each exclusion from parts 264/265, and provides definitions of excluded units, such as wastewater treatment unit and elementary neutralization unit. It locates and describes the requirements for waste analysis and personnel training. It also describes the purpose of a contingency plan and lists the emergency notification procedures. It describes manifest procedures and responsibilities, and lists the unmanifested waste reporting requirements.

NONE

1995-11-01T23:59:59.000Z

409

Emptying of the Storage for Solid Radioactive Waste in the Greifswald Nuclear Power Plant  

SciTech Connect (OSTI)

On the Greifswald site, 8 WWER 440 reactor units are located and also several facilities to handle fuel and radwaste. After the reunification of Germany, the final decision was taken to decommission all these Russian designed reactors. Thus, EWN is faced with a major decommissioning project in the field of nuclear power stations. One of the major tasks before the dismantling of the plant is the complete disposal of the operational waste. Among other facilities, a store for solid radioactive waste is located on the site, which has been filled over 17 years of operation of units 1 to 4. The paper presents the disposal technology development and results achieved. This activity is the first project in the operational history of the Russian type serial reactor line WWER-440.

Hartmann, B.; Fischer, J.

2002-02-26T23:59:59.000Z

410

Waste receiving and processing facility module 1, detailed design report  

SciTech Connect (OSTI)

WRAP 1 baseline documents which guided the technical development of the Title design included: (a) A/E Statement of Work (SOW) Revision 4C: This DOE-RL contractual document specified the workscope, deliverables, schedule, method of performance and reference criteria for the Title design preparation. (b) Functional Design Criteria (FDC) Revision 1: This DOE-RL technical criteria document specified the overall operational criteria for the facility. The document was a Revision 0 at the beginning of the design and advanced to Revision 1 during the tenure of the Title design. (c) Supplemental Design Requirements Document (SDRD) Revision 3: This baseline criteria document prepared by WHC for DOE-RL augments the FDC by providing further definition of the process, operational safety, and facility requirements to the A/E for guidance in preparing the design. The document was at a very preliminary stage at the onset of Title design and was revised in concert with the results of the engineering studies that were performed to resolve the numerous technical issues that the project faced when Title I was initiated, as well as, by requirements established during the course of the Title II design.

Not Available

1993-10-01T23:59:59.000Z

411

Leak-Path Factor Analysis for the Nuclear Materials Storage Facility  

SciTech Connect (OSTI)

Leak-path factors (LPFs) were calculated for the Nuclear Materials Storage Facility (NMSF) located in the Plutonium Facility, Building 41 at the Los Alamos National Laboratory Technical Area 55. In the unlikely event of an accidental fire powerful enough to fail a container holding actinides, the subsequent release of oxides, modeled as PuO{sub 2} aerosols, from the facility and into the surrounding environment was predicted. A 1-h nondestructive assay (NDA) laboratory fire accident was simulated with the MELCOR severe accident analysis code. Fire-driven air movement along with wind-driven air infiltration transported a portion of these actinides from the building. This fraction is referred to as the leak-path factor. The potential effect of smoke aerosol on the transport of the actinides was investigated to verify the validity of neglecting the smoke as conservative. The input model for the NMSF consisted of a system of control volumes, flow pathways, and surfaces sufficient to model the thermal-hydraulic conditions within the facility and the aerosol transport data necessary to simulate the transport of PuO{sub 2} particles. The thermal-hydraulic, heat-transfer, and aerosol-transport models are solved simultaneously with data being exchanged between models. A MELCOR input model was designed such that it would reproduce the salient features of the fire per the corresponding CFAST calculation. Air infiltration into and out of the facility would be affected strongly by wind-driven differential pressures across the building. Therefore, differential pressures were applied to each side of the building according to guidance found in the ASHRAE handbook using a standard-velocity head equation with a leading multiplier to account for the orientation of the wind with the building. The model for the transport of aerosols considered all applicable transport processes, but the deposition within the building clearly was dominated by gravitational settling.

Shaffer, C.; Leonard, M.

1999-06-13T23:59:59.000Z

412

Waste-to-energy facilities. January 1985-October 1991 (Citations from the NTIS Data Base). Rept. for Jan 85-Oct 91  

SciTech Connect (OSTI)

The bibliography contains citations concerning technical, economic, and environmental evaluations of facilities that convert waste to energy. Solid waste and municipal waste conversion facilities are highlighted. Feasibility studies, technical design, emissions studies, and markets for the resulting energy are discussed. Heat and electrical generation facilities are emphasized. (Contains 187 citations with title list and subject index.)

Not Available

1991-09-01T23:59:59.000Z

413

EIS-0062: Double-Shell Tanks for Defense High Level Waste Storage, Savannah River Site, Aiken, SC  

Broader source: Energy.gov [DOE]

This EIS analyzes the impacts of the various design alternatives for the construction of fourteen 1.3 million gallon high-activity radioactive waste tanks. The EIS further evaluates the effects of these alternative designs on tank durability, on the ease of waste retrieval from such tanks, and the choice of technology and timing for long-term storage or disposal of the wastes.

414

Facility Effluent Monitoring Plan for the Waste Receiving and Processing (WRAP) Facility  

SciTech Connect (OSTI)

A facility effluent monitoring plan is required by the U.S. Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee public safety, or the environment. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan ensures long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and must be updated, as a minimum, every 3 years.

DAVIS, W.E.

2000-03-08T23:59:59.000Z

415

Savannah River Site - Salt Waste Processing Facility: Briefing on the Salt Waste Processing Facility Independent Technical Review  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG |September2-SCORECARD-01-24-13 Page 1 of 1Sandra L. BurrellSarai Salt Waste

416

RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

This report presents compiled information concerning a facility investigation of waste area group 6(WAG-6), of the solid waste management units (SWMU'S) at Oak Ridge National Laboratory (ORNL). The WAG is a shallow ground disposal area for low-level radioactive wastes and chemical wastes. The report contains information on hydrogeological data, contaminant characterization, radionuclide concentrations, risk assessment from doses to humans and animals and associated cancer risks, exposure via food chains, and historical data. (CBS)

Not Available

1991-09-01T23:59:59.000Z