Powered by Deep Web Technologies
Note: This page contains sample records for the topic "legacy tru waste" 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.


1

The Nevada Test Site Legacy TRU Waste - The WIPP Central Characterization Project  

SciTech Connect (OSTI)

This paper discusses the Central Characterization Project (CCP) designed by the Waste Isolation Pilot Plant (WIPP) to aid sites, especially those sites with small quantities of transuranic (TRU) waste streams, in disposing of legacy waste at their facility. Because of the high cost of contracting vendors with the characterization capabilities necessary to meet the WIPP Waste Acceptance Criteria, utilizing the CCP is meant to simplify the process for small quantity sites. The paper will describe the process of mobilization of the vendors through CCP, the current production milestones that have been met, and the on-site lessons learned.

Norton, J. F.; Lahoud, R. G.; Foster, B. D.; VanMeighem, J.

2003-02-25T23:59:59.000Z

2

A facility design for repackaging ORNL CH-TRU legacy waste in Building 3525  

SciTech Connect (OSTI)

For the last 25 years, the Oak Ridge National Laboratory (ORNL) has conducted operations which have generated solid, contact-handled transuranic (CH-TRU) waste. At present the CH-TRU waste inventory at ORNL is about 3400 55-gal drums retrievably stored in RCRA-permitted, aboveground facilities. Of the 3400 drums, approximately 2600 drums will need to be repackaged. The current US Department of Energy (DOE) strategy for disposal of these drums is to transport them to the Waste Isolation Pilot Plant (WIPP) in New Mexico which only accepts TRU waste that meets a very specific set of criteria documented in the WIPP-WAC (waste acceptance criteria). This report describes activities that were performed from January 1994 to May 1995 associated with the design and preparation of an existing facility for repackaging and certifying some or all of the CH-TRU drums at ORNL to meet the WIPP-WAC. For this study, the Irradiated Fuel Examination Laboratory (IFEL) in Building 3525 was selected as the reference facility for modification. These design activities were terminated in May 1995 as more attractive options for CH-TRU waste repackaging were considered to be available. As a result, this document serves as a final report of those design activities.

Huxford, T.J.; Cooper, R.H. Jr.; Davis, L.E.; Fuller, A.B.; Gabbard, W.A.; Smith, R.B. [Oak Ridge National Lab., TN (United States); Guay, K.P. [S. M. Stroller Corp. (United States); Smith, L.C. [United Energy Services Corp. (United States)

1995-07-01T23:59:59.000Z

3

Transuranic (TRU) Waste Processing Center- Overview  

Broader source: Energy.gov [DOE]

DOE established the TRU Waste Processing Center (TWPC) as a regional center for the management, treatment, packaging and shipment of DOE TRU waste legacy inventory. TWPC is also responsible for managing and treating Low Level and Mixed Low Level Waste generated at ORNL. TWPC is operated by Wastren Advantage, Inc. (WAI) under contract to the DOE's Oak Ridge Office.

4

Transuranic (TRU) Waste | Department of Energy  

Office of Environmental Management (EM)

Transuranic (TRU) Waste Transuranic (TRU) Waste Transuranic (TRU) Waste Defined by the WIPP Land Withdrawal Act as "waste containing more than 100 nanocuries of alpha-emitting...

5

DOE Completes TRU Waste Cleanup at Bettis | Department of Energy  

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

TRU Waste Cleanup at Bettis TRU Waste Cleanup at Bettis DOE Completes TRU Waste Cleanup at Bettis September 23, 2011 - 12:00pm Addthis Media Contact Deb Gill www.wipp.energy.gov 575-234-7270 CARLSBAD, N.M. - The U.S. Department of Energy (DOE) has successfully completed cleanup of all Cold War legacy transuranic (TRU) waste at the Bettis Atomic Power Laboratory (BAPL) near Pittsburgh, Pa., permanently disposing of it at the Waste Isolation Pilot Plant (WIPP). BAPL is the 20th site to be completely cleaned of legacy TRU waste. This milestone was achieved using approximately $640,000 of a $172 million investment from the American Recovery and Reinvestment Act to expedite legacy waste cleanup activities across the DOE complex. This summer, TRU waste cleanup was also completed at the Nuclear Radiation Development, LLC,

6

DOE Achieves Second TRU Waste Cleanup | Department of Energy  

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

Achieves Second TRU Waste Cleanup Achieves Second TRU Waste Cleanup DOE Achieves Second TRU Waste Cleanup October 6, 2011 - 12:00pm Addthis Media Contact Deb Gill www.wipp.energy.gov 575-234-7270 CARLSBAD, N.M. -The U.S. Department of Energy has successfully removed all legacy contact-handled transuranic (TRU) waste from the Argonne National Laboratory (ANL), near Chicago, Illinois. In September, all legacy TRU waste was removed from the Bettis Atomic Power Laboratory (BAPL), near Pittsburgh, Pennsylvania. Maintained by the DOE, ANL is the country's first science and engineering research national laboratory. This milestone was supported by $83,000 provided to the National Transuranic Waste Program as part of a $172 million American Recovery and Reinvestment Act investment to expedite legacy TRU waste disposal activities across the DOE complex.

7

DOE Achieves Second TRU Waste Cleanup | Department of Energy  

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

Achieves Second TRU Waste Cleanup Achieves Second TRU Waste Cleanup DOE Achieves Second TRU Waste Cleanup October 6, 2011 - 12:00pm Addthis Media Contact Deb Gill www.wipp.energy.gov 575-234-7270 CARLSBAD, N.M. -The U.S. Department of Energy has successfully removed all legacy contact-handled transuranic (TRU) waste from the Argonne National Laboratory (ANL), near Chicago, Illinois. In September, all legacy TRU waste was removed from the Bettis Atomic Power Laboratory (BAPL), near Pittsburgh, Pennsylvania. Maintained by the DOE, ANL is the country's first science and engineering research national laboratory. This milestone was supported by $83,000 provided to the National Transuranic Waste Program as part of a $172 million American Recovery and Reinvestment Act investment to expedite legacy TRU waste disposal activities across the DOE complex.

8

Optimizing the National TRU waste system transportation program.  

SciTech Connect (OSTI)

The goal of the National TRU Waste Program (NTP) is to operate the system safely and cost-effectively, in compliance with applicable regulations and agreements, and at full capacity in a fully integrated mode. One of the objectives of the Department of Energy's Carlsbad Field Office (DOE/CBFO) is to complete the current Waste Isolation Pilot Plant (WIPP) mission for the disposal of the nation's legacy transuranic (TRU) waste at least IO years earlier thus saving approximately %7B. The National TRU Waste Optimization Plan (1) recommends changes to accomplish this. This paper discusses the optimization of the National TRU Waste System Transportation Program.

Lott, S. A. (Sheila A.); Countiss, S. (Sue)

2002-01-01T23:59:59.000Z

9

Progress Update: TRU Waste Shipping  

SciTech Connect (OSTI)

A progress update at the Savannah River Site. A continued effort on shipping TRU waste to WIPP in Carlsbad, New Mexico.

Cody, Tom

2010-01-01T23:59:59.000Z

10

On Going TRU Waste Disposition  

SciTech Connect (OSTI)

The ongoing effort to contain dangerous, radioactive TRU waste. Under the Recovery Act, the Savannah River Site is able to safely test and transport these items to WIPP in Carlsbad, New Mexico.

Cody, Tom

2010-01-01T23:59:59.000Z

11

LANL sets TRU waste hauling record  

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

sets TRU waste hauling record sets TRU waste hauling record LANL sets TRU waste hauling record TRU waste consists of clothing, tools, rags, debris, soil, and other items contaminated with radioactive elements, mostly plutonium. October 4, 2011 TRU waste from LANL to WIPP TRU waste from LANL to WIPP Contact Colleen Curran Communications Office (505) 664-0344 Email LOS ALAMOS, New Mexico, October 4, 2011-Los Alamos National Laboratory has set a new LANL record for the amount of transuranic (TRU) waste from past nuclearoperations shipped in a single year to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) near Carlsbad, NM. In fact, the Laboratory has shipped record numbers of transuranic waste each of the past three years. The Laboratory's TRU Waste Program completed 171 shipments in the past

12

Technological enhancements in TRU waste management.  

SciTech Connect (OSTI)

On March 26, 1999, the Waste Isolation Pilot Plant (WIPP) received its first shipment of transuranic (TRU) waste. On November 26, 1999, the Hazardous Waste Facility Permit (HWFP) to receive mixed TRU waste at WIPP became effective. Having achieved these two milestones, facilitating and supporting the characterization, transportation, and disposal of TRU waste became the major challenges for the National TRU Waste Program. After the WIPP began receiving waste, it was evident that, at the rate at which TRU waste was being shipped to and received at WIPP, the facility was not being used to its full potential, nor would it be unless improvements to the TRU waste management system were made. This paper describes some of the efforts to optimize (to make as functional as possible) characterization, transportation, and disposal of TRU waste; some of the technological enhancements necessary to achieve an optimized national transuranic waste system (1); and the interplay between regulatory change and technology development

Elkins, N. Z. (Ned Z.); Moody, D. C. (David C.)

2002-01-01T23:59:59.000Z

13

TRU waste-sampling program  

SciTech Connect (OSTI)

As part of a TRU waste-sampling program, Los Alamos National Laboratory retrieved and examined 44 drums of /sup 238/Pu- and /sup 239/Pu-contaminated waste. The drums ranged in age from 8 months to 9 years. The majority of drums were tested for pressure, and gas samples withdrawn from the drums were analyzed by a mass spectrometer. Real-time radiography and visual examination were used to determine both void volumes and waste content. Drum walls were measured for deterioration, and selected drum contents were reassayed for comparison with original assays and WIPP criteria. Each drum tested at atmospheric pressure. Mass spectrometry revealed no problem with /sup 239/Pu-contaminated waste, but three 8-month-old drums of /sup 238/Pu-contaminated waste contained a potentially hazardous gas mixture. Void volumes fell within the 81 to 97% range. Measurements of drum walls showed no significant corrosion or deterioration. All reassayed contents were within WIPP waste acceptance criteria. Five of the drums opened and examined (15%) could not be certified as packaged. Three contained free liquids, one had corrosive materials, and one had too much unstabilized particulate. Eleven drums had the wrong (or not the most appropriate) waste code. In many cases, disposal volumes had been inefficiently used. 2 refs., 23 figs., 7 tabs.

Warren, J.L.; Zerwekh, A.

1985-08-01T23:59:59.000Z

14

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect (OSTI)

The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria within which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP.

GREAGER, T.M.

1999-09-09T23:59:59.000Z

15

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect (OSTI)

The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria with in which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP.

GREAGER, T.M.

1999-12-14T23:59:59.000Z

16

RH-TRU Waste Content Codes  

SciTech Connect (OSTI)

The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document describes the inventory of RH-TRU waste within the transportation parameters specified by the Remote-Handled Transuranic Waste Authorized Methods for Payload Control (RH-TRAMPAC).1 The RH-TRAMPAC defines the allowable payload for the RH-TRU 72-B. This document is a catalog of RH-TRU 72-B authorized contents by site. A content code is defined by the following components: A two-letter site abbreviation that designates the physical location of the generated/stored waste (e.g., ID for Idaho National Laboratory [INL]). The site-specific letter designations for each of the sites are provided in Table 1. A three-digit code that designates the physical and chemical form of the waste (e.g., content code 317 denotes TRU Metal Waste). For RH-TRU waste to be transported in the RH-TRU 72-B, the first number of this three-digit code is 3. The second and third numbers of the three-digit code describe the physical and chemical form of the waste. Table 2 provides a brief description of each generic code. Content codes are further defined as subcodes by an alpha trailer after the three-digit code to allow segregation of wastes that differ in one or more parameter(s). For example, the alpha trailers of the subcodes ID 322A and ID 322B may be used to differentiate between waste packaging configurations. As detailed in the RH-TRAMPAC, compliance with flammable gas limits may be demonstrated through the evaluation of compliance with either a decay heat limit or flammable gas generation rate (FGGR) limit per container specified in approved content codes. As applicable, if a container meets the watt*year criteria specified by the RH-TRAMPAC, the decay heat limits based on the dose-dependent G value may be used as specified in an approved content code. If a site implements the administrative controls outlined in the RH-TRAMPAC and Appendix 2.4 of the RH-TRU Payload Appendices, the decay heat or FGGR limits based on a 10-day shipping period (rather than the standard 60-day shipping period) may be used as specified in an approved content code. Requests for new or revised content codes may be submitted to the WIPP RH-TRU Payload Engineer for review and approval, provided all RH-TRAMPAC requirements are met.

Washington TRU Solutions

2007-07-01T23:59:59.000Z

17

Training Underway for TRU Waste Employees Hired For Recovery...  

Office of Environmental Management (EM)

Training Underway for TRU Waste Employees Hired For Recovery Act Project Training Underway for TRU Waste Employees Hired For Recovery Act Project July 29, 2009 - 12:00pm Addthis...

18

Repackaging Rocky Flats Legacy Transuranic Waste  

SciTech Connect (OSTI)

Repackaging legacy Transuranic (TRU), Transuranic Mixed (TRM), Low Level Waste (LLW), and Low Level Mixed (LLM) waste requires good characterization skills and the ability to adapt to less than ideal conditions. Repackaging legacy waste in a facility that is not undergoing Decontamination and Decommission (D and D) is optimum. However, repackaging any waste in a D and D facility, under cold and dark conditions, can be difficult. Cold and dark conditions are when the heating and air conditioning are no longer in service and the lighting consists of strands of lights hung throughout each of the rooms. Working under these conditions adds an additional level of stress and danger that must be addressed. The use of glovebags was very useful at Rocky Flats during the D and D of many buildings. Glovebags can be adapted for many different types of wastes and unusual conditions. Repackaging of legacy TRU waste, in a D and D facility, can be accomplished safely and cost effectively with the use of glovebags. In conclusion: the use of glovebags to repackage legacy TRU, TRM, LLW, or LLM waste was done safely and cost effectively at Rocky Flats. The cost of using glovebags was minimal. Glovebags are easily adaptable to whatever the waste configuration is. The use of glovebags, for repackaging of Legacy waste, allows D and D efforts to stay on schedule and on task. Without the use of glovebags, additional gloveboxes would have been required at Rocky Flats. Larger items, such as the HEPA filters, would have required the construction of a new large item repackaging glovebox. Repackaging in glovebags allows the freedom to either locate the glovebag by the waste or locate the glovebag in a place that least impacts D and D efforts. The use of glovebags allowed numerous configurations of waste to be repackaged without the use of gloveboxes. During the D and D of the Rocky Flats facility, which was in a cold and dark stage, D and D work was not impacted by the repackaging activity. Glovebags work well in facilities that are in the process of D and D or still in full operations because glovebags are very safe and cost effective.

McTaggart, Jerri Lynne [Los Alamos National Laboratory, 115 N. Main St., Carlsbad, New Mexico, 88220 (United States)

2008-01-15T23:59:59.000Z

19

Transuranic (TRU) Waste Phase I Retrieval Plan  

SciTech Connect (OSTI)

From 1970 to 1987, TRU and suspect TRU wastes at Hanford were placed in the SWBG. At the time of placement in the SWBG these wastes were not regulated under existing Resource Conservation and Recovery Act (RCRA) regulations, since they were generated and disposed of prior to the effective date of RCRA at the Hanford Site (1987). From the standpoint of DOE Order 5820.2A1, the TRU wastes are considered retrievably stored, and current plans are to retrieve these wastes for shipment to WIPP for disposal. This plan provides a strategy for the Phase I retrieval that meets the intent of TPA milestone M-91 and Project W-113, and incorporates the lessons learned during TRU retrieval campaigns at Hanford, LANL, and SRS. As in the original Project W-113 plans, the current plan calls for examination of approximately 10,000 suspect-TRU drums located in the 218-W-4C burial ground followed by the retrieval of those drums verified to contain TRU waste. Unlike the older plan, however, this plan proposes an open-air retrieval scenario similar to those used for TRU drum retrieval at LANL and SRS. Phase I retrieval consists of the activities associated with the assessment of approximately 10,000 55-gallon drums of suspect TRU-waste in burial ground 218-W-4C and the retrieval of those drums verified to contain TRU waste. Four of the trenches in 218-W-4C (Trenches 1, 4, 20, and 29) are prime candidates for Phase I retrieval because they contain large numbers of suspect TRU drums, stacked from 2 to 5 drums high, on an asphalt pad. In fact, three of the trenches (Trenches 1 , 20, and 29) contain waste that has not been covered with soil, and about 1500 drums can be retrieved without excavation. The other three trenches in 218-W-4C (Trenches 7, 19, and 24) are not candidates for Phase I retrieval because they contain significant numbers of boxes. Drums will be retrieved from the four candidate trenches, checked for structural integrity, overpacked, if necessary, and assayed at the burial ground. A mobile assay system will be used to determine if the drum is LLW (Le., contains <100 nCi/g). LLW will remain disposed of in the 218-W-4C Burial Ground. TRU waste will be retrieved and staged in the burial ground until it can be shipped to the CWC. The TRU drums will be stored at the CWC until they can be moved to WRAP. The WRAP facility will prepare the waste for shipment to WIPP for final disposal. For planning purposes, approximately 50% of the 10,000 drums have been estimated to contain LLW.

MCDONALD, K.M.

2000-09-28T23:59:59.000Z

20

Thermal Pretreatment For TRU Waste Sorting  

SciTech Connect (OSTI)

Japan Atomic Energy Agency conducted a study on thermal treatment of TRU waste to develop a removal technology for materials that are forbidden for disposal. The thermal pretreatment in which hot nitrogen and/or air is introduced to the waste is a process of removing combustibles, liquids, and low melting point metals from PVC wrapped TRU waste. In this study, thermal pretreatment of simulated waste was conducted using a desktop thermal treatment vessel and a laboratory scale thermal pretreatment system. Combustibles and low melting point metals are effectively separated from wastes by choosing appropriate temperature of flowing gases. Combustibles such as papers, PVC, oil, etc. were removed and low melting point metals such as zinc, lead, and aluminum were separated from the simulated waste by the thermal pretreatment. (authors)

Sasaki, T.; Aoyama, Y.; Miyamoto, Y.; Yamaguchi, H. [Japan Atomic Energy Agency, Tokai-mura, Ibaraki (Japan)

2008-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

Thermal processing systems for TRU mixed waste  

SciTech Connect (OSTI)

This paper presents preliminary ex situ thermal processing system concepts and related processing considerations for remediation of transuranic (TRU)-contaminated wastes (TRUW) buried at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL). Anticipated waste stream components and problems are considered. Thermal processing conditions required to obtain a high-integrity, low-leachability glass/ceramic final waste form are considered. Five practical thermal process system designs are compared. Thermal processing of mixed waste and soils with essentially no presorting and using incineration followed by high temperature melting is recommended. Applied research and development necessary for demonstration is also recommended.

Eddy, T.L.; Raivo, B.D.; Anderson, G.L.

1992-01-01T23:59:59.000Z

22

Thermal processing systems for TRU mixed waste  

SciTech Connect (OSTI)

This paper presents preliminary ex situ thermal processing system concepts and related processing considerations for remediation of transuranic (TRU)-contaminated wastes (TRUW) buried at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL). Anticipated waste stream components and problems are considered. Thermal processing conditions required to obtain a high-integrity, low-leachability glass/ceramic final waste form are considered. Five practical thermal process system designs are compared. Thermal processing of mixed waste and soils with essentially no presorting and using incineration followed by high temperature melting is recommended. Applied research and development necessary for demonstration is also recommended.

Eddy, T.L.; Raivo, B.D.; Anderson, G.L.

1992-08-01T23:59:59.000Z

23

DOE Reaches Recovery Act Goal With Cleanup of All Legacy Transuranic Waste  

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

Reaches Recovery Act Goal With Cleanup of All Legacy Reaches Recovery Act Goal With Cleanup of All Legacy Transuranic Waste at Sandia National Laboratories DOE Reaches Recovery Act Goal With Cleanup of All Legacy Transuranic Waste at Sandia National Laboratories May 3, 2012 - 12:00pm Addthis Media Contact Deb Gill, U.S. DOE Carlsbad Field Office, (575) 234-7270 CARLSBAD, N.M., May 3, 2012 -The U.S. Department of Energy (DOE) completed cleanup of the Cold War legacy transuranic (TRU) waste at Sandia National Laboratories (Sandia) in Albuquerque, New Mexico when four shipments of remote-handled (RH) TRU waste from Sandia arrived at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, N.M. for permanent disposal on May 2, 2012. The DOE Carlsbad Field Office (CBFO) reached one of its final milestones under the American Recovery and Reinvestment Act (ARRA) with the legacy TRU

24

Transuranic (TRU) Waste Phase I Retrieval Plan  

SciTech Connect (OSTI)

Phase I retrieval of post-1970 TRU wastes from burial ground 218-W-4C can be done in a safe, efficient, and cost-effective manner. Initiating TRU retrieval by retrieving uncovered drums from Trenches 1, 20, and 29, will allow retrieval to begin under the current SWBG safety authorization basis. The retrieval of buried drums from Trenches 1, 4, 20, and 29, which will require excavation, will commence once the uncovered drum are retrieved. This phased approach allows safety analysis for drum venting and drum module excavation to be completed and approved before the excavation proceeds. In addition, the lessons learned and the operational experience gained from the retrieval of uncovered drums can be applied to the more complicated retrieval of the buried drums. Precedents that have been set at SRS and LANL to perform retrieval without a trench cover, in the open air, should be followed. Open-air retrieval will result in significant cost savings over the original plans for Phase I retrieval (Project W-113). Based on LANL and SRS experience, open-air retrieval will have no adverse impacts to the environment or to the health and safety of workers or the public. Assaying the waste in the SWBG using a mobile assay system, will result in additional cost savings. It is expected that up to 50% of the suspect-TRU wastes will assay as LLW, allowing those waste to remain disposed of in the SWBG. Further processing, with its associated costs, will only occur to the portion of the waste that is verified to be TRU. Retrieval should be done, to the extent possible, under the current SWBG safety authorization basis as a normal part of SWBG operations. The use of existing personnel and existing procedures should be optimized. By working retrieval campaigns, typically during the slow months, it is easier to coordinate the availability of necessary operations personnel, and it is easier to coordinate the availability of a mobile assay vendor.

MCDONALD, K.M.

1999-08-27T23:59:59.000Z

25

TRU Waste Sampling Program: Volume I. Waste characterization  

SciTech Connect (OSTI)

Volume I of the TRU Waste Sampling Program report presents the waste characterization information obtained from sampling and characterizing various aged transuranic waste retrieved from storage at the Idaho National Engineering Laboratory and the Los Alamos National Laboratory. The data contained in this report include the results of gas sampling and gas generation, radiographic examinations, waste visual examination results, and waste compliance with the Waste Isolation Pilot Plant-Waste Acceptance Criteria (WIPP-WAC). A separate report, Volume II, contains data from the gas generation studies.

Clements, T.L. Jr.; Kudera, D.E.

1985-09-01T23:59:59.000Z

26

Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan  

SciTech Connect (OSTI)

The Quality Assurance Project Plan (QAPjP) has been prepared for waste characterization activities to be conducted by the Transuranic (TRU) Project at the Hanford Site to meet requirements set forth in the Waste Isolation Pilot Plan (WIPP) Hazardous Waste Facility Permit, 4890139088-TSDF, Attachment B, including Attachments B1 through B6 (WAP) (DOE, 1999a). The QAPjP describes the waste characterization requirements and includes test methods, details of planned waste sampling and analysis, and a description of the waste characterization and verification process. In addition, the QAPjP includes a description of the quality assurance/quality control (QA/QC) requirements for the waste characterization program. Before TRU waste is shipped to the WIPP site by the TRU Project, all applicable requirements of the QAPjP shall be implemented. Additional requirements necessary for transportation to waste disposal at WIPP can be found in the ''Quality Assurance Program Document'' (DOE 1999b) and HNF-2600, ''Hanford Site Transuranic Waste Certification Plan.'' TRU mixed waste contains both TRU radioactive and hazardous components, as defined in the WLPP-WAP. The waste is designated and separately packaged as either contact-handled (CH) or remote-handled (RH), based on the radiological dose rate at the surface of the waste container. RH TRU wastes are not currently shipped to the WIPP facility.

GREAGER, T.M.

2000-12-06T23:59:59.000Z

27

It Just Keeps Getting Better-Tru Waste Inventory  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) opened on March 26, 1999, becoming the nation's first deep geologic repository for the permanent disposal of defense-generated transuranic (TRU) waste. In May 1998, the U. S. Environmental Protection Agency (EPA) certified WIPP and re-certified WIPP in March 2006. The knowledge of TRU waste inventory is fundamental to packaging, transportation, disposal strategies, resource allocation, and is also imperative when working in a regulatory framework. TRU waste inventory data are used to define the waste that will fill the WIPP repository in terms of volume, radionuclides, waste material parameters, other chemical components, and to model the impact of the waste on the performance of the WIPP over a 10,000-year evolution. The data that pertain to TRU waste is defined in the WIPP Land Withdrawal Act (LWA), as '..waste containing more that 100 nanocuries of alpha-emitting transuranic isotopes per gram of waste, with half-lives greater than 20 years..' Defining TRU waste further, the wastes are classified as either contact-handled (CH) or remote-handled (RH) TRU waste, depending on the dose rate at the surface of the waste container. CH TRU wastes are packaged with an external surface dose rate not greater than 200 milli-rem (mrem) per hour, while RH TRU wastes are packaged with an external surface dose rate of 200 mrem per hour or greater. The Los Alamos National Laboratory-Carlsbad Operations (LANL-CO) Inventory Team has developed a powerful new database, the Comprehensive Inventory Database (CID), to maintain the TRU waste inventory information. The CID is intended to replace the Transuranic Waste Baseline Inventory Database (TWBID), Revision 2.1, as the central inventory information repository for tracking all existing and potential (TRU) waste generated across the Department of Energy (DOE) TRU waste complex. It is also the source for information submitted for the Annual TRU Waste Inventory Reports some of which will be used in future Compliance Re-certification Applications (CRAs) for the WIPP. Currently, the DOE is preparing for the second re-certification, CRA-2009. The CID contains comprehensive TRU waste inventory that is consistent, relevant, and easily accessible to support DOE needs, not only the CRAs and performance assessments, but also waste management planning activities and other regulatory needs (e.g., National Environmental Policy Act (NEPA) analyses). The comprehensive inventory contains information obtained via inventory updates and approved acceptable knowledge (AK) characterization information to ensure inventory data integrity is maintained and the inventory is current. The TRU waste inventory is maintained in the CID under configuration management as defined in the LANL-CO Quality Assurance Program. The CID was developed using Microsoft{sup TM} Access Data Project{sup TM} (ADP) technology with a Microsoft SQL Server{sup TM} back end. The CID is user friendly, contains more fields, provides for easy upload of data, and has the capability to generate fully qualified data reports. To go along with the new database, the LANL-CO Inventory Team has developed an improved data collection/screening process and has excellent communications with the TRU waste site personnel. WIPP has now received over 6,000 shipments, emplaced over 50,000 cubic meters of CH waste, and successfully completed one re-certification. With a new robust qualified database, the CID, to maintain the inventory information, the TRU waste inventory information is continuously improving in quality, accuracy, and usability (better). (authors)

Lott, S.; Crawford, B.; McInroy, W.; Van Soest, G.; McTaggart, J.; Guerin, D. [Los Alamos National Laboratory-Carlsbad Operations, Carlsbad, NM (United States); Patterson, R. [U.S. Department of Energy Carlsbad, Field Office, Carlsbad, NM (United States)

2008-07-01T23:59:59.000Z

28

EM's Los Alamos TRU Waste Campaign Heads Toward Completion | Department  

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

EM's Los Alamos TRU Waste Campaign Heads Toward Completion EM's Los Alamos TRU Waste Campaign Heads Toward Completion EM's Los Alamos TRU Waste Campaign Heads Toward Completion November 20, 2013 - 12:00pm Addthis Advanced techniques allowed crews at Los Alamos National Laboratory to decontaminate large boxes of waste so it could be shipped as mixed low-level rather than transuranic waste. Advanced techniques allowed crews at Los Alamos National Laboratory to decontaminate large boxes of waste so it could be shipped as mixed low-level rather than transuranic waste. The EM program at Los Alamos National Laboratory exceeded its shipping goals in fiscal year 2013, shipping twice as much waste as it did in fiscal year 2012. The EM program at Los Alamos National Laboratory exceeded its shipping goals in fiscal year 2013, shipping twice as much waste as it did in fiscal

29

Terminating Safeguards on Excess Special Nuclear Material: Defense TRU Waste Clean-up and Nonproliferation - 12426  

SciTech Connect (OSTI)

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

Hayes, Timothy [Los Alamos National Laboratory, Carlsbad Operations Group (United States); Nelson, Roger [Department Of Energy, Carlsbad Operations Office (United States)

2012-07-01T23:59:59.000Z

30

EA-1962: Analysis for Below Grade Suspect Transuranic (TRU) Waste...  

Energy Savers [EERE]

of waste type and determination of a final disposal path. Per DOE Order 435.1, Change 1, Radioactive Waste Management, and its associated guide, legacy waste at Los Alamos...

31

Safety Enhancements for TRU Waste Handling - 12258  

SciTech Connect (OSTI)

For years, proper Health Physics practices and 'As Low As Reasonably Achievable' (ALARA) principles have fostered the use of glove boxes or other methods of handling (without direct contact) high activities of radioactive material. The physical limitations of using glove boxes on certain containers have resulted in high-activity wastes being held in storage awaiting a path forward. Highly contaminated glove boxes and other remote handling equipment no longer in use have also been added to the growing list of items held for storage with no efficient method of preparation for proper disposal without creating exposure risks to personnel. This is especially true for wastes containing alpha-emitting radionuclides such as Plutonium and Americium that pose significant health risks to personnel if these Transuranic (TRU) wastes are not controlled effectively. Like any good safety program or root cause investigation PFNW has found that the identification of the cause of a negative change, if stopped, can result in a near miss and lessons learned. If this is done in the world of safety, it is considered a success story and is to be shared with others to protect the workers. PFNW believes that the tools, equipment and resources have improved over the past number of years but that the use of them has not progressed at the same rate. If we use our tools to timely identify the effect on the work environment and immediately following or possibly even simultaneously identify the cause or some of the causal factors, we may have the ability to continue to work rather than succumb to the start and stop-work mentality trap that is not beneficial in waste minimization, production efficiency or ALARA. (authors)

Cannon, Curt N. [Perma-Fix Northwest Richland, Inc., Richland, WA 99354 (United States)

2012-07-01T23:59:59.000Z

32

Oak Ridge National Laboratory TRU Waste Processing Center Tank Waste Processing Supernate Processing System  

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

TRU Waste Processing Center TRU Waste Processing Center ORNL TRU Waste Processing Center Tank Waste Processing Supernate (SN) Processing System Presented by Don F. Gagel Vice President and Chief Technology Officer EnergX LLC ORNL TRU Waste Processing Center 1/21/09 2 SRS Technology Transfer, ORNL SN Process Overview SN Process Facility ORNL TRU Waste Processing Center 3 Waste Concentration Using Evaporator Evaporator Concentrates Waste Vapor stream superheated and HEPA-filtered Vapor stream exhausted to main ventilation system Supernate Pump and Evaporator Discharge Pump circulate waste between selected tank and evaporator during concentration. Evaporator Discharge Pump Supernate Pump Supernate Tank Evaporator Exhaust Blower ORNL TRU Waste Processing Center 4 Tank Sampling/ Transfer To Dryer Tank

33

RH-TRU Waste Content Codes (RH-TRUCON)  

SciTech Connect (OSTI)

The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document describes the inventory of RH-TRU waste within the transportation parameters specified by the Remote-Handled Transuranic Waste Authorized Methods for Payload Control (RH-TRAMPAC).1 The RH-TRAMPAC defines the allowable payload for the RH-TRU 72-B. This document is a catalog of RH-TRU 72-B authorized contents by site. A content code is defined by the following components: A two-letter site abbreviation that designates the physical location of the generated/stored waste (e.g., ID for Idaho National Laboratory [INL]). The site-specific letter designations for each of the sites are provided in Table 1. A three-digit code that designates the physical and chemical form of the waste (e.g., content code 317 denotes TRU Metal Waste). For RH-TRU waste to be transported in the RH-TRU 72-B, the first number of this three-digit code is 3. The second and third numbers of the three-digit code describe the physical and chemical form of the waste. Table 2 provides a brief description of each generic code. Content codes are further defined as subcodes by an alpha trailer after the three-digit code to allow segregation of wastes that differ in one or more parameter(s). For example, the alpha trailers of the subcodes ID 322A and ID 322B may be used to differentiate between waste packaging configurations. As detailed in the RH-TRAMPAC, compliance with flammable gas limits may be demonstrated through the evaluation of compliance with either a decay heat limit or flammable gas generation rate (FGGR) limit per container specified in approved content codes. As applicable, if a container meets the watt*year criteria specified by the RH-TRAMPAC, the decay heat limits based on the dose-dependent G value may be used as specified in an approved content code. If a site implements the administrative controls outlined in the RH-TRAMPAC and Appendix 2.4 of the RH-TRU Payload Appendices, the decay heat or FGGR limits based on a 10-day shipping period (rather than the standard 60-day shipping period) may be used as specified in an approved content code. Requests for new or revised content codes may be submitted to the WIPP RH-TRU Payload Engineer for review and approval, provided all RH-TRAMPAC requirements are met.

Washington TRU Solutions

2007-05-30T23:59:59.000Z

34

RH-TRU Waste Content Codes (RH-TRUCON)  

SciTech Connect (OSTI)

The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document describes the inventory of RH-TRU waste within the transportation parameters specified by the Remote-Handled Transuranic Waste Authorized Methods for Payload Control (RH-TRAMPAC).1 The RH-TRAMPAC defines the allowable payload for the RH-TRU 72-B. This document is a catalog of RH-TRU 72-B authorized contents by site. A content code is defined by the following components: A two-letter site abbreviation that designates the physical location of the generated/stored waste (e.g., ID for Idaho National Laboratory [INL]). The site-specific letter designations for each of the sites are provided in Table 1. A three-digit code that designates the physical and chemical form of the waste (e.g., content code 317 denotes TRU Metal Waste). For RH-TRU waste to be transported in the RH-TRU 72-B, the first number of this three-digit code is 3. The second and third numbers of the three-digit code describe the physical and chemical form of the waste. Table 2 provides a brief description of each generic code. Content codes are further defined as subcodes by an alpha trailer after the three-digit code to allow segregation of wastes that differ in one or more parameter(s). For example, the alpha trailers of the subcodes ID 322A and ID 322B may be used to differentiate between waste packaging configurations. As detailed in the RH-TRAMPAC, compliance with flammable gas limits may be demonstrated through the evaluation of compliance with either a decay heat limit or flammable gas generation rate (FGGR) limit per container specified in approved content codes. As applicable, if a container meets the watt*year criteria specified by the RH-TRAMPAC, the decay heat limits based on the dose-dependent G value may be used as specified in an approved content code. If a site implements the administrative controls outlined in the RH-TRAMPAC and Appendix 2.4 of the RH-TRU Payload Appendices, the decay heat or FGGR limits based on a 10-day shipping period (rather than the standard 60-day shipping period) may be used as specified in an approved content code. Requests for new or revised content codes may be submitted to the WIPP RH-TRU Payload Engineer for review and approval, provided all RH-TRAMPAC requirements are met.

Washington TRU Solutions LLC

2007-08-01T23:59:59.000Z

35

RH-TRU Waste Inventory Characterization by AK and Proposed WIPP RH-TRU Waste Characterization Objectives  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE)-Carlsbad Field Office (CBFO) has developed draft documentation to present the proposed Waste Isolation Pilot Plant (WIPP) remote-handled (RH-) transuranic (TRU) waste characterization program to its regulators, the U.S. Environmental Protection Agency and the New Mexico Environment Department. Compliance with Title 40, Code of Federal Regulations, Parts 191 and 194; the WIPP Land Withdrawal Act (PL 102-579); and the WIPP Hazardous Waste Facility Permit, as well as the Certificates of Compliance for the 72-B and 10-160B Casks, requires that specific waste parameter limits be imposed on DOE sites disposing of TRU waste at WIPP. The DOE-CBFO must control the sites' compliance with the limits by specifying allowable characterization methods. As with the established WIPP contact handled TRU waste characterization program, the DOE-CBFO has proposed a Remote-Handled TRU Waste Acceptance Criteria (RH-WAC) document consolidating the requirements from various regulatory drivers and proposed allowable characterization methods. These criteria are consistent with the recommendation of a recent National Academy Sciences/National Research Council to develop an RH-TRU waste characterization approach that removes current self imposed requirements that lack a legal or safety basis. As proposed in the draft RH-WAC and other preliminary documents, the DOE-CBFO RH-TRU waste characterization program proposes the use of acceptable knowledge (AK) as the primary method for obtaining required characterization information. The use of AK involves applying knowledge of the waste in light of the materials or processes used to generate the waste. Documentation, records, or processes providing information about various attributes of a waste stream, such as chemical, physical, and radiological properties, may be used as AK and may be applied to individual waste containers either independently or in conjunction with radiography, visual examination, assay, and other sampling and analytical data. RH-TRU waste cannot be shipped to WIPP on the basis of AK alone if documentation demonstrating that all of the prescribed limits in the RH-WAC are met is not available, discrepancies exist among AK source documents describing the same waste stream and the most conservative assumptions regarding those documents indicates that a limit will not be met, or all required data are not available for a given waste stream.

Most, W. A.; Kehrman, R.; Gist, C.; Biedscheid, J.; Devarakonda, J.; Whitworth, J.

2002-02-26T23:59:59.000Z

36

The Department of Energy Announces Major Cold War Legacy Waste Cleanup  

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

The Department of Energy Announces Major Cold War Legacy Waste The Department of Energy Announces Major Cold War Legacy Waste Cleanup Milestone The Department of Energy Announces Major Cold War Legacy Waste Cleanup Milestone September 28, 2011 - 8:54am Addthis CARLSBAD, NM - The U.S. Department of Energy today announced that the Waste Isolation Pilot Plant (WIPP) received its 10,000th shipment of transuranic (TRU) waste over the weekend. This marks an important milestone in DOE's mission to clean up the country's Cold War legacy. "This accomplishment reflects the hard work and dedication of our workers and contractors," said Energy Secretary Steven Chu. "It also demonstrates the Department's commitment to future generations as we continue our cleanup mission as safely and quickly as possible." The 10,000th shipment, which consisted of defense-generated contact-handled

37

The Road to Re-certification: WIPP TRU Waste Inventory  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP), located near Carlsbad, New Mexico, is a deep geologic repository for the disposal of transuranic (TRU) wastes generated by atomic energy defense activities. The WIPP Land Withdrawal Act (LWA) [1] requires the U.S. Department of Energy (DOE) to submit documentation to the U.S. Environmental Protection Agency (EPA) that demonstrates WIPP's continuing compliance with the disposal regulations in Title 40 of the Code of Federal Regulations (CFR) Part 191 Subparts B and C, not later than five years after initial receipt of waste for disposal at the repository, and every five years thereafter until the decommissioning of the facility is completed. On May 18, 1998, after review of the Compliance Certification Application (CCA) (63 FR 27405), the EPA certified that the WIPP did comply with the final disposal regulations and criteria of 40 CFR parts 191 and 194. On March 26, 1999, the first receipt of contact-handled (CH) TRU waste was received at WIPP thus initiating the 5-year countdown to the first re-certification. Five years after the first receipt of waste at WIPP, on March 26, 2004, the DOE submitted a Compliance Re-certification Application (CRA) [2]. The CRA includes TRU waste inventory as a key factor. The TRU waste inventory defines what is expected to be emplaced in the repository; and, therefore, how the performance of the repository will be affected. Performance of the WIPP is determined via the Performance Assessment (PA), a set of complex algorithms used to model the long-term performance of the repository. The TRU waste inventory data that are important to this assessment include: 1) volumes of stored, projected and emplaced waste; 2) radionuclide activity concentrations; 3) waste material parameter densities; 4) estimates of the masses of chelating agents; 5) estimates of the oxyanions; 6) estimates of expected cement masses; and 7) estimates of the types and amounts of materials that will be used to emplace the waste. The data that are collected and maintained as the TRU waste inventory provide the waste source term used in the PA to model long-term repository performance. (authors)

Crawford, B.A.; Lott, S.A.; Sparks, L.D.; Van Soest, G.; Mclnroy, B. [Los Alamos National Laboratory -Carlsbad Operations, 115 N. Main St., Carlsbad, NM 88220 (United States)

2006-07-01T23:59:59.000Z

38

Transuranic (TRU) Waste Processing Center- Cask Processing Enclosure  

Broader source: Energy.gov [DOE]

Wastren Advantage, Inc., the DOE Prime contractor for the TRU Waste Processing Center (TWPC) conceived, designed, and constructed the new Cask Processing Enclosure (CPE) approach based on experience gained to date from Remote Handled (RH) waste processing. The CPE was designed August to October 2011, constructed from October 2011 to April 2012, and Start-up Readiness activities have just been completed. Initial radiological operations are targeted for July 19, 2012.

39

Test Plan: WIPP bin-scale CH TRU waste tests  

SciTech Connect (OSTI)

This WIPP Bin-Scale CH TRU Waste Test program described herein will provide relevant composition and kinetic rate data on gas generation and consumption resulting from TRU waste degradation, as impacted by synergistic interactions due to multiple degradation modes, waste form preparation, long-term repository environmental effects, engineered barrier materials, and, possibly, engineered modifications to be developed. Similar data on waste-brine leachate compositions and potentially hazardous volatile organic compounds released by the wastes will also be provided. The quantitative data output from these tests and associated technical expertise are required by the WIPP Performance Assessment (PA) program studies, and for the scientific benefit of the overall WIPP project. This Test Plan describes the necessary scientific and technical aspects, justifications, and rational for successfully initiating and conducting the WIPP Bin-Scale CH TRU Waste Test program. This Test Plan is the controlling scientific design definition and overall requirements document for this WIPP in situ test, as defined by Sandia National Laboratories (SNL), scientific advisor to the US Department of Energy, WIPP Project Office (DOE/WPO). 55 refs., 16 figs., 19 tabs.

Molecke, M.A.

1990-08-01T23:59:59.000Z

40

Preparation of Safety Basis Documents for Transuranic (TRU) Waste Facilities  

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

5506-2007 5506-2007 April 2007 DOE STANDARD Preparation of Safety Basis Documents for Transuranic (TRU) Waste Facilities U.S. Department of Energy Washington, D.C. 20585 AREA-SAFT DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-5506-2007 ii Available on the Department of Energy Technical Standards Program Web Site at Http://tis.eh.doe.gov/techstds/ DOE-STD-5506-2007 iii Foreword This Standard provides analytical assumptions and methods, as well as hazard controls to be used when developing Safety Basis (SB) documents for transuranic (TRU) waste facilities in the U.S. Department of Energy (DOE) Complex. It also provides supplemental technical

Note: This page contains sample records for the topic "legacy tru waste" 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

TRU Waste Management Program. Cost/schedule optimization analysis  

SciTech Connect (OSTI)

This Current Year Work Plan presents in detail a description of the activities to be performed by the Joint Integration Office Rockwell International (JIO/RI) during FY86. It breaks down the activities into two major work areas: Program Management and Program Analysis. Program Management is performed by the JIO/RI by providing technical planning and guidance for the development of advanced TRU waste management capabilities. This includes equipment/facility design, engineering, construction, and operations. These functions are integrated to allow transition from interim storage to final disposition. JIO/RI tasks include program requirements identification, long-range technical planning, budget development, program planning document preparation, task guidance development, task monitoring, task progress information gathering and reporting to DOE, interfacing with other agencies and DOE lead programs, integrating public involvement with program efforts, and preparation of reports for DOE detailing program status. Program Analysis is performed by the JIO/RI to support identification and assessment of alternatives, and development of long-term TRU waste program capabilities. These analyses include short-term analyses in response to DOE information requests, along with performing an RH Cost/Schedule Optimization report. Systems models will be developed, updated, and upgraded as needed to enhance JIO/RI's capability to evaluate the adequacy of program efforts in various fields. A TRU program data base will be maintained and updated to provide DOE with timely responses to inventory related questions.

Detamore, J.A.; Raudenbush, M.H.; Wolaver, R.W.; Hastings, G.A.

1985-10-01T23:59:59.000Z

42

TRU Waste Management Program cost/schedule optimization analysis  

SciTech Connect (OSTI)

The cost/schedule optimization task is a necessary function to insure that program goals and plans are optimized from a cost and schedule aspect. Results of this study will offer DOE information with which it can establish, within institutional constraints, the most efficient program for the long-term management and disposal of contact handled transuranic waste (CH-TRU). To this end, a comprehensive review of program cost/schedule tradeoffs has been made, to identify any major cost saving opportunities that may be realized by modification of current program plans. It was decided that all promising scenarios would be explored, and institutional limitations to implementation would be described. Since a virtually limitless number of possible scenarios can be envisioned, it was necessary to distill these possibilities into a manageable number of alternatives. The resultant scenarios were described in the cost/schedule strategy and work plan document. Each scenario was compared with the base case: waste processing at the originating site; transport of CH-TRU wastes in TRUPACT; shipment of drums in 6-Packs; 25 year stored waste workoff; WIPP operational 10/88, with all sites shipping to WIPP beginning 10/88; and no processing at WIPP. Major savings were identified in two alternate scenarios: centralize waste processing at INEL and eliminate rail shipment of TRUPACT. No attempt was made to calculate savings due to combination of scenarios. 1 ref., 5 figs., 1 tab. (MHB)

Detamore, J.A. (Rockwell International Corp., Albuquerque, NM (United States). Joint Integration Office); Raudenbush, M.H.; Wolaver, R.W.; Hastings, G.A. (Stoller (S.M.) Corp., Boulder, CO (United States))

1985-10-01T23:59:59.000Z

43

Facility Utilization and Risk Analysis for Remediation of Legacy Transuranic Waste at the Savannah River Site - 13572  

SciTech Connect (OSTI)

Savannah River Nuclear Solutions (SRNS) completed the Accelerated TRU Project for remediating legacy waste at the Savannah River Site with significant cost and schedule efficiencies due to early identification of resources and utilization of risk matrices. Initial project planning included identification of existing facilities that could be modified to meet the technical requirements needed for repackaging and remediating the waste. The project schedule was then optimized by utilization of risk matrices that identified alternate strategies and parallel processing paths which drove the overall success of the project. Early completion of the Accelerated TRU Project allowed SRNS to pursue stretch goals associated with remediating very difficult TRU waste such as concrete casks from the hot cells in the Savannah River National Laboratory. Project planning for stretch goals also utilized existing facilities and the risk matrices. The Accelerated TRU project and stretch goals were funded under the American Recovery and Reinvestment Act (ARRA). (authors)

Gilles, Michael L.; Gilmour, John C. [Savannah River Nuclear Solutions, LLC (United States)] [Savannah River Nuclear Solutions, LLC (United States)

2013-07-01T23:59:59.000Z

44

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2004-10-01T23:59:59.000Z

45

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-03-15T23:59:59.000Z

46

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-01-30T23:59:59.000Z

47

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codesand corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-01-15T23:59:59.000Z

48

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-11-20T23:59:59.000Z

49

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2006-08-15T23:59:59.000Z

50

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2006-01-18T23:59:59.000Z

51

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-05-01T23:59:59.000Z

52

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-12-15T23:59:59.000Z

53

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-06-20T23:59:59.000Z

54

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2006-06-20T23:59:59.000Z

55

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-08-15T23:59:59.000Z

56

CH-TRU Waste Content Codes (CH TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2004-12-01T23:59:59.000Z

57

Microbial Transformation of TRU and Mixed Wastes: Actinide Speciation and Waste Volume Reduction  

SciTech Connect (OSTI)

I. To characterize the biodegradation of cellulosic materials using Fourier Transform Infrared (FTIR) Spectroscopy. II. To develop an electrochemical/spectroscopic methodology to characterize TRU waste microbial transformation III. To develop molecular models of TRU complexes in order to understand microbial transformation In all cases, objectives are designed to compliment the efforts from other team members, and will be periodically coordinated through the lead P.I. at Brookhaven National Laboratory (BNL), A.J. Francis.

Halada, Gary P.

2004-12-01T23:59:59.000Z

58

Microsoft Word - DOE Exceeds TRU Waste Cleanup Goal at LANL.doc  

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

DOE Exceeds 2012 TRU Waste Cleanup Goal at DOE Exceeds 2012 TRU Waste Cleanup Goal at Los Alamos National Laboratory CARLSBAD, N.M., October 3, 2012 -The Waste Isolation Pilot Plant (WIPP) Central Characterization Project (CCP) and Los Alamos National Laboratory (LANL) exceeded a fiscal year 2012 goal of characterizing and shipping 800 cubic meters of transuranic (TRU) waste, fulfilling a commitment to the state of New Mexico. The 800 cubic meters goal was exceeded by more than 100 cubic meters, with the vast majority of the TRU waste characterized as defense related TRU and permanently disposed at WIPP. To accomplish this achievement, the WIPP CCP increased the amount of waste that was certified, ensuring it met all the requirements for disposal at WIPP. This resulted in the ability to

59

Legacy Risk Measure for Environmental Management Waste  

SciTech Connect (OSTI)

The Idaho National Engineering and Environmental Laboratory (INEEL) is investigating the development of a comprehensive and quantitative risk model framework for environmental management activities at the site. Included are waste management programs (high-level waste, transuranic waste, low-level waste, mixed low-level waste, spent nuclear fuel, and special nuclear materials), major environmental restoration efforts, major decontamination and decommissioning projects, and planned long-term stewardship activities. Two basic types of risk estimates are included: risks from environmental management activities, and long-term legacy risks from wastes/materials. Both types of risks are estimated using the Environment, Safety, and Health Risk Assessment Program (ESHRAP) developed at the INEEL. Given these two types of risk calculations, the following evaluations can be performed: Risk evaluation of an entire program (covering waste/material as it now exists through disposal or other end states) Risk comparisons of alternative programs or activities Comparisons of risk benefit versus risk cost for activities or entire programs Ranking of programs or activities by risk Ranking of wastes/materials by risk Evaluation of site risk changes with time as activities progress Integrated performance measurement using indicators such as injury/death and exposure rates. This paper discusses the definition and calculation of legacy risk measures and associated issues. The legacy risk measure is needed to support three of the seven types of evaluations listed above: comparisons of risk benefit versus risk cost, ranking of wastes/materials by risk, and evaluation of site risk changes with time.

Eide, Steven Arvid; Nitschke, Robert Leon

2002-02-01T23:59:59.000Z

60

HANFORD SITE RIVER PROTECTION PROJECT (RPP) TRANSURANIC (TRU) TANK WASTE IDENTIFICATION & PLANNING FOR REVRIEVAL TREATMENT & EVENTUAL DISPOSAL AT WIPP  

SciTech Connect (OSTI)

The CH2M HILL Manford Group, Inc. (CHG) conducts business to achieve the goals of the Office of River Protection (ORP) at Hanford. As an employee owned company, CHG employees have a strong motivation to develop innovative solutions to enhance project and company performance while ensuring protection of human health and the environment. CHG is responsible to manage and perform work required to safely store, enhance readiness for waste feed delivery, and prepare for treated waste receipts for the approximately 53 million gallons of legacy mixed radioactive waste currently at the Hanford Site tank farms. Safety and environmental awareness is integrated into all activities and work is accomplished in a manner that achieves high levels of quality while protecting the environment and the safety and health of workers and the public. This paper focuses on the innovative strategy to identify, retrieve, treat, and dispose of Hanford Transuranic (TRU) tank waste at the Waste Isolation Pilot Plant (WIPP).

KRISTOFZSKI, J.G.; TEDESCHI, R.; JOHNSON, M.E.; JENNINGS, M

2006-01-18T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

Waste Isolation Pilot Plant simulated RH TRU waste experiments: Data and interpretation pilot  

SciTech Connect (OSTI)

The simulated, i.e., nonradioactive remote-handled transuranic waste (RH TRU) experiments being conducted underground in the Waste Isolation Pilot Plant (WIPP) were emplaced in mid-1986 and have been in heated test operation since 9/23/86. These experiments involve the in situ, waste package performance testing of eight full-size, reference RH TRU containers emplaced in horizontal, unlined test holes in the rock salt ribs (walls) of WIPP Room T. All of the test containers have internal electrical heaters; four of the test emplacements were filled with bentonite and silica sand backfill materials. We designed test conditions to be ``near-reference`` with respect to anticipated thermal outputs of RH TRU canisters and their geometrical spacing or layout in WIPP repository rooms, with RH TRU waste reference conditions current as of the start date of this test program. We also conducted some thermal overtest evaluations. This paper provides a: detailed test overview; comprehensive data update for the first 5 years of test operations; summary of experiment observations; initial data interpretations; and, several status; experimental objectives -- how these tests support WIPP TRU waste acceptance, performance assessment studies, underground operations, and the overall WIPP mission; and, in situ performance evaluations of RH TRU waste package materials plus design details and options. We provide instrument data and results for in situ waste container and borehole temperatures, pressures exerted on test containers through the backfill materials, and vertical and horizontal borehole-closure measurements and rates. The effects of heat on borehole closure, fracturing, and near-field materials (metals, backfills, rock salt, and intruding brine) interactions were closely monitored and are summarized, as are assorted test observations. Predictive 3-dimensional thermal and structural modeling studies of borehole and room closures and temperature fields were also performed.

Molecke, M.A.; Argueello, G.J.; Beraun, R.

1993-04-01T23:59:59.000Z

62

ABSORBING WIPP BRINES: A TRU WASTE DISPOSAL STRATEGY  

SciTech Connect (OSTI)

Los Alamos National Laboratory (LANL) has completed experiments involving 15 each, 250- liter experimental test containers of transuranic (TRU) heterogeneous waste immersed in two types of brine similar to those found in the underground portion of the Waste Isolation Pilot Plant (WIPP). To dispose of the waste without removing the brine from the test containers, LANL added commercially available cross-linked polyacrylate granules to absorb the 190 liters of brine in each container, making the waste compliant for shipping to the WIPP in a Standard Waste Box (SWB). Prior to performing the absorption, LANL and the manufacturer of the absorbent conducted laboratory and field tests to determine the ratio of absorbent to brine that would fully absorb the liquid. Bench scale tests indicated a ratio of 10 parts Castile brine to one part absorbent and 6.25 parts Brine A to one part absorbent. The minimum ratio of absorbent to brine was sought because headspace in the containers was limited. However, full scale testing revealed that the ratio should be adjusted to be about 15% richer in absorbent. Additional testing showed that the absorbent would not apply more than 13.8 kPa pressure on the walls of the vessel and that the absorbent would still function normally at that pressure and would not degrade in the approximately 5e-4 Sv/hr radioactive field produced by the waste. Heat generation from the absorption was minimal. The in situ absorption created a single waste stream of 8 SWBs whereas the least complicated alternate method of disposal would have yielded at least an additional 2600 liters of mixed low level liquid waste plus about two cubic meters of mixed low level solid waste, and would have resulted in higher risk of radiation exposure to workers. The in situ absorption saved $311k in a combination of waste treatment, disposal, material and personnel costs compared to the least expensive alternative and $984k compared to the original plan.

Yeamans, D. R.; Wrights, R. S.

2002-02-25T23:59:59.000Z

63

Absorbing WIPP brines : a TRU waste disposal strategy.  

SciTech Connect (OSTI)

Los Alamos National Laboratory (LANL) has completed experiments involving 15 each, 250-liter experimental test containers of transuranic (TRU) heterogeneous waste immersed in two types of brine similar to those found in the underground portion of the Waste Isolation Pilot Plant (WIPP). To dispose of the waste without removing the brine from the test containers, LANL added commercially available cross-linked polyacrylate granules to absorb the 190 liters of brine in each container, making the waste compliant for shipping to the WlPP in a Standard Waste Box (SWB). Prior to performing the absorption, LANL and the manufacturer of the absorbent conducted laboratory and field tests to determine the ratio of absorbent to brine that would fully absorb the liquid. Bench scale tests indicated a ratio of 10 parts Castile brine to one part absorbent and 6.25 parts Brine A to one part absorbent. The minimum ratio of absorbent to brine was sought because headspace in the containers was limited. However, full scale testing revealed that the ratio should be adjusted to be about 15% richer in absorbent. Additional testing showed that the absorbent would not apply more than 13.8 kPa pressure on the walls of the vessel and that the absorbent would still function normally at that pressure and would not degrade in the approximately 5e-4 Sv/hr radioactive field produced by the waste. Heat generation from the absorption was minimal. The in situ absorption created a single waste stream of 8 SWBs whereas the least complicated alternate method of disposal would have yielded at least an additional 2600 liters of mixed low level liquid waste plus about two cubic meters of mixed low level solid waste, and would have resulted in higher risk of radiation exposure to workers. The in situ absorption saved $3 1 lk in a combination of waste treatment, disposal, material and personnel costs compared to the least expensive alternative and $984k compared to the original plan.

Yeamans, D. R. (David R.); Wright, R. (Robert)

2002-01-01T23:59:59.000Z

64

The Department of Energy Announces Major Cold War Legacy Waste Cleanup  

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

Media Contact: (208) 586-4940 For Immediate Release: September 28, 2011 The Department of Energy Announces Major Cold War Legacy Waste Cleanup Milestone Waste Isolation Pilot Plant Receives 10,000th Shipment CARLSBAD, NM - The U.S. Department of Energy today announced that the Waste Isolation Pilot Plant (WIPP) received its 10,000th shipment of transuranic (TRU) waste over the weekend. This marks an important milestone in DOE�s mission to clean up the country�s Cold War legacy. "This accomplishment reflects the hard work and dedication of our workers and contractors," said Energy Secretary Steven Chu. "It also demonstrates the Department�s commitment to future generations as we continue our cleanup mission as safely and quickly as possible."

65

Settlement Agreement on TRU Mixed Waste Storage at Nevada Test Site Summary  

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

Settlement Agreement for Transuranic (TRU) Mixed Settlement Agreement for Transuranic (TRU) Mixed Waste Storage Issues at the Nevada Test Site (NTS) State Nevada Agreement Type Settlement Agreement Legal Driver(s) RCRA Scope Summary Settle the Finding of Alleged Violation (FOAV) and Order of November 1, 1990, and the FOAV of June 24, 1991, related to the TRU waste storage pad at Area 5 of the NTS Parties DOE; Nevada Department of Environmental Protection Date 6/11/1992 SCOPE * Settle the Finding of Alleged Violation (FOAV) and Order of November 1, 1990, and the FOAV of June 24, 1991, related to the TRU waste storage pad at Area 5 of the NTS. ESTABLISHING MILESTONES * Within 90 days of the effective date of this Agreement, DOE will provide to NDEP documentation of why the current inventory of TRU mixed waste cannot be removed

66

Waste Isolation Pilot Plant TruDock crane system analysis  

SciTech Connect (OSTI)

The WIPP TruDock crane system located in the Waste Handling Building was identified in the WIPP Safety Analysis Report (SAR), November 1995, as a potential accident concern due to failures which could result in a dropped load. The objective of this analysis is to evaluate the frequency of failure of the TruDock crane system resulting in a dropped load and subsequent loss of primary containment, i.e. drum failure. The frequency of dropped loads was estimated to be 9.81E-03/year or approximately one every 102 years (or, for the 25% contingency, 7.36E-03/year or approximately one every 136 years). The dominant accident contributor was the failure of the cable/hook assemblies, based on failure data obtained from NUREG-0612, as analyzed by PLG, Inc. The WIPP crane system undergoes a rigorous test and maintenance program, crane operation is discontinued following any abnormality, and the crane operator and load spotter are required to be trained in safe crane operation, therefore it is felt that the WIPP crane performance will exceed the data presented in NUREG-0612 and the estimated failure frequency is felt to be conservative.

Morris, B.C. [Westinghouse Electric Corp., Pittsburgh, PA (United States); Carter, M. [Westinghouse Electric Corp., Carlsbad, NM (United States). Waste Isolation Div.

1996-10-01T23:59:59.000Z

67

Legacy Risk Measure for Environmental Waste  

SciTech Connect (OSTI)

The Idaho National Engineering and Environmental Laboratory (INEEL) is investigating the development of a comprehensive and quantitative risk model framework for environmental management activities at the site. Included are waste management programs (high-level waste, transuranic waste, low-level waste, mixed low-level waste, spent nuclear fuel, and special nuclear materials), major environmental restoration efforts, major decontamination and decommissioning projects, and planned long-term stewardship activities. Two basic types of risk estimates are included: risks from environmental management activities, and long-term legacy risks from wastes/materials. Both types of risks are estimated using the Environment, Safety, and Health Risk Assessment Program (ESHRAP) developed at the INEEL. Given these two types of risk calculations, the following evaluations can be performed: risk evaluation of an entire program (covering waste/material as it now exists through disposal or other e nd states); risk comparisons of alternative programs or activities; comparisons of risk benefit versus risk cost for activities or entire programs; ranking of programs or activities by risk; ranking of wastes/materials by risk; evaluation of site risk changes with time as activities progress; and integrated performance measurement using indicators such as injury/death and exposure rates. This paper discusses the definition and calculation of legacy risk measures and associated issues. The legacy risk measure is needed to support three of the seven types of evaluations listed above: comparisons of risk benefit versus risk cost, ranking of wastes/materials by risk, and evaluation of site risk changes with time.

Eide, S. A.; Nitschke, R. L.

2002-02-26T23:59:59.000Z

68

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

69

DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation  

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

ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment October 3, 2011 - 12:00pm Addthis DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment CARLSBAD, N.M. - The Waste Isolation Pilot Plant (WIPP) received its

70

DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation  

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

DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment October 3, 2011 - 12:00pm Addthis DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment CARLSBAD, N.M. - The Waste Isolation Pilot Plant (WIPP) received its

71

E-Print Network 3.0 - assay tru waste Sample Search Results  

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

Summary: (TRU) Waste Facilities U.S. Department of Energy Washington, D.C. 20585 AREA-SAFT DISTRIBUTION... to be used when developing Safety Basis (SB) documents for transuranic...

72

MANAGING THE RETRIEVAL RISK OF BURIED TRANSURANIC (TRU) WASTE WITH UNIQUE CHARACTERISTICS  

SciTech Connect (OSTI)

United States-Department of Energy (DOE) sites that store transuranic (TRU) waste are almost certain to encounter waste packages with characteristics that are so unique as to warrant special precautions for retrieval. At the Hanford Site, a subgroup of stored TRU waste (12 drums) had special considerations due to the radioactive source content of plutonium oxide (PuO{sub 2}), and the potential for high heat generation, pressurization, criticality, and high radiation. These characteristics bear on the approach to safely retrieve, overpack, vent, store, and transport the waste package. Because of the potential risk to personnel, contingency planning for unexpected conditions played an effective role in work planning and in preparing workers for the field inspection activity. As a result, the integrity inspections successfully confirmed waste package configuration and waste confinement without experiencing any perturbations due to unanticipated packaging conditions. This paper discusses the engineering and field approach to managing the risk of retrieving TRU waste with unique characteristics.

WOJTASEK, R.D.; GADD, R.R.; GREENWELL, R.D.

2006-01-19T23:59:59.000Z

73

The effect of vibration on alpha radiolysis of transuranic (TRU) waste  

SciTech Connect (OSTI)

This paper reports on previously unpublished scoping work related to the potential for vibration to redistribute radionuclides on transuranic (TRU) waste. If this were to happen, the amount of gases generated, including hydrogen, could be increased above the undisturbed levels. This could be an important consideration for transport of TRU wastes either at DOE sites or from them to a future repository, e.g., the Waste Isolation Pilot Plant (WIPP). These preliminary data on drums of real waste seem to suggest that radionuclide redistribution does not occur. However improvements in the experimental methodology are suggested to enhance safety of future experiments on real wastes as well as to provide more rigorous data.

Zerwekh, A.; Kosiewicz, S. (Los Alamos National Lab., NM (United States)); Warren, J. (NFT, Inc., Lakewood, CO (United States))

1993-01-01T23:59:59.000Z

74

The effect of vibration on alpha radiolysis of transuranic (TRU) waste  

SciTech Connect (OSTI)

This paper reports on previously unpublished scoping work related to the potential for vibration to redistribute radionuclides on transuranic (TRU) waste. If this were to happen, the amount of gases generated, including hydrogen, could be increased above the undisturbed levels. This could be an important consideration for transport of TRU wastes either at DOE sites or from them to a future repository, e.g., the Waste Isolation Pilot Plant (WIPP). These preliminary data on drums of real waste seem to suggest that radionuclide redistribution does not occur. However improvements in the experimental methodology are suggested to enhance safety of future experiments on real wastes as well as to provide more rigorous data.

Zerwekh, A.; Kosiewicz, S. [Los Alamos National Lab., NM (United States); Warren, J. [NFT, Inc., Lakewood, CO (United States)

1993-02-01T23:59:59.000Z

75

LANL Shatters Records in First Year of Accelerated TRU Waste Shipping  

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

Shatters Records in First Year of Accelerated TRU Waste Shatters Records in First Year of Accelerated TRU Waste Shipping Effort LANL Shatters Records in First Year of Accelerated TRU Waste Shipping Effort December 27, 2012 - 12:00pm Addthis From left, EM Deputy Assistant Secretary for Waste Management Frank Marcinowski, San Ildefonso Pueblo Governor Terry Aguilar, Los Alamos County Council Chair Sharon Stover, New Mexico Governor Susana Martinez, Los Alamos Site Office Manager Kevin Smith, and Laboratory Director Charles McMillan applaud as the 1,000th shipment of waste leaves Los Alamos National Laboratory. From left, EM Deputy Assistant Secretary for Waste Management Frank Marcinowski, San Ildefonso Pueblo Governor Terry Aguilar, Los Alamos County Council Chair Sharon Stover, New Mexico Governor Susana Martinez, Los

76

LANL Shatters Records in First Year of Accelerated TRU Waste Shipping  

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

LANL Shatters Records in First Year of Accelerated TRU Waste LANL Shatters Records in First Year of Accelerated TRU Waste Shipping Effort LANL Shatters Records in First Year of Accelerated TRU Waste Shipping Effort December 27, 2012 - 12:00pm Addthis From left, EM Deputy Assistant Secretary for Waste Management Frank Marcinowski, San Ildefonso Pueblo Governor Terry Aguilar, Los Alamos County Council Chair Sharon Stover, New Mexico Governor Susana Martinez, Los Alamos Site Office Manager Kevin Smith, and Laboratory Director Charles McMillan applaud as the 1,000th shipment of waste leaves Los Alamos National Laboratory. From left, EM Deputy Assistant Secretary for Waste Management Frank Marcinowski, San Ildefonso Pueblo Governor Terry Aguilar, Los Alamos County Council Chair Sharon Stover, New Mexico Governor Susana Martinez, Los

77

Quality assurance (QA) plan for the transportation and receipt of transuranic (TRU) waste  

SciTech Connect (OSTI)

The Department of Energy (DOE) Albuquerque Operations (AL) Office of Projects and Energy Programs has been assigned the responsibility for administration of the disposal of Contact-Handled (CH) Transuranic (TRU) contaminated material (waste) from generator/storage sites of the United States defense programs that are operated by the DOE. This responsibility encompasses all activities associated with the certification of TRU waste and the transportation, receipt and disposal of that waste at the Waste Isolation Pilot Plant (WIPP). The WIPP is located near Carlsbad, New Mexico and is being developed under the management of the DOE WIPP Project Office (WPO). The DOE/WPO is a branch of the DOE/AL and has been delegated overall responsibility for all aspects of the WIPP program. This report describes the quality assurance plan for the TRU waste transportation and receipt of waste.

Not Available

1990-02-01T23:59:59.000Z

78

Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program  

SciTech Connect (OSTI)

The Performance Demonstration Program (PDP) for Nondestructive Assay (NDA) is a test program designed to yield data on measurement system capability to characterize drummed transuranic (TRU) waste generated throughout the Department of Energy (DOE) complex. The tests are conducted periodically and provide a mechanism for the independent and objective assessment of NDA system performance and capability relative to the radiological characterization objectives and criteria of the Office of Characterization and Transportation (OCT). The primary documents requiring an NDA PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC), which requires annual characterization facility participation in the PDP, and the Quality Assurance Program Document (QAPD). This NDA PDP implements the general requirements of the QAPD and applicable requirements of the WAC. Measurement facilities must demonstrate acceptable radiological characterization performance through measurement of test samples comprised of pre-specified PDP matrix drum/radioactive source configurations. Measurement facilities are required to analyze the NDA PDP drum samples using the same procedures approved and implemented for routine operational waste characterization activities. The test samples provide an independent means to assess NDA measurement system performance and compliance per criteria delineated in the NDA PDP Plan. General inter-comparison of NDA measurement system performance among DOE measurement facilities and commercial NDA services can also be evaluated using measurement results on similar NDA PDP test samples. A PDP test sample consists of a 55-gallon matrix drum containing a waste matrix type representative of a particular category of the DOE waste inventory and nuclear material standards of known radionuclide and isotopic composition typical of DOE radioactive material. The PDP sample components are made available to participating measurement facilities as designated by the Carlsbad Field Office (CBFO). The nuclear material type, mass and associated alpha activity of the NDA PDP radioactive standard sets have been specified and fabricated to allow assembly of PDP samples that simulate TRU alpha activity concentrations, radionuclidic/isotopic distributions and physical forms typical of the DOE TRU waste inventory. The PDP matrix drum waste matrix types were derived from an evaluation of information contained in the Transuranic Waste Baseline Inventory Report (TWBIR) to ensure representation of prevalent waste types and their associated matrix characteristics in NDA PDP testing. NDA drum analyses required by the Waste Isolation Pilot Plant (WIPP) may only be performed by measurement facilities that comply with the performance criteria as set forth in the NDA PDP Plan. In this document, these analyses are referred to as WIPP analyses, and the wastes on which they are performed are referred to as WIPP wastes.

Carlsbad Field Office

2005-08-03T23:59:59.000Z

79

New Facility Aids in Lab's Capability to Ship TRU Waste to WIPP |  

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

Facility Aids in Lab's Capability to Ship TRU Waste to WIPP Facility Aids in Lab's Capability to Ship TRU Waste to WIPP New Facility Aids in Lab's Capability to Ship TRU Waste to WIPP December 1, 2011 - 12:00pm Addthis Workers move standard waste boxes to the High-Energy Real Time Radiography facility. Workers move standard waste boxes to the High-Energy Real Time Radiography facility. A standard waste box enters the HE-RTR at Los Alamos National Laboratory. The facility x-rays waste drums that contain high-density items such as motors and pumps and larger containers known as standard waste boxes. A standard waste box enters the HE-RTR at Los Alamos National Laboratory. The facility x-rays waste drums that contain high-density items such as motors and pumps and larger containers known as standard waste boxes. Workers move standard waste boxes to the High-Energy Real Time Radiography facility.

80

Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program  

SciTech Connect (OSTI)

The Performance Demonstration Program (PDP) for nondestructive assay (NDA) consists of a series of tests to evaluate the capability for NDA of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements obtained from NDA systems used to characterize the radiological constituents of TRU waste. The primary documents governing the conduct of the PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC; DOE 1999a) and the Quality Assurance Program Document (QAPD; DOE 1999b). The WAC requires participation in the PDP; the PDP must comply with the QAPD and the WAC. The WAC contains technical and quality requirements for acceptable NDA. This plan implements the general requirements of the QAPD and applicable requirements of the WAC for the NDA PDP. Measurement facilities demonstrate acceptable performance by the successful testing of simulated waste containers according to the criteria set by this PDP Plan. Comparison among DOE measurement groups and commercial assay services is achieved by comparing the results of measurements on similar simulated waste containers reported by the different measurement facilities. These tests are used as an independent means to assess the performance of measurement groups regarding compliance with established quality assurance objectives (QAO's). Measurement facilities must analyze the simulated waste containers using the same procedures used for normal waste characterization activities. For the drummed waste PDP, a simulated waste container consists of a 55-gallon matrix drum emplaced with radioactive standards and fabricated matrix inserts. These PDP sample components are distributed to the participating measurement facilities that have been designated and authorized by the Carlsbad Field Office (CBFO). The NDA Drum PDP materials are stored at these sites under secure conditions to protect them from loss, tampering, or accidental damage. Using removable PDP radioactive standards, isotopic activities in the simulated waste containers are varied to the extent possible over the range of concentrations anticipated in actual waste characterization situations. Manufactured matrices simulate expected waste matrix conditions and provide acceptable consistency in the sample preparation process at each measurement facility. Analyses that are required by the Waste Isolation Pilot Plant (WIPP) to demonstrate compliance with various regulatory requirements and that are included in the PDP may only be performed by measurement facilities that demonstrate acceptable performance in the PDP. These analyses are referred to as WIPP analyses, and the wastes on which they are performed are referred to as WIPP wastes in this document.

DOE Carlsbad Field Office

2001-04-06T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

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

82

Performance Demonstration Program Plan for Nondestructive Assay of Boxed Wastes for the TRU Waste Characterization Program  

SciTech Connect (OSTI)

The Performance Demonstration Program (PDP) for nondestructive assay (NDA) consists of a series of tests to evaluate the capability for NDA of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements obtained from NDA systems used to characterize the radiological constituents of TRU waste. The primary documents governing the conduct of the PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC; DOE 1999a) and the Quality Assurance Program Document (QAPD; DOE 1999b). The WAC requires participation in the PDP; the PDP must comply with the QAPD and the WAC. The WAC contains technical and quality requirements for acceptable NDA. This plan implements the general requirements of the QAPD and applicable requirements of the WAC for the NDA PDP for boxed waste assay systems. Measurement facilities demonstrate acceptable performance by the successful testing of simulated waste containers according to the criteria set by this PDP Plan. Comparison among DOE measurement groups and commercial assay services is achieved by comparing the results of measurements on similar simulated waste containers reported by the different measurement facilities. These tests are used as an independent means to assess the performance of measurement groups regarding compliance with established quality assurance objectives (QAOs). Measurement facilities must analyze the simulated waste containers using the same procedures used for normal waste characterization activities. For the boxed waste PDP, a simulated waste container consists of a modified standard waste box (SWB) emplaced with radioactive standards and fabricated matrix inserts. An SWB is a waste box with ends designed specifically to fit the TRUPACT-II shipping container. SWBs will be used to package a substantial volume of the TRU waste for disposal. These PDP sample components are distributed to the participating measurement facilities that have been designated and authorized by the Carlsbad Field Office (CBFO). The NDA Box PDP materials are stored at these sites under secure conditions to protect them from loss, tampering, or accidental damage. Using removable PDP radioactive standards, isotopic activities in the simulated waste containers are varied to the extent possible over the range of concentrations anticipated in actual waste characterization situations. Manufactured matrices simulate expected waste matrix configurations and provide acceptable consistency in the sample preparation process at each measurement facility. Analyses that are required by the Waste Isolation Pilot Plant (WIPP) to demonstrate compliance with various regulatory requirements and that are included in the PDP may only be performed by measurement facilities that demonstrate acceptable performance in the PDP. These analyses are referred to as WIPP analyses, and the wastes on which they are performed are referred to as WIPP wastes in this document.

Carlsbad Field Office

2001-01-31T23:59:59.000Z

83

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

SciTech Connect (OSTI)

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

Biedscheid, J.; Stahl, S.; Devarakonda, M.; Peters, K.; Eide, J.

2002-02-26T23:59:59.000Z

84

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

85

Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan  

SciTech Connect (OSTI)

The Transuranic Waste Characterization Quality Assurance Program Plan required each US Department of Energy (DOE) site that characterizes transuranic waste to be sent the Waste Isolation Pilot Plan that addresses applicable requirements specified in the QAPP.

GREAGER, T.M.

1999-09-09T23:59:59.000Z

86

NR-SRS TRU Waste Shipments Milestone June 4 2013.docx  

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

June 4, 2013 June 4, 2013 Bill Taylor, DOE-SR, (803) 952-8564 bill.taylor@srs.gov DT Townsend, SRNS, (803) 952-7566 Dt-lawrence.townsend@srs.gov Savannah River Site Exceeds Waste Shipment Goals AIKEN, S.C. - During the month of April, the Savannah River Site met two new milestone records towards analyzing, preparing, packaging and shipping radioactive transuranic (TRU) waste bound for a

87

Preliminary identification of interfaces for certification and transfer of TRU waste to WIPP  

SciTech Connect (OSTI)

This study complements the national program to certify that newly generated and stored, unclassified defense transuranic (TRU) wastes meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria. The objectives of this study were to identify (1) the existing organizational structure at each of the major waste-generating and shipping sites and (2) the necessary interfaces between the waste shippers and WIPP. The interface investigations considered existing waste management organizations at the shipping sites and the proposed WIPP organization. An effort was made to identify the potential waste-certifying authorities and the lines of communication within these organizations. The long-range goal of this effort is to develop practicable interfaces between waste shippers and WIPP to enable the continued generation, interim storage, and eventual shipment of certified TRU wastes to WIPP. Some specific needs identified in this study include: organizational responsibility for certification procedures and quality assurance (QA) program; simple QA procedures; and specification and standardization of reporting forms and procedures, waste containers, and container labeling, color coding, and code location.

Whitty, W.J.; Ostenak, C.A.; Pillay, K.K.S.

1982-02-01T23:59:59.000Z

88

Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan  

SciTech Connect (OSTI)

The Transuranic Waste Characterization Quality Assurance Program Plan required each U.S. Department of Energy (DOE) site that characterizes transuranic waste to be sent the Waste Isolation Pilot Plan that addresses applicable requirements specified in the quality assurance project plan (QAPP).

GREAGER, T.M.

1999-12-14T23:59:59.000Z

89

MANAGEMENT OF TRANSURANIC (TRU) WASTE RETRIEVAL PROJECT RISKS SUCCESSES IN THE STARTUP OF THE HANFORD 200 AREA TRU WASTE RETRIEVAL PROJECT  

SciTech Connect (OSTI)

A risk identification and mitigation method applied to the Transuranic (TRU) Waste Retrieval Project performed at the Hanford 200 Area burial grounds is described. Retrieval operations are analyzed using process flow diagramming. and the anticipated project contingencies are included in the Authorization Basis and operational plans. Examples of uncertainties assessed include degraded container integrity, bulged drums, unknown containers, and releases to the environment. Identification and mitigation of project risks contributed to the safe retrieval of over 1700 cubic meters of waste without significant work stoppage and below the targeted cost per cubic meter retrieved. This paper will be of interest to managers, project engineers, regulators, and others who are responsible for successful performance of waste retrieval and other projects with high safety and performance risks.

GREENWLL, R.D.

2005-01-20T23:59:59.000Z

90

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

91

Retrieval and Repackaging of RH-TRU Waste - General Presentation Modular Hot Cell Technology  

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

Paul Murray Paul Murray Oak Ridge, TN July 29, 2009 Retrieval and Repackaging of RH-TRU Waste- GENERAL PRESENTATION MODULAR HOT CELL TECHNOLOGY AREVA FEDERAL SERVICES - OAK RIDGE, TN - GENERAL PRESENTATION OF MODULAR HOT CELL TECHNOLOGY - July 29, 2009 ADAPTING AREVA'S TECHNOLOGY AREVA Worldwide Nuclear Lifecycle Transmission & Distribution Renewable Energy AREVA US Nuclear Fuel Services Nuclear Engineering Services AREVA Federal Services, LLC. (AFS) Federal Services Major Projects * MOX-MFFF * Yucca Mountain Project * DUF6 * Plateau Remediation Contract * Washington River Closure Project * SRS Liquid Waste AREVA FEDERAL SERVICES - OAK RIDGE, TN - GENERAL PRESENTATION OF MODULAR HOT CELL TECHNOLOGY - July 29, 2009 ADAPTING AREVA'S TECHNOLOGY AFS Technology Provider

92

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

93

System to control contamination during retrieval of buried TRU waste  

DOE Patents [OSTI]

A system to control contamination during the retrieval of hazardous waste comprising an outer containment building, an inner containment building, within the outer containment building, an electrostatic radioactive particle recovery unit connected to and in communication with the inner and outer containment buildings, and a contaminate suppression system including a moisture control subsystem, and a rapid monitoring system having the ability to monitor conditions in the inner and outer containment buildings.

Menkhaus, Daniel E. (Idaho Falls, ID); Loomis, Guy G. (Idaho Falls, ID); Mullen, Carlan K. (Idaho Falls, ID); Scott, Donald W. (Idaho Falls, ID); Feldman, Edgar M. (Idaho Falls, ID); Meyer, Leroy C. (Idaho Falls, ID)

1993-01-01T23:59:59.000Z

94

"TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than  

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

"TRU" Success: SRS Recovery Act Prepares to Complete Shipment of "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than 5,000 Cubic Meters of Nuclear Waste to WIPP "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than 5,000 Cubic Meters of Nuclear Waste to WIPP With the American Recovery and Reinvestment Act funding, Savannah River Site (SRS) continues to safely treat and dispose of radioactive waste created while producing materials for nuclear weapons throughout the Cold War. The DOE site in Aiken, S.C., is safely, steadily, and cost-effectively making progress to analyze, measure, and then carefully cleanup or dispose of legacy transuranic (TRU) waste remaining at SRS after the lengthy nuclear arms race. "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than

95

"TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than  

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

"TRU" Success: SRS Recovery Act Prepares to Complete Shipment of "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than 5,000 Cubic Meters of Nuclear Waste to WIPP "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than 5,000 Cubic Meters of Nuclear Waste to WIPP With the American Recovery and Reinvestment Act funding, Savannah River Site (SRS) continues to safely treat and dispose of radioactive waste created while producing materials for nuclear weapons throughout the Cold War. The DOE site in Aiken, S.C., is safely, steadily, and cost-effectively making progress to analyze, measure, and then carefully cleanup or dispose of legacy transuranic (TRU) waste remaining at SRS after the lengthy nuclear arms race. "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than

96

In-situ stabilization of TRU/mixed waste project at the INEEL  

SciTech Connect (OSTI)

Throughout the DOE complex, buried waste poses a threat to the environment by means of contaminant transport. Many of the sites contain buried waste that is untreated, prior to disposal, or insufficiently treated, by today`s standards. One option to remedy these disposal problems is to stabilize the waste in situ. This project was in support of the Transuranic/Mixed Buried Waste - Arid Soils product line of the Landfill Focus Area, which is managed currently by the Idaho National Engineering Laboratory (BNL) provided the analytical laboratory and technical support for the various stabilization activities that will be performed as part of the In Situ Stabilization of TRU/Mixed Waste project at the INEL. More specifically, BNL was involved in laboratory testing that included the evaluation of several grouting materials and their compatibility, interaction, and long-term durability/performance, following the encapsulation of various waste materials. The four grouting materials chosen by INEL were: TECT 1, a two component, high density cementious grout, WAXFIX, a two component, molten wax product, Carbray 100, a two component elastomeric epoxy, and phosphate cement, a two component ceramic. A simulated waste stream comprised of sodium nitrate, Canola oil, and INEL soil was used in this study. Seven performance and durability tests were conducted on grout/waste specimens: compressive strength, wet-dry cycling, thermal analysis, base immersion, solvent immersion, hydraulic conductivity, and accelerated leach testing.

Milian, L.W.; Heiser, J.H.; Adams, J.W.; Rutenkroeger, S.P.

1997-08-01T23:59:59.000Z

97

Final Environmental Impact Statement for Treating Transuranic (TRU)/Alpha Low-level Waste at the Oak Ridge National Laboratory Oak Ridge, Tennessee  

SciTech Connect (OSTI)

The DOE proposes to construct, operate, and decontaminate/decommission a TRU Waste Treatment Facility in Oak Ridge, Tennessee. The four waste types that would be treated at the proposed facility would be remote-handled TRU mixed waste sludge, liquid low-level waste associated with the sludge, contact-handled TRU/alpha low-level waste solids, and remote-handled TRU/alpha low-level waste solids. The mixed waste sludge and some of the solid waste contain metals regulated under the Resource Conservation and Recovery Act and may be classified as mixed waste. This document analyzes the potential environmental impacts associated with five alternatives--No Action, the Low-Temperature Drying Alternative (Preferred Alternative), the Vitrification Alternative, the Cementation Alternative, and the Treatment and Waste Storage at Oak Ridge National Laboratory (ORNL) Alternative.

N /A

2000-06-30T23:59:59.000Z

98

Performance Demonstration Program Plan for Nondestructive Assay for the TRU Waste Characterization Program. Revision 1  

SciTech Connect (OSTI)

The Performance Demonstration Program (PDP) for Nondestructive Assay (NDA) consists of a series of tests conducted on a regular frequency to evaluate the capability for nondestructive assay of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed with TRU waste characterization systems. Measurement facility performance will be demonstrated by the successful analysis of blind audit samples according to the criteria set by this Program Plan. Intercomparison between measurement groups of the DOE complex will be achieved by comparing the results of measurements on similar or identical blind samples reported by the different measurement facilities. Blind audit samples (hereinafter referred to as PDP samples) will be used as an independent means to assess the performance of measurement groups regarding compliance with established Quality Assurance Objectives (QAOs). As defined for this program, a PDP sample consists of a 55-gallon matrix drum emplaced with radioactive standards and fabricated matrix inserts. These PDP sample components, once manufactured, will be secured and stored at each participating measurement facility designated and authorized by Carlsbad Area Office (CAO) under secure conditions to protect them from loss, tampering, or accidental damage.

None

1997-05-01T23:59:59.000Z

99

Savannah River Site Public and regulatory involvement in the transuranic (TRU) program and their effect on decisions to dispose of Pu-238 heat source tru waste onsite  

SciTech Connect (OSTI)

The key to successful public involvement at the Savannah River Site (SRS) has been and continues to be vigorous, up-front involvement of the public and state regulators with technical experts. The SRS Waste Management Program includes all forms of radioactive waste. All of the decisions associated with the management of these wastes are of interest to the public and successful program implementation would be impossible without including the public up-front in the program formulation. Serious problems can result if program decisions are made without public involvement, and if the public is informed after key decisions are made. This paper will describe the regulatory and public involvement program and their effects on the decisions concerning the disposal at the Savannah River Site (SRS) of heat source Pu-238 TRU waste. As can be imagined, a decision to dispose of TRU waste onsite versus shipment to the Waste Isolation Pilot Plan (WIPP) in New Mexico for disposal is of considerable interest to the stakeholders in South Carolina. The interaction between the stakeholders not only include the general public, but also the South Carolina Department of Health and Environmental Control (SCDHEC) and Region IV of the Environmental Protection Agency (EPA). The discussions, educational sessions, and negotiations include resolution of equity issues as well and moved forward to an understanding of the difficulties including risk management faced by the Ship-to- WIPP program. Once the program was better understood, the real negotiations concerning equity, safety, and risk to workers from handling Pu-238 waste could begin. This paper will also discuss the technical, regulatory, and public involvement aspects of disposal onsite that must be properly communicated if the program is to be successful. The Risk Based End State Vision Report for the Savannah River Site includes a variance that proposes on-site near surface disposal of waste from the program to produce Pu-238 heat sources for deep space probes. On-site disposal would greatly reduce the risk to workers by eliminating the need to repackage the waste in order to characterize it and ship it to the Waste Isolation Pilot Plant. Significant cost savings can also be realized. A performance assessment was completed to demonstrate that on-site disposal of this waste can be done while meeting the Department of Energy and EPA performance objectives for disposal of TRU waste in a non-WIPP location such as the SRS. This analysis provides a means of demonstrating the technical basis for this alternative to management, stakeholders and regulators. The technical analysis is required to demonstrate that the performance objectives contained in 40 CFR 191, Environmental Protection Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes will be met over a 10,000 year period. This paper will describe the successful results of this technical, regulatory, and public involvement program, explore why and how the accomplishments occurred, and describe the future challenges along with the road map for the future. In doing this, the TRU Ship-to-WIPP program must be described to give the readers an understanding of the technical complexities that must be communicated successfully to achieve constructive stakeholder participation and regulatory approval. (authors)

Bert Crapse, H.M. [U. S. Department of Energy, Washington (United States); Sonny, W.T. [Goldston Washington Savannah River Company (United States)

2007-07-01T23:59:59.000Z

100

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

Note: This page contains sample records for the topic "legacy tru waste" 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

Record of Decision on Treating Transuranic (TRU)/Alpha Low-Level Waste at the Oak Ridge National Laboratory (DOE/EIS-0305) (8/9/00)  

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

83 83 Federal Register / Vol. 65, No. 154 / Wednesday, August 9, 2000 / Notices 1 TRU waste is waste containing alpha-emitting radionuclides with an atomic number greater than 92 and half-lives greater than 20 years, at concentrations greater than 100 nanocuries per gram of waste. 2 Alpha low-level waste is low-level waste that contains alpha-emitting isotopes. 3 Mixed waste contains radioactive waste regulated under the Atomic Energy Act of 1954, as amended, and a hazardous component subject to RCRA regulation. 4 Low-level waste is any radioactive waste that is not classified as high-level waste, spent nuclear fuel, TRU waste, byproduct material, or mixed waste. 5 Remote-handled TRU/alpha low-level waste contains alpha-, beta-, and gamma-emitting isotopes with a surface dose rate greater than 200 millirem

102

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

SciTech Connect (OSTI)

Compliance requirements are presented for certifying that unclassified, newly generated (NG), contact-handled (CH) transuranic (TRU) solid wastes from defense programs meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). Where appropriate, transportation and interim storage requirements are incorporated; however, interim storage sites may have additional requirements consistent with these requirements. All applicable Department of Energy (DOE) orders must continue to be met. The compliance requirements for stored or buried waste are not addressed in this 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

103

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

104

Project Plan, Status, and Lessons Learned for the LANL 3,706 m{sup 3} TRU Waste Campaign - 13085  

SciTech Connect (OSTI)

The Los Alamos National Laboratory (LANL) is currently engaged in a campaign to disposition 3,706 m{sup 3} of transuranic (TRU) waste stored above grade at its Technical Area 54 (TA-54) Area G waste management facility before June 30, 2014. This campaign includes complete removal of all non-cemented above-grade TRU waste that was in storage on October 1, 2011, and is defined as 3,706 m{sup 3} of material. TRU waste containers were placed into storage up to 40 years ago, and most of the older containers must be remediated to address compliance issues before the waste can be characterized, certified as meeting the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), and shipped for disposition. More than half of the remaining TRU waste volume stored above grade is contained within oversize boxes that contain waste items that must be repackaged or size reduced. Facilities and major types of equipment needed to remediate and characterize the TRU waste inventory include two additional oversize box processing lines that are being brought into service as Nuclear Hazard Category III facilities in fiscal year (FY) 2013. Multiple work shifts are scheduled for most remediation lines in FY 2013. An integrated risk-based project management schedule for all disposition activities has been developed that is based on a 'Solution Package' approach. Inventories of containers that have issues in common were compiled into about 15 waste categories and about 75 'Solution Packages' that identify all of the activities needed to disposition the inventory of TRU waste in storage. Scheduled activities include all precursor activities to begin remediation, remediation processing, characterization and certification to the WIPP WAC, and shipping of containers to WIPP. Other industrial processing practices that have been adopted to improve efficiency include staging of containers for remediation, characterization, and shipping; establishment of a transportation center; and load management practices for transportation payloads. Progress and accomplishments during FY 2012 are reviewed, and plans for FY 2013 are presented in some detail. Lessons learned on adoption of industrial processing practices are also discussed. (authors)

Johns-Hughes, K.W.; Clemmons, J.S.; Cox, D.R.; Hargis, K.M. [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, New Mexico 87545 (United States)] [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, New Mexico 87545 (United States); Bishop, M.L. [Los Alamos Site Office, National Nuclear Security Administration, U. S. Department of Energy, 3747 W. Jemez Road, Los Alamos, New Mexico 87545 (United States)] [Los Alamos Site Office, National Nuclear Security Administration, U. S. Department of Energy, 3747 W. Jemez Road, Los Alamos, New Mexico 87545 (United States)

2013-07-01T23:59:59.000Z

105

WIPP TRANSURANIC WASTE How has the WIPP TRU Waste Inventory Changed  

E-Print Network [OSTI]

of tank waste from the Hanford site that is currently managed as high-level waste. None of this waste has that these Hanford tank wastes will be treated and will eventually be able to meet the WIPP waste acceptance criteria on the Hanford Tank Waste and K-Basin Sludges that were included in the waste inventory for recertifica- tion

106

Workers at Hanford Site Achieve Recovery Act Legacy Cleanup Goals Ahead of Schedule  

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

July 27, 2011 July 27, 2011 Workers at Hanford Site Achieve Recovery Act Legacy Cleanup Goals Ahead of Schedule RICHLAND, Wash. - The Hanford Site re- cently surpassed American Recovery and Reinvestment Act goals to accelerate the cleanup of legacy waste and fuels. Workers recently achieved three waste management goals ahead of a Sept. 30, 2011 target. The three goals focus on re- ducing Hanford's onsite waste inventory as part of the work funded by $1.6 billion the Richland Operations Office received from the Recovery Act. The three goals are: * Retrieve 50 cubic meters of Remote-Handled (RH) Transuranic (TRU) waste. Workers have re- trieved 84 cubic meters of the waste to date. Compared to contact-handled TRU waste, RH TRU waste requires additional radiation dose

107

Development of the remote-handled transuranic waste radioassay data quality objectives. An evaluation of RH-TRU waste inventories, characteristics, radioassay methods and capabilities  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant will accept remote-handled transuranic waste as early as October of 2001. Several tasks must be accomplished to meet this schedule, one of which is the development of Data Quality Objectives (DQOs) and corresponding Quality Assurance Objectives (QAOs) for the assay of radioisotopes in RH-TRU waste. Oak Ridge National Laboratory (ORNL) was assigned the task of providing to the DOE QAO, information necessary to aide in the development of DQOs for the radioassay of RH-TRU waste. Consistent with the DQO process, information needed and presented in this report includes: identification of RH-TRU generator site radionuclide data that may have potential significance to the performance of the WIPP repository or transportation requirements; evaluation of existing methods to measure the identified isotopic and quantitative radionuclide data; evaluation of existing data as a function of site waste streams using documented site information on fuel burnup, radioisotope processing and reprocessing, special research and development activities, measurement collection efforts, and acceptable knowledge; and the current status of technologies and capabilities at site facilities for the identification and assay of radionuclides in RH-TRU waste streams. This report is intended to provide guidance in developing the RH-TRU waste radioassay DQOs, first by establishing a baseline from which to work, second, by identifying needs to fill in the gaps between what is known and achievable today and that which will be required before DQOs can be formulated, and third, by recommending measures that should be taken to assure that the DQOs in fact balance risk and cost with an achievable degree of certainty.

Meeks, A.M.; Chapman, J.A.

1997-09-01T23:59:59.000Z

108

Immobilization and Waste Form Product Acceptance for Low Level and TRU Waste Forms  

SciTech Connect (OSTI)

The Tanks Focus Area is supporting technology development in immobilization of both High Level (HLW) and Low Level (LLW) radioactive wastes. The HLW process development at Hanford and Idaho is patterned closely after that of the Savannah River (Defense Waste Processing Facility) and West Valley Sites (West Valley Demonstration Project). However, the development and options open to addressing Low Level Waste are diverse and often site specific. To start, it is important to understand the breadth of Low Level Wastes categories.

Holtzscheiter, E.W. [Westinghouse Savannah River Company, AIKEN, SC (United States); Harbour, J.R.

1998-05-01T23:59:59.000Z

109

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

SciTech Connect (OSTI)

Compliance requirements are presented for certifying that unclassified, newly generated, contact-handled (CH) transuranic (TRU) solid wastes from defense programs meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). Where appropriate, transportation and interim storage requirements are incorporated, however, interim storage sites may have additional requirements consistent with these requirements. All applicable DOE orders must continue to be met. The compliance requirements for stored or buried waste are not addressed in this 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

110

Comparison of risk-dominant scenario assumptions for several TRU waste facilities in the DOE complex  

SciTech Connect (OSTI)

In order to gain a risk management perspective, the DOE Rocky Flats Field Office (RFFO) initiated a survey of other DOE sites regarding risks from potential accidents associated with transuranic (TRU) storage and/or processing facilities. Recently-approved authorization basis documents at the Rocky Flats Environmental Technology Site (RFETS) have been based on the DOE Standard 3011 risk assessment methodology with three qualitative estimates of frequency of occurrence and quantitative estimates of radiological consequences to the collocated worker and the public binned into three severity levels. Risk Class 1 and 2 events after application of controls to prevent or mitigate the accident are designated as risk-dominant scenarios. Accident Evaluation Guidelines for selection of Technical Safety Requirements (TSRs) are based on the frequency and consequence bin assignments to identify controls that can be credited to reduce risk to Risk Class 3 or 4, or that are credited for Risk Class 1 and 2 scenarios that cannot be further reduced. This methodology resulted in several risk-dominant scenarios for either the collocated worker or the public that warranted consideration on whether additional controls should be implemented. RFFO requested the survey because of these high estimates of risks that are primarily due to design characteristics of RFETS TRU waste facilities (i.e., Butler-type buildings without a ventilation and filtration system, and a relatively short distance to the Site boundary). Accident analysis methodologies and key assumptions are being compared for the DOE sites responding to the survey. This includes type of accidents that are risk dominant (e.g., drum explosion, material handling breach, fires, natural phenomena, external events, etc.), source term evaluation (e.g., radionuclide material-at-risk, chemical and physical form, damage ratio, airborne release fraction, respirable fraction, leakpath factors), dispersion analysis (e.g., meteorological assumptions, distance to receptors, plume meander, deposition, and other factors affecting the calculated {chi}/Q), dose assessments (specific activities, inhalation dose conversion factors, breathing rates), designated frequency of occurrence, and risk assignment per the DOE Standard 3011 methodology. Information from the sites is being recorded on a spreadsheet to facilitate comparisons. The first response from Westinghouse Safety Management Solutions for the Savannah River Site (SRS) also provided a detailed analysis of the major differences in methods and assumptions between RFETS and SRS, which forms much of the basis for this paper. Other sites responding to the survey include the Idaho National Engineering and Environmental Laboratory (INEEL), Hanford, and the Los Alamos National Laboratory (LANL).

Foppe, T.L. [Foppe and Associates, Inc., Golden, CO (United States); Marx, D.R. [Westinghouse Safety Management Solutions, Inc., Aiken, SC (United States)

1999-06-01T23:59:59.000Z

111

MINIMIZING WASTE AND COST IN DISPOSITION OF LEGACY RESIDUES  

SciTech Connect (OSTI)

Research is being conducted at the Los Alamos National Laboratory (LANL) which is directed toward development of a quantitative basis for disposition of actinide-bearing process residues (both legacy residues and residues generated from ongoing programmatic operations). This research is focused in two directions: (1) identifying minimum negative consequence (waste, dose, cost) dispositions working within regulatory safeguards termination criteria, and (2) evaluating logistics/consequences of across-the-board residue discards such as authorized at Rocky Flats under a safeguards termination variance. The first approach emphasizes Laboratory commitments to environmental stewardship, worker safety, and fiscal responsibility. This approach has been described as the Plutonium Disposition Methodology (PDM) in deference to direction provided by DOE Albuquerque. The second approach is born of the need to expedite removal of residues from storage for programmatic and reasons and residue storage safety concerns. Any disposition path selected must preserve the legal distinction between residues as Special Nuclear Material (SNM) and discardable materials as waste in order to insure the continuing viability of Laboratory plutonium processing facilities for national security operations.

J. BALKEY; M. ROBINSON

2001-05-01T23:59:59.000Z

112

WIPP Documents - National TRU Program  

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

Label 1 Label 1 Content 1 Label 2 Content 2 Large file size alert This symbol means the document may be a large file size. National TRU Program Annual Transuranic Waste Inventory Report - 2012 DOE/TRU-12-3425 Effective date 10/12 The information presented in the ATWIR - 2012 serves as a current baseline of the TRU waste inventory for potential disposal at WIPP and may be considered in future Compliance Recertification Applications. The TRU Waste Inventory Profile Reports (Appendices A and B) reflect the information reported by the TRU waste sites Mobile Systems Capabilities for Transuranic Waste Characterization A comprehensive database documenting all available technologies related to mobile characterization, treatment, and repackaging of transuranic waste. Performance Demonstration Program Management Plan

113

Application of Robotics and X-ray Radiography to the Examination of Large Contact Handled Transuranic (TRU) Waste Containers  

SciTech Connect (OSTI)

The US Department of Energy, Savannah River Site is storing a large number of transuranic (TRU) waste containers that are to be shipped to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. Radiographic examination of waste containers is required prior to shipment. This paper will discuss the TRU waste container positioning system and safety system provided by PaR Systems, Inc., Shoreview, MN, to the inspection system prime contractor, Hytec, Inc., Los Alamos, NM. Most containers will be over-packed in large metal shipping containers (TRUPACT-III). The largest containers are 2.8 m x 1.9 m x 1.9 m and weigh 5600 kg. In addition, smaller containers and drums are inspected. The containers are manipulated to view the contents from various directions. The motions of the container, X-ray source and X-ray detectors are coordinated to obtain a constant viewing area relative to the item of interest in the container. (authors)

Pe, A.S. [PaR Systems, Inc., PaR Systems Inc., Shoreview, MN (United States)

2007-07-01T23:59:59.000Z

114

Conversion of historic waste treatment process for production of an LDR and WIPP/WAC compliant TRU wasteform  

SciTech Connect (OSTI)

In support of the historic weapons production mission at the, Rocky Flats Environmental Technology Site (RFETS), several liquid waste treatment processes were designed, built and operated for treatment of plutonium-contaminated aqueous waste. Most of these @ processes ultimately resulted in the production of a cemented wasteform. One of these treatment processes was the Miscellaneous Aqueous Waste Handling and Solidification Process, commonly referred to as the Bottlebox process. Due to a lack of processing demand, Bottlebox operations were curtailed in late 1989. Starting in 1992, a treatment capability for stabilization of miscellaneous, Resource Conservation and Recovery Act (RCRA) hazardous, plutonium-nitrate solutions was identified. This treatment was required to address potentially unsafe storage conditions for these liquids. The treatment would produce a TRU wasteform. It thus became necessary to restart the Bottlebox process, but under vastly different conditions and constraints than existed prior to its curtailment. This paper provides a description of the historical Bottlebox process and process controls; and then describes, in detail, all of the process and process control changes that were implemented to convert the treatment system such that a Waste Isolation Pilot Plant (WIPP) and a Land Disposal Requirements (LDR) compliant wasteform would be produced. The rationale for imposition of LDRs on a TRU wasteform is discussed. In addition, this paper discusses the program changes implemented to meet modem criticality safety, Conduct of Operations, and Department of Energy Nuclear Facility restart requirements.

Dunn, R.P.; Wagner, R.A.

1997-03-01T23:59:59.000Z

115

Safety evaluation for packaging (onsite) for the concrete-shielded RH TRU drum for the 327 Postirradiation Testing Laboratory  

SciTech Connect (OSTI)

This safety evaluation for packaging authorizes onsite transport of Type B quantities of radioactive material in the Concrete Shielded Remote-Handled Transuranic Waste (RH TRU) Drum per HNF-PRO-154, Responsibilities and Procedures for all Hazardous Material Shipments. The drum will be used for transport of 327 Building legacy waste from the 300 Area to a solid waste storage facility on the Hanford Site.

Smith, R.J.

1998-03-31T23:59:59.000Z

116

Preliminary fire hazard analysis for the PUTDR and TRU trenches in the Solid Waste Burial Ground  

SciTech Connect (OSTI)

This document represents the Preliminary Fire Hazards Analysis for the Pilot Unvented TRU Drum Retrieval effort and for the Transuranic drum trenches in the low level burial grounds. The FHA was developed in accordance with DOE Order 5480.7A to address major hazards inherent in the facility.

Gaschott, L.J.

1995-06-16T23:59:59.000Z

117

Type B Accident Investigation of the April 8, 2003, Electrical Arc Blast at the Foster Wheeler Environmental Corporation TRU Waste Processing Facility, Oak Ridge, Tennessee  

Broader source: Energy.gov [DOE]

At approximately 0330 hours on April 8, 2003, a phase-to-phase arc blast occurred in the boiler electrical control panel at the Foster Wheeler Environmental Corporation (FWENC) Transuranic (TRU) Waste Processing Facility. The boiler was providing steam for the evaporator and was reportedly operating at about 10% of its capacity.

118

Radioactive and nonradioactive waste intended for disposal at the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

Transuranic (TRU) waste generated by the handling of plutonium in research on or production of US nuclear weapons will be disposed of in the Waste Isolation Pilot Plant (WIPP). This paper describes the physical and radiological properties of the TRU waste that will be deposited in the WIPP. This geologic repository will accommodate up to 175,564 m{sup 3} of TRU waste, corresponding to 168,485 m{sup 3} of contact-handled (CH-) TRU waste and 7,079 m{sup 3} of remote-handled (RH-) TRU waste. Approximately 35% of the TRU waste is currently packaged and stored (i.e., legacy) waste, with the remainder of the waste to be packaged or generated and packaged in activities before the year 2033, the closure time for the repository. These wastes were produced at 27 US Department of Energy (DOE) sites in the course of generating defense nuclear materials. The radionuclide and nonradionuclide inventories for the TRU wastes described in this paper were used in the 1996 WIPP Compliance Certification Application (CCA) performance assessment calculations by Sandia National Laboratories/New Mexico (SNL/NM).

SANCHEZ,LAWRENCE C.; DREZ,P.E.; RATH,JONATHAN S.; TRELLUE,H.R.

2000-05-19T23:59:59.000Z

119

DOE - Office of Legacy Management -- MURR  

Office of Legacy Management (LM)

Missouri Missouri Missouri University Research Reactor (MURR), Missouri, Site This Site All Sites All LM Quick Search Key Documents and Links All documents are Adobe Acrobat files. pdf_icon Key Documents Fact Sheet Please be green. Do not print these documents unless absolutely necessary. Request a paper copy of any document by submitting a Document Request. All Site Documents All documents are Adobe Acrobat files. pdf_icon Fact Sheet Other Documents Fact Sheet Missouri University Research Reactor Site Fact Sheet December 15, 2011 Other Documents Removal of TRU Waste from the Missouri University Research Reactor Final Closeout Report September 16, 2004 Approval of the Critical Decision 4 for the Mixed Transuranic (TRU) Waste Removal Project, University of Missouri Research Reactor (MURR), Columbia, Missouri, and Transfer of Records to Office of Legacy Management (LM) August 24, 2004

120

Process Description for the Retrieval of Earth Covered Transuranic (TRU) Waste Containers at the Hanford Site  

SciTech Connect (OSTI)

This document describes process and operational options for retrieval of the contact-handled suspect transuranic waste drums currently stored below grade in earth-covered trenches at the Hanford Site. Retrieval processes and options discussed include excavation, container retrieval, venting, non-destructive assay, criticality avoidance, incidental waste handling, site preparation, equipment, and shipping.

DEROSA, D.C.

2000-01-13T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

DOE - Office of Legacy Management -- Waste Isolation Pilot Plant - 019  

Office of Legacy Management (LM)

Waste Isolation Pilot Plant - 019 Waste Isolation Pilot Plant - 019 FUSRAP Considered Sites Site: Waste Isolation Pilot Plant (019) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The Waste Isolation Pilot Plant, or WIPP, is the world¿s first underground repository licensed to safely and permanently dispose of transuranic radioactive waste left from the research and production of nuclear weapons. Transuranic waste consists primarily of clothing, tools, rags, and other disposable items contaminated with small amounts of radioactive elements, mostly plutonium. After more than 20 years of scientific study and public input, WIPP began operations on March 26, 1999. Located in the remote

122

Neutron and gamma-ray nondestructive examination of contact-handled transuranic waste at the ORNL TRU Waste Drum Assay Facility  

SciTech Connect (OSTI)

A nondestructive assay system, which includes the Neutron Assay System (NAS) and the Segmented Gamma Scanner (SGS), for the quantification of contact-handled (<200 mrem/h total radiation dose rate at contact with container) transuranic elements (CH-TRU) in bulk solid waste contained in 208-L and 114-L drums has been in operation at the Oak Ridge National Laboratory since April 1982. The NAS has been developed and demonstrated by Los Alamos National Laboratory (LANL) and the Oak Ridge National Laboratory (ORNL) for use by most US Department of Energy Defense Plant (DOE-DP) sites. More research and development is required, however, before the NAS can provide complete assay results for other than routine defense waste. To date, 525 ORNL waste drums have been assayed, with varying degrees of success. The isotopic complexity of the ORNL waste creates a correspondingly complex assay problem. The NAS and SGS assay data are presented and discussed. Neutron matrix effects, the destructive examination facility, and enriched uranium fuel-element assays are also discussed.

Schultz, F.J.; Coffey, D.E.; Norris, L.B.; Haff, K.W.

1985-03-01T23:59:59.000Z

123

Compliance with Waste Acceptance Criteria of WIPP and NTS for Vitrified Low-Level and TRU Waste Forms  

SciTech Connect (OSTI)

A joint project between the Oak Ridge National Laboratory (ORNL) and the Savannah River Technology Center (SRTC) has been established to evaluate vitrification as an option for the immobilization of waste within ORNL tank farms. This paper presents details of calculations based on current best available analyses of the Oak Ridge Tanks on the limits for waste loadings imposed by the waste acceptance criteria.

Harbour, J.R. [Westinghouse Savannah River Company, AIKEN, SC (United States); Andrews, M.K.

1998-07-01T23:59:59.000Z

124

An Effective Waste Management Process for Segregation and Disposal of Legacy Mixed Waste at Sandia National Laboratories/New Mexico  

SciTech Connect (OSTI)

Sandia National Laboratories/New Mexico (SNL/NM) is a research and development facility that generates many highly diverse, low-volume mixed waste streams. Under the Federal Facility Compliance Act, SNL/NM must treat its mixed waste in storage to meet the Land Disposal Restrictions treatment standards. Since 1989, approximately 70 cubic meters (2500 cubic feet) of heterogeneous, poorly characterized and inventoried mixed waste was placed in storage that could not be treated as specified in the SNL/NM Site Treatment Plan. A process was created to sort the legacy waste into sixteen well- defined, properly characterized, and precisely inventoried mixed waste streams (Treatability Groups) and two low-level waste streams ready for treatment or disposal. From June 1995 through September 1996, the entire volume of this stored mixed waste was sorted and inventoried through this process. This process was planned to meet the technical requirements of the sorting operation and to identify and address the hazards this operation presented. The operations were routinely adapted to safely and efficiently handle a variety of waste matrices, hazards, and radiological conditions. This flexibility was accomplished through administrative and physical controls integrated into the sorting operations. Many Department of Energy facilities are currently facing the prospect of sorting, characterizing, and treating a large inventory of mixed waste. The process described in this paper is a proven method for preparing a diverse, heterogeneous mixed waste volume into segregated, characterized, inventoried, and documented waste streams ready for treatment or disposal.

Hallman, Anne K. [Sandia National Labs., Albuquerque, NM (United States); Meyer, Dann [IT Corporation, Albuquerque, NM (United States); Rellergert, Carla A. [Roy F. Weston, Inc., Albuquerque, NM (United States); Schriner, Joseph A. [Automated Solutions of Albuquerque, Albuquerque, NM (United States)

1998-06-01T23:59:59.000Z

125

An effective waste management process for segregation and disposal of legacy mixed waste at Sandia National Laboratories/New Mexico  

SciTech Connect (OSTI)

Sandia National Laboratories/New Mexico (SNL/NM) is a research and development facility that generates many highly diverse, low-volume mixed waste streams. Under the Federal Facility Compliance Act, SNL/NM must treat its mixed waste in storage to meet the Land Disposal Restrictions treatment standards. Since 1989, approximately 70 cubic meters (2,500 cubic feet) of heterogeneous, poorly characterized and inventoried mixed waste was placed in storage that could not be treated as specified in the SNL/NM Site Treatment Plan. A process was created to sort the legacy waste into sixteen well-defined, properly characterized, and accurately inventoried mixed waste streams (Treatability Groups) and two low-level waste streams ready for treatment or disposal. From June 1995 through September 1996, the entire volume of this stored mixed waste was sorted and inventoried. This process was planned to meet the technical requirements of the sorting operation and to identify and address the hazards this operation presented. The operations were routinely adapted to safely and efficiently handle a variety of waste matrices, hazards, and radiological conditions. This flexibility was accomplished through administrative and physical controls integrated into the sorting operations. Many Department of Energy facilities are currently facing the prospect of sorting, characterizing, and treating a large inventory of mixed waste. The process described in this report is a proven method for preparing a diverse, heterogeneous mixed waste volume into segregated, characterized, inventoried, and documented waste streams ready for treatment or disposal.

Hallman, A.K. [Sandia National Labs., Albuquerque, NM (United States); Meyer, D. [IT Corp., Albuquerque, NM (United States); Rellergert, C.A. [Roy F. Weston, Inc., Albuquerque, NM (United States); Schriner, J.A. [Automated Solutions of Albuquerque, Inc., NM (United States)

1998-04-01T23:59:59.000Z

126

DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies Update  

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

EM HQ Updates Waste Disposition Overview Christine Gelles Associate Deputy Assistant Secretary for Waste Management Office of Environmental Management EM SSAB Chairs Meeting 5 November 2013 www.energy.gov/EM 2 * Waste Management Accomplishments and Priorities * National TRU Program Update * LLW/MLLW Disposal Update * Other Programmatic Updates * Disposition Maps - Current Tools Discussion Outline www.energy.gov/EM 3 FY13 Waste Management Accomplishments * WIPP: Emplaced 5,065 cubic meters of TRU with 89 percent of shipments departed from TRU waste sites as planned * Los Alamos: Met Framework Agreement goal for FY 13 ahead of schedule, disposing of over 1,800 cubic meters of legacy managed TRU waste * Oak Ridge: Partnered with regulators to develop strategy for

127

WIPP Uses Recovery Act Funding to Reduce Nuclear Waste Footprint |  

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

Uses Recovery Act Funding to Reduce Nuclear Waste Footprint Uses Recovery Act Funding to Reduce Nuclear Waste Footprint WIPP Uses Recovery Act Funding to Reduce Nuclear Waste Footprint August 1, 2011 - 12:00pm Addthis Media Contact Deb Gill www.wipp.energy.gov 575-234-7270 CARLSBAD, N.M. - The U.S. Department of Energy's (DOE's) Carlsbad Field Office (CBFO) reduced the nuclear waste footprint by using American Recovery and Reinvestment Act funds to expedite the clean up of five transuranic (TRU) waste storage sites and to make important infrastructure improvements at the Waste Isolation Pilot Plant (WIPP). Expediting TRU waste shipments supports DOE's goal to dispose of 90 percent of legacy TRU waste by 2015, saving taxpayers million of dollars in storage and maintenance costs. Recovery Act funds allowed highly trained teams to safely prepare and load

128

Comparative assessment of TRU waste forms and processes. Volume II. Waste form data, process descriptions, and costs.  

SciTech Connect (OSTI)

This volume contains supporting information for the comparative assessment of the transuranic waste forms and processes summarized in Volume I. Detailed data on the characterization of the waste forms selected for the assessment, process descriptions, and cost information are provided. The purpose of this volume is to provide additional information that may be useful when using the data in Volume I and to provide greater detail on particular waste forms and processes. Volume II is divided into two sections and two appendixes. The first section provides information on the preparation of the waste form specimens used in this study and additional characterization data in support of that in Volume I. The second section includes detailed process descriptions for the eight processes evaluated. Appendix A lists the results of MCC-1 leach test and Appendix B lists additional cost data. 56 figures, 12 tables.

Ross, W.A.; Lokken, R.O.; May, R.P.; Roberts, F.P.; Thornhill, R.E.; Timmerman, C.L.; Treat, R.L.; Westsik, J.H. Jr.

1982-09-01T23:59:59.000Z

129

Preliminary Study of Radioactive Waste Package Made of High-Strength and Ultra Low-Permeability Concrete for Geological Disposal of TRU Wastes  

SciTech Connect (OSTI)

We have been developing a radioactive waste package made of high-strength and ultra low-permeability concrete (HSULPC) for geological disposal of TRU wastes, which is expected to be much more impervious to water than conventional concrete. In this study, basic data for the HSULPC regarding its the impervious character and the thermodynamics during cement hydration were obtained through water permeability measurements using cold isostatic pressing (CIP) and adiabatic concrete hydration experiments, respectively. Then, a prediction tool to find concrete package construction conditions to avoid thermal cracking was developed, which could deal with coupled calculations of cement hydration, heat transfer, stress, and cracking. The developed tool was applied to HSULPC hydration on a small-scale cylindrical model to examine whether there was any effect on cracking which depended on the ratio of concrete cylinder thickness to its inner diameter. The results were compared to experiments. For concrete with a compressive strength of 200MPa, the water permeability coefficient was 4 x 10{sup 19} m/s. Dependences of activation energy and frequency factor on degree of cement hydration had a sharp peaking due to the nucleation rate-determining step, and a gradual increase region due to the diffusion rate-determining step. From analyses of the small-scale cylindrical model, dependences of the maximum principal stress on the radius were obtained. When the ratio of the concrete thickness to the heater diameter was around 1, the risk of cracking was predicted to be minimized. These numerical predictions from the developed tool were verified by experiments.

Matsuo, T.; Kawasaki, T.; Sakamoto, H.; Asano, E.; Takei, A.; Shibuya, K.; Katagiri, M.

2003-02-27T23:59:59.000Z

130

Transuranic Waste Program Framework Agreement - December Deliverable July 2012  

SciTech Connect (OSTI)

Framework agreement deliverables are: (1) 'DOE/NNSA commits to complete removal of all non-cemented above-ground EM Legacy TRU and newly generated TRU currently-stored at Area G as of October 1, 2011, by no later than June 30, 2014. This inventory of above-ground TRU is defined as 3706 cubic meters of material.' (2) 'DOE commits to the complete removal of all newly generated TRU received in Area G during FY 2012 and 2013 by no later than December 31, 2014.' (3) 'Based on projected funding profiles, DOE/NNSA will develop by December 31, 2012, a schedule, including pacing milestones, for disposition of the below-ground TRU requiring retrieval at Area G.' Objectives are to: (1) restore the 'Core Team' to develop the December, 2012 deliverable; (2) obtain agreement on the strategy for below ground water disposition; and (3) establish timeline for completion of the deliverable. Below Grade Waste Strategy is to: (1) Perform an evaluation on below grade waste currently considered retrievable TRU; (2) Only commit to retrieve waste that must be retrieved; (3) Develop the Deliverable including Pacing Milestones based on planned commitments; (4) Align all Regulatory Documents for Consistency; and (5) answer these 3 primary questions, is the waste TRU; is the waste retrievable, can retrieval cause more harm than benefit?

Jones, Patricia [Los Alamos National Laboratory

2012-07-19T23:59:59.000Z

131

Preliminary Notice of Violation, Washington TRU Solutions, LLC- EA-2004-08  

Broader source: Energy.gov [DOE]

Issued to Washington TRU Solutions, LLC, related to the Transportainer Procurement and Fabrication Deficiencies at the Waste Isolation Pilot Plant

132

UP2 400 High Activity Oxide Legacy Waste Retrieval Project Scope and Progress-13048  

SciTech Connect (OSTI)

The High Activity Oxide facility (HAO) reprocessed sheared and dissolved 4500 metric tons of light water reactor fuel the fuel of the emerging light water reactor spent fuel between 1976 and 1998. Over the period, approximately 2200 tons of process waste, composed primarily of sheared hulls, was produced and stored in a vast silo in the first place, and in canisters stored in pools in subsequent years. Upon shutdown of the facility, AREVA D and D Division in La Hague launched a thorough investigation and characterization of the silos and pools content, which then served as input data for the definition of a legacy waste retrieval and reconditioning program. Basic design was conducted between 2005 and 2007, and was followed by an optimization phase which lead to the definition of a final scenario and budget, 12% under the initial estimates. The scenario planned for the construction of a retrieval and reconditioning cell to be built on top of the storage silo. The retrieved waste would then be rinsed and sorted, so that hulls could subsequently be sent to La Hague high activity compacting facility, while resins and sludge would be cemented within the retrieval cell. Detailed design was conducted successfully from 2008 until 2011, while a thorough research and development program was conducted in order to qualify each stage of the retrieval and reconditioning process, and assist in the elaboration of the final waste package specification. This R and D program was defined and conducted as a response and mitigation of the major project risks identified during the basic design process. Procurement and site preparatory works were then launched in 2011. By the end of 2012, R and D is nearly completed, the retrieval and reconditioning process have been secured, the final waste package specification is being completed, the first equipment for the retrieval cell is being delivered on site, while preparation works are allowing to free up space above and around the silo, to allow for construction which is scheduled to being during the first semester of 2013. The elaboration of the final waste package is still undergoing and expected to be completed by then end of 2013, following some final elements of R and D required to demonstrate the full compatibility of the package with deep geological repository. The HAO legacy waste retrieval project is so far the largest such project entering operational phase on the site of La Hague. It is on schedule, under budget, and in conformity with the delivery requirements set by the French Safety Authority, as well as other stakeholders. This project paves the way for the successful completion of AREVA La Hague other legacy waste retrieval projects, which are currently being drafted or already in active R and D phase. (authors)

Chabeuf, Jean-Michel; Varet, Thierry [AREVA Site Value Development Business Unit, La Hague Site (France)] [AREVA Site Value Development Business Unit, La Hague Site (France)

2013-07-01T23:59:59.000Z

133

EIS-0305: Treating Transuranic (TRU)/Alpha Low-Level at the Oak Ridge  

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

05: Treating Transuranic (TRU)/Alpha Low-Level at the Oak 05: Treating Transuranic (TRU)/Alpha Low-Level at the Oak Ridge National Laboratory, Oak Ridge, Tennessee EIS-0305: Treating Transuranic (TRU)/Alpha Low-Level at the Oak Ridge National Laboratory, Oak Ridge, Tennessee SUMMARY This EIS evaluates DOE's proposal to construct, operate, and decontaminate/decommission a Transuranic (TRU) Waste Treatment Facility in Oak Ridge, Tennessee. The four waste types that would be treated at the proposed facility would be remote-handled TRU mixed waste sludge, liquid low-level waste associated with the sludge, contact-handled TRU/alpha low-level waste solids, and remote-handled TRU/alpha low-level waste solids. The mixed waste sludge and some of the solid waste contain metals regulated under the Resource Conservation and Recovery Act and may be

134

Innovations in the Assay of Un-Segregated Multi-Isotopic Grade TRU Waste Boxes with SuperHENC and FRAM Technology  

SciTech Connect (OSTI)

The Super High Efficiency Neutron Coincidence Counter (SuperHENC) was originally developed by BIL Solutions Inc., Los Alamos National Laboratory (LANL) and Rocky Flats Environmental Technology Site (RFETS) for assay of transuranic (TRU) waste in Standard Waste Boxes (SWB) at Rocky Flats. This mobile system was a key component in the shipment of over 4,000 SWBs to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The system was WIPP certified in 2001 and operated at the site for four years. The success of this system, a passive neutron coincidence counter combined with high resolution gamma spectroscopy, led to the order of two new units, delivered to Hanford in 2004. Several new challenges were faced at Hanford: For example, the original RFETS system was calibrated for segregated waste streams such that metals, plastics, wet combustibles and dry combustibles were separated by 'Item Description Codes' prior to assay. Furthermore, the RFETS mission of handling only weapons grade plutonium, enabled the original SuperHENC to benefit from the use of known Pu isotopics. Operations at Hanford, as with most other DOE sites, generate un-segregated waste streams, with a wide diversity of Pu isotopics. Consequently, the new SuperHENCs are required to deal with new technical challenges. The neutron system's software and calibration methodology have been modified to encompass these new requirements. In addition, PC-FRAM software has been added to the gamma system, providing a robust isotopic measurement capability. Finally a new software package has been developed that integrates the neutron and gamma data to provide a final assay results and analysis report. The new system's performance has been rigorously tested and validated against WIPP quality requirements. These modifications, together with the mobile platform, make the new SuperHENC far more versatile in handling diverse waste streams and allow for rapid redeployment around the DOE complex. (authors)

Simpson, A. P.; Barber, S. [BIL Solutions Inc., 4001 Office Court Drive no 800, Santa Fe, NM 87507 (United States); Abdurrahman, N. M. [Fluor Hanford, PO Box 1000, Mail Stop T4-52, Richland, WA 99352 (United States)

2006-07-01T23:59:59.000Z

135

Transuranic contaminated waste form characterization and data base  

SciTech Connect (OSTI)

This volume contains 5 appendices. Title listing are: technologies for recovery of transuranics; nondestructive assay of TRU contaminated wastes; miscellaneous waste characteristics; acceptance criteria for TRU waste; and TRU waste treatment technologies.

Kniazewycz, B.G.; McArthur, W.C.

1980-07-01T23:59:59.000Z

136

Project plans for transuranic waste at small quantity sites in the Department of Energy comples-10522  

SciTech Connect (OSTI)

Los Alamos National Laboratory, Carlsbad Office (LANL-CO), has been tasked to write Project Plans for all of the Small Quantity Sites (SQS) with defense related Transuranic (TRU) waste in the Department of Energy (DOE) complex. Transuranic Work-Off Plans were precursors to the Project Plans. LANL-CO prepared a Work-Off Plan for each small quantity site. The Work-Off Plan that identified issues, drivers, schedules, and inventory. Eight sites have been chosen to deinventory their legacy TRU waste; Bettis Atomic Power Laboratory, General Electric-Vallecitos Nuclear Center, Lawrence Berkeley National Laboratory, Lawrence Livermore National Laboratory-Area 300, Nevada Test Site, Nuclear Radiation Development, Sandia National Laboratory, and the Separations Process Research Unit. Each plan was written for contact and/or remote handled waste if present at the site. These project plans will assist the small quantity sites to ship legacy TRU waste offsite and de-inventory the site of legacy TRU waste. The DOE is working very diligently to reduce the nuclear foot print in the United States. Each of the eight SQSs will be de-inventoried of legacy TRU waste during a campaign that ends September 2011. The small quantity sites have a fraction of the waste that large quantity sites possess. During this campaign, the small quantity sites will package all of the legacy TRU waste and ship to Idaho or directly to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The sites will then be removed from the Transuranic Waste Inventory if they are de-inventoried of all waste. Each Project Plan includes the respective site inventory report, schedules, resources, drivers and any issues. These project plans have been written by the difficult waste team and will be approved by each site. Team members have been assigned to each site to write site specific project plans. Once the project plans have been written, the difficult team members will visit the sites to ensure nothing has been overlooked and to verify the inventory. After each site has approved their project plan, the site will begin writing procedures and packaging/repackaging their waste. In some cases the sites have already begun the process. The waste will be shipped after all of the waste has been characterized and approved.

Mctaggart, Jerri Lynne [Los Alamos National Laboratory; Lott, Sheila [Los Alamos National Laboratory; Gadbury, Casey [DOE

2009-01-01T23:59:59.000Z

137

New Facility Saves $20 Million, Accelerates Waste Processing | Department  

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

Facility Saves $20 Million, Accelerates Waste Processing Facility Saves $20 Million, Accelerates Waste Processing New Facility Saves $20 Million, Accelerates Waste Processing August 15, 2012 - 12:00pm Addthis The new Cask Processing Enclosure (CPE) facility is located at the Transuranic Waste Processing Center (TWPC). The Transuranic Waste Processing Center (TWPC) processes, repackages, and ships the site's legacy TRU waste offsite. OAK RIDGE, Tenn. - Oak Ridge's EM program recently began operations at a newly constructed facility that will accelerate the completion of remote-handled transuranic (TRU) waste processing at the site by two years and save taxpayers more than $20 million. The new Cask Processing Enclosure (CPE) facility is located at the Transuranic Waste Processing Center (TWPC). TWPC processes, repackages, and

138

Westinghouse TRU Solutions Launches New Web Site  

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

TRU Solutions LLC Launches New Web Site TRU Solutions LLC Launches New Web Site CARLSBAD, N.M., February 2, 2001 - Westinghouse TRU Solutions LLC (WTS) today launched its new Web site. WTS is the new management and operating contractor for the U.S. Department of Energy (DOE) at the Waste Isolation Pilot Plant (WIPP). The Web site, www.trusolutionsnm.com, is designed to provide up-to-date information about WTS and establish a mechanism for receiving feedback. "We want to make the transition to the new company as smooth as possible," said Hank Herrera, WTS President and General Manager. "The Web site enables us to effectively communicate the WTS role, objectives, and challenges to employees, clients, elected officials, and other stakeholders." The Web site contains sections about the formation of TRU Solutions, the new

139

Mobile/Modular Deployment Project-Enhancing Efficiencies within the National Transuranic Waste Program.  

SciTech Connect (OSTI)

In 1999, the National Transuranic (TRU) Waste Program (NTP) achieved two significant milestones. First, the Waste Isolation Plant (WIPP) opened in March for the permanent disposal of TRU waste generated by, and temporarily stored at, various sites supporting the nation's defense programs. Second, the Hazardous Waste Facility Permit, issued by the New Mexico Environment Department, for WIPP became effective in November. While the opening of WIPP brought to closure a number of scientific, engineering, regulatory, and political challenges, achieving this major milestone led to a new set of challenges-how to achieve the Department of Energy's (DOE's) NTP end-state vision: All TRU waste from DOE sites scheduled for closure is removed All legacy TRU waste from DOE sites with an ongoing nuclear mission is disposed 0 All newly generated TRU waste is disposed as it is generated The goal is to operate the national TRU waste program safely, cost effectively, in compliance with applicable regulations and agreements, and at full capacity in a fully integrated mode. The existing schedule for TRU waste disposition would achieve the NTP vision in 2034 at an estimated life-cycle cost of $16B. The DOE's Carlsbad Field Office (CBFO) seeks to achieve this vision early-by at least 10 years- while saving the nation an estimated $48 to $6B. CBFO's approach is to optimize, or to make as functional as possible, TRU waste disposition. That is, to remove barriers that impede waste disposition, and increase the rate and cost efficiency of waste disposal at WIPP, while maintaining safety. The Mobile/Modular Deployment Project (MMDP) is the principal vehicle for implementing DOE's new commercial model of using best business practices of national authorization basis, standardization, and economies of scale to accelerate the completion of WIPP's mission. The MMDP is one of the cornerstones of the National TRU Waste System Optimization Project (1). The objective of the MMDP is to increase TRU waste shipment and disposal rates from currently certified sites as well as to provide a means to remove TRU waste from sites that have no characterization capability.

Triay, I. R. (Ines R.); Basabilvazo, G. B. (George B.); Countiss, S. (Sue); Moody, D. C. (David C.); Behrens, R. G. (Robert G.); Lott, S. A. (Sheila A.)

2002-01-01T23:59:59.000Z

140

TRU TeamWorks  

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

, 2004 , 2004 By the Numbers WIPP marks five-year anniversary Shipments scheduled to arrive at WIPP for the week of 4/4/04 - 4/10/04: 18 Total shipments received at WIPP: 2,456 Total volume disposed at WIPP: 19,042 m 3 FY04 Performance Metrics D E P A R T M E N T O F E N E R G Y U N I T E D S T A T ES O F A M E R I C A TeamWorks TeamWorks TRU A weekly e-newsletter for the Waste Isolation Pilot Plant team For those who endured the early morning cold of March 26, 1999, to witness WIPP's first shipment, it may seem like yesterday. Yet Friday marked five years of WIPP operations. Relative newcomer to WIPP - but not to the waste management industry - CBFO Deputy Manager Lloyd Piper observed, "The transformation from a facility in "standby" mode to operational mode has been nothing short of amazing."

Note: This page contains sample records for the topic "legacy tru waste" 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

Disposal of TRU Waste from the PFP in pipe overpack containers to WIPP Including New Security Requirements  

SciTech Connect (OSTI)

The Department of Energy is responsible for the safe management and cleanup of the DOE complex. As part of the cleanup and closure of the Plutonium Finishing Plant (PFP) located on the Hanford site, the nuclear material inventory was reviewed to determine the appropriate disposition path. Based on the nuclear material characteristics, the material was designated for stabilization and packaging for long term storage and transfer to the Savannah River Site, or a decision for discard was made. The discarded material was designated as waste material and slated for disposal to the Waste Isolation Pilot Plant (WIPP). Prior to preparing any residue wastes for disposal at the WIPP, several major activities need to be completed. As detailed a processing history as possible of the material including origin of the waste must be researched and documented. A technical basis for termination of safeguards on the material must be prepared and approved. Utilizing process knowledge and processing history, the material must be characterized, sampling requirements determined, acceptable knowledge package and waste designation completed prior to disposal. All of these activities involve several organizations including the contractor, DOE, state representatives and other regulators such as EPA. At PFP, a process has been developed for meeting the many, varied requirements and successfully used to prepare several residue waste streams including Rocky Flats incinerator ash, hanford incinerator ash and Sand, Slag and Crucible (SS and C) material for disposal. These waste residues are packed into Pipe Overpack Containers for shipment to the WIPP.

HOPKINS, A.M.

2003-02-01T23:59:59.000Z

142

High Hydrogen Concentrations Detected In The Underground Vaults For RH-TRU Waste At INEEL Compared With Calculated Values Using The INEEL-Developed Computer Code  

SciTech Connect (OSTI)

About 700 remote-handled transuranic (RH-TRU) waste drums are stored in about 144 underground vaults at the Intermediate-Level Transuranic Storage Facility at the Idaho National Environmental and Engineering Laboratorys (INEELs) Radioactive Waste Management Complex (RWMC). These drums were shipped to the INEEL from 1976 through 1996. During recent monitoring, concentrations of hydrogen were found to be in excess of lower explosive limits. The hydrogen concentration in one vault was detected to be as high as 18% (by volume). This condition required evaluation of the safety basis for the facility. The INEEL has developed a computer program to estimate the hydrogen gas generation as a function of time and diffusion through a series of layers (volumes), with a maximum five layers plus a sink/environment. The program solves the first-order diffusion equations as a function of time. The current version of the code is more flexible in terms of user input. The program allows the user to estimate hydrogen concentrations in the different layers of a configuration and then change the configuration after a given time; e.g.; installation of a filter on an unvented drum or placed in a vault or in a shipping cask. The code has been used to predict vault concentrations and to identify potential problems during retrieval and aboveground storage. The code has generally predicted higher hydrogen concentrations than the measured values, particularly for the drums older than 20 year, which could be due to uncertainty and conservative assumptions in drum age, heat generation rate, hydrogen generation rate, Geff, and diffusion rates through the layers.

Rajiv Bhatt; Soli Khericha

2005-02-01T23:59:59.000Z

143

TRASH TO TREASURE: CONVERTING COLD WAR LEGACY WASTE INTO WEAPONS AGAINST CANCER  

SciTech Connect (OSTI)

As part of its commitment to clean up Cold War legacy sites, the U.S. Department of Energy (DOE) has initiated an exciting and unique project to dispose of its inventory of uranium-233 (233U) stored at Oak Ridge National Laboratory (ORNL), and extract isotopes that show great promise in the treatment of deadly cancers. In addition to increasing the supply of potentially useful medical isotopes, the project will rid DOE of a nuclear concern and cut surveillance and security costs. For more than 30 years, DOE's ORNL has stored over 1,200 containers of fissile 233U, originally produced for several defense-related projects, including a pilot study that looked at using 233U as a commercial reactor fuel. This uranium, designated as special nuclear material, requires expensive security, safety, and environmental controls. It has been stored at an ORNL facility, Building 3019A, that dates back to the Manhattan Project. Down-blending the material to a safer form, rather than continuing to store it, will eliminate a $15 million a year financial liability for the DOE and increase the supply of medical isotopes by 5,700 percent. During the down-blending process, thorium-229 (229Th) will be extracted. The thorium will then be used to extract actinium-225 (225Ac), which will ultimately supply its progeny, bismuth-213 (213Bi), for on-going cancer research. The research includes Phase II clinical trials for the treatment of acute myelogenous leukemia at Sloan-Kettering Memorial Cancer Center in New York, as well as other serious cancers of the lungs, pancreas, and kidneys using a technique known as alpha-particle radioimmunotherapy. Alpha-particle radioimmunotherapy is based on the emission of alpha particles by radionuclides. 213Bi is attached to a monoclonal antibody that targets specific cells. The bismuth then delivers a high-powered but short-range radiation dose, effectively killing the cancerous cells but sparing the surrounding tissue. Production of the actinium and bismuth would be a private venture at no cost to the government. Isotek Systems, LLC, was commissioned by the DOE to execute the project, known as the 233U Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown Project. Isotek is a partnership between Duratek Federal Services, Burns and Roe Enterprises, and Nuclear Fuel Services. By pooling their pioneering experiences in nuclear engineering and design, nuclear recycling, and waste management, the partnership has developed a novel process to meet this clean-up milestone. The project is not only important for its cancer treatment potential, but also for setting the stage for reducing global threats through the down-blending of materials.

Nicholas, R.G.; Lacy, N.H.; Butz, T.R.; Brandon, N.E.

2004-10-06T23:59:59.000Z

144

Accelerating the disposition of transuranic waste from LANL - 9495  

SciTech Connect (OSTI)

Los Alamos National Laboratory (LANL) was established during World War II with a single mission -- to design and build an atomic bomb. In the 65 years since, nuclear weapons physics, design and engineering have been the Laboratory's primary and sustaining mission. Experimental and process operations -- and associated cleanout and upgrade activities -- have generated a significant inventory of transuranic (TRU) waste that is stored at LANL's Technical Area 54, Material Disposal Area G (MDA G). When the Waste Isolation Pilot Plant (WIPP) opened its doors in 1999, LANL's TRU inventory totaled about 10,200 m{sup 3}, with a plutonium 239-equivalent curie (PE Ci) content of approximately 250,000 curies. By December 2008, a total of about 2,300 m3 (61,000 PE Ci) had been shipped to WIPP from LANL. This has resulted in a net reduction of about 1,000 m{sup 3} of TRU inventory over that time frame. This paper presents progress in dispositioning legacy and newly-generated transuranic waste (TRU) from ongoing missions at the LANL. The plans for, and lessons learned, in dispositioning several hundred high-activity TRU waste drums are reviewed. This waste population was one of the highest risks at LANL. Technical challenges in disposition of the high-activity drums are presented. These provide a preview of challenges to be addressed in dispositioning the remaining 6,800 m{sup 3} of TRU stored above ground and 2,400 m{sup 3} of TRU waste that is 'retrievably' stored below-grade. LANL is using subcontractors for much of this work and has formed a strong partnership with WIPP and its contractor to address this cleanup challenge.

Shepard, Mark D [Los Alamos National Laboratory; Stiger, Susan G [Los Alamos National Laboratory; Blankenhorn, James A [Los Alamos National Laboratory; Rael, George J [Los Alamos National Laboratory; Moody, David C [U.S DOE

2009-01-01T23:59:59.000Z

145

WIPP Hazardous Waste Permit - Approved Modifications  

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

Modification to Add South Access Road for Transportation of TRU Mixed Waste dated March 17, 2011 Class 1 Permit Modification Notification to Revise TRU-Pact III Management...

146

Enforcement Letter, Washington TRU Solutions - September 8, 2006 |  

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

Washington TRU Solutions - September 8, 2006 Washington TRU Solutions - September 8, 2006 Enforcement Letter, Washington TRU Solutions - September 8, 2006 September 8, 2006 Enforcement Letter issued to Washington TRU Solutions, LLC related to Quality Assurance Deficiencies associated with the Super High-Efficiency Neutron Counter Non-Destructive Assay System Refurbishment at the Waste Isolation Pilot Plant The Office of Price-Anderson Enforcement (OE) has conducted a preliminary evaluation of the deficiencies described in Noncompliance Tracking System (NTS) report NTS-CBFO-WIPP-WIPP-2006-0001. Our evaluation included review of the investigation/causal analysis and discussion with you and other site personnel during an informal conference held on August 1, 2006. Enforcement Letter, Washington TRU Solutions -September 8, 2006

147

Transuranic Waste Burning Potential of Thorium Fuel in a Fast Reactor - 12423  

SciTech Connect (OSTI)

Westinghouse Electric Company (referred to as 'Westinghouse' in the rest of this paper) is proposing a 'back-to-front' approach to overcome the stalemate on nuclear waste management in the US. In this approach, requirements to further the societal acceptance of nuclear waste are such that the ultimate health hazard resulting from the waste package is 'as low as reasonably achievable'. Societal acceptability of nuclear waste can be enhanced by reducing the long-term radiotoxicity of the waste, which is currently driven primarily by the protracted radiotoxicity of the transuranic (TRU) isotopes. Therefore, a transition to a more benign radioactive waste can be accomplished by a fuel cycle capable of consuming the stockpile of TRU 'legacy' waste contained in the LWR Used Nuclear Fuel (UNF) while generating waste which is significantly less radio-toxic than that produced by the current open U-based fuel cycle (once through and variations thereof). Investigation of a fast reactor (FR) operating on a thorium-based fuel cycle, as opposed to the traditional uranium-based is performed. Due to a combination between its neutronic properties and its low position in the actinide chain, thorium not only burns the legacy TRU waste, but it does so with a minimal production of 'new' TRUs. The effectiveness of a thorium-based fast reactor to burn legacy TRU and its flexibility to incorporate various fuels and recycle schemes according to the evolving needs of the transmutation scenario have been investigated. Specifically, the potential for a high TRU burning rate, high U-233 generation rate if so desired and low concurrent production of TRU have been used as metrics for the examined cycles. Core physics simulations of a fast reactor core running on thorium-based fuels and burning an external TRU feed supply have been carried out over multiple cycles of irradiation, separation and reprocessing. The TRU burning capability as well as the core isotopic content have been characterized. Results will be presented showing the potential for thorium to reach a high TRU transmutation rate over a wide variety of fuel types (oxide, metal, nitride and carbide) and transmutation schemes (recycle or partition of in-bred U-233). In addition, a sustainable scheme has been devised to burn the TRU accumulated in the core inventory once the legacy TRU supply has been exhausted, thereby achieving long-term virtually TRU-free. A comprehensive 'back-to-front' approach to the fuel cycle has recently been proposed by Westinghouse which emphasizes achieving 'acceptable', low-radiotoxicity, high-level waste, with the intent not only to satisfy all technical constraints but also to improve public acceptance of nuclear energy. Following this approach, the thorium fuel cycle, due to its low radiotoxicity and high potential for TRU transmutation has been selected as a promising solution. Additional studies not shown here have shown significant reduction of decay heat. The TRU burning potential of the Th-based fuel cycle has been illustrated with a variety of fuel types, using the Toshiba ARR to perform the analysis, including scenarios with continued LWR operation of either uranium fueled or thorium fueled LWRs. These scenarios will afford overall reduction in actinide radiotoxicity, however when the TRU supply is exhausted, a continued U- 235 LWR operation must be assumed to provide TRU makeup feed. This scenario will never reach the characteristically low TRU content of a closed thorium fuel cycle with its associated potential benefits on waste radiotoxicity, as exemplified by the transition scenario studied. At present, the cases studied indicate ThC as a potential fuel for maximizing TRU burning, while ThN with nitrogen enriched to 95% N-15 shows the highest breeding potential. As a result, a transition scenario with ThN was developed to show that a sustainable, closed Th-cycle can be achieved starting from burning the legacy TRU stock and completing the transmutation of the residual TRU remaining in the core inventory after the legacy TRU external supply has been

Wenner, Michael; Franceschini, Fausto; Ferroni, Paolo [Westinghouse Electric Company LLC,Cranberry Township, PA, 16066 (United States); Sartori, Alberto; Ricotti, Marco [Politecnico di Milano, Milan (Italy)

2012-07-01T23:59:59.000Z

148

Type B Accident Investigation Board Report Employee Puncture Wound at the F-TRU Waste Remediation Facility at the Savannah River Site on June 14, 2010  

Broader source: Energy.gov [DOE]

This report documents the results of the Type B Accident Investigation Board investigation of the June 14, 2010, employee puncture wound at the Department of Energy (DOE) Savannah River Site (SRS) F-TRU Wste Facility located in the F Canyon Facility.

149

Managing Legacy Records for Formerly Utilized Sites Remedial Action Program Sites  

Broader source: Energy.gov [DOE]

Managing Legacy Records for Formerly Utilized Sites Remedial Action Program Sites (Waste Management Conference 2008)

150

A Robust Power Remote Manipulator for Use in Waste Sorting, Processing, and Packaging - 12158  

SciTech Connect (OSTI)

Disposition of radioactive waste is one of the Department of Energy's (DOE's) highest priorities. A critical component of the waste disposition strategy is shipment of Transuranic (TRU) waste from DOE's Oak Ridge Reservation to the Waste Isolation Plant Project (WIPP) in Carlsbad, New Mexico. This is the mission of the DOE TRU Waste Processing Center (TWPC). The remote-handled TRU waste at the Oak Ridge Reservation is currently in a mixed waste form that must be repackaged in to meet WIPP Waste Acceptance Criteria (WAC). Because this remote-handled legacy waste is very diverse, sorting, size reducing, and packaging will require equipment flexibility and strength that is not possible with standard master-slave manipulators. To perform the wide range of tasks necessary with such diverse, highly contaminated material, TWPC worked with S.A. Technology (SAT) to modify SAT's Power Remote Manipulator (PRM) technology to provide the processing center with an added degree of dexterity and high load handling capability inside its shielded cells. TWPC and SAT incorporated innovative technologies into the PRM design to better suit the operations required at TWPC, and to increase the overall capability of the PRM system. Improving on an already proven PRM system will ensure that TWPC gains the capabilities necessary to efficiently complete its TRU waste disposition mission. The collaborative effort between TWPC and S.A. Technology has yielded an extremely capable and robust solution to perform the wide range of tasks necessary to repackage TRU waste containers at TWPC. Incorporating innovative technologies into a proven manipulator system, these PRMs are expected to be an important addition to the capabilities available to shielded cell operators. The PRMs provide operators with the ability to reach anywhere in the cell, lift heavy objects, perform size reduction associated with the disposition of noncompliant waste. Factory acceptance testing of the TWPC Powered Remote Manipulators has completed at SAT's Colorado facility, and on-site training at TWPC is scheduled to start in early 2012. (authors)

Cole, Matt; Martin, Scott [S.A. Technology, Loveland, Colorado 80537, Transuranic Waste Processing Center, Lenoir City, TN 37771 (United States)

2012-07-01T23:59:59.000Z

151

Microsoft Word - Last Legacy Waste Shipment for EM Weekly 4-7...  

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

site lead for the U.S. Department of Energy (DOE). "It reduces the cost of long-term storage, surveillance, and maintenance of waste materials. It frees up space on the site to...

152

Trench Bathtubbing and Surface Plutonium Contamination at a Legacy Radioactive Waste Site  

Science Journals Connector (OSTI)

Radioactive waste containing a few grams of plutonium (Pu) was disposed between 1960 and 1968 in trenches at the Little Forest Burial Ground (LFBG), near Sydney, Australia. A water sampling point installed in a former trench has enabled the radionuclide ...

Timothy E. Payne; Jennifer J. Harrison; Catherine E. Hughes; Mathew P. Johansen; Sangeeth Thiruvoth; Kerry L. Wilsher; Dioni I. Cendn; Stuart I. Hankin; Brett Rowling; Atun Zawadzki

2013-11-20T23:59:59.000Z

153

DOE Cites Washington TRU Solutions for Nuclear Safety Violations |  

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

Washington TRU Solutions for Nuclear Safety Violations Washington TRU Solutions for Nuclear Safety Violations DOE Cites Washington TRU Solutions for Nuclear Safety Violations December 22, 2005 - 4:53pm Addthis WASHINGTON, D.C. -- The Department of Energy (DOE) today notified Washington TRU Solutions (WTS) that it will fine the company $192,500 for violations of the department's nuclear safety requirements. The Preliminary Notice of Violation (PNOV) issued today cites a number of deficiencies that led to a series of low-level plutonium uptakes by workers at a WTS mobile facility (MOVER) stationed at the Lawrence Livermore National Laboratory (LLNL) in Livermore, Calif. The violations reflected WTS' limited understanding of the design and operational limitations of the MOVER facility, a portable waste processing facility designed to be

154

Solution Speciation of Plutonium and Americium at an Australian Legacy Radioactive Waste Disposal Site  

Science Journals Connector (OSTI)

During the 1960s, radioactive waste containing small amounts of plutonium (Pu) and americium (Am) was disposed in shallow trenches at the Little Forest Burial Ground (LFBG), located near the southern suburbs of Sydney, Australia. ... It should also be taken into account that, at some sites, such as the Maxey Flats disposal site,(19) codisposed organic contaminants have been implicated in actinide mobilization. ...

Atsushi Ikeda-Ohno; Jennifer J. Harrison; Sangeeth Thiruvoth; Kerry Wilsher; Henri K. Y. Wong; Mathew P. Johansen; T. David Waite; Timothy E. Payne

2014-08-15T23:59:59.000Z

155

DOE/EIS-0026-SA-4: Supplement Analysis for Use of the 10-160B Transportation Cask for RH-TRU Waste Shipments to WIPP (12/17/02)  

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

1-04 15,22 FROM,L AND M TECH 1-04 15,22 FROM,L AND M TECH ID,5052347038 PAGE 3/15 [TX/RX NO 6044] 141003 08/31/2004 TOE 15:22 PAGE 4/15 IC,5052347038 AUG-31-04 15,22 FROM,L AND M TECH PAGE 1 of 9 Supplement Analysis for USE OF THE IO-160B TRANSPORTATION CASK FOR RH-TRUWASTE SHIPMENTS TO WIPP 1.0 INTRODUCTION The U.S. Department of Energy (DOE) is propo~ing to use the CNS lO-160B, Type B Shipping Cask (referred to in this document simply as the lO-160B) to transport remote handled (RH) transuranic (TRU) wastes to the Waste Isolation Pilot Plant (WIPP). DOE originally examined the impacts ofWlPP operations in the Waste Isolation Pilot Plant Disposal Phase Final Supplemental Environmental Impact Statement, DOE/EIS-OO26-S-2, (SEIS~II). This Supplement Analysis (SA) discusses environmental impacts associated with

156

TRU drum corrosion task team report  

SciTech Connect (OSTI)

During routine inspections in March 1996, transuranic (TRU) waste drums stored at the Radioactive Waste Management Complex (RWMC) were found with pinholes and leaking fluid. These drums were overpacked, and further inspection discovered over 200 drums with similar corrosion. A task team was assigned to investigate the problem with four specific objectives: to identify any other drums in RWMC TRU storage with pinhole corrosion; to evaluate the adequacy of the RWMC inspection process; to determine the precise mechanism(s) generating the pinhole drum corrosion; and to assess the implications of this event for WIPP certifiability of waste drums. The task team investigations analyzed the source of the pinholes to be Hcl-induced localized pitting corrosion. Hcl formation is directly related to the polychlorinated hydrocarbon volatile organic compounds (VOCs) in the waste. Most of the drums showing pinhole corrosion are from Content Code-003 (CC-003) because they contain the highest amounts of polychlorinated VOCs as determined by headspace gas analysis. CC-001 drums represent the only other content code with a significant number of pinhole corrosion drums because their headspace gas VOC content, although significantly less than CC-003, is far greater than that of the other content codes. The exact mechanisms of Hcl formation could not be determined, but radiolytic and reductive dechlorination and direct reduction of halocarbons were analyzed as the likely operable reactions. The team considered the entire range of feasible options, ranked and prioritized the alternatives, and recommended the optimal solution that maximizes protection of worker and public safety while minimizing impacts on RWMC and TRU program operations.

Kooda, K.E.; Lavery, C.A.; Zeek, D.P.

1996-05-01T23:59:59.000Z

157

WASTE MANAGEMENT AT SRS - MAKING IT HAPPEN  

SciTech Connect (OSTI)

The past five years have witnessed a remarkable transition in the pace and scope of waste management activities at SRS. At the start of the new M&O contract in 1996, little was being done with the waste generated at the site apart from storing it in readiness for future treatment and disposal. Large volumes of legacy waste, particularly TRU and Low Level Waste, had accumulated over many years of operation of the site's nuclear facilities, and the backlog was increasing. WSRC proposed the use of the talents of the ''best in class'' partners for the new contract which, together with a more commercial approach, was expected to deliver more results without a concomitant increase in cost. This paper charts the successes in the Solid Waste arena and analyzes the basis for success.

Heenan, T. F.; Kelly, S.

2002-02-25T23:59:59.000Z

158

TRU TeamWorks  

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

to Senior Advisor for EM David Huizenga on Feb. 25 at the 2013 Waste Management (WM) Conference, conducted by WM Symposia in Phoenix, Ariz. Huizenga and Franco participated...

159

Acceptable Knowledge Summary Report for Mixed TRU Waste Streams: SR-W026-221F-HET-A through D  

SciTech Connect (OSTI)

This document, along with referenced supporting documents provides a defensible and auditable record of acceptable knowledge for the heterogeneous debris mixed transuranic waste streams generated in the FB-Line after January 25, 1990 and before March 20, 1997.

Lunsford, G.F.

2001-10-02T23:59:59.000Z

160

Contact-Handled and Remote-Handled Transuranic Waste Packaging  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Provides specific instructions for packaging and/or repackaging contact-handled transuranic (CH-TRU) and remote-handled transuranic (RH-TRU) waste in a manner consistent with DOE O 435.1, Radioactive Waste Management, DOE M 435.1-1 Chg 1, Radioactive Waste Management Manual, CH-TRU and RH-TRU waste transportation requirements, and Waste Isolation Pilot Plant (WIPP) programmatic requirements. Does not cancel other directives.

2011-08-09T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

Nevada Test Site Perspective on Characterization and Loading of Legacy Transuranic Drums Utilizing the Central Characterization Project  

SciTech Connect (OSTI)

The Nevada Test Site (NTS) has successfully completed a multi-year effort to characterize and ship 1860 legacy transuranic (TRU) waste drums for disposal at the Waste Isolation Pilot Plant (WIPP), a permanent TRU disposal site. This has been a cooperative effort among the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), the U.S. Department of Energy, Carlsbad Field Office (DOE/CBFO), the NTS Management and Operations (M&O) contractor Bechtel Nevada (BN), and various contractors under the Central Characterization Project (CCP) umbrella. The success is due primarily to the diligence, perseverance, and hard work of each of the contractors, the DOE/CBFO, and NNSA/NSO, along with the support of the U.S. Department of Energy, Headquarters (DOE/HQ). This paper presents, from an NTS perspective, the challenges and successes of utilizing the CCP for obtaining a certified characterization program, sharing responsibilities for characterization, data validation, and loading of TRU waste with BN to achieve disposal at WIPP from a Small Quantity Site (SQS) such as the NTS. The challenges in this effort arose from two general sources. First, the arrangement of DOE/CBFO contractors under the CCP performing work and certifying waste at the NTS within a Hazard Category 2 (HazCat 2) non-reactor nuclear facility operated by BN, presented difficult challenges. The nuclear safety authorization basis, safety liability and responsibility, conduct of operations, allocation and scheduling of resources, and other issues were particularly demanding. The program-level and field coordination needed for the closely interrelated characterization tasks was extensive and required considerable effort by all parties. The second source of challenge was the legacy waste itself. None of the waste was generated at the NTS. The waste was generated at Lawrence Livermore National Laboratory (LLNL), Lawrence Berkeley Laboratory (LBL), Lynchburg, Rocky Flats Environmental Technology Site (RFETS), and a variety of other sites over 20 years ago, making the development of Acceptable Knowledge a significant and problematic effort. In addition, the characterization requirements, and data quality objectives for shipment and WIPP disposal today, were non-existent when this waste was generated, resulting in real-time adjustments to unexpected conditions.

R.G. Lahoud; J. F. Norton; I. L. Siddoway; L. W. Griswold

2006-01-01T23:59:59.000Z

162

Preliminary Notice of Violation, Washington TRU Solutions, LLC - EA-2004-08  

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

TRU Solutions, LLC - TRU Solutions, LLC - EA-2004-08 Preliminary Notice of Violation, Washington TRU Solutions, LLC - EA-2004-08 August 30, 2004 Preliminary Notice of Violation issued to Washington TRU Solutions, LLC, related to the Transportainer Procurement and Fabrication Deficiencies at the Waste Isolation Pilot Plant Department of Energy's Office of Price-Anderson Enforcement (OE) initiated an investigation of the issues with a full review of relevant documentation. In addition, discussions that involved Department of Energy Carlsbad Field Office (DOE-CBFO) and Washington TRU Solutions, LLC (WTS) personnel took place in Carlsbad on May 11-12, 2004. Our findings were provided to you in an Investigation Summary Report dated June 25, 2004. An Enforcement Conference was held with you and members of your staff on July

163

Waste Isolation Pilot Plant, National Transuranic Program Have Banner Year  

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

Plant, National Transuranic Program Have Plant, National Transuranic Program Have Banner Year in 2013 Waste Isolation Pilot Plant, National Transuranic Program Have Banner Year in 2013 December 24, 2013 - 12:00pm Addthis Since WIPP became operational in March 1999, it has surpassed receiving 11,000 shipments, which traveled over 14 million safe loaded miles over the nation’s highways through WIPP’s transportation program — equal to about 29 trips around the moon. WIPP has permanently disposed of more than 89,000 cubic meters of TRU waste — enough to fill more than 35 Olympic-size swimming pools. In 2013, WIPP is on course in support of the Los Alamos National Laboratory framework agreement with the State of New Mexico for complete removal of the above ground TRU waste stored at Area G by June 30, 2014. WIPP has cleaned 22 sites of legacy TRU waste.

164

Transuranic Waste Tabletop  

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

Transuranic (TRU) Waste Transuranic (TRU) Waste (Hazard Class 7 Radioactive) Moderator's Version of Tabletop Prepared for the Department of Energy Office of Transportation and Emergency Management 02B00215-07D.p65 This page intentionally left blank table of contents Transportation Emergency Preparedness Program (TEPP) planning tools planning tools planning tools planning tools T T T T Tr r r r ransur ansur ansur ansur ansuranic (TRU) W anic (TRU) W anic (TRU) W anic (TRU) W anic (TRU) Waste aste aste aste aste (Hazar (Hazar (Hazar (Hazar (Hazard Class 7 Radio d Class 7 Radio d Class 7 Radio d Class 7 Radio d Class 7 Radioactiv activ activ activ active) e) e) e) e) Moder Moder Moder Moder Moderat at at at ator' or' or' or' or's V s V s V s V s Version of T ersion of T ersion of T ersion of T ersion of Tablet ablet ablet ablet abletop

165

TRU TeamWorks  

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

8, 2012 8, 2012 WIPP Quick Facts (As of 9-26-12) 10,849 Shipments received since opening (10,252 CH and 597 RH) 83,693 Cubic meters of waste disposed (82,394 CH and 299 RH) 162,472 Containers disposed in the underground (161,882 CH and 590 RH) Photo above right: CBFO Deputy Manager Ed Ziemianski presents a WIPP team with the Green Zia Program Silver Level Award from the New Mexico Environment Department on Aug. 15, 2012 in recognition of environmental initiatives. Shown right of Ziemianski is Farok Sharif, WTS President and General Manager. New WIPP Management and Operating Contractor to start October 1 Nuclear Waste Partnership LLC (NWP) will start work as the WIPP Management and Operating Contractor on Monday, October 1. WIPP receives Green Zia Award The Waste Isolation Pilot Plant (WIPP), the U.S. Department of Energy (DOE)

166

Waste Isolation Pilot Plant | Department of Energy  

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

Waste Isolation Pilot Plant Waste Isolation Pilot Plant Waste Isolation Pilot Plant Waste Isolation Pilot Plant | June 2007 Salt Disposal Investigations Waste Isolation Pilot Plant | June 2007 Salt Disposal Investigations The mission of the Waste Isolation Pilot Plant site is to provide permanent, underground disposal of TRU and TRU-mixed wastes (wastes that also have hazardous chemical components). TRU waste consists of clothing, tools, and debris left from the research and production of nuclear weapons. TRU waste is contaminated with small amounts of plutonium and other TRU radioactive elements. Over the next 35 years, WIPP is expected to receive approximately 175,000 cubic meters of waste from various DOE sites. Enforcement September 8, 2006 Enforcement Letter, Washington TRU Solutions - September 8, 2006

167

Workers at Hanford Site Achieve Recovery Act Legacy Cleanup Goals Ahead of Schedule  

Broader source: Energy.gov [DOE]

The Hanford Site recently surpassed American Recovery and Reinvestment Act goals to accelerate the cleanup of legacy waste and fuels.

168

GEANT4 Simulation of a Scintillating-Fibre Tracker for the Cosmic-ray Muon Tomography of Legacy Nuclear Waste Containers  

E-Print Network [OSTI]

Cosmic-ray muons are highly penetrative charged particles that are observed at sea level with a flux of approximately one per square centimetre per minute. They interact with matter primarily through Coulomb scattering, which is exploited in the field of muon tomography to image shielded objects in a wide range of applications. In this paper, simulation studies are presented that assess the feasibility of a scintillating-fibre tracker system for use in the identification and characterisation of nuclear materials stored within industrial legacy waste containers. A system consisting of a pair of tracking modules above and a pair below the volume to be assayed is simulated within the GEANT4 framework using a range of potential fibre pitches and module separations. Each module comprises two orthogonal planes of fibres that allow the reconstruction of the initial and Coulomb-scattered muon trajectories. A likelihood-based image reconstruction algorithm has been developed that allows the container content to be det...

Clarkson, Anthony; Hoek, Matthias; Ireland, David G; Johnstone, Russell; Kaiser, Ralf; Keri, Tibor; Lumsden, Scott; Mahon, David F; McKinnon, Bryan; Murray, Morgan; Nutbeam-Tuffs, Sian; Shearer, Craig; Staines, Cassie; Yang, Guangliang; Zimmerman, Colin

2013-01-01T23:59:59.000Z

169

The Design and Performance of a Scintillating-Fibre Tracker for the Cosmic-ray Muon Tomography of Legacy Nuclear Waste Containers  

E-Print Network [OSTI]

Tomographic imaging techniques using the Coulomb scattering of cosmic-ray muons are increasingly being exploited for the non-destructive assay of shielded containers in a wide range of applications. One such application is the characterisation of legacy nuclear waste materials stored within industrial containers. The design, assembly and performance of a prototype muon tomography system developed for this purpose are detailed in this work. This muon tracker comprises four detection modules, each containing orthogonal layers of Saint-Gobain BCF-10 2mm-pitch plastic scintillating fibres. Identification of the two struck fibres per module allows the reconstruction of the incoming and Coulomb-scattered muon trajectories. These allow the container content, with respect to the atomic number Z of the scattering material, to be determined through reconstruction of the scattering location and magnitude. On each detection layer, the light emitted by the fibre is detected by a single Hamamatsu H8500 MAPMT with two fibre...

Clarkson, Anthony; Hoek, Matthias; Ireland, David G; Johnstone, Russell; Kaiser, Ralf; Keri, Tibor; Lumsden, Scott; Mahon, David F; McKinnon, Bryan; Murray, Morgan; Nutbeam-Tuffs, Sian; Shearer, Craig; Staines, Cassie; Yang, Guangliang; Zimmerman, Colin

2013-01-01T23:59:59.000Z

170

Unresolved issues for the disposal of remote-handled transuranic waste in the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The purpose of the Waste Isolation Pilot Plant (WIPP) is to dispose of 176,000 cubic meters of transuranic (TRU) waste generated by the defense activities of the US Government. The envisioned inventory contains approximately 6 million cubic feet of contact-handled transuranic (CH TRU) waste and 250,000 cubic feet of remote handled transuranic (RH TRU) waste. CH TRU emits less than 0.2 rem/hr at the container surface. Of the 250,000 cubic feet of RH TRU waste, 5% by volume can emit up to 1,000 rem/hr at the container surface. The remainder of RH TRU waste must emit less than 100 rem/hr. These are major unresolved problems with the intended disposal of RH TRU waste in the WIPP. (1) The WIPP design requires the canisters of RH TRU waste to be emplaced in the walls (ribs) of each repository room. Each room will then be filled with drums of CH TRU waste. However, the RH TRU waste will not be available for shipment and disposal until after several rooms have already been filled with drums of CH TRU waste. RH TRU disposal capacity will be loss for each room that is first filled with CH TRU waste. (2) Complete RH TRU waste characterization data will not be available for performance assessment because the facilities needed for waste handling, waste treatment, waste packaging, and waste characterization do not yet exist. (3) The DOE does not have a transportation cask for RH TRU waste certified by the US Nuclear Regulatory Commission (NRC). These issues are discussed along with possible solutions and consequences from these solutions. 46 refs.

Silva, M.K.; Neill, R.H.

1994-09-01T23:59:59.000Z

171

TERRORISM'S LEGACY  

Science Journals Connector (OSTI)

TERRORISM'S LEGACY ... MORE THAN FOUR YEARS AFTER terrorists destroyed the World Trade Center (WTC), lower Manhattan residents like Craig Hall still don't know whether their homes harbor toxic dust from the twin towers' collapse. ... Many, though probably not all, of the homes in the area were carefully cleaned after the Sept. 11, 2001, terrorist attacks. ...

CHERYL HOGUE

2006-01-09T23:59:59.000Z

172

TRU TeamWorks  

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

4, 2013 4, 2013 WIPP Quick Facts (As of 1-23-13) 11,112 Shipments received since opening (10,483 CH and 629 RH) 85,498 Cubic meters of waste disposed (85,185 CH and 313 RH) 165,172 Containers disposed in the underground (164,545 CH and 627 RH) WIPP employee honored by American Red Cross WIPP's Bob Walker was among a handful of honorees at the American Red Cross' Southeastern New Mexico Real Heroes Breakfast & Awards held January 10 in Hobbs. The organization awarded Real Heroes in various categories. Walker received the Military Hero award, recognizing the time and financial assistance he gives to help "his military brothers and sisters" who have served or are currently serving. A veteran himself, taking care of returning soldiers and their families is something Walker is known for. He

173

Tank Waste Committee - Transcribed Flipcharts  

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

TRU waste retrieval Provided the State of New Mexico concurs Determine not HLW (process knowledge) As long as meets all applicable requirements "evaluation" not...

174

Solid waste retrieval. Phase 1, Operational basis  

SciTech Connect (OSTI)

This Document describes the operational requirements, procedures, and options for execution of the retrieval of the waste containers placed in buried storage in Burial Ground 218W-4C, Trench 04 as TRU waste or suspect TRU waste under the activity levels defining this waste in effect at the time of placement. Trench 04 in Burial Ground 218W-4C is totally dedicated to storage of retrievable TRU waste containers or retrievable suspect TRU waste containers and has not been used for any other purpose.

Johnson, D.M.

1994-09-30T23:59:59.000Z

175

DOE Exercises 5 Year Option on Washington TRU Solutions Contract to Operate  

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

Exercises 5 Year Option on Washington TRU Solutions Contract to Exercises 5 Year Option on Washington TRU Solutions Contract to Operate WIPP DOE Exercises 5 Year Option on Washington TRU Solutions Contract to Operate WIPP January 18, 2005 - 9:55am Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) announced today that it has decided to exercise the five year option in the Washington TRU Solutions LLC ("WTS") contract to continue managing and operating the Department's Waste Isolation Pilot Plant (WIPP), located in New Mexico. The option DOE exercised is a part of the WIPP contract that was competitively procured in 2000. The WTS contract will now run through September 30, 2010 with an estimated value over the five year timeframe of approximately $704 million. "We are very pleased to take this step," said Kyle McSlarrow, Deputy

176

TRU Solutions Announces $20,500 in Scholarships For Eddy and Lea County Students  

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

Sherry Reese Sherry Reese Public Outreach (505) 234-7592 http://www.wipp.ws Waste Isolation Pilot Plant P.O. Box 2078 Carlsbad, New Mexico 88221 TRU Solutions News For Immediate Release TRU Solutions Announces $20,500 in Scholarships For Eddy and Lea County Students CARLSBAD, N.M., February 18, 2003 - Steve Warren, Washington TRU Solutions (WTS) General Manager, has announced up to $20,500 in scholarships for Eddy and Lea County students in 2003. Applications are available now from area high school and college counselors. WTS, formerly Westinghouse TRU Solutions, will award the scholarships this spring in conjunction with area high schools, the Carlsbad Foundation and several non-profit organizations. Scholarships are available in any of the following three areas of study at an accredited

177

Washington TRU Solutions Inc | Open Energy Information  

Open Energy Info (EERE)

Solutions Inc Jump to: navigation, search Name: Washington TRU Solutions, Inc. Place: Carlsbad, New Mexico Zip: 88220 Product: New Mexico-based managing and operating contractor...

178

Waste Isolation Pilot Plant Update | Department of Energy  

Office of Environmental Management (EM)

Isolation Pilot Plant Update Waste Isolation Pilot Plant Update Waste Isolation Pilot Plant Update More Documents & Publications TRUPACT-III Quick Facts "TRU" Success: SRS Recovery...

179

IPP RH-TRU Waste Study - Summary  

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

for evaluation: releases by gas generation, groundwater transport, human intrusion and heat generation. Study Findings A summary of the important findings of the Remote-Handled...

180

Waste Disposal and Recovery Act Efforts at the Oak Ridge Reservation,OAS-RA-L-12-01  

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

Waste Disposal and Recovery Act Waste Disposal and Recovery Act Efforts at the Oak Ridge Reservation INS-RA-L-12-01 December 2011 Department of Energy Washington, DC 20585 December 16, 2011 MEMORANDUM FOR THE MANAGER, OAK RIDGE OFFICE FROM: Sandra D. Bruce Assistant Inspector General for Inspections Office of Inspector General SUBJECT: INFORMATION: Inspection Report on "Waste Disposal and Recovery Act Efforts at the Oak Ridge Reservation" BACKGROUND The Department of Energy's (Department) expends billions of dollars to clean up contaminated sites and dispose of hazardous waste. The Department's Oak Ridge Office (ORO) is responsible for processing and disposing of the Transuranic (TRU) waste on the Oak Ridge Reservation (ORR), including approximately 3,500 cubic meters of legacy remote-handled (RH) and contact-

Note: This page contains sample records for the topic "legacy tru waste" 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

GEANT4 Simulation of a Scintillating-Fibre Tracker for the Cosmic-ray Muon Tomography of Legacy Nuclear Waste Containers  

E-Print Network [OSTI]

Cosmic-ray muons are highly penetrative charged particles that are observed at sea level with a flux of approximately one per square centimetre per minute. They interact with matter primarily through Coulomb scattering, which is exploited in the field of muon tomography to image shielded objects in a wide range of applications. In this paper, simulation studies are presented that assess the feasibility of a scintillating-fibre tracker system for use in the identification and characterisation of nuclear materials stored within industrial legacy waste containers. A system consisting of a pair of tracking modules above and a pair below the volume to be assayed is simulated within the GEANT4 framework using a range of potential fibre pitches and module separations. Each module comprises two orthogonal planes of fibres that allow the reconstruction of the initial and Coulomb-scattered muon trajectories. A likelihood-based image reconstruction algorithm has been developed that allows the container content to be determined with respect to the atomic number Z of the scattering material. Images reconstructed from this simulation are presented for a range of anticipated scenarios that highlight the expected image resolution and the potential of this system for the identification of high-Z materials within a shielded, concrete-filled container. First results from a constructed prototype system are presented in comparison with those from a detailed simulation. Excellent agreement between experimental data and simulation is observed showing clear discrimination between the different materials assayed throughout.

Anthony Clarkson; David J. Hamilton; Matthias Hoek; David G. Ireland; Russell Johnstone; Ralf Kaiser; Tibor Keri; Scott Lumsden; David F. Mahon; Bryan McKinnon; Morgan Murray; Sian Nutbeam-Tuffs; Craig Shearer; Cassie Staines; Guangliang Yang; Colin Zimmerman

2013-09-13T23:59:59.000Z

182

CH-TRU Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-10-15T23:59:59.000Z

183

CRAD, Radiological Controls - Oak Ridge National Laboratory TRU...  

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

Radiological Controls - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Radiological Controls - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 A...

184

CRAD, Safety Basis - Oak Ridge National Laboratory TRU ALPHA...  

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

Safety Basis - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Safety Basis - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 A section of Appendix C...

185

CRAD, Quality Assurance - Oak Ridge National Laboratory TRU ALPHA...  

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

Quality Assurance - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Quality Assurance - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 A section of...

186

CRAD, Management - Oak Ridge National Laboratory TRU ALPHA LLWT...  

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

Management - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Management - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 A section of Appendix C to...

187

Transportation Refrigeration Unit (TRU) Retrofit with HUSS Active...  

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

Transportation Refrigeration Unit (TRU) Retrofit with HUSS Active Diesel Particulate Filters Transportation Refrigeration Unit (TRU) Retrofit with HUSS Active Diesel Particulate...

188

CRAD, Conduct of Operations - Oak Ridge National Laboratory TRU...  

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

Conduct of Operations - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Conduct of Operations - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 A...

189

A Novel Fuel/Reactor Cycle to Implement the 300 Years Nuclear Waste Policy Approach - 12377  

SciTech Connect (OSTI)

A thorium-based fuel cycle system can effectively burn the currently accumulated commercial used nuclear fuel and move to a sustainable equilibrium where the actinide levels in the high level waste are low enough to yield a radiotoxicity after 300 years lower than that of the equivalent uranium ore. The second step of the Westinghouse approach to solving the waste 'problem' has been completed. The thorium fuel cycle has indeed the potential of burning the legacy TRU and achieve the waste objective proposed. Initial evaluations have been started for the third step, development and selection of appropriate reactors. Indications are that the probability of show-stoppers is rather remote. It is, therefore, believed that development of the thorium cycle and associated technologies will provide a permanent solution to the waste management. Westinghouse is open to the widest collaboration to make this a reality. (authors)

Carelli, M.D.; Franceschini, F.; Lahoda, E.J. [Westinghouse Electric Company LLC., Cranberry Township, PA (United States); Petrovic, B. [Georgia Institute of Technology, Atlanta, GA (United States)

2012-07-01T23:59:59.000Z

190

Tru-Lite | Open Energy Information  

Open Energy Info (EERE)

Tru-Lite Tru-Lite Jump to: navigation, search Logo: Tru-Lite Name Tru-Lite Address 13695 E. Davies Place Place Centennial, Colorado Zip 80112 Sector Efficiency Product Daylighting applications Website http://www.tru-lite.com/ Coordinates 39.5887688°, -104.8291724° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":39.5887688,"lon":-104.8291724,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

191

Hanford site transuranic waste certification plan  

SciTech Connect (OSTI)

As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of U.S. Department of Energy (DOE) Order 5820.2A, ''Radioactive Waste Management, and the Waste Acceptance Criteria for the Waste Isolation Pilot Plant' (DOE 1996d) (WIPP WAC). The WIPP WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WIPP WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their management of TRU waste and TRU waste shipments before transferring waste to WIPP. The Hanford Site must also ensure that its TRU waste destined for disposal at WIPP meets requirements for transport in the Transuranic Package Transporter41 (TRUPACT-11). The U.S. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-I1 requirements in the ''Safety Analysis Report for the TRUPACT-II Shipping Package'' (NRC 1997) (TRUPACT-I1 SARP).

GREAGER, T.M.

1999-05-12T23:59:59.000Z

192

Environmental assessment for transuranic waste work-off plan, Los Alamos National Laboratory. Rough draft: Final report  

SciTech Connect (OSTI)

The Los Alamos National Laboratory (LANL) generates transuranic (TRU) waste in a variety of programs related to national defense. TRU waste is a specific class of radioactive waste requiring permanent isolation. Most defense-related TRU waste will be permanently disposed of in the Waste Isolation Pilot Plant (WIPP). WIPP is a deep geologic repository located in southeastern New Mexico and is now in the testing phase of development. All waste received by Wipp must conform with established Waste Acceptance Criteria (WAC). The purpose of the proposed action is to retrieve stored TRU waste and prepare the waste for shipment to and disposal WIPP. Stored TRU waste LANL is represented by four waste forms. The facilities necessary for work-off activities are tailored to the treatment and preparation of these four waste forms. Preparation activities for newly generated TRU waste are also covered by this action.

Not Available

1990-10-26T23:59:59.000Z

193

Resource Conservation and Recovery Act, Part B Permit Application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 2, Chapter C, Appendix C1--Chapter C, Appendix C3 (beginning), Revision 3  

SciTech Connect (OSTI)

This volume contains appendices for the following: Rocky Flats Plant and Idaho National Engineering Laboratory waste process information; TRUPACT-II content codes (TRUCON); TRUPACT-II chemical list; chemical compatibility analysis for Rocky Flats Plant waste forms; chemical compatibility analysis for waste forms across all sites; TRU mixed waste characterization database; hazardous constituents of Rocky Flats Transuranic waste; summary of waste components in TRU waste sampling program at INEL; TRU waste sampling program; and waste analysis data.

Not Available

1993-03-01T23:59:59.000Z

194

COMPREHENSIVE LEGACY MANAGEMENT  

Office of Legacy Management (LM)

Comprehensive Legacy Management and Institutional Controls Plan U.S. Department of Energy Volume I-Legacy Management Plan Doc. No. S03496-8.0-Final Page 6 January 2015...

195

Remote-handled transuranic waste study  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) was developed by the US Department of Energy (DOE) as a research and development facility to demonstrate the safe disposal of transuranic (TRU) radioactive wastes generated from the Nation`s defense activities. The WIPP disposal inventory will include up to 250,000 cubic feet of TRU wastes classified as remote handled (RH). The remaining inventory will include contact-handled (CH) TRU wastes, which characteristically have less specific activity (radioactivity per unit volume) than the RH-TRU wastes. The WIPP Land Withdrawal Act (LWA), Public Law 102-579, requires a study of the effect of RH-TRU waste on long-term performance. This RH-TRU Waste Study has been conducted to satisfy the requirements defined by the LWA and is considered by the DOE to be a prudent exercise in the compliance certification process of the WIPP repository. The objectives of this study include: conducting an evaluation of the impacts of RH-TRU wastes on the performance assessment (PA) of the repository to determine the effects of Rh-TRU waste as a part of the total WIPP disposal inventory; and conducting a comparison of CH-TRU and RH-TRU wastes to assess the differences and similarities for such issues as gas generation, flammability and explosiveness, solubility, and brine and geochemical interactions. This study was conducted using the data, models, computer codes, and information generated in support of long-term compliance programs, including the WIPP PA. The study is limited in scope to post-closure repository performance and includes an analysis of the issues associated with RH-TRU wastes subsequent to emplacement of these wastes at WIPP in consideration of the current baseline design. 41 refs.

NONE

1995-10-01T23:59:59.000Z

196

Nuclear waste management. Quarterly progress report, January-March 1980  

SciTech Connect (OSTI)

Reported are: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, criteria for defining waste isolation, and spent fuel and pool component integrity. (DLC)

Platt, A.M.; Powell, J.A. (comps.)

1980-06-01T23:59:59.000Z

197

Natural and Enhanced Attenuation of Soil and Groundwater at the Monument Valley, Arizona, DOE Legacy Waste Site10281  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE), the Navajo Nation, and the University of Arizona are exploring natural and enhanced attenuation remedies for groundwater contamination at a former uranium-ore processing site near Monument Valley, Arizona. DOE removed radioactive tailings from the Monument Valley site in 1994. Nitrate and ammonium, waste products of the milling process, remain in an alluvial groundwater plume spreading from the soil source where tailings were removed. Planting and irrigating two native shrubs, fourwing saltbush and black greasewood, markedly reduced both nitrate and ammonium in the source area over an 8-year period. Total nitrogen dropped from 350 mg/kg in 2000 to less than 200 mg/kg in 2008. Most of the reduction is attributable to irrigation-enhanced microbial denitrification rather than plant uptake. However, soil moisture and percolation flux monitoring show that the plantings control the soil water balance in the source area, preventing additional leaching of nitrogen compounds. Enhanced denitrification and phytoremediation also look promising for plume remediation. Microcosm experiments, nitrogen isotopic fractionation analysis, and solute transport modeling results suggest that (1) up to 70 percent of nitrate in the plume has been lost through natural denitrification since the mill was closed in 1968, and (2) injection of ethanol may accelerate microbial denitrification in plume hot spots. A field-scale ethanol injection pilot study is underway. Landscape-scale remote sensing methods developed for the project suggest that transpiration from restored native phreatophyte populations rooted in the aquifer could limit further expansion of the plume. An evaluation of landfarm phytoremediation, the irrigation of native shrub plantings with high nitrate water pumped from the alluvial aquifer, is also underway.

Waugh, W.J. [S.M. Stoller Corporation, Grand Junction, CO; Miller, D.E. [S.M. Stoller Corporation, Grand Junction, CO; Morris, S.A. [S.M. Stoller Corporation, Grand Junction, CO; Sheader, L.R. [S.M. Stoller Corporation, Grand Junction, CO; Glenn, E.P. [University of Arizona, Tucson, AZ; Moore, D. [University of Arizona, Tucson, AZ; Carroll, K.C. [University of Arizona, Tucson, AZ; Benally, L. [Navajo Nation, Window Rock, AZ; Roanhorse, M. [Navajo Nation, Window Rock, AZ; Bush, R.P. [U.S. Department of Energy, Grand Junction, CO; none,

2010-03-07T23:59:59.000Z

198

COMPLIANCE FOR HANFORD WASTE RETRIEVAL RADIOACTIVE AIR EMISSIONS  

SciTech Connect (OSTI)

{sm_bullet} Since 1970, approximately 38,000 suspect transuranic (TRU) and TRU waste cont{approx}iners have been placed in retrievable storage on the Hanford Site in the 200Area's burial grounds. {sm_bullet} TRU waste is defined as waste containing greater than 100 nanocuries/gram of alpha emitting transuranic isotopes with half lives greater than 20 years. {sm_bullet} The United States currentl{approx}permanently disposes of TRU waste at the Waste Isolation Pilot Plant (WIPP).

FM SIMMONS

2009-06-30T23:59:59.000Z

199

Enforcement Documents - Waste Isolation Pilot Plant | Department of Energy  

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

Waste Isolation Pilot Plant Waste Isolation Pilot Plant Enforcement Documents - Waste Isolation Pilot Plant September 8, 2006 Enforcement Letter, Washington TRU Solutions - September 8, 2006 Enforcement Letter issued to Washington TRU Solutions, LLC related to Quality Assurance Deficiencies associated with the Super High-Efficiency Neutron Counter Non-Destructive Assay System Refurbishment at the Waste Isolation Pilot Plant October 28, 2004 Enforcement Letter, Diversified Metal Products, Inc - October 28, 2004 Issued to Diversified Metal Products, Inc. related to Transportainer Fabrication Deficiencies for the Waste Isolation Pilot Plant August 30, 2004 Preliminary Notice of Violation, Washington TRU Solutions, LLC - EA-2004-08 Preliminary Notice of Violation issued to Washington TRU Solutions, LLC,

200

Record of Decision for the Solid Waste Program, Hanford Site, Richland, WA: Storage and Treatment of Low-Level Waste and Mixed Low-Level Waste; Disposal of Low-Level Waste and Mixed Low-Level Waste, and Storage, Processing, and Certification of Transuran  

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

9 9 Federal Register / Vol. 69, No. 125 / Wednesday, June 30, 2004 / Notices mixed low-level waste, and TRU waste shipments using Year 2000 census data and an updated version of the RADTRAN computer code to calculate potential risks associated with shipping. This analysis included the route- specific impacts of transporting the West Jefferson TRU waste to Hanford and subsequent shipment of this waste to WIPP. Due to the additional TRU waste generated and identified at West Jefferson subsequent to DOE's September 6, 2002, decision, DOE's currently estimated total number of 18 shipments (3 completed RH-TRU waste shipments, 14 remaining RH-TRU waste shipments, and 1 remaining CH-TRU waste shipment) exceeds DOE's prior estimate of total shipments by 3. However, the currently estimated

Note: This page contains sample records for the topic "legacy tru waste" 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

Oak Ridge National Laboratory Transuranic Waste Certification Program  

SciTech Connect (OSTI)

The US Department of Energy (DOE) has requested that all DOE facilities handling defense transuranic (TRU) waste develop and implement a program whereby all TRU waste will be contained, stored, and shipped to the Waste Isolation Pilot Plant (WIPP) in accordance with the requirements set forth in the DOE certification documents WIPP-DOE-069, 114, 120, 137, 157, and 158. The program described in this report describes how Oak Ridge National Laboratory (ORNL) intends to comply with these requirements and the techniques and procedures used to ensure that ORNL TRU wastes are certifiable for shipment to WIPP. This document describes the program for certification of newly generated (NG) contact-handled transuranic (CH-TRU) waste. Previsions have been made for addenda, which will extend the coverage of this document to include certification of stored CH-TRU and NG and stored remote-handled transuranic (RH-TRU) waste, as necessary. 24 refs., 11 figs., 4 tabs.

Smith, J.H.; Bates, L.D.; Box, W.D.; Aaron, W.S.; Setaro, J.A.

1988-08-01T23:59:59.000Z

202

WIPP (Waste Isolation Pilot Plant) test phase plan: Performance assessment  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) is responsible for managing the disposition of transuranic (TRU) wastes resulting from nuclear weapons production activities of the United States. These wastes are currently stored nationwide at several of the DOE's waste generating/storage sites. The goal is to eliminate interim waste storage and achieve environmentally and institutionally acceptable permanent disposal of these TRU wastes. The Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico is being considered as a disposal facility for these TRU wastes. This document describes the first of the following two major programs planned for the Test Phase of WIPP: Performance Assessment -- determination of the long-term performance of the WIPP disposal system in accordance with the requirements of the EPA Standard; and Operations Demonstration -- evaluation of the safety and effectiveness of the DOE TRU waste management system's ability to emplace design throughput quantities of TRU waste in the WIPP underground facility. 120 refs., 19 figs., 8 tabs.

Not Available

1990-04-01T23:59:59.000Z

203

Nuclear waste management. Quarterly progress report, October-December 1979  

SciTech Connect (OSTI)

Progress and activities are reported on the following: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization programs, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, monitoring of unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions technology, spent fuel and fuel pool integrity program, and engineered barriers. (DLC)

Platt, A.M.; Powell, J.A. (comps.)

1980-04-01T23:59:59.000Z

204

Hanford Tank Waste Information Enclosure 1 Hanford Tank Waste Information  

E-Print Network [OSTI]

Hanford Tank Waste Information Enclosure 1 1 Hanford Tank Waste Information 1.0 Summary This information demonstrates the wastes in the twelve Hanford Site tanks meet the definition of transuranic (TRU. The wastes in these twelve (12) tanks are not high-level waste (HLW), and contain more than 100 nanocuries

205

CRAD, Training - Oak Ridge National Laboratory TRU ALPHA LLWT...  

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

Training - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Training - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 A section of Appendix C to DOE G...

206

Annual Transuranic Waste Inventory Report - 2013  

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

of TRU waste streams. Five waste streams have been moved from Potential to WIPP-bound status to be in alignment with the CBFO screening memorandum (Patterson 2010) provided in...

207

Technical Evaluations of Proposed Remote-Handled Transuranic Waste Characterization Requirements at WIPP  

SciTech Connect (OSTI)

Characterization, packaging, transport, handling and disposal of remotely handled transuranic (RH TRU) waste at WIPP will be different than similar operations with contact handled transuranic (CH TRU) waste. This paper presents results of technical evaluations associated with the planned disposal of remotely handled transuranic waste at the Waste Isolation Pilot Plant (WIPP).

Anastas, G.; Channell, J. K.

2002-02-26T23:59:59.000Z

208

LANL reaches waste shipment milestone  

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

LANL reaches waste shipment milestone LANL reaches waste shipment milestone LANL reaches waste shipment milestone The Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total. May 31, 2011 A shipment of transuranic waste on its way to the WIPP repository A shipment of transuranic waste on its way to the WIPP repository. Contact Fred deSousa Communicatons Office (505) 665-3430 Email LOS ALAMOS, New Mexico, May 31, 2011 - Los Alamos National Laboratory has reached an important milestone in its campaign to ship transuranic (TRU) waste from Cold War-era nuclear operations to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. This month, the Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total.

209

Transuranic contaminated waste container characterization and data base. Revision I  

SciTech Connect (OSTI)

The Nuclear Regulatory Commission (NRC) is developing regulations governing the management, handling and disposal of transuranium (TRU) radioisotope contaminated wastes as part of the NRC's overall waste management program. In the development of such regulations, numerous subtasks have been identified which require completion before meaningful regulations can be proposed, their impact evaluated and the regulations implemented. This report was prepared to assist in the development of the technical data base necessary to support rule-making actions dealing with TRU-contaminated wastes. An earlier report presented the waste sources, characteristics and inventory of both Department of Energy (DOE) generated and commercially generated TRU waste. In this report a wide variety of waste sources as well as a large TRU inventory were identified. The purpose of this report is to identify the different packaging systems used and proposed for TRU waste and to document their characteristics. This document then serves as part of the data base necessary to complete preparation and initiate implementation of TRU waste container and packaging standards and criteria suitable for inclusion in the present TRU waste management program. It is the purpose of this report to serve as a working document which will be used as appropriate in the TRU Waste Management Program. This report, and those following, will be compatible not only in format, but also in reference material and direction.

Kniazewycz, B.G.

1980-05-01T23:59:59.000Z

210

WIPP News Releases  

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

War Legacy Waste Cleanup Milestone September 23 DOE Completes TRU Waste Cleanup at Bettis September 15 DOE Hosts German Energy Official, Signs MOU to Share WIPP Information...

211

Documentation of TRU biological transport model (BIOTRAN)  

SciTech Connect (OSTI)

Inclusive of Appendices, this document describes the purpose, rationale, construction, and operation of a biological transport model (BIOTRAN). This model is used to predict the flow of transuranic elements (TRU) through specified plant and animal environments using biomass as a vector. The appendices are: (A) Flows of moisture, biomass, and TRU; (B) Intermediate variables affecting flows; (C) Mnemonic equivalents (code) for variables; (D) Variable library (code); (E) BIOTRAN code (Fortran); (F) Plants simulated; (G) BIOTRAN code documentation; (H) Operating instructions for BIOTRAN code. The main text is presented with a specific format which uses a minimum of space, yet is adequate for tracking most relationships from their first appearance to their formulation in the code. Because relationships are treated individually in this manner, and rely heavily on Appendix material for understanding, it is advised that the reader familiarize himself with these materials before proceeding with the main text.

Gallegos, A.F.; Garcia, B.J.; Sutton, C.M.

1980-01-01T23:59:59.000Z

212

A Comprehensive Solution for Managing TRU and LLW From Generation to Final Disposition - 13205  

SciTech Connect (OSTI)

A LANL multi-disciplinary team faced the challenge of building and delivering a waste information system capable of managing radioactive, hazardous, and industrial waste from cradle to grave. The result is the Waste Compliance and Tracking System (WCATS) a flexible, adaptive system that has allowed LANL to consolidate its legacy applications into one system, and leverage the advantages of managing all waste types within a single scalable enterprise application. Key functionality required for robust waste operations, include: waste characterization, waste identification, transportation, inventory management, waste processing, and disposal. In order to maintain data quality, field operations such as waste identification, surveillance checklists, wall-to-wall inventory assessments, waste transfers, shipment pickup and receipt, and simple consolidation operations are captured by the operator or technician using mobile computers. Work flow is managed via end-user defined work paths, to ensure that unit operations are performed in the correct order. Regulatory compliance reports and algorithms are provided to support typical U.S. EPA, DOT, NRC, and DOE requirements, including the EPA hazardous waste manifest, NRC LLW manifest, DOE nuclear material at risk, RCRA TSDF inventory rules, and so forth. The WCATS application has allowed LANL to migrate and consolidate its disparate legacy applications. The design and implementation is generalized so that facility owners can customize the user interface, setup facilities and unit operations (i.e., treatment, storage, disposal, characterization, and administrative), define inventory compliance rules, and establish custom work flow requirements. (authors)

Tozer, Justin C.; Sanchez, Edwina G.; Dorries, Alison M. [Los Alamos National Laboratory, Los Alamos, NM 87544 (United States)] [Los Alamos National Laboratory, Los Alamos, NM 87544 (United States)

2013-07-01T23:59:59.000Z

213

D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE  

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

10 CFR Ch. X (1-1-12 Edition) Pt. 1022 D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE Siting, construction or expansion, and op- eration of disposal facilities for transuranic (TRU) waste and TRU mixed waste (TRU waste also containing hazardous waste as designated in 40 CFR part 261). D12 INCINERATORS Siting, construction, and operation of in- cinerators, other than research and develop- ment incinerators or incinerators for non- hazardous solid waste (as designated in 40 CFR 261.4(b)). PART 1022-COMPLIANCE WITH FLOODPLAIN AND WETLAND EN- VIRONMENTAL REVIEW REQUIRE- MENTS Subpart A-General Sec. 1022.1 Background. 1022.2 Purpose and scope. 1022.3 Policy. 1022.4 Definitions. 1022.5 Applicability. 1022.6 Public inquiries. Subpart B-Procedures for Floodplain and

214

CRAD, Radiological Controls - Oak Ridge National Laboratory TRU ALPHA LLWT  

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

TRU TRU ALPHA LLWT Project CRAD, Radiological Controls - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 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 a November 2003 assessment of the Radiation Protection Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory TRU ALPHA LLWT Project. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Radiological Controls - Oak Ridge National Laboratory TRU ALPHA LLWT Project More Documents & Publications CRAD, Quality Assurance - Oak Ridge National Laboratory TRU ALPHA LLWT

215

CRAD, Training - Oak Ridge National Laboratory TRU ALPHA LLWT Project |  

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

TRU ALPHA LLWT TRU ALPHA LLWT Project CRAD, Training - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 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 a November 2003 assessment of the Training Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory TRU ALPHA LLWT Project. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Training - Oak Ridge National Laboratory TRU ALPHA LLWT Project More Documents & Publications CRAD, Quality Assurance - Oak Ridge National Laboratory TRU ALPHA LLWT Project

216

Preliminary Notice of Violation, Washington TRU Solutions, LLC...  

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

2005 Issued to Washington TRU Solutions, LLC, related to Radiological Uptakes at the Mobile Visual Examination and Repackaging Facility at Lawrence Livermore National Laboratory...

217

Process Knowledge Summary Report for Materials and Fuels Complex Contact-Handled Transuranic Debris Waste  

SciTech Connect (OSTI)

This Process Knowledge Summary Report summarizes the information collected to satisfy the transportation and waste acceptance requirements for the transfer of transuranic (TRU) waste between the Materials and Fuels Complex (MFC) and the Advanced Mixed Waste Treatment Project (AMWTP). The information collected includes documentation that addresses the requirements for AMWTP and the applicable portion of their Resource Conservation and Recovery Act permits for receipt and treatment of TRU debris waste in AMWTP. This report has been prepared for contact-handled TRU debris waste generated by the Idaho National Laboratory at MFC. The TRU debris waste will be shipped to AMWTP for purposes of supercompaction. This Process Knowledge Summary Report includes information regarding, but not limited to, the generation process, the physical form, radiological characteristics, and chemical contaminants of the TRU debris waste, prohibited items, and packaging configuration. This report, along with the referenced supporting documents, will create a defensible and auditable record for waste originating from MFC.

R. P. Grant; P. J. Crane; S. Butler; M. A. Henry

2010-02-01T23:59:59.000Z

218

Strontium and cesium release mechanisms during unsaturated flow through waste-weathered Hanford sediments  

E-Print Network [OSTI]

Plutonium from Simulated Hanford Tank-Waste Sludges. Separ.Containing Tank Waste at Hanford. Separ. Sci. Technol. 2005,T. B. , Sr/TRU Removal from Hanford High Level Waste. Separ.

Chang, H.

2013-01-01T23:59:59.000Z

219

Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) ...  

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

Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) A transuranic (TRU) waste shipment makes its way to the...

220

Waste Isolation Pilot Plant - Enforcement Documents  

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

Enforcement Documents Enforcement Documents Waste Isolation Pilot Plant Enforcement Letter issued to Washington TRU Solutions, LLC related to Quality Assurance Deficiencies associated with the Super High-Efficiency Neutron Counter Non-Destructive Assay System Refurbishment at the Waste Isolation Pilot Plant, September 8, 2006 Preliminary Notice of Violation issued to Washington TRU Solutions, LLC, related to Radiological Uptakes at the Mobile Visual Examination and Repackaging Facility at Lawrence Livermore National Laboratory, December 22, 2005 (EA-2005-08) - Washington TRU Solutions, LLC - Press Release, December 22, 2005 Enforcement Letter issued to Diversified Metal Products, Inc. related to Transportainer Fabrication Deficiencies for the Waste Isolation Pilot Plant, October 28, 2004

Note: This page contains sample records for the topic "legacy tru waste" 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

Waste acceptance criteria for the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), DOE/WIPP-069, was initially developed by a U.S. Department of Energy (DOE) Steering Committee to provide performance requirements to ensure public health and safety as well as the safe handling of transuranic (TRU) waste at the WIPP. This revision updates the criteria and requirements of previous revisions and deletes those which were applicable only to the test phase. The criteria and requirements in this document must be met by participating DOE TRU Waste Generator/Storage Sites (Sites) prior to shipping contact-handled (CH) and remote-handled (RH) TRU waste forms to the WIPP. The WIPP Project will comply with applicable federal and state regulations and requirements, including those in Titles 10, 40, and 49 of the Code of Federal Regulations (CFR). The WAC, DOE/WIPP-069, serves as the primary directive for assuring the safe handling, transportation, and disposal of TRU wastes in the WIPP and for the certification of these wastes. The WAC identifies strict requirements that must be met by participating Sites before these TRU wastes may be shipped for disposal in the WIPP facility. These criteria and requirements will be reviewed and revised as appropriate, based on new technical or regulatory requirements. The WAC is a controlled document. Revised/changed pages will be supplied to all holders of controlled copies.

NONE

1996-04-01T23:59:59.000Z

222

Graphics-based site information management at Hanford TRU burial grounds  

SciTech Connect (OSTI)

The objective of the project described in this paper is to demonstrate the use of integrated computer graphics and database techniques in managing nuclear waste facilities. The graphics-based site information management system (SIMS) combines a three- dimensional graphic model of the facility with databases which describe the facility's components and waste inventory. The SIMS can create graphic visualization of any site data. The SIMS described here is being used by Westinghouse Hanford Company (WHC) as part of its transuranic (TRU) waste retrieval program at the Hanford Reservation. It is being used to manage an inventory of over 38,000 containers, to validate records, and to help visualize conceptual designs of waste retrieval operations.

Rod, S.R. (Pacific Northwest Lab., Washington, DC (United States))

1992-04-01T23:59:59.000Z

223

Graphics-based site information management at Hanford TRU burial grounds  

SciTech Connect (OSTI)

The objective of the project described in this paper is to demonstrate the use of integrated computer graphics and database techniques in managing nuclear waste facilities. The graphics-based site information management system (SIMS) combines a three- dimensional graphic model of the facility with databases which describe the facility`s components and waste inventory. The SIMS can create graphic visualization of any site data. The SIMS described here is being used by Westinghouse Hanford Company (WHC) as part of its transuranic (TRU) waste retrieval program at the Hanford Reservation. It is being used to manage an inventory of over 38,000 containers, to validate records, and to help visualize conceptual designs of waste retrieval operations.

Rod, S.R. [Pacific Northwest Lab., Washington, DC (United States)

1992-04-01T23:59:59.000Z

224

Legacy: Order (2015-CE-14025)  

Broader source: Energy.gov [DOE]

DOE ordered The Legacy Companies to pay a $8,000 civil penalty after finding Legacy had failed to certify that refrigerator Maxx-Ice brand basic model MCR3U complies with the applicable energy conservation standards.

225

Interim Storage of RH-TRU 72B Canisters at the DOE Oak Ridge Reservation  

SciTech Connect (OSTI)

This paper describes an evaluation performed by the Department of Energy (DOE) Oak Ridge Operations (ORO) office for potential interim storage of remote-handled (RH) transuranic (TRU) 72B waste canisters at the Oak Ridge National Laboratory (ORNL). The evaluation included the conceptual design of a devoted canister storage facility and an assessment of the existing RHTRU waste storage facilities for storage of canisters. The concept for the devoted facility used modular concrete silos located on an above-grade storage pad. The assessment of the existing facilities considered the potential methods, facility modifications, and conceptual equipment that might be used for storage of 400 millisievert per hour (mSv/hr) canisters. The results of the evaluation indicated that the initial investment into a devoted facility was relatively high as compared to the certainty that significant storage capacity was necessary prior to the Waste Isolation Pilot Plant (WIPP) accepting RH-TRU waste for disposal. As an alternative, the use of individual concrete overpacks provided an incremental method that could be used with the existing storage facilities and outside storage pads. For the concrete overpack concepts considered, the cylindrical design stored in a vertical orientation was determined to be the most effective.

Forrester, T. W.; Hunt, R. A.; Riner, G. L.

2002-02-26T23:59:59.000Z

226

Preparation of the First Shipment of Transuranic Waste by the Los Alamos National Laboratory: A Rest Stop on the Road to WIPP  

SciTech Connect (OSTI)

The Los Alamos National Laboratory (LANL) achieved a national milestone on the road to shipping transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) when it received certification authority on September 12, 1997. Since that time, LANL has been characterizing a non-mixed TRU waste stream and preparing shipments of this TRU waste for disposal in the WIPP. The paper describes the TRU waste identified as waste stream TA-55-43 Lot No. 01 from LANL Technical Area-55 and the process used to determine that it does not contain hazardous waste regulated by the Resource Conservation Recovery Act (RCRA) or the New Mexico Hazardous Waste Act (HWA). The non-mixed determination is based on the acceptable knowledge (AK) characterization process, which clearly shows that the waste does not exhibit any RCRA characteristics nor meet any RCRA listing descriptions. LANL has certified TRU waste from waste stream TA-55-43 Lot No. 01 and is prepared to certify additional quantities of TRU waste horn other non-mixed TRU waste streams. Assembly and preparation of AK on the processes that generated TRU waste is recognized as a necessary part of the process for having waste ready for shipment to the WIPP.

Allen, G.; Barr, A.; Betts, S.E.; Farr, J.; Foxx, J.; Gavett, M.A.; Janecky, D.R.; Kosiewicz, S.T.; Liebman, C.P.; Montoya, A.; Poths, H.; Rogers, P.S.Z.; Taggart, D.P.; Triay, I.R.; Vigil, G.I.; Vigil, J.J.; Wander, S.G.; Yeamans, D.

1999-02-01T23:59:59.000Z

227

CRAD, Quality Assurance - Oak Ridge National Laboratory TRU ALPHA LLWT  

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

Quality Assurance - Oak Ridge National Laboratory TRU ALPHA Quality Assurance - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Quality Assurance - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 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 a November 2003 assessment of the Quality Assurance Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory TRU ALPHA LLWT Project. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Quality Assurance - Oak Ridge National Laboratory TRU ALPHA LLWT Project More Documents & Publications

228

An Alternative to Performing Remote-Handled Transuranic Waste Container Headspace Gas Sampling and Analysis  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) is operating under a Resource Conservation and Recovery Act (RCRA) Hazardous Waste Facility Permit (HWFP) for contact-handled (CH) transuranic (TRU) waste. The HWFP contains limitations on allowable emissions from waste disposed in the underground. This environmental performance standard imposed on the WIPP consists of limiting volatile organic compound (VOC) emissions from emplaced waste to ensure protection of human health and the environment. The standard is currently met by tracking individual waste container headspace gas concentrations, which are determined by headspace gas sampling and analysis of CH TRU waste containers. The WIPP is seeking a HWFP modification to allow the disposal of remote-handled (RH) TRU waste. Because RH TRU waste is limited to approximately 5% of the waste volume and is emplaced in the disposal room walls, it is possible to bound the potential RH TRU waste contribution to VOC emissions using conservative upper bounds. These conservative upper bounds were developed as an alternative to RH TRU waste canister headspace gas sampling and analysis. The methodology used to perform the calculations used to evaluate VOC emissions from emplaced RH TRU waste canisters applied the same equations as those used to evaluate VOC emissions in the original HWFP application.

Spangler, L. R.; Djordjevic, S. M.; Kehrman, R. F.; Most, W. A.

2002-02-26T23:59:59.000Z

229

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |  

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

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE April 1, 2010 - 12:00pm Addthis An operator uses robotic manipulators to process RH TRU. An operator uses robotic manipulators to process RH TRU. Idaho - The Waste Disposition Project Team at the Department of Energy's Idaho Site has continued to keep its commitment to remove remote handled (RH) transuranic (TRU) waste out of Idaho, protecting the Snake River Plain Aquifer and keeping the Office of Environmental Management's commitment to environmental clean up. In 2007, the first shipment of RH TRU waste left the gates of the Idaho Site, headed to the Waste Isolation Pilot Plant (WIPP) for disposal. In the three years since, devoted individuals on the CH2M-WG, Idaho's (CWI)

230

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |  

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

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE April 1, 2010 - 12:00pm Addthis An operator uses robotic manipulators to process RH TRU. An operator uses robotic manipulators to process RH TRU. Idaho - The Waste Disposition Project Team at the Department of Energy's Idaho Site has continued to keep its commitment to remove remote handled (RH) transuranic (TRU) waste out of Idaho, protecting the Snake River Plain Aquifer and keeping the Office of Environmental Management's commitment to environmental clean up. In 2007, the first shipment of RH TRU waste left the gates of the Idaho Site, headed to the Waste Isolation Pilot Plant (WIPP) for disposal. In the three years since, devoted individuals on the CH2M-WG, Idaho's (CWI)

231

Tru-ly Clean - What Does It Mean?  

SciTech Connect (OSTI)

The evolution and genesis of the definition of transuranic waste (known as TRU) and its application to the cleanup criteria applied to soils contaminated with transuranics, specifically plutonium, has been a matter of discussion at contaminated sites in the United States and elsewhere. Cleanup decisions and the processes that led up to those decisions have varied at several plutonium contaminated sites within the United States and without the pacific region. The sites with radionuclide soil action levels include Bikini and Enewetak Atolls, Republic of the Marshall Islands; Johnston Atoll, Hawaii; the Hanford Site in Washington State; the Nevada Test Site; the Rocky Flats Environmental Technology Site in Colorado; the Chariot Site in north Alaska; and the Maralinga Site in Australia. The soil-action level developed for Rocky Flats by the U.S. Department of Energy, U.S. Environmental Protection Agency, and the Colorado Department of Public Health and Environment for plutonium is one of the higher soil-action levels approved by regulatory agencies that is considered protective for future use of land at a cleanup site. The Republic of the Marshall Islands has adopted a relatively conservative cleanup standard to accommodate the subsistence lifestyle of the islanders, while the Rocky Flats Environmental Technology Site has been transferred to the U.S. Department of the Interior to be used as a fish and wildlife refuge, a land use that resulted in a less conservative plutonium soil cleanup level. (authors)

Hopkins, A. [Fluor Hanford, Inc, Richland, WA (United States)

2008-07-01T23:59:59.000Z

232

Office of Legacy Management Significant Environmental Aspects  

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

9/2013 9/2013 Office of Legacy Management Significant Environmental Aspects The mission of the U.S. Department of Energy (DOE) Office of Legacy Management (LM) is to safely manage DOE's postclosure responsibilities and ensure the future protection of human health and the environment. We have evaluated all of our activities for their potential impact on the environment, and we have identified those aspects that could have a significant impact if they were not controlled. This information is used to develop programs to prevent or mitigate potential impacts and to establish prioritized goals, objectives, and targets for continually improving performance. Our significant environmental aspects fall into four categories: * Waste generation and minimization

233

Microsoft Word - Final_DOE_Cleanup_of_Legacy_TRU_at_SNL_Release...  

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

Radiation Development, LLC - New York * Argonne National Laboratory - Illinois * Bettis Atomic Power Laboratory - Pennsylvania * Sandia National Laboratories - New Mexico...

234

SEPARATION AND EXTRACTION OF PLUTONIUM IN MIXED WASTE  

SciTech Connect (OSTI)

The Sonatol process uses ultrasonic agitation in fluorinated surfactant solutions to remove radioactive particles from surfaces. Filtering the suspended particles allows the solutions to be reused indefinitely. The current work applies the Sonatol process to the decontamination of heterogeneous legacy Pu-238 waste that exhibits excessive hydrogen gas generation, which prevents transportation of the waste to the Waste Isolation Pilot Plant. Bartlett Services, Inc. (BSI) designed and fabricated a prototype decontamination system within a replica of a Savannah River Site glovebox. In Phase I, BSI conducted cold testing with surrogate waste material to verify that the equipment, operating procedures, and test protocols would support testing with Pu-238 in Phase II. The surrogate waste material is representative of known constituents of legacy job control waste. Two sub-micron sized Pu-238 simulants were added to the surrogate waste so that decontamination could be tested. The first simulant was an Osram Sylvania Phosphor 2284C powder that fluoresces under ultraviolet light. The use of the fluorescent simulant allows rapid, inexpensive system startup testing because residuals can be assayed using a digital camera. The results of digital pixel analysis (DPA) are available immediately and do not require use of licensed material. The second simulant, which was used for integrated cold testing, was a cerium oxide powder that was activated in a research reactor neutron flux and assayed by photon spectroscopy. The surrogate transuranic (TRU) waste material was contaminated with Pu-238 simulants and loaded into the cleaning chamber, where the surrogates were ultrasonically agitated and rinsed. The decontaminated materials were then assayed for surface contamination by DPA to establish optimum operating parameters and provide process quality control. Selected samples were sent to the Massachusetts Institute of Technology for neutron activation analysis (NAA). NAA testing resulted in weighted average decontamination factors (DFs) in the range of 125 to 157 for the surrogate waste mixtures. The weighted DFs for the organic portion of the surrogate waste mixtures ranged from 66 to 140. The NAA DF for inorganic material was 370. Other than the removal of particulate contamination, the processed samples were unchanged by decontamination. Most NAA samples were irradiated after decontamination. However, several samples were irradiated in the reactor core prior to decontamination in order to investigate the possible interference of radiation induced imbedding of particles in organic materials. The radiation dose was in excess of 110 Mrad. The NAA DF for samples irradiated before decontamination was six.

Arthur E. Desrosiers, ScD, CHP; Robert Kaiser, ScD; Jason Antkowiak; Justin Desrosiers; Josh Jondro; Adam Kulczyk

2002-12-13T23:59:59.000Z

235

Solid Waste Processing Center Primary Opening Cells Systems, Equipment and Tools  

SciTech Connect (OSTI)

This document addresses the remote systems and design integration aspects of the development of the Solid Waste Processing Center (SWPC), a facility to remotely open, sort, size reduce, and repackage mixed low-level waste (MLLW) and transuranic (TRU)/TRU mixed waste that is either contact-handled (CH) waste in large containers or remote-handled (RH) waste in various-sized packages.

Bailey, Sharon A.; Baker, Carl P.; Mullen, O Dennis; Valdez, Patrick LJ

2006-04-17T23:59:59.000Z

236

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

237

Microsoft Word - Argonne Release Final  

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

(ANL), near Chicago, Illinois. In September, all legacy TRU waste was removed from the Bettis Atomic Power Laboratory (BAPL), near Pittsburgh, Pennsylvania. Maintained by the DOE,...

238

Supplement Analysis for Disposal of Polychlorinated Biphenyl-Commingled Transuranic Waste at the Waste Isolation Pilot Plant (DOE/EIS-0026-SA02) (6/23/04)  

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

Disposal of Disposal of Polychlorinated Biphenyl-Commingled Transuranic Waste at the Waste Isolation Pilot Plant (DOE/EIS-0026-SA02) 1.0 Purpose and Need for Action Transuranic (TRU) waste is waste that contains alpha particle-emitting radionuclides with atomic numbers greater than uranium (92) and half-lives greater than 20 years, in concentrations greater than 100 nanocuries per gram of waste. Some TRU wastes are mixed with polychlorinated biphenyls (PCBs) (referred to as PCB-commingled TRU waste). PCBs exist in DOE's TRU waste as mixtures of synthetic organic chemicals with physical properties ranging from oily liquids to waxy solids. Exposure to PCBs can result in adverse health effects. For example, PCBs in blood or in fatty tissue as a result of inhalation, ingestion, or dermal absorption may cause reproductive effects,

239

Phase 2, Solid waste retrieval strategy  

SciTech Connect (OSTI)

Solid TRU retrieval, Phase 1 is scheduled to commence operation in 1998 at 218W-4C-T01 and complete recovery of the waste containers in 2001. Phase 2 Retrieval will recover the remaining buried TRU waste to be retrieved and provide the preliminary characterization by non-destructive means to allow interim storage until processing for disposal. This document reports on researching the characterization documents to determine the types of wastes to be retrieved and where located, waste configurations, conditions, and required methods for retrieval. Also included are discussions of wastes encompassed by Phase 2 for which there are valid reasons to not retrieve.

Johnson, D.M.

1994-09-29T23:59:59.000Z

240

Waste Isolation Pilot Plant Status and Plans - 2012 - 12049  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP), a deep geologic repository for safe disposal of long-lived transuranic radioactive waste related to the nation's defense, is completing its 12. year of operations. WIPP's mission includes coordination of all Department of Energy (DOE) sites to prepare, package and characterize transuranic (TRU) waste for final shipment and emplacement in WIPP. Five of the 10 disposal panels planned have been filled and sealed from ventilation. Additional small quantity sites have been de-inventoried by consolidating their waste through the certified characterization line at the Idaho National Laboratory (INL). New emplacement methods for RH waste in shielded containers are being considered for disposal by WIPP's regulatory authorities. A new large Type B shipping package, was added to the WIPP transportation fleet, and facility modifications to the WIPP waste unloading and emplacement processes for large containers were completed in 2011. Shipments from the Savannah River site in these new large rectangular packages began in August 2011. Licensing efforts are proceeding for a new criticality control over-pack container that will allow almost twice the fissile content to be shipped than previously. This will reduce the number and cost of shipments of Special Nuclear Material (SNM) declared as waste. Modifications to WIPP regulatory requirements for the disposal footprint and disposal unit closure systems are in progress. These, and other developments, make for exciting times at WIPP. This paper provides an up-to-date look at the many aspects of America's only deep geologic long-lived radioactive waste repository, which is completing its 12. year of operations. A record year of safe and compliant shipments to WIPP tops the list of accomplishments in 2011. Four more small quantity sites were de-inventoried by consolidating their waste through the certified characterization line at INL in 2011. A new Type B shipping package, the TRUPACT-III has been added to the transportation fleet, and large waste boxes are being shipped from SRS without the need for repackaging. New emplacement methods for remote-handled waste in shielded containers are undergoing regulatory review. WIPP plans to license a new criticality control payload container that will allow almost twice the fissile content to be shipped than previously, thereby reducing the number and cost of shipments of SNM declared as waste. Other regulatory modifications planned in 2012 include approval of a design change that would replace the disposal concept for panels 9 and 10 from using the common access drifts (the 'mains') with a new footprint south of panels 4 and 5. DOE also plans to change the panel closure design set forth in its certification by EPA and the HWFP by the NMED. The panel closure design change will be a rule making under EPA's procedures and a class 3 permit modification request under NMED procedures. Plans for achieving 90% of legacy TRU waste retrieval and emplacement in WIPP by 2015 have been developed. Key to the success of this so-called 90/15 plan is adequate funding, both for WIPP operations, as well as for TRU retrieval programs at the generator sites. (authors)

Nelson, Roger A.; Ziemianski, Edward J. [U.S. Department of Energy, Carlsbad, NM 88220 (United States)

2012-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

TRU-DOENV--787Rev3.indd  

National Nuclear Security Administration (NNSA)

of Energy, National Nuclear Security Administration Nevada Site Offi ce at the Nevada Test Site. Transuranic waste contains man-made radioactive elements heavier than uranium,...

242

Organic and TRU screening for 200 West Area SST interim stabilization activities  

SciTech Connect (OSTI)

This SD documents the preliminary work performed during the effort to better understand the magnitude and nature of transuranic (TRU) and/or complexed wastes contained in the 200 West Area single shell tank (SSTs). This preliminary work identified which of the SST interstitial liquids in question had adequate characterizations and performed a limited compatibility assessment based upon those characterizations. This allowed a determination of the TRU activity in the liquid and the waste type which describes the liquid. The waste type, complexed or non-complexed, was determined by a calculated total organic carbon (TOC) concentration when the waste containing the measured TOC value is evaporated to the composition of double-shell slurry feed (DSSF). DSSF was defined as the concentration at which aluminum bearing solids begin to precipitate (the sodium aluminate boundary), or when the OH concentration reached 8.0 as determined by the PREDICT evaporator simulation program. Two sets of results are presented. The first set identified only those tanks with adequate characterization data, and listed the remaining tanks as unknowns. These results have the higher level of confidence. The second result set used engineering judgement to estimate applicable characterization data where none existed. This allowed a tentative classification to be made for all but one of the tanks considered unknowns from the first result set. These results may have utility if decisions must be made in the absence additional, improved waste characterizations. This information was used in developing the follow-on laboratory testing to more precisely defined the magnitude and specifics of the compatibility problems.

Estey, S.D.

1996-01-01T23:59:59.000Z

243

Legacy Initiatives - EERE Commercialization Office  

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

Legacy Initiatives Small Business and Clean Energy Alliance (CEA) Partnership The U.S. Department of Energy (DOE) Small Business and Clean Energy Alliance (CEA) Partnership...

244

Lab sets new record for waste volume removed  

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

Lab Sets New Record for Waste Volume Removed Lab Sets New Record for Waste Volume Removed Community Connections: Our link to Northern New Mexico Communities Latest Issue:Dec. 2013 - Jan. 2014 All Issues » submit Lab sets new record for waste volume removed The Transuranic Waste Program has met its commitment to ship 800 cubic meters of TRU waste to the Waste Isolation Pilot Plant during fiscal year 2012. November 1, 2012 dummy image Read our archives Contacts Editor Linda Anderman Email Community Programs Office Kurt Steinhaus Email A lot of people worked together to make this happen, including our partners at the State of New Mexico and WIPP, as well as NNSA, the Los Alamos Site Office, and the Laboratory. The LANL Transuranic (TRU) Waste Program has met its commitment to ship 800 cubic meters of TRU waste to the Waste Isolation Pilot Plant (WIPP) during

245

Recommendation 215: Recommendation on Remaining Legacy Materials...  

Office of Environmental Management (EM)

5: Recommendation on Remaining Legacy Materials on the Oak Ridge Reservation Recommendation 215: Recommendation on Remaining Legacy Materials on the Oak Ridge Reservation The board...

246

MRI Beginnings - a Legacy | GE Global Research  

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

Legacy From Nobel Ideas to Industrial Success - Bill Edelstein's Legacy Scott Smith 2014.06.13 Edelsteinwith-MRmachine Nuclear magnetic resonance (NMR) was discovered in...

247

Waste acceptance criteria for the Waste Isolation Pilot Plant. Revision 4  

SciTech Connect (OSTI)

This Revision 4 of the Waste Acceptance Criteria (WAC), WIPP-DOE-069, identifies and consolidates existing criteria and requirements which regulate the safe handling and preparation of Transuranic (TRU) waste packages for transportation to and emplacement in the Waste Isolation Pilot Plant (WIPP). This consolidation does not invalidate any existing certification of TRU waste to the WIPP Operations and Safety Criteria (Revision 3 of WIPP-DOE--069) and/or Transportation: Waste Package Requirements (TRUPACT-II Safety Analysis Report for Packaging [SARP]). Those documents being consolidated, including Revision 3 of the WAC, currently support the Test Phase.

Not Available

1991-12-01T23:59:59.000Z

248

Nondestructive radioassay for waste management: an assessment  

SciTech Connect (OSTI)

Nondestructive Assay (NDA) for Transuranic Waste Management is used to mean determining the amount of transuranic (TRU) isotopes in crates, drums, boxes, cans, or other containers without having to open the container. It also means determining the amount of TRU in soil, bore holes, and other environmental testing areas without having to go through extensive laboratory wet chemistry analyses. it refers to radioassay techniques used to check for contamination on objects after decontamination and to determine amounts of TRU in waste processing streams without taking samples to a laboratory. Gednerally, NDA instrumentation in this context refers to all use of radioassay which does not involve taking samples and using wet chemistry techniques. NDA instruments have been used for waste assay at some sites for over 10 years and other sites are just beginning to consider assay of wastes. The instrumentation used at several sites is discussed in this report. Almost all these instruments in use today were developed for special nuclear materials safeguards purposes and assay TRU waste down to the 500 nCi/g range. The need for instruments to assay alpha particle emitters at 10 nCi/g or less has risen from the wish to distinguish between Low Level Waste (LLW) and TRU Waste at the defined interface of 10 nCi/g. Wastes have historically been handled as TRU wastes if they were just suspected to be transuranically contaminated but their exact status was unknown. Economic and political considerations make this practice undesirable since it is easier and less costly to handle LLW. This prompted waste generators to want better instrumentation and led the Transuranic Waste Management Program to develop and test instrumentation capable of assaying many types of waste at the 10 nCi/g level. These instruments are discussed.

Lehmkuhl, G.D.

1981-06-01T23:59:59.000Z

249

Waste Form Development for the Solidification of PDCF/MOX Liquid Waste Streams  

SciTech Connect (OSTI)

At the Savannah River Site, part of the Department of Energy's nuclear materials complex located in South Carolina, cementation has been selected as the solidification method for high-alpha and low-activity waste streams generated in the planned plutonium disposition facilities. A Waste Solidification Building (WSB) that will be used to treat and solidify three radioactive liquid waste streams generated by the Pit Disassembly and Conversion Facility) and the Mixed Oxide Fuel Fabrication Facility is in the preliminary design stage. The WSB is expected to treat a transuranic (TRU) waste stream composed primarily of americium and two low-level waste (LLW) streams. The acidic wastes will be concentrated in the WSB evaporator and neutralized in a cement head tank prior to solidification. A series of TRU mixes were prepared to produce waste forms exhibiting a range of processing and cured properties. The LLW mixes were prepared using the premix from the preferred TRU waste form. All of the waste forms tested passed the Toxicity Characteristic Leaching Procedure. After processing in the WSB, current plans are to dispose of the solidified TRU waste at the Waste Isolation Pilot Plant in New Mexico and the solidified LLW waste at an approved low-level waste disposal facility.

COZZI, ALEX

2004-02-18T23:59:59.000Z

250

Environmental waste disposal contracts awarded  

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

Environmental contracts awarded locally Environmental contracts awarded locally Environmental waste disposal contracts awarded locally Three small businesses with offices in Northern New Mexico awarded nuclear waste clean-up contracts. April 3, 2012 Worker moves drums of transuranic (TRU) waste at a staging area A worker stages drums of transuranic waste at Los Alamos National Laboratory's Technical Area 54. the Lap ships such drums to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) in Southern New Mexico. The Lab annually averages about 120 shipments of TRU waste to WIPP. Contact Small Business Office (505) 667-4419 Email "They will be valuable partners in the Lab's ability to dispose of the waste safely and efficiently." Small businesses selected for environmental work at LANL

251

Construction Begins on New Waste Processing Facility | Department of Energy  

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

Construction Begins on New Waste Processing Facility Construction Begins on New Waste Processing Facility Construction Begins on New Waste Processing Facility February 9, 2012 - 12:00pm Addthis Workers construct a new facility that will help Los Alamos National Laboratory accelerate the shipment of transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad for permanent disposal. Workers construct a new facility that will help Los Alamos National Laboratory accelerate the shipment of transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad for permanent disposal. Construction has begun on a new facility that will help Los Alamos National Laboratory accelerate the shipment of transuranic (TRU) waste stored in large boxes at Technical Area 54, Area G. Construction has begun on a new facility that will help Los Alamos National

252

Idaho's Advanced Mixed Waste Treatment Project Details 2013  

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

Idaho's Advanced Mixed Waste Treatment Project Details 2013 Idaho's Advanced Mixed Waste Treatment Project Details 2013 Accomplishments Idaho's Advanced Mixed Waste Treatment Project Details 2013 Accomplishments December 24, 2013 - 12:00pm Addthis IDAHO FALLS, Idaho - EM and its contractor, Idaho Treatment Group (ITG), safely and compliantly met all of their production and shipping targets in the Advanced Mixed Waste Treatment Project (AMWTP) at the Idaho site in 2013. AMWTP's purpose is to safely process and dispose of transuranic (TRU) and mixed low-level waste (MLLW). The defense-related TRU waste is sent to the Waste Isolation Pilot Plant in New Mexico, and the MLLW is sent to other federal and commercial disposal sites. AMWTP is the largest shipper of contact-handled TRU waste to WIPP. In 2013, AMWTP sent 2,444.69 cubic

253

Los Alamos National Laboratory Transuranic Waste Program Exceeds Planned  

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

Los Alamos National Laboratory Transuranic Waste Program Exceeds Los Alamos National Laboratory Transuranic Waste Program Exceeds Planned Shipping Goal Los Alamos National Laboratory Transuranic Waste Program Exceeds Planned Shipping Goal May 1, 2012 - 12:00pm Addthis LOS ALAMOS, N.M. - Los Alamos National Laboratory's (LANL) Transuranic (TRU) Waste Program is looking at another record-setting month for the amount of TRU waste leaving Material Disposal Area G, headed to the Waste Isolation Pilot Plant (WIPP) for permanent disposal. LANL exceeded its planned removal of TRU waste from Area G in April, shipping more than 91 cubic meters of waste to WIPP - more than the Lab has ever shipped there in a single month. The Lab is headed for an even more successful May, with 99 cubic meters shipped to WIPP as of May 22. "Our shipping performance reflects the acceleration that began last

254

Idaho's Advanced Mixed Waste Treatment Project Details 2013  

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

Idaho's Advanced Mixed Waste Treatment Project Details 2013 Idaho's Advanced Mixed Waste Treatment Project Details 2013 Accomplishments Idaho's Advanced Mixed Waste Treatment Project Details 2013 Accomplishments December 24, 2013 - 12:00pm Addthis IDAHO FALLS, Idaho - EM and its contractor, Idaho Treatment Group (ITG), safely and compliantly met all of their production and shipping targets in the Advanced Mixed Waste Treatment Project (AMWTP) at the Idaho site in 2013. AMWTP's purpose is to safely process and dispose of transuranic (TRU) and mixed low-level waste (MLLW). The defense-related TRU waste is sent to the Waste Isolation Pilot Plant in New Mexico, and the MLLW is sent to other federal and commercial disposal sites. AMWTP is the largest shipper of contact-handled TRU waste to WIPP. In 2013, AMWTP sent 2,444.69 cubic

255

Lab sets new record for waste shipments  

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

New record for waste shipments New record for waste shipments Lab sets new record for waste shipments LANL completing its 132nd transuranic (TRU) waste shipment of fiscal year 2010 to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. August 20, 2010 LANL's shipment of transuranic waste leaves Los Alamos. LANL's shipment of transuranic waste leaves Los Alamos. Contact Fred deSousa Communications Office (505) 500-5672 Email "Removing this waste from Los Alamos is crucial to our plans for overall cleanup." Each shipment moves LANL closer to cleanup LOS ALAMOS, New Mexico, August 20, 2010-Los Alamos National Laboratory set a new LANL record on Friday by completing its 132nd transuranic (TRU) waste shipment of fiscal year 2010 to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The shipment eclipsed last year's

256

LEGACY MANAGEMENT REQUIRES INFORMATION  

SciTech Connect (OSTI)

''Legacy Management Requires Information'' describes the goal(s) of the US Department of Energy's Office of Legacy Management (LM) relative to maintaining critical records and the way those goals are being addressed at Hanford. The paper discusses the current practices for document control, as well as the use of modern databases for both storing and accessing the data to support cleanup decisions. In addition to the information goals of LM, the Hanford Federal Facility Agreement and Consent Order, known as the ''Tri-Party Agreement'' (TPA) is one of the main drivers in documentation and data management. The TPA, which specifies discrete milestones for cleaning up the Hanford Site, is a legally binding agreement among the US Department of Energy (DOE), the Washington State Department of Ecology (Ecology), and the US Environmental Protection Agency (EPA). The TPA requires that DOE provide the lead regulatory agency with the results of analytical laboratory and non-laboratory tests/readings to help guide them in making decisions. The Agreement also calls for each signatory to preserve--for at least ten years after the Agreement has ended--all of the records in its or its contractors, possession related to sampling, analysis, investigations, and monitoring conducted. The tools used at Hanford to meet TPA requirements are also the tools that can satisfy the needs of LM.

CONNELL, C.W.; HILDEBRAND, R.D.

2006-12-14T23:59:59.000Z

257

Oak Ridge National Laboratory contact-handled Transuranic Waste Certification Program plan  

SciTech Connect (OSTI)

The Oak Ridge National Laboratory (ORNL) is required by Department of Energy (DOE) Order 5820.2A to package its transuranic (TRU) waste to comply with waste acceptance criteria (WAC) for the Waste Isolation Pilot Plant (WIPP). TRU wastes are defined in DOE Order 5820.A as those radioactive wastes that are contaminated with alpha-emitting transuranium radionuclides having half-lives greater than 20 years and concentrations greater than 100 nCi/g at the time of the assay. In addition, ORNL handles U{sup 233}, Cm{sup 244}, and Cf{sup 252} as TRU waste radionuclides. The ORNL Transuranic Waste Certification Program was established to ensure that all TRU waste at ORNL is packaged to meet the required transportation and storage criteria for shipping to and storage at the WIPP. The objective of this document is to describe the methods that will be used at ORNL to package contact handled-transuranic (CH-TRU) waste to meet the criteria set forth in the WIPP certification requirements documents. This document addresses newly generated (NG) CH-TRU waste. Stored CH-TRU will be repackaged. This document is organized to provide a brief overview of waste generation operations at ORNL, along with details on data management for CH-TRU waste. The methods used to implement this plan are discussed briefly along with the responsibilities and authorities of applicable organizations. Techniques used for waste data collection, records control, and data archiving are defined. Procedures for the procurement and handling of waste containers are also described along with related quality control methods. 11 refs., 3 figs.

Smith, J.H.; Smith, M.A.

1990-08-01T23:59:59.000Z

258

EIS-0305: Treating Transuranic (TRU)/Alpha Low-Level at the Oak...  

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

05: Treating Transuranic (TRU)Alpha Low-Level at the Oak Ridge National Laboratory, Oak Ridge, Tennessee EIS-0305: Treating Transuranic (TRU)Alpha Low-Level at the Oak Ridge...

259

EIS-0305: Treating Transuranic (TRU)/Alpha Low-Level at the Oak...  

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

305: Treating Transuranic (TRU)Alpha Low-Level at the Oak Ridge National Laboratory, Oak Ridge, Tennessee EIS-0305: Treating Transuranic (TRU)Alpha Low-Level at the Oak Ridge...

260

Safer Transportation and Disposal of Remote Handled Transuranic Waste - 12033  

SciTech Connect (OSTI)

Since disposal of remote handled (RH) transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP) began in 2007, the Department of Energy (DOE) has had difficulty meeting the plans and schedule for disposing this waste. PECOS Management Services, Inc. (PECOS) assessed the feasibility of proposed alternate RH-TRU mixed waste containerisation concepts that would enhance the transportation rate of RH-TRU waste to WIPP and increase the utilization of available WIPP space capacity for RH-TRU waste disposal by either replacing or augmenting current and proposed disposal methods. In addition engineering and operational analyses were conducted that addressed concerns regarding criticality, heat release, and worker exposure to radiation. The results of the analyses showed that the concept, development, and use of a concrete pipe based design for an RH-TRU waste shipping and disposal container could be potentially advantageous for disposing a substantial quantity of RHTRU waste at WIPP in the same manner as contact-handled RH waste. Additionally, this new disposal method would eliminate the hazard associated with repackaging this waste in other containers without the requirement for NRC approval for a new shipping container. (authors)

Rojas, Vicente; Timm, Christopher M.; Fox, Jerry V. [PECOS Management Services, Inc., Albuquerque, NM (United States)

2012-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

Office of Legacy Management  

Office of Legacy Management (LM)

Energy Energy Office of Legacy Management JUL 1 0 2008 Alonso Ramirez, Scientific Director EI Verde Research Station Institute for Tropical Ecosystem Studies University of Puerto Rico P.o. Box 21910 San Juan, PR 00931 .Subject: Regulatory Status of Study Area 4 Dear Dr. Ramirez: I want to thank you and your staff, especially John Bithom for taking time to escort us to Study Area 4 several weeks ago. While planning the visit to the EI Verde Research Station, we mentioned that the radioactive materials license for the tree in Study Area 4 was terminated. Termination was based on radiological conditions meeting criteria for protectiveness. At that time, we sent by email the application to amend the University of Puerto Rico radioactive materials license, which we

262

LANL Reaches Waste Shipment Milestone: Waste from Cold War-era weapons  

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

Reaches Waste Shipment Milestone: Waste from Cold War-era Reaches Waste Shipment Milestone: Waste from Cold War-era weapons production being shipped to WIPP LANL Reaches Waste Shipment Milestone: Waste from Cold War-era weapons production being shipped to WIPP May 31, 2011 - 12:00pm Addthis Media Contact Fred deSousa 505-665-3430 fdesousa@lanl.gov LOS ALAMOS, New Mexico - Los Alamos National Laboratory has reached an important milestone in its campaign to ship transuranic (TRU) waste from Cold War-era nuclear operations to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. This month, the Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total. The waste, sent from LANL to WIPP in more than 750 shipments since 1999,

263

January 23, 2007: WIPP receives first shipment of waste | Department of  

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

January 23, 2007: WIPP receives first shipment of waste January 23, 2007: WIPP receives first shipment of waste January 23, 2007: WIPP receives first shipment of waste January 23, 2007: WIPP receives first shipment of waste January 23, 2007 The Department's Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, receives (pdf) its first shipment of remote-handled (RH) transuranic (TRU) radioactive waste. The waste, which consisted of three 30-gallon drums of radioactive debris waste and originated at DOE's Idaho National Laboratory, was transported inside a shielded RH-72B shipping cask, providing the same low radiation levels as the contact-handled (CH) TRU wastes that have been shipped to WIPP since 1999. "This first shipment of RH-TRU waste is particularly significant to DOE," notes DOE Assistant

264

Robust Solution to Difficult Hydrogen Issues When Shipping Transuranic Waste to the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) has been open, receiving, and disposing of transuranic (TRU) waste since March 26, 1999. The majority of the waste has a path forward for shipment to and disposal at the WIPP, but there are about two percent (2%) or approximately 3,020 cubic meters (m{sup 3}) of the volume of TRU waste (high wattage TRU waste) that is not shippable because of gas generation limits set by the U.S. Nuclear Regulatory Commission (NRC). This waste includes plutonium-238 waste, solidified organic waste, and other high plutonium-239 wastes. Flammable gases are potentially generated during transport of TRU waste by the radiolysis of hydrogenous materials and therefore, the concentration at the end of the shipping period must be predicted. Two options are currently available to TRU waste sites for solving this problem: (1) gas generation testing on each drum, and (2) waste form modification by repackaging and/or treatment. Repackaging some of the high wattage waste may require up to 20:1 drum increase to meet the gas generation limits of less than five percent (5%) hydrogen in the inner most layer of confinement (the layer closest to the waste). (This is the limit set by the NRC.) These options increase waste handling and transportation risks and there are high costs and potential worker exposure associated with repackaging this high-wattage TRU waste. The U.S. Department of Energy (DOE)'s Carlsbad Field Office (CBFO) is pursuing a twofold approach to develop a shipping path for these wastes. They are: regulatory change and technology development. For the regulatory change, a more detailed knowledge of the high wattage waste (e.g., void volumes, gas generation potential of specific chemical constituents) may allow refinement of the current assumptions in the gas generation model for Safety Analysis Reports for Packaging for Contact-Handled (CH) TRU waste. For technology development, one of the options being pursued is the use of a robust container, the ARROW-PAK{trademark} System. (1) The ARROW-PAK{trademark} is a macroencapsulation treatment technology, developed by Boh Environmental, LLC, New Orleans, Louisiana. This technology has been designed to withstand any unexpected hydrogen deflagration (i.e. no consequence) and other benefits such as criticality control.

Countiss, S. S.; Basabilvazo, G. T.; Moody, D. C. III; Lott, S. A.; Pickerell, M.; Baca, T.; CH2M Hill; Tujague, S.; Svetlik, H.; Hannah, T.

2003-02-27T23:59:59.000Z

265

CRAD, Management- Oak Ridge National Laboratory TRU ALPHA LLWT Project  

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 a November 2003 assessment of the Management Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory TRU ALPHA LLWT Project.

266

Advanced Safeguards Approaches for New TRU Fuel Fabrication Facilities  

SciTech Connect (OSTI)

This second report in a series of three reviews possible safeguards approaches for the new transuranic (TRU) fuel fabrication processes to be deployed at AFCF specifically, the ceramic TRU (MOX) fuel fabrication line and the metallic (pyroprocessing) line. The most common TRU fuel has been fuel composed of mixed plutonium and uranium dioxide, referred to as MOX. However, under the Advanced Fuel Cycle projects custom-made fuels with higher contents of neptunium, americium, and curium may also be produced to evaluate if these minor actinides can be effectively burned and transmuted through irradiation in the ABR. A third and final report in this series will evaluate and review the advanced safeguards approach options for the ABR. In reviewing and developing the advanced safeguards approach for the new TRU fuel fabrication processes envisioned for AFCF, the existing international (IAEA) safeguards approach at the Plutonium Fuel Production Facility (PFPF) and the conceptual approach planned for the new J-MOX facility in Japan have been considered as a starting point of reference. The pyro-metallurgical reprocessing and fuel fabrication process at EBR-II near Idaho Falls also provided insight for safeguarding the additional metallic pyroprocessing fuel fabrication line planned for AFCF.

Durst, Philip C.; Ehinger, Michael H.; Boyer, Brian; Therios, Ike; Bean, Robert; Dougan, A.; Tolk, K.

2007-12-15T23:59:59.000Z

267

TruLifesaver American Heart Association Basic Life Support Course  

E-Print Network [OSTI]

TruLifesaver American Heart Association Basic Life Support Course The Truman Institute P: 660 concepts of high-quality CPR · The American Heart Association Chain of Survival · Differences between Cost includes all instruction, materials and two year certification with the American Heart Association

Gering, Jon C.

268

Waste Isolation Pilot Plant Update  

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

Update Update J. R. Stroble Director, National TRU Program U.S. Department of Energy Carlsbad Field Office National Transportation Stakeholder Forum May 11, 2011 Denver, Colorado 2 2 Shipments received at WIPP to date: 9,493 Contact-handled: 9,019 Remote-handled: 474 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 44 84 366 947 818 1,002 98 8 997 1,144 730 1,032 Total Shipments by Calendar Year (Including intersite shipments) 1,194 CH TRU waste shipments only CH and RH TRU waste shipments 472 to date Accomplishments -2010 Shipments Shipments Received - (as of May 2, 2011) Site Shipments Loaded Miles Argonne National Laboratory

269

Recommended strategy for the disposal of remote-handled transuranic waste  

SciTech Connect (OSTI)

The current baseline plan for RH TRU (remote-handled transuranic) waste disposal is to package the waste in special canisters for emplacement in the walls of the waste disposal rooms at the Waste Isolation Pilot Plant (WIPP). The RH waste must be emplaced before the disposal rooms are filled by contact-handled waste. Issues which must be resolved for this plan to be successful include: (1) construction of RH waste preparation and packaging facilities at large-quantity sites; (2) finding methods to get small-quantity site RH waste packaged and certified for disposal; (3) developing transportation systems and characterization facilities for RH TRU waste; (4) meeting lag storage needs; and (5) gaining public acceptance for the RH TRU waste program. Failure to resolve these issues in time to permit disposal according to the WIPP baseline plan will force either modification to the plan, or disposal or long-term storage of RH TRU waste at non-WIPP sites. The recommended strategy is to recognize, and take the needed actions to resolve, the open issues preventing disposal of RH TRU waste at WIPP on schedule. It is also recommended that the baseline plan be upgraded by adopting enhancements such as revised canister emplacement strategies and a more flexible waste transport system.

Bild, R.W. [Sandia National Lab., Albuquerque, NM (United States). Program Integration Dept.

1994-07-01T23:59:59.000Z

270

Characteristics of transuranic waste at Department of Energy sites  

SciTech Connect (OSTI)

This document reports data and information on TRU waste from all DOE generating and storage sites. The geographical location of the sites is shown graphically. There are four major sections in this document. The first three cover the TRU waste groups known as Newly Generated, Stored, and Buried Wastes. Subsections are included under Newly Generated and Stored on contact-handled and remote-handled waste. These classifications of waste are defined, and the current or expected totals of each are given. Figure 1.3 shows the total amount of Buried and Stored TRU waste. Preparation of this document began in 1981, and most of the data are as of December 31, 1980. In a few cases data were reported to December 31, 1981, and these have been noted. The projections in the Newly Generated section were made, for the most part, at the end of 1981.

Jensen, R.T.; Wilkinson, F.J. III

1983-05-01T23:59:59.000Z

271

2012 Annual Planning Summary for Legacy Management  

Broader source: Energy.gov [DOE]

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2012 and 2013 within Legacy Management.

272

Keeping Track of the National Transuranic Program Complex Defense Transuranic Waste  

SciTech Connect (OSTI)

The long-term performance of the Waste Isolation Pilot Plant (WIPP) disposal system in southeastern New Mexico is assessed periodically using transuranic (TRU) waste physical and radiological properties and other information describing the waste. This TRU waste estimate is based on the best knowledge of the TRU waste across the DOE complex at the time repository performance is assessed. TRU waste inventory was collected from each of the Department of Energy (DOE) sites that generated TRU waste for the Compliance Certification Application (CCA) and subsequently for the Compliance Re-certification Application (CRA) in order to support the assessments that ultimately led to certification and re-certification of the WIPP. In each case, information was collected, stored and maintained in the Transuranic Waste Baseline Inventory Database (TWBID) that was used to generate tables describing the volumetric, physical, and radiological properties of the TRU waste. The tables and other descriptions of the waste were reported in baseline reports for the certification and the re-certification. Information maintained in the TWBID database has now been transferred to a new qualified database that utilizes a more efficient operating configuration. This database known as the Comprehensive Inventory Database (CID) will be the information repository for TRU waste destined to WIPP, and the source for information submitted for annual Transuranic Waste Inventory Update Reports to be used in future repository performance assessments (PAs) and re-certifications. The information that has been collected will support a wider range of data needs including waste management, transportation and strategic planning. (authors)

Crawford, B.; Lott, S.; McInroy, W.; VanSoest, G. [Los Alamos National Laboratory-Carlsbad Operations, Carlsbad, NM (United States); Patterson, R. [U.S. Department of Energy Carlsbad Field Office, Carlsbad, NM (United States)

2007-07-01T23:59:59.000Z

273

Certification document for newly generated contact-handled transuranic waste  

SciTech Connect (OSTI)

The US Department of Energy has requested that all national laboratories handling defense waste develop and augment a program whereby all newly generated contact-handled transuranic (TRU) waste be contained, stored, and then shipped to the Waste Isolation Pilot Plant (WIPP) in accordance with the requirements set forth in WIPP-DOE-114. The program described in this report delineates how Oak Ridge National Laboratory intends to comply with these requirements and lists the procedures used by each generator to ensure that their TRU wastes are certifiable for shipment to WIPP.

Box, W.D.; Setaro, J.

1984-01-01T23:59:59.000Z

274

Westinghouse TRU Solutions LLC Earns Small Business Program Award  

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

For Immediate Release For Immediate Release Westinghouse TRU Solutions LLC Earns Small Business Program Award CARLSBAD, N.M., July 10, 2001 - Westinghouse TRU Solutions LLC (WTS) was recognized recently by the U.S. Department of Energy (DOE) with the Outstanding HUBZone Business Achievement Award. WTS was selected for the award by DOE's Secretarial Small Business Program "This award is a reflection of our commitment to DOE's Small Business Program to provide opportunities for small business concerns," said John Lee, WTS General Manager. "I am proud of the work our procurement group does in this regard." WTS was selected to receive the HUBZone Business Achievement Award based on the amount of money the company spent and the percentage of purchases it made in

275

Characterization of past and present waste streams from the 325 Radiochemistry Building  

SciTech Connect (OSTI)

The purpose of this report is to characterize, as far as possible, the solid waste generated by the 325 Radiochemistry Building since its construction in 1953. Solid waste as defined in this document is any containerized or self-contained material that has been declared waste. This characterization is of particular interest in the planning of transuranic (TRU) waste retrieval operations including the Waste Receiving and Processing (WRAP) Facility. Westinghouse Hanford Company (Westinghouse Hanford) and Battelle Pacific Northwest Laboratory (PNL) activities at Building 325 have generated approximately 4.4% and 2.4%, respectively, of the total volume of TRU waste currently stored at the Hanford Site.

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

1993-12-01T23:59:59.000Z

276

Los Alamos National Laboratory Accelerates Transuranic Waste Shipments:  

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

Los Alamos National Laboratory Accelerates Transuranic Waste Los Alamos National Laboratory Accelerates Transuranic Waste Shipments: Spurred by a major wildfire in 2011, Los Alamos National Laboratory's TRU Waste Program accelerates shipments of transuranic waste stored aboveground to the Waste Isolation Pilot Plan Los Alamos National Laboratory Accelerates Transuranic Waste Shipments: Spurred by a major wildfire in 2011, Los Alamos National Laboratory's TRU Waste Program accelerates shipments of transuranic waste stored aboveground to the Waste Isolation Pilot Plan July 2, 2012 - 12:00pm Addthis New Mexico Governor Susana Martinez greets Terry Aguilar, governor of San Ildefonso Pueblo, while Frank Marcinowski (lower right), EM deputy assistant secretary of waste management, and Dan Cox, LANL associate deputy director for environmental affairs, look on.

277

DOE Seeks Independent Evaluation of Remote-Handled Waste Program  

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

Seeks Independent Evaluation Seeks Independent Evaluation Of Remote-Handled Waste Program CARLSBAD, N.M., July 24, 2001 - An independent panel of scientific and engineering experts will convene July 30 in Carlsbad to evaluate U.S. Department of Energy (DOE) plans for managing remote-handled (RH) transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP). DOE's Carlsbad Field Office has asked the American Society of Mechanical Engineers and the Institute for Regulatory Science to review its proposed RH-TRU waste program. The program must be approved by the New Mexico Environment Department and the U.S. Environmental Protection Agency before DOE will be permitted to accept and dispose of RH-TRU waste at WIPP. "Safety and compliance are our primary considerations in developing the plans for

278

U.S. Department of Energy Carlsbad Field Office Waste Isolation...  

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

Field Office (575) 234-7270 www.wipp.energy.gov DOE Completes TRU Waste Cleanup at Bettis CARLSBAD, N.M., September 23, 2011 - The U.S. Department of Energy (DOE) has...

279

EIS-0026-S2: Waste Isolation Pilot Plant Disposal Phase, Carlsbad, New Mexico  

Broader source: Energy.gov [DOE]

SEIS-II evaluates environmental impacts resulting from the various treatment options; the transportation of TRU waste to WIPP using truck, a combination of truck and regular rail service, and a...

280

E-Print Network 3.0 - automated waste canister Sample Search...  

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

Summary: (TRU) Waste Facilities U.S. Department of Energy Washington, D.C. 20585 AREA-SAFT DISTRIBUTION... to be used when developing Safety Basis (SB) documents for transuranic...

Note: This page contains sample records for the topic "legacy tru waste" 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

Chicago Pile reactors create enduring research legacy - Argonne's  

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

Chicago Pile reactors create enduring research Chicago Pile reactors create enduring research legacy About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy

282

CRAD, Safety Basis - Oak Ridge National Laboratory TRU ALPHA LLWT Project |  

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

TRU ALPHA LLWT TRU ALPHA LLWT Project CRAD, Safety Basis - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 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 a November 2003 assessment of the Safety Basis portion of an Operational Readiness Review of the Oak Ridge National Laboratory TRU ALPHA LLWT Project. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Safety Basis - Oak Ridge National Laboratory TRU ALPHA LLWT Project More Documents & Publications CRAD, Conduct of Operations - Oak Ridge National Laboratory TRU ALPHA LLWT

283

Long-range master plan for defense transuranic waste management  

SciTech Connect (OSTI)

The Long Range Master Plan for the Defense Transuranic Waste Program (DTWP), or ''Master Plan,'' details current TRU waste management plans and serves as a framework for the DTWP. Not all final decisions concerning activities presented in the Master Plan have been made (e.g., land withdrawal legislation, the WIPP Compliance and Operational Plan and the TRUPACT Certificate of Compliance). It is the goal of the DTWP to end interim storage and achieve permanent disposal of TRU waste. To accomplish this goal, as much TRU waste as possible will be certified to meet the WIPP Acceptance Criteria (WAC). The certified waste will then be disposed of at WIPP. The small quantity of waste which is not practical to certify will be disposed of via alternative methods that require DOE Headquarters approval and shall comply with the National Environmental Policy Act requirements and EPA/State Regulations. The definition of TRU waste is ''without regard to source or form, waste that is contaminated with alpha-emitting transuranium radionuclides with half-lives greater than 20 years and concentrations greater than 100 nanocuries/gram (nCi/g) at the time of assay. Heads of Field Elements can determine that other alpha contaminated wastes, peculiar to a specific site, must be managed as transuranic waste.''

Not Available

1988-12-01T23:59:59.000Z

284

Hanford site transuranic waste sampling plan  

SciTech Connect (OSTI)

This sampling plan (SP) describes the selection of containers for sampling of homogeneous solids and soil/gravel and for visual examination of transuranic and mixed transuranic (collectively referred to as TRU) waste generated at the U.S. Department of Energy (DOE) Hanford Site. The activities described in this SP will be conducted under the Hanford Site TRU Waste Certification Program. This SP is designed to meet the requirements of the Transuranic Waste Characterization Quality Assurance Program Plan (CAO-94-1010) (DOE 1996a) (QAPP), site-specific implementation of which is described in the Hanford Site Transuranic Waste Characterization Program Quality Assurance Project Plan (HNF-2599) (Hanford 1998b) (QAPP). The QAPP defines the quality assurance (QA) requirements and protocols for TRU waste characterization activities at the Hanford Site. In addition, the QAPP identifies responsible organizations, describes required program activities, outlines sampling and analysis strategies, and identifies procedures for characterization activities. The QAPP identifies specific requirements for TRU waste sampling plans. Table 1-1 presents these requirements and indicates sections in this SP where these requirements are addressed.

GREAGER, T.M.

1999-05-13T23:59:59.000Z

285

Waste acceptance and waste loading for vitrified Oak Ridge tank waste  

SciTech Connect (OSTI)

The Office of Science and Technology of the DOE has funded a joint project between the Oak Ridge National Laboratory (ORNL) and the Savannah River Technology Center (SRTC) to evaluate vitrification and grouting for the immobilization of sludge from ORNL tank farms. The radioactive waste is from the Gunite and Associated Tanks (GAAT), the Melton Valley Storage Tanks (MVST), the Bethel Valley Evaporator Service Tanks (BVEST), and the Old Hydrofractgure Tanks (OHF). Glass formulation development for sludge from these tanks is discussed in an accompanying article for this conference (Andrews and Workman). The sludges contain transuranic radionuclides at levels which will make the glass waste form (at reasonable waste loadings) TRU. Therefore, one of the objectives for this project was to ensure that the vitrified waste form could be disposed of at the Waste Isolation Pilot Plant (WIPP). In order to accomplish this, the waste form must meet the WIPP Waste Acceptance Criteria (WAC). An alternate pathway is to send the glass waste forms for disposal at the Nevada Test Site (NTS). A sludge waste loading in the feed of 6 wt percent will lead to a waste form which is non-TRU and could potentially be disposed of at NTS. The waste forms would then have to meet the requirements of the NTS WAC. This paper presents SRTC`s efforts at demonstrating that the glass waste form produced as a result of vitrification of ORNL sludge will meet all the criteria of the WIPP WAC or NTS WAC.

Harbour, J.R.; Andrews, M.K.

1997-06-06T23:59:59.000Z

286

The Second Opening of the Waste Isolation Pilot Plant? Review of Salient Characteristics and Unique Operational Considerations for Remote Handled Transuranic Waste  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) intends to dispose of remote handled (RH) transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP) beginning in 2005. (1) Four principle regulatory agencies are involved in the process of approving the RH TRU waste activities. The DOE is responsible for operational activities. The U. S. Nuclear Regulatory Commission (NRC) approves the design and use of shipping containers. The U.S. Environmental Protection Agency (EPA) is responsible for assuring safe and environmentally effective long-term disposal of the radioactive component of the waste and operational environmental monitoring. The New Mexico Environment Department (NMED) is responsible for the handling and the disposal of the non-radioactive hazardous component of the waste. The Environmental Evaluation Group (EEG) is responsible for performing independent technical oversight of all WIPP activities, and will comment on documents and practices for the various regulated RH TRU waste activities. The DOE has already obtained the necessary approvals from the NRC, and has submitted a Class 3 Modification request to the NMED. On December 16, 2002 the DOE Carlsbad Field Office (CBFO) provided the EPA with a notice of proposed change, in accordance with 40 CFR 194.4 (b) (3), to receive and dispose of remote handled transuranic waste. (2) WIPP procedures for the management of RH TRU waste at the site are being developed. While there are no issues with current NRC Certificates of Compliance for the RH TRU waste shipping containers, it is likely that there will be some controversy over other aspects of the currently planned RH TRU waste program. These issues may include: (1) the published RH TRU waste inventory, (2) the characterization of the radionuclide portion of the waste, for which one planned method is to use dose-to-Curie conversions, and (3) the plans to use bounding estimates for the hazardous portion of the WIPP waste, rather than measuring VOCs on a container-by-container basis or by representative sampling as is done for contact handled transuranic (CH TRU) waste. This paper discusses the currently planned process and the possible issues related to the DOE's efforts to dispose RH TRU waste at the WIPP.

Anastas, G.; Walker, B.A.

2003-02-24T23:59:59.000Z

287

Nuclear waste management. Quarterly progress report, April-June 1980  

SciTech Connect (OSTI)

The status of the following programs is reported: high-level waste immobilization; alternative waste forms; Nuclear Waste Materials Characterization Center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; mobility of organic complexes of fission products in soils; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology; systems study on engineered barriers; criteria for defining waste isolation; spent fuel and fuel pool component integrity program; analysis of spent fuel policy implementation; asphalt emulsion sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and development of backfill material.

Platt, A.M.; Powell, J.A. (comps.)

1980-09-01T23:59:59.000Z

288

Waste Inspection Tomography (WIT)  

SciTech Connect (OSTI)

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

Bernardi, R.T.

1995-12-01T23:59:59.000Z

289

Waste Management Program. Technical progress report, Aporil-June 1983  

SciTech Connect (OSTI)

This quarterly report provides current information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant. The studies on environmental and safety assessments, process and equipment development, TRU waste, and low-level waste are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations Program: surveillance and maintenance, waste concentration, low-level effluent waste, tank replacement/waste transfer, and solid waste storage and related activities.

None

1984-02-01T23:59:59.000Z

290

Waste Isolation Pilot Plant Safety Analysis Report  

SciTech Connect (OSTI)

The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions`` (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.`` This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment.

NONE

1995-11-01T23:59:59.000Z

291

Resource Conservation and Recovery Act, Part B permit application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 3, Chapter C, Appendix C3 (conclusion)--Chapter C, Appendix C9: Revision 3  

SciTech Connect (OSTI)

This volume contains appendices for the following: results of extraction procedure (EP) toxicity data analyses; summary of headspace gas analysis in Rocky Flats Plant sampling program-FY 1988; waste drum gas generation sampling program at Rocky Flats Plant during FY 1988; TRU waste sampling program waste characterization; summary of headspace gas analyses in TRU waste sampling program; summary of volatile organic compounds analyses in TRU waste sampling program; totals analysis versus toxicity characteristic leaching procedure; Waste Isolation Pilot Plant waste characterization sampling and analysis methods; Waste Isolation Pilot Plant waste characterization analytical methods; data reduction, validation and reporting; examples of waste screening checklists; and Waste Isolation Pilot Plant generator/storage site waste screening and acceptance audit program.

Not Available

1993-03-01T23:59:59.000Z

292

Transuranic waste baseline inventory report. Revision No. 3  

SciTech Connect (OSTI)

The Transuranic Waste Baseline Inventory Report (TWBIR) establishes a methodology for grouping wastes of similar physical and chemical properties from across the U.S. Department of Energy (DOE) transuranic (TRU) waste system into a series of {open_quotes}waste profiles{close_quotes} that can be used as the basis for waste form discussions with regulatory agencies. The purpose of Revisions 0 and 1 of this report was to provide data to be included in the Sandia National Laboratories/New Mexico (SNL/NM) performance assessment (PA) processes for the Waste Isolation Pilot Plant (WIPP). Revision 2 of the document expanded the original purpose and was also intended to support the WIPP Land Withdrawal Act (LWA) requirement for providing the total DOE TRU waste inventory. The document included a chapter and an appendix that discussed the total DOE TRU waste inventory, including nondefense, commercial, polychlorinated biphenyls (PCB)-contaminated, and buried (predominately pre-1970) TRU wastes that are not planned to be disposed of at WIPP.

NONE

1996-06-01T23:59:59.000Z

293

Hanford`s remote-handled transuranic and transuranic mixed waste volume assessment  

SciTech Connect (OSTI)

This study documents the results of an assessment of each Hanford program`s potential RH-TRU(M) waste forecast volumes. Of this 3,470 m{sup 3} of remote-handled transuranic and transuranic mixed (RH-TRU[M]) forecast waste, the Environmental Restoration program is the only program generating waste (360 m{sup 3}) after the closure of the WIPP in FY 2033. Previous forecast assessments have estimated Hanford`s RH-TRU(M) waste volumes to range from 4,000 m{sup 3} to 45,000 m{sup 3}. In FY 1995, the RH-TRU(M) waste forecast was approximately 22,200 m{sup 3} (BIR), which exceeds the WIPP remote-handled capacity. The FY-1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary (WHC-EP-0900) published in February 1996 stated that the baseline RH-TRU(M) waste volume was 13,350 m{sup 3}. The primary reason for the three different estimates results from two programmatic baseline revisions: Tank Waste Remediation Systems (TWRS) and Environmental Restoration (EM-40). The difference in the TWRS programmatic baseline is due to a revised programmatic baseline for the disposition of the long-length equipment currently present in the tanks. The difference in the Environmental Restoration programmatic baseline is due to an assessment based on recent experience that many of the facilities at Hanford will not contain RH-TRU(M) waste during decontamination and decommissioning and that for many other facilities, the RH-TRU(M) waste volumes will not be as great as previously estimated.

Templeton, K.J.; DeForest, T.J.; Hladek, K.L.

1996-03-01T23:59:59.000Z

294

Parametric study of radionuclide characterization -- Low-level waste. Draft  

SciTech Connect (OSTI)

The criteria and guidance given in this addendum specifically address the classification of low-level waste at the Hanford Reservation into Category 1, Category 3, and Greater Than Category 3 (GTC3). These categories are developed based on the performance assessment (PA) being conducted for the Hanford Site. The radionuclides and their concentration for each category are listed in the revised Table 1-1 (Attachment 1). The information to classify the waste for US Department of Transportation (DOT) and to classify Transuranic (TRU)/ Non-TRU, Contact Handled (CH)/Remote Handled (RH) waste is given in WHC-EP-0063-3 (WHC 1991).

Amir, S.J.

1993-04-01T23:59:59.000Z

295

Record of Decision for the Department of Energy's Waste Management Program; Treatment and Storage of Transuranic Waste  

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

3630 3630 Federal Register / Vol. 63, No. 15 / Friday, January 23, 1998 / Notices to agreements DOE has entered into, such as those with States, relating to the treatment and storage of TRU waste. Future NEPA review could include, but would not necessarily be limited to, analysis of the need to supplement existing environmental reviews. DOE would conduct all such TRU waste shipments between sites in accordance with applicable transportation requirements and would coordinate these shipments with appropriate State, Tribal and local authorities. This Record of Decision was prepared in coordination with the Record of Decision issued on January 16, 1998, on disposal of DOE's TRU waste, which is based on the Waste Isolation Pilot Plant Disposal Phase Final Supplemental Environmental Impact Statement (WIPP

296

Categorical Exclusion Determinations: Legacy Management | Department of  

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

Legacy Management Legacy Management Categorical Exclusion Determinations: Legacy Management Categorical Exclusion Determinations issued by Legacy Mangement. DOCUMENTS AVAILABLE FOR DOWNLOAD May 28, 2013 CX-010396: Categorical Exclusion Determination Bioremediation Injection and Related Activities at the Pinellas Site, Largo, Florida CX(s) Applied: B3.1, B6.1 Date: 05/28/2013 Location(s): Florida Offices(s): Legacy Management May 28, 2013 CX-010533: Categorical Exclusion Determination Road Maintenance on roads Used to Access Groundwater Monitoring Wells South of the Tuba City, Arizona, Uranium Mill Tailing Remedial Action Title I Site CX(s) Applied: B1.3, B3.3, B6.1 Date: 05/28/2013 Location(s): Arizona Offices(s): Legacy Management November 2, 2012 CX-009399: Categorical Exclusion Determination

297

Office of Legacy Management … Post Competition Accountability Report  

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

Post Competition Accountability Quarterly Report: High Performing Organization Proposal 2012 This report serves as an official record of the quarterly cost, personnel, and performance information for the Office of Legacy Management to satisfy the post competition accountability requirements. Page 1 of 2 Fiscal Years (FY) 2012 - 2016: Reporting Period: First Quarter, FY2013 I. MANAGEMENT EXCELLENCE GOALS Cutting Waste (Improving Efficiency) 1. Limit Program Direction increases to levels allowed by OMB for inflation. 2. Comply with OMB guidance, OMB-M-12-12, Promoting Efficient Spending, regarding mission- related travel. Quarterly Cost Report Funded Activity HPO Plan Cost Adjusted Budget Cost (ABC) Estimated Actual Cost (EAC) Explanation for Differences

298

Melter development needs assessment for RWMC buried wastes  

SciTech Connect (OSTI)

This report presents a survey and initial assessment of the existing state-of-the-art melter technology necessary to thermally treat (stabilize) buried TRU waste, by producing a highly leach resistant glass/ceramic waste form suitable for final disposal. Buried mixed transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) represents an environmental hazard requiring remediation. The Environmental Protection Agency (EPA) placed the INEL on the National Priorities List in 1989. Remediation of the buried TRU-contaminated waste via the CERCLA decision process is required to remove INEL from the National Priorities List. A Waste Technology Development (WTD) Preliminary Systems Design and Thermal Technologies Screening Study identified joule-heated and plasma-heated melters as the most probable thermal systems technologies capable of melting the INEL soil and waste to produce the desired final waste form (Iron-Enriched Basalt (IEB) glass/ceramic). The work reported herein then surveys the state of existing melter technology and assesses it within the context of processing INEL buried TRU wastes and contaminated soils. Necessary technology development work is recommended.

Donaldson, A.D.; Carpenedo, R.J.; Anderson, G.L.

1992-02-01T23:59:59.000Z

299

Melter development needs assessment for RWMC buried wastes  

SciTech Connect (OSTI)

This report presents a survey and initial assessment of the existing state-of-the-art melter technology necessary to thermally treat (stabilize) buried TRU waste, by producing a highly leach resistant glass/ceramic waste form suitable for final disposal. Buried mixed transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) represents an environmental hazard requiring remediation. The Environmental Protection Agency (EPA) placed the INEL on the National Priorities List in 1989. Remediation of the buried TRU-contaminated waste via the CERCLA decision process is required to remove INEL from the National Priorities List. A Waste Technology Development (WTD) Preliminary Systems Design and Thermal Technologies Screening Study identified joule-heated and plasma-heated melters as the most probable thermal systems technologies capable of melting the INEL soil and waste to produce the desired final waste form [Iron-Enriched Basalt (IEB) glass/ceramic]. The work reported herein then surveys the state of existing melter technology and assesses it within the context of processing INEL buried TRU wastes and contaminated soils. Necessary technology development work is recommended.

Donaldson, A.D.; Carpenedo, R.J.; Anderson, G.L.

1992-02-01T23:59:59.000Z

300

Leach tests of simulated low-level transuranic waste forms containing transuranic elements  

SciTech Connect (OSTI)

Simulations of waste forms that could be produced by slagging pyrolysis incineration of low-level transuranic (TRU) wastes stored at the Idaho National Engineering Laboratory (INEL) have been fabricated containing the transuranic isotopes /sup 237/Np, /sup 239/Pu, /sup 241/Am, and /sup 244/Cm at levels of approximately 1 ..mu..Ci/g of each. Leach tests were performed on frit; concrete monoliths made with frit and Portland cement; and vitrified monoliths of average INEL TRU waste, INEL soil, and simulated Rocky Flats plant sludge. Static leach tests were performed at 90, 70, 40, and 25/sup 0/C in deionized water for up to 364 days. Leachates were analyzed for the TRU elements by alpha spectrometry. From the leaching results the following generalizations can be made: (1) cemented frit and vitrified sludge waste forms produce leachates with the highest pHs (> 11) and have the lowest TRU leach rates, 10/sup -4/ g/m/sup 2/ d at 90/sup 0/C; (2) neptunium has a higher leach rate than the other three TRU elements by as much as two orders of magnitude for all waste forms tested except cemented frit; and (3) only the vitrified soil samples display a marked temperature dependence for leach rates of all four TRU elements.

Welch, J.M.; Sill, C.W.; Flinn, J.E.

1983-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

Leach tests of simulated low-level transuranic waste forms containing transuranic elements  

SciTech Connect (OSTI)

Simulations of waste forms that might be produced by slagging pyrolysis incineration of low-level transuranic (TRU) wastes stored at the Idaho National Engineering Laboratory (INEL) have been fabricated containing the transuranic isotopes /sup 237/Np, /sup 239/Pu, /sup 241/Am, /sup 244/Cm at levels of approximately 1 ..mu..Ci per gram of each. Leach tests were performed using frit and vitrified monolithic specimens of average INEL TRU waste, portland cement monoliths made with frit as aggregate, and vitrified monoliths of INEL soil and simulated Rocky Flats sludge. Static leach tests were performed at 90, 70, 40, and 25/sup 0/C in deionized water for up to 364 days. Leachates were analyzed for the TRU elements by alpha spectrometry. The following generalizations can be made: (1) Cemented frit and vitrified sludge waste forms produce leachates with the highest pHs (>11) and have the lowest TRU leach rates, 10/sup -4/ g/m/sup 2/.d at 90/sup 0/C. (2) Neptunium has a higher leach rate than the other three TRU elements by as much as two orders of magnitude for all waste forms tested except cemented frit. (3) Only the vitrified soil samples display a marked temperature dependence for leach rates of all four TRU elements.

Welch, J.M.; Sill, C.W.; Flinn, J.E.

1982-01-01T23:59:59.000Z

302

Legacy Management Specific Training | Department of Energy  

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

Legacy Management Specific Training Legacy Management Specific Training Legacy Management Specific Training Registration Information The following courses are specific to Legacy Management Employees, for more information about the courses below or to register for any of these courses please contact Chequita Johnson. Mandatory Training ECOMM, Environmental-Related External Communication (E-COMM) Tracking System GPP101, Management of Government Personal Property RM 102, Basic Records Management Training (DOE) Training at All LM Site Offices EC 100, Environmental Management System General Awareness (DOE) ER 200, Site Emergency Preparedness [All sites except Grand Junction] SC 105, Security Awareness Briefing Washington, DC HQ Mini Coop Briefing Fernald, OH FE110, Fernald Preserve Site Awareness Briefing

303

Office of Legacy Management | Department of Energy  

Office of Legacy Management (LM)

Office of Legacy Management Timbered ore bin and adits (mine openings) at a Defense-Related Uranium Mine located in southwestern Montrose County, Colorado Timbered ore bin and...

304

CHARACTERIZATION THROUGH DATA QUALITY OBJECTIVES AND CERTIFICATION OF REMOTE-HANDLED TRANSURANIC WASTE GENERATOR/STORAGE SITES FOR SHIPMENT TO THE WIPP  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) is operating to receive and dispose of contact-handled (CH) transuranic (TRU) waste. The Department of Energy (DOE) Carlsbad Field Office (CBFO) is seeking approval from the Environmental Protection Agency (EPA) and the New Mexico Environment Department (NMED) of the remote-handled (RH) TRU characterization plan to allow disposal of RH TRU waste in the WIPP repository. In addition, the DOE-CBFO has received approval from the Nuclear Regulatory Commission (NRC) to use two shipping casks for transporting RH TRU waste. Each regulatory agency (i.e., EPA, NMED, and NRC) has different requirements that will have to be met through the use of information collected by characterizing the RH TRU waste. Therefore, the DOE-CBFO has developed a proposed characterization program for obtaining the RH TRU waste information necessary to demonstrate that the waste meets the applicable regulatory requirements. This process involved the development of a comprehensive set of Data Quality Objectives (DQOs) comprising the various regulatory requirements. The DOE-CBFO has identified seven DQOs for use in the RH TRU waste characterization program. These DQOs are defense waste determination, TRU waste determination, RH TRU determination, activity determination, RCRA physical and chemical properties, prohibited item determination, and EPA physical and chemical properties. The selection of the DQOs were based on technical, legal and regulatory drivers that assure the health and safety of the workers, the public, to protect the environment, and to comply with the requirements of the regulatory agencies. The DOE-CBFO also has the responsibility for the certification of generator/storage sites to ship RH TRU mixed waste to the WIPP for disposal. Currently, thirteen sites across the DOE complex are generators of RH TRU waste or store the waste at their location for other generators. Generator/storage site certification involves review and approval of site-specific programmatic documents that demonstrate compliance with the WIPP waste characterization and transportation requirements. Additionally, procedures must be developed to implement programmatic requirements and adequacy of those procedures determined. Finally, on-site audits evaluate the technical and administrative implementation and effectiveness of the operating procedures.

Spangler, L.R.; Most, Wm.A.; Kehrman, R.F.; Gist, C.S.

2003-02-27T23:59:59.000Z

305

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

306

Microbial Transformations of TRU and Mixed Wastes: Actinide Speciation and Waste Volume Reduction  

SciTech Connect (OSTI)

Cellosic samples were prepared 1/29/92 at BNL from various sources, including white and brown paper towel, and Kimwipes. The mixed cellulosics were cut into 1 cm x 1 cm squares and transferred to glass serum bottles and various treatments were conducted: unamended (U) samples were filled with nitrogen-purged brine from G-Seep (4.1 M Na+ and 5.1 Cl- with minor amounts of Mg, K, and Ca and 0.3 M sulfate (Brush, 1990)); unamended/inoculated (UI) samples were filled with bacteria-containing surface lake water, sediment, and halite from the underground at the WIPP site; amended/inoculated (AI) samples were inoculated in this fashion and amended with nutrients; and amended/inoculated/excess nitrate (AINO3) samples were inoculated with excess nitrate in the form of KNO3 (5 g L-1 (49.5 mM)). Further information on sample preparation is available. All samples were analyzed by Fourier transform infrared spectroscopy (FTIR) at SBU to identify any transformations in cellulosic material which may have occurred during treatment and storage.

Halada, Gary P.

2005-06-01T23:59:59.000Z

307

Effects of Intermediate Ethanol Blends on Legacy Vehicles and...  

Office of Environmental Management (EM)

Effects of Intermediate Ethanol Blends on Legacy Vehicles and Small Non-Road Engines, Report 1 Updated Feb 2009 Effects of Intermediate Ethanol Blends on Legacy Vehicles and...

308

Los Alamos exceeds waste shipping goal  

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

Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos shipped 1,074 cubic meters of transuranic (TRU) and mixed low-level waste to the Waste Isolation Pilot Plant and other approved waste disposal facilities. July 8, 2013 A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. Contact Fred deSousa Communications Office (505) 665-3430 Email "We've made significant progress removing waste stored above ground at Area G, and we made this progress while maintaining an excellent safety record," said Jeff Mousseau, associate director of Environmental Programs

309

Los Alamos exceeds waste shipping goal  

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

Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos shipped 1,074 cubic meters of transuranic (TRU) and mixed low-level waste to the Waste Isolation Pilot Plant and other approved waste disposal facilities. July 8, 2013 A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. Contact Fred deSousa Communications Office (505) 665-3430 Email "We've made significant progress removing waste stored above ground at Area G, and we made this progress while maintaining an excellent safety record," said Jeff Mousseau, associate director of Environmental Programs

310

Remote-Handled Transuranic Waste Drum Venting - Operational Experience and Lessons Learned  

SciTech Connect (OSTI)

Remote-handled transuranic (RH TRU) waste drums must be vented to meet transportation and disposal requirement before shipment to the Waste Isolation Pilot Plant. The capability to perform remote venting of drums was developed and implemented at the Idaho National Laboratory. Over 490 drums containing RH TRU waste were successfully vented. Later efforts developed and implemented a long-stem filter to breach inner waste bags, which reduced layers of confinement and mitigated restrictive transportation wattage limits. This paper will provide insight to the technical specifications for the drum venting system, development, and testing activities, startup, operations, and lessons learned. (authors)

Clements, Th.L.Jr.; Bhatt, R.N.; Troescher, P.D. [CH2M-WG Idaho/Idaho National Laboratory, Idaho Falls, ID (United States); Wickland, T.J.; Anderson, L.; Wood, R. [Nuclear Filter Technology, Golden, CO (United States); Lattin, W.J. [Department of Energy-Idaho Operations Office, Idaho Falls, ID (United States)

2008-07-01T23:59:59.000Z

311

Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Facility |  

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

Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Facility Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Facility August 18, 2011 - 12:00pm Addthis Idaho State Patrol Troopers Rick Stouse and Tony Anderson inspected the TRUPACTS, containers which contain TRU waste, and trailer containing the final shipment of Hanford offsite waste. The Idaho State Patrol officers have played an important role in AMWTP's success by inspecting every one of AMWTP's nearly 3,900 shipments. Idaho State Patrol Troopers Rick Stouse and Tony Anderson inspected the TRUPACTS, containers which contain TRU waste, and trailer containing the final shipment of Hanford offsite waste. The Idaho State Patrol officers have played an important role in AMWTP's success by inspecting every one of

312

DOE Seeks Trucking Services for Transuranic Waste Shipments | Department of  

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

Trucking Services for Transuranic Waste Shipments Trucking Services for Transuranic Waste Shipments DOE Seeks Trucking Services for Transuranic Waste Shipments March 30, 2011 - 12:00pm Addthis Media Contact Bill Taylor 513-246-0539 william.taylor@emcbc.doe.gov Cincinnati -- The Department of Energy (DOE) today will issue a Request for Proposals for the continuation of carrier services to transport transuranic waste (TRU) between DOE sites and the Waste Isolation Pilot Plant (WIPP) site, near Carlsbad, New Mexico. The transportation of TRU waste is accomplished by contracted trucking carriers that ship the waste via public highways on custom designed trailers. The contract will be an Indefinite Delivery/ Indefinite Quantity (ID/IQ) contract using firm-fixed- price delivery task orders. The estimated contract cost is $80-$100 million over a five-year contract

313

Fernald Preserve, Fernald, Ohio Comprehensive Legacy  

Office of Legacy Management (LM)

September 2013 September 2013 LMS/FER/S03496-7.0 Revision 7.0 Draft This page intentionally left blank LMS/FER/S03496-7.0 Comprehensive Legacy Management and Institutional Controls Plan Volumes I and II Fernald Preserve Fernald, Ohio September 2013 Revision 7 Draft This page intentionally left blank Volume I Legacy Management Plan January 2013September 2013 U.S. Department of Energy Revision 67 FinalDraft This page intentionally left blank Emergency Contact Legacy Management 24-hour Monitored Security Telephone Number (877) 695-5322 This page intentionally left blank U.S. Department of Energy Comprehensive Legacy Management and Institutional Controls Plan Doc. No. S03496-7.0-Draft Volume I-Legacy Management Plan

314

College of Legacy Management | Department of Energy  

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

Legacy Management Legacy Management College of Legacy Management College of Legacy Management Vision The College of Legacy Management (CLM) provides DOE program offices with access to the types of training that enables LM to execute its mission of protecting human health and the environment. CLM strives to: Encourage a high-quality workforce Ensure employees get the right skills, at the right time Empower employees to take charge of their own careers through accessible training Retain a best-in-class workforce by providing learning opportunities Maintain and share mission-critical knowledge Increase performance through the development of strong leaders Remain one of the best places to work in the Federal Government by investing in education CLM is a gateway to professional development opportunities including

315

Legacy Management FUSRAP Sites | Department of Energy  

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

Legacy Management FUSRAP Sites Legacy Management FUSRAP Sites Legacy Management FUSRAP Sites Legacy Management FUSRAP Sites Long-Term Surveillance and Maintenance (LTS&M) of Remediated FUSRAP Sites The DOE Office of Legacy Management (LM) established LTS&M requirements for remediated FUSRAP sites. DOE evaluates the final site conditions of a remediated site on the basis of risk for different future uses. DOE then confirms that LTS&M requirements will maintain protectiveness. Most Formerly Utilized Sites Remedial Action Program (FUSRAP) sites are remediated to conditions that pose no risk to human health and the environment under any future use scenario. With regulator concurrence, these sites are released for unrestricted use. No ongoing surveillance is required and LM responsibilities consist of preserving site records and

316

WIPP contractor receives VPP Legacy of Stars Award 2013  

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

Management and Operating Contractor Management and Operating Contractor Recognized for Continuous Safety Performance CARLSBAD, N.M., September 20, 2013 - The U.S. Department of Energy (DOE) recognized Nuclear Waste Partnership LLC (NWP), the Waste Isolation Pilot Plant (WIPP) management and operating (M&O) contractor, with the Voluntary Protection Program (VPP) Legacy of Stars Award in latter August 2013. "Safety is central to everything we do, and achieving this elite designation validates our work and the safety-focused culture we strive to create," said Farok Sharif, NWP President and Project Manager, who received the award with Kevin Miller, United Steel Workers Local Bargaining Unit VPP Ombudsman, at the VPP Participants' Association National Conference

317

Quality assurance program plan for cesium legacy project  

SciTech Connect (OSTI)

This Quality Assurance Program Plan (QAPP) provides information on how the Quality Assurance Program is implemented for the Cesium Legacy Project. It applies to those items and tasks which affect the completion of activities identified in the work breakdown structure of the Project Management Plan (PMP). These activities include all aspects of cask transportation, project related operations within the 324 Building, and waste management as it relates to the specific activities of this project. General facility activities (i.e. 324 Building Operations, Central Waste Complex Operations, etc.) are covered in other appropriate QAPPs. The 324 Building is currently transitioning from being a Pacific Northwest National Laboratory (PNNL) managed facility to a B and W Hanford Company (BWHC) managed facility. During this transition process existing PNNL procedures and documents will be utilized until replaced by BWHC procedures and documents.

Tanke, J.M.

1997-05-22T23:59:59.000Z

318

"TRU" Success: SRS Recovery Act Prepares to Complete Shipment...  

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

More Than 5,000 Cubic Meters of Nuclear Waste to WIPP More Documents & Publications TRUPACT-III Quick Facts EIS-0026-SA-06: Supplement Analysis Waste Isolation Pilot Plant Update...

319

WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs  

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

For immediate release WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs CARLSBAD, N.M., December 21, 2011 - The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) has received the first of eight planned defense-related remote- handled transuranic (RH-TRU) waste shipments from Sandia National Laboratories (SNL) in Albuquerque. The shipment arrived December 16 for permanent disposal in WIPP's underground repository. DOE National TRU Program Director J.R. Stroble said the shipment is significant to WIPP. "Our goal is to reduce the nation's nuclear waste footprint and we routinely receive shipments from around the country," said Stroble. "This first shipment of RH-TRU waste from

320

Shipment and Disposal of Solidified Organic Waste (Waste Type IV) to the Waste Isolation Pilot Plant (WIPP)  

SciTech Connect (OSTI)

In April of 2005, the last shipment of transuranic (TRU) waste from the Rocky Flats Environmental Technology Site to the WIPP was completed. With the completion of this shipment, all transuranic waste generated and stored at Rocky Flats was successfully removed from the site and shipped to and disposed of at the WIPP. Some of the last waste to be shipped and disposed of at the WIPP was waste consisting of solidified organic liquids that is identified as Waste Type IV in the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) document. Waste Type IV waste typically has a composition, and associated characteristics, that make it significantly more difficult to ship and dispose of than other Waste Types, especially with respect to gas generation. This paper provides an overview of the experience gained at Rocky Flats for management, transportation and disposal of Type IV waste at WIPP, particularly with respect to gas generation testing. (authors)

D'Amico, E. L [Washington TRU Solutions (United States); Edmiston, D. R. [John Hart and Associates (United States); O'Leary, G. A. [CH2M-WG Idaho, LLC (United States); Rivera, M. A. [Aspen Resources Ltd., Inc. (United States); Steward, D. M. [Boulder Research Enterprises, LLC (United States)

2006-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

Waste Isolation Pilot Plant Recovery Plan  

Broader source: Energy.gov [DOE]

This Recovery Plan provides a safe and compliant approach to resuming operations at the Waste Isolation Pilot Plant (WIPP), the repository for disposal of the nations defense transuranic (TRU) waste. The U.S. Department of Energy (DOE) is committed to resuming operations by the first quarter of calendar year 2016, and this Recovery Plan outlines the Departments approach to meet that schedule while prioritizing safety, health, and environmental protection.

322

Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The purpose of this document is to summarize the waste acceptance criteria applicable to the transportation, storage, and disposal of contact-handled transuranic (CH-TRU) waste at the Waste Isolation Pilot Plant (WIPP). These criteria serve as the U.S. Department of Energy's (DOE) primary directive for ensuring that CH-TRU waste is managed and disposed of in a manner that protects human health and safety and the environment.The authorization basis of WIPP for the disposal of CH-TRU waste includes the U.S.Department of Energy National Security and Military Applications of Nuclear EnergyAuthorization Act of 1980 (reference 1) and the WIPP Land Withdrawal Act (LWA;reference 2). Included in this document are the requirements and associated criteriaimposed by these acts and the Resource Conservation and Recovery Act (RCRA,reference 3), as amended, on the CH-TRU waste destined for disposal at WIPP.|The DOE TRU waste sites must certify CH-TRU waste payload containers to thecontact-handled waste acceptance criteria (CH-WAC) identified in this document. Asshown in figure 1.0, the flow-down of applicable requirements to the CH-WAC istraceable to several higher-tier documents, including the WIPP operational safetyrequirements derived from the WIPP CH Documented Safety Analysis (CH-DSA;reference 4), the transportation requirements for CH-TRU wastes derived from theTransuranic Package Transporter-Model II (TRUPACT-II) and HalfPACT Certificates ofCompliance (references 5 and 5a), the WIPP LWA (reference 2), the WIPP HazardousWaste Facility Permit (reference 6), and the U.S. Environmental Protection Agency(EPA) Compliance Certification Decision and approval for PCB disposal (references 7,34, 35, 36, and 37). The solid arrows shown in figure 1.0 represent the flow-down of allapplicable payload container-based requirements. The two dotted arrows shown infigure 1.0 represent the flow-down of summary level requirements only; i.e., the sitesmust reference the regulatory source documents from the U.S. Nuclear RegulatoryCommission (NRC) and the New Mexico Environment Department (NMED) for acomprehensive and detailed listing of the requirements.This CH-WAC does not address the subject of waste characterization relating to adetermination of whether the waste is hazardous; rather, the sites are referred to theWaste Analysis Plan (WAP) contained in the WIPP Hazardous Waste Facility Permit fordetails of the sampling and analysis protocols to be used in determining compliance withthe required physical and chemical properties of the waste. Requirements andassociated criteria pertaining to a determination of the radiological properties of thewaste, however, are addressed in appendix A of this document. The collectiveinformation obtained from waste characterization records and acceptable knowledge(AK) serves as the basis for sites to certify that their CH-TRU waste satisfies the WIPPwaste acceptance criteria listed herein.

Washington TRU Solutions LLC

2005-12-29T23:59:59.000Z

323

Overview of the Government of Canada Nuclear Legacy Liabilities Program - 13551  

SciTech Connect (OSTI)

Nuclear legacy liabilities have resulted from more than 60 years of nuclear research and development carried out on behalf of Canada. The liabilities are located at Atomic Energy of Canada Limited's (AECL) Chalk River Laboratories in Ontario and Whiteshell Laboratories in Manitoba, as well as three shutdown prototype reactors in Ontario and Quebec that are being maintained in a safe storage state. Estimated at about $7.4 billion (current day dollars), these liabilities consist of disused nuclear facilities and associated infrastructure, a wide variety of buried and stored waste, and contaminated lands. In 2006, the Government of Canada adopted a long-term strategy to deal with the nuclear legacy liabilities and initiated a five-year, $520 million start-up phase, thereby creating the Nuclear Legacy Liabilities Program (NLLP). The Government of Canada renewed the NLLP in 2011 with a $439-million three-year second phase that ends March 31, 2014. The projects and activities carried out under the Program focus on infrastructure decommissioning, environmental restoration, improving the management of legacy radioactive waste, and advancing the long-term strategy. The NLLP is being implemented through a Memorandum of Understanding between Natural Resources Canada (NRCan) and AECL whereby NRCan is responsible for policy direction and oversight, including control of funding, and AECL is responsible for implementing the program of work and holding and administering all licences, facilities and lands. (authors)

Metcalfe, D.; McCauley, D. [Natural Resources Canada, Ottawa, Ontario, K1A 0E4 (Canada)] [Natural Resources Canada, Ottawa, Ontario, K1A 0E4 (Canada); Miller, J.; Brooks, S. [Atomic Energy of Canada Limited, Chalk River, Ontario, K0J 1J0 (Canada)] [Atomic Energy of Canada Limited, Chalk River, Ontario, K0J 1J0 (Canada)

2013-07-01T23:59:59.000Z

324

Management activities for retrieved and newly generated transuranic waste, Savannah River Plant  

SciTech Connect (OSTI)

The purpose of this Environmental Assessment (EA) is to assess the potential environmental impacts of the retrieval and processing of retrieved and newly generated transuranic (TRU) radioactive waste at the Savannah River Plant (SRP), including the transportation of the processes TRU waste to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. A new TRU Waste Facility (TWF) will be constructed at SRP to retrieve and process the SRP TRU waste in interim storage to meet WIPP criteria. This EA has been prepared in compliance with the National Environmental Policy Act (NEPA) of 1969, as amended, and the requirements of the Council of Environmental Quality Regulations for implementing NEPA (40 CFR Parts 1500--1508). The National Environmental Policy Act (NEPA) requires the assessment of environmental consequences of all major federal actions that may affect the quality of the human environment. This document describes the environmental impact of constructing and operating the TWF facility for processing and shipment of the TRU waste to WIPP and considers alternatives to the proposed action. 40 refs., 12 figs., 12 tabs.

Not Available

1988-08-01T23:59:59.000Z

325

LANL sets waste shipping record for fourth consecutive year  

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

LANL Sets Waste Shipping Record LANL Sets Waste Shipping Record Community Connections: Our link to Northern New Mexico Communities Latest Issue:Dec. 2013 - Jan. 2014 All Issues » submit LANL sets waste shipping record for fourth consecutive year The Laboratory has transported more than 1,000 shipments to WIPP since that facility opened in 1999. September 1, 2012 dummy image Read our archives Contacts Editor Linda Anderman Email Community Programs Office Kurt Steinhaus Email Our goal this fiscal year is 184 shipments, and we are on track to surpass that by a substantial margin. For the fourth consecutive year, Los Alamos National Laboratory's Transuranic (TRU) Waste Program sent a record number of shipments to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, N.M. for permanent storage. The Laboratory's 172nd shipment of TRU waste this year left Los Alamos

326

Identification of potential transuranic waste tanks at the Hanford Site  

SciTech Connect (OSTI)

The purpose of this document is to identify potential transuranic (TRU) material among the Hanford Site tank wastes for possible disposal at the Waste Isolation Pilot Plant (WIPP) as an alternative to disposal in the high-level waste (HLW) repository. Identification of such material is the initial task in a trade study suggested in WHC-EP-0786, Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The scope of this document is limited to the identification of those tanks that might be segregated from the HLW for disposal as TRU, and the bases for that selection. It is assumed that the tank waste will be washed to remove soluble inert material for disposal as low-level waste (LLW), and the washed residual solids will be vitrified for disposal. The actual recommendation of a disposal strategy for these materials will require a detailed cost/benefit analysis and is beyond the scope of this document.

Colburn, R.P.

1995-05-05T23:59:59.000Z

327

Lab Ahead of Schedule Processing Waste in Large Boxes | Department of  

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

Lab Ahead of Schedule Processing Waste in Large Boxes Lab Ahead of Schedule Processing Waste in Large Boxes Lab Ahead of Schedule Processing Waste in Large Boxes March 30, 2012 - 12:00pm Addthis A framework agreement between DOE and the State of New Mexico calls for the Lab’s TRU Waste Program to ship 3,706 cubic meters of combustible or dispersible transuranic waste to WIPP for permanent disposal by June 30, 2014. A framework agreement between DOE and the State of New Mexico calls for the Lab's TRU Waste Program to ship 3,706 cubic meters of combustible or dispersible transuranic waste to WIPP for permanent disposal by June 30, 2014. Processing waste in large boxes is ahead of schedule due to worker skill, efficient processing and good planning. Processing waste in large boxes is ahead of schedule due to worker skill,

328

Enforcement Letter, Washington TRU Solutions - September 8, 2006...  

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

related to Quality Assurance Deficiencies associated with the Super High-Efficiency Neutron Counter Non-Destructive Assay System Refurbishment at the Waste Isolation Pilot Plant...

329

DOE Exercises 5 Year Option on Washington TRU Solutions Contract...  

Energy Savers [EERE]

and operating the Department's Waste Isolation Pilot Plant (WIPP), located in New Mexico. The option DOE exercised is a part of the WIPP contract that was competitively...

330

Controlling Beryllium Contaminated Material And Equipment For The Building 9201-5 Legacy Material Disposition Project  

SciTech Connect (OSTI)

This position paper addresses the management of beryllium contamination on legacy waste. The goal of the beryllium management program is to protect human health and the environment by preventing the release of beryllium through controlling surface contamination. Studies have shown by controlling beryllium surface contamination, potential airborne contamination is reduced or eliminated. Although there are areas in Building 9201-5 that are contaminated with radioactive materials and mercury, only beryllium contamination is addressed in this management plan. The overall goal of this initiative is the compliant packaging and disposal of beryllium waste from the 9201-5 Legacy Material Removal (LMR) Project to ensure that beryllium surface contamination and any potential airborne release of beryllium is controlled to levels as low as practicable in accordance with 10 CFR 850.25.

Reynolds, T. D.; Easterling, S. D.

2010-10-01T23:59:59.000Z

331

Los Alamos National Laboratory transuranic waste quality assurance project plan. Revision 1  

SciTech Connect (OSTI)

This Transuranic (TRU) Waste Quality Assurance Project Plan (QAPjP) serves as the quality management plan for the characterization of transuranic waste in preparation for certification and transportation. The Transuranic Waste Characterization/Certification Program (TWCP) consists of personnel who sample and analyze waste, validate and report data; and provide project management, quality assurance, audit and assessment, and records management support, all in accordance with established requirements for disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP) facility. This QAPjP addresses how the TWCP meets the quality requirements of the Carlsbad Area Office (CAO) Quality Assurance Program Description (QAPD) and the technical requirements of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP). The TWCP characterizes and certifies retrievably stored and newly generated TRU waste using the waste selection, testing, sampling, and analytical techniques and data quality objectives (DQOs) described in the QAPP, the Los Alamos National Laboratory Transuranic Waste Certification Plan (Certification Plan), and the CST Waste Management Facilities Waste Acceptance Criteria and Certification [Los Alamos National Laboratory (LANL) Waste Acceptance Criteria (WAC)]. At the present, the TWCP does not address remote-handled (RH) waste.

NONE

1997-04-14T23:59:59.000Z

332

INDIANAPOLIS LEAVES A LEGACY OF ENERGY EFFICIENCY  

Broader source: Energy.gov [DOE]

The City of Indianapolis, Indiana, used its status as host of the 2012 Super Bowl to address inefficiencies in the areas older housing stock and leave behind a legacy of energy efficiency. Seeking...

333

DOE Selects Two Small Businesses to Truck Transuranic Waste to New Mexico  

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

Two Small Businesses to Truck Transuranic Waste to New Two Small Businesses to Truck Transuranic Waste to New Mexico Waste Isolation Pilot Plant DOE Selects Two Small Businesses to Truck Transuranic Waste to New Mexico Waste Isolation Pilot Plant January 9, 2012 - 12:00pm Addthis Media Contact Bill Taylor 803-952-8564 bill.taylor@srs.gov Cincinnati - The Department of Energy (DOE) today awarded two small-business contracts to CAST Specialty Transportation, Inc. and Visionary Solutions, LLC, to provide trucking services to transport transuranic (TRU) waste, from DOE and other defense-related TRU waste generator sites to the Waste Isolation Pilot Plant (WIPP) site, near Carlsbad, New Mexico. The contracts are firmfixed-price with cost-reimbursable expenses over five years. CAST Specialty Transportation, Inc. of Henderson, Colorado, will begin

334

Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) | Department of  

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

Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) A transuranic (TRU) waste shipment makes its way to the Waste Isolation Pilot Plant in Carlsbad, N.M. A transuranic (TRU) waste shipment makes its way to the Waste Isolation Pilot Plant in Carlsbad, N.M. On February 17, 2011, DOE issued the Draft Environmental Impact Statement (EIS) for the Disposal of Greater-Than-Class C (GTCC) Low-Level Radioactive Waste (LLRW) and GTCC-Like Waste (Draft EIS, DOE/EIS-0375D) for public review and comment. DOE is inviting public comments on this Draft EIS during a 120-day public comment period, from the date of publication of the EIS's Notice of Availability in the Federal Register. During the comment

335

Tank Waste Corporate Board Meeting 07/29/09 | Department of Energy  

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

9/09 9/09 Tank Waste Corporate Board Meeting 07/29/09 The following documents are associated with the Tank Waste Corporate Board Meeting held on July 29th, 2009. Fuel Cycle Research and Development Program Retrieval and Repackaging of RH-TRU Waste - General Presentation Modular Hot Cell Technology Tank Waste System Integrated Project Team Gunite Tanks Waste Retrieval and Closure Operations at Oak Ridge Nattional Laboratory Integrated Facilities Disposition Program Oak Ridge National Laboratory TRU Waste Processing Center Tank Waste Processing Supernate Processing System Chemical Cleaning Program Review Enhanced Chemical Cleaning Hanford Single-Shell Tank Integrity Program Modeling the Performance of Engineered Systems for Closure and Near-Surface Disposal Nuclear Safety R&D in the Waste Processing Technology Development &

336

Microsoft PowerPoint - EM SSAB Chairs Webinar - Marcinowski Waste Strategies.042413  

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

Chair's Meeting Chair's Meeting Waste Disposition Strategies Update www.energy.gov/EM 1 Waste Disposition Strategies Update Frank Marcinowski Deputy Assistant Secretary for Waste Management Office of Environmental Management April 25, 2013 * Recent Program Accomplishments * FY13 Waste Management Priorities * FY14 Waste Management Priorities * Los Alamos Update * LLW/MLLW Disposition Options Discussion Outline www.energy.gov/EM 2 * Hanford TRU Tank Disposition Initiative * GTCC EIS * Mercury Supplemental EIS * Excess Material and Metal Recycling * DOE Order 435.1, Radioactive Waste Management * Blue Ribbon Commission Related Activities Recent Program Accomplishments * Continued progress towards removal of Los Alamos TRU waste, in accord with Framework Agreement * Submitted WIPP Hazardous Waste Facility permit modification for

337

State of New Mexico Issues Permit For Remote-Handled Waste at WIPP |  

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

of New Mexico Issues Permit For Remote-Handled Waste at WIPP of New Mexico Issues Permit For Remote-Handled Waste at WIPP State of New Mexico Issues Permit For Remote-Handled Waste at WIPP October 16, 2006 - 1:35pm Addthis Enables DOE to Permanently Move Waste to the WIPP Repository for Safe Disposal CARLSBAD, NM - U.S. Department of Energy (DOE) today announced that the New Mexico Environment Department (NMED) issued a revised hazardous waste facility permit for DOE's Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The revised permit enables WIPP to receive and dispose of remote-handled (RH) transuranic (TRU) radioactive waste currently stored at DOE clean-up sites across the country. WIPP expects to receive its first RH-TRU waste shipment in the coming months, as soon as the regulatory approvals are obtained.

338

U.S. Department of Energy Waste Isolation Pilot Plant  

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

WIPP Community Relations Plan Web Page Click Here Current Solicitations Current Contracts Carlsbad Field Office The U.S. Department of Energy Carlsbad Field Office has responsibility for the Waste Isolation Pilot Plant and the NationalTransuranic (TRU) Program. The office's mission is to provide safe, compliant, and efficient characterization, transportation, and disposal of defense-related TRU waste. Its vision is to enable a nuclear future for our country by providing safe and environmentally responsible waste management. Overview Overview opening screen The Waste Isolation Pilot Plant, or WIPP, safely disposes of the nation's defense-related transuranic radioactive waste. Located in the Chihuahuan Desert, outside Carlsbad, N.M., WIPP began disposal operations in March 1999.

339

Microsoft Word - Tran Waste final report 2-8-05.doc  

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

Transuranic Waste Management at Transuranic Waste Management at Los Alamos National Laboratory DOE/IG-0673 February 2005 REPORT ON TRANSURANIC WASTE MANAGEMENT AT LOS ALAMOS NATIONAL LABORATORY TABLE OF CONTENTS Legacy Transuranic Waste Disposal Details of Finding 1 Recommendations and Comments 4 Appendices 1. Objective, Scope, and Methodology 6 2. Transuranic Waste Storage 8 3. Prior Audit Reports 10 4. Management Comments 11 Legacy Transuranic Waste Disposal Page 1 Details of Finding Background Los Alamos National Laboratory (Los Alamos) has been involved in the development, production, and maintenance of the Nation's nuclear weapons stockpile for over six decades. Research, development, and fabrication of weapons components produced a

340

Annual report on the development and characterization of solidified forms for nuclear wastes, 1979  

SciTech Connect (OSTI)

Development and characterization of solidified nuclear waste forms is a major continuing effort at Pacific Northwest Laboratory. Contributions from seven programs directed at understanding chemical composition, process conditions, and long-term behaviors of various nuclear waste forms are included in this report. The major findings of the report are included in extended figure captions that can be read as brief technical summaries of the research, with additional information included in a traditional narrative format. Waste form development proceeded on crystalline and glass materials for high-level and transuranic (TRU) wastes. Leaching studies emphasized new areas of research aimed at more basic understanding of waste form/aqueous solution interactions. Phase behavior and thermal effects research included studies on crystal phases in defense and TRU waste glasses and on liquid-liquid phase separation in borosilicate waste glasses. Radiation damage effects in crystals and glasses from alpha decay and from transmutation are reported.

Chick, L.A.; McVay, G.L.; Mellinger, G.B.; Roberts, F.P.

1980-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

Waste Acceptance for Vitrified Sludge from Oak Ridge Tank Farms  

SciTech Connect (OSTI)

The Tanks Focus Area of the DOE`s Office of Science and Technology (EM-50) has funded the Savannah River Technology Center (SRTC) to develop formulations which can incorporate sludges from Oak Ridge Tank Farms into immobilized glass waste forms. The four tank farms included in this study are: Melton Valley Storage Tanks (MVST), Bethel Valley Evaporation Service Tanks (BVEST), Gunite and Associated Tanks (GAAT), and Old Hydrofracture Tanks (OHF).The vitrified waste forms must be sent for disposal either at the Waste Isolation Pilot Plant (WIPP) or the Nevada Test Site (NTS). Waste loading in the glass is the major factor in determining where the waste will be sent and whether the waste will be remote-handled (RH) or contact-handled (CH). In addition, the waste loading significantly impacts the costs of vitrification operations and transportation to and disposal within the repository.This paper focuses on disposal options for the vitrified Oak Ridge Tank sludge waste as determined by the WIPP (1) and NTS (2) Waste Acceptance Criteria (WAC). The concentrations for both Transuranic (TRU) and beta/gamma radionuclides in the glass waste form will be presented a a function of sludge waste loading. These radionuclide concentrations determine whether the waste forms will be TRU (and therefore disposed of at WIPP) and whether the waste forms will be RH or CH.

Harbour, J.R. [Westinghouse Savannah River Company, AIKEN, SC (United States); Andrews, M.K.

1998-03-01T23:59:59.000Z

342

2014 Annual Planning Summary for the Office of Legacy Management  

Broader source: Energy.gov [DOE]

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2014 and 2015 within the Office of Legacy Management..

343

2013 Annual Planning Summary for the Office of Legacy Management  

Broader source: Energy.gov [DOE]

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2013 and 2014 within the Office of Legacy Management .

344

DOE - Office of Legacy Management -- Fernald  

Office of Legacy Management (LM)

Ohio Ohio Fernald Preserve, Ohio Key Documents and Links Fernald Preserve, Harrison, Ohio, Fact Sheet pdf_icon Draft 2014 Comprehensive Legacy Management and Institutional Controls Plan pdf_icon Comprehensive Legacy Management and Institutional Controls Plan (LMICP): Volume I-Legacy Management Plan pdf_icon Volume II-Institutional Controls Plan pdf_icon Attachment A pdf_icon Attachment B pdf_icon Attachment C pdf_icon Attachment D pdf_icon Attachment E pdf_icon 2012 Site Environmental Report pdf_icon Visitors Center Site Reports Wetland Mitigation Monitoring Report Environmental Monitoring Data - Downloadable Files Fernald Closure Project Website Disclaimer Fernald Citizens Advisory Board Website Disclaimer Fernald Natural Resource Trustee Disclaimer Please be green - do not print these documents unless absolutely necessary

345

Categorical Exclusion Determinations: Legacy Management | Department of  

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

December 22, 2011 December 22, 2011 CX-007752: Categorical Exclusion Determination Routine Activities at the Hallam, Nebraska, Decommissioned Reactor Site CX(s) Applied: B1.3, B1.24, B3.1 Date: 12/22/2011 Location(s): Nebraska Offices(s): Legacy Management December 14, 2011 CX-007441: Categorical Exclusion Determination Routine Actions at the Central Nevada Test Area CX(s) Applied: B1.3, B3.1 Date: 12/14/2011 Location(s): Nevada Offices(s): Legacy Management December 13, 2011 CX-007440: Categorical Exclusion Determination Routine Maintenance Activities at the Grand Junction Regional Airport, Colorado, Calibration Model Facility CX(s) Applied: B1.3, B1.24 Date: 12/13/2011 Location(s): Colorado Offices(s): Legacy Management December 13, 2011 CX-007439: Categorical Exclusion Determination

346

Categorical Exclusion Determinations: Legacy Management | Department of  

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

March 16, 2010 March 16, 2010 CX-001392: Categorical Exclusion Determination Fill in Former Meander Channel near the Naturita, Colorado Processing Site CX(s) Applied: B1.20 Date: 03/16/2010 Location(s): Naturita, Colorado Office(s): Legacy Management March 4, 2010 CX-001115: Categorical Exclusion Determination Hand Auger Samples in East Fork Arroyo, Shiprock, New Mexico Disposal Site CX(s) Applied: B3.1 Date: 03/04/2010 Location(s): Shiprock, New Mexico Office(s): Legacy Management March 2, 2010 CX-001116: Categorical Exclusion Determination Transfer Salmon Property to the Forestry Commission, State of Mississippi CX(s) Applied: B1.25 Date: 03/02/2010 Location(s): Salmon, Mississippi Office(s): Legacy Management February 20, 2010 CX-001000: Categorical Exclusion Determination Maintenance Projects

347

Office of Legacy Management | Department of Energy  

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

Office of Legacy Management Office of Legacy Management Bluewater, New Mexico, Disposal Site Read more Central Nevada Test Area, Nevada Read more Rocky Flats, Colorado, Site Read more Abandoned Uranium Mines Report to Congress Read more Tuba City, Arizona, Disposal Site Read more Announcements DOE has launched a website for the Asset Revitalization Initiative (ARI), a DOE-wide effort to advance the beneficial reuse of its unique and diverse mix of assets, including land, facilities, infrastructure, equipment, technologies, natural resources and a highly skilled workforce. The U.S. Department of Energy Office of Legacy Management has prepared the October-December 2013 Program Update newsletter. Registration is now open for the 2014 National Environmental Justice Conference &Training Program. For more information see our English or

348

Office of Legacy Management | Department of Energy  

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

Office of Legacy Management Office of Legacy Management Bluewater, New Mexico, Disposal Site Read more Central Nevada Test Area, Nevada Read more Rocky Flats, Colorado, Site Read more Abandoned Uranium Mines Report to Congress Read more Tuba City, Arizona, Disposal Site Read more Announcements DOE has launched a website for the Asset Revitalization Initiative (ARI), a DOE-wide effort to advance the beneficial reuse of its unique and diverse mix of assets, including land, facilities, infrastructure, equipment, technologies, natural resources and a highly skilled workforce. The U.S. Department of Energy Office of Legacy Management has prepared the July-September 2013 Program Update newsletter. Registration is now open for the 2014 National Environmental Justice Conference &Training Program. For more information see our English or

349

Legacy Management Contacts | Department of Energy  

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

Legacy Management Contacts Legacy Management Contacts Legacy Management Contacts Title Name Phone Fax LM Director David Geiser (202) 586-7550 (202) 586-8403 Office of Business Operations Director Barbara McNeal Lloyd (202) 586-7550 (202) 586-8403 Benefits Continuity Team Patrick Ring Team Leader (202) 586-1835 (202) 586-1540 Planning, Budget, and Acquisition Team Jane Powell, Team Leader (202) 586-3924 (202) 586-1540 Archives and Information Management Team John Montgomery Team Leader (304) 413-0816 (304) 413-0540 Human Resource Management Patricia Poole-Shirriel Team Leader (202) 586-0402 (202) 586-1540 Administrative Team Teresa Collins Team Leader (202) 586-8259 (202) 586-1540 Office of Site Operations Director Tom Pauling (202) 586-1782 (202) 586-1540 Environmental Team 1

350

Comparison of New and Legacy TATBs  

SciTech Connect (OSTI)

Two newly synthesized versions of the insensitive high explosive (IHE) 1,3,5-triamino-2,4,6-trinitrobenzenes (TATBs) were compared to two legacy explosives currently used by the Department of Energy. Except for thermal analysis, small scale safety tests could not distinguish between the different synthetic routes. Morphologies of new TATBs were less faceted and more spherical. The particle size distribution of one new material was similar to legacy TATBs, but the other was very fine. Densities and submicron structure of the new TATBs were also significantly different from the legacy explosives. Pressed pellets of the new explosives were less dense. Recrystallization from sulfolane improved the density and thermal stability of both new TATBs, though the morphology of the recrystallized TATB was nearly hexagonal platelets.

Hoffman, D M; Willey, T M; Mitchell, A R; DePiero, S C

2007-11-08T23:59:59.000Z

351

Waste inspection tomography (WIT)  

SciTech Connect (OSTI)

The WIT program will provide an inspection system that offers the nuclear waste evaluator a unique combination of tools for regulatory-driven characterization of low-level waste (LLW), transuranic waste (TRU), and mixed waste drums. WIT provides nondestructive, noninvasive, and environmentally safe inspections using X-ray and gamma ray technologies, with reasonable cost and throughput. Two emission imaging techniques will be employed for characterizing materials in waste containers. The first of these is gamma emission tomography, commonly called single-photon emission computed tomography (SPECT). Rather than using an external radiation source, SPECT uses the emission of radioactive materials within the object of interest for imaging. In this case, emission from actual nuclear waste within a container will provide a three-dimensional image of the radioactive substances in the container. The second emission technique will use high-purity germanium detectors for gamma ray spectroscopy. This technique, called nondestructive assay (NDA), can identify the emitting isotopic species and strength. Work in emission tomography and assay of nuclear waste has been undertaken at Lawrence Livermore National Laboratory using a technique called Passive Tomography. Results from a process development unit are presented.

Bernardi, R.T.; Han, K.S.

1994-12-31T23:59:59.000Z

352

COLORADO STATE-WIDE FOREST LEGACY ASSESSMENT OF NEED  

E-Print Network [OSTI]

for property owners. These ten criteria were developed through a survey conducted as part of this AON and for identification of Forest Legacy Areas (FLA's) within the state. Section 1 of this document presents information of which influence Forest Legacy Program implementation. Section 2 presents the Forest Legacy Area (FLA

353

DOE - Office of Legacy Management -- Hallam  

Office of Legacy Management (LM)

Nebraska Nebraska Hallam, Nebraska, Decommissioned Reactor Site A D&D Program Site hallam_map As part of the DOE Defense Decontamination and Decommissioning (D&D) Program, the Office of Legacy Management manages the Hallam Decommissioned Reactor Site and ensures compliance with applicable federal, state, and local environmental protection laws and regulations, executive orders, and internal DOE policies. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and maintenance, records-related activities, and stakeholder support. For more information about the Hallam site, view the fact sheet. Site Documents and Links Contact Us Inspection/Sampling Schedule Hallam Decommissioned Reactor Site Mapping and Monitoring (GEMS)

354

Waste Isolation Pilot Plant Annual Site Enviromental Report for 2008  

SciTech Connect (OSTI)

The purpose of the Waste Isolation Pilot Plant Annual Site Environmental Report for 2008 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to characterize site environmental management performance; summarize environmental occurrences and responses reported during the calendar year; confirm compliance with environmental standards and requirements; highlight significant facility programs and efforts; and describe how compliance and environmental improvement is accomplished through the WIPP Environmental Management System (EMS). The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC), Washington TRU Solutions LLC (WTS), maintain and preserve the environmental resources at the Waste Isolation Pilot Plant (WIPP). DOE Order 231.1A; DOE Order 450.1A, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1A, which requires that DOE facilities submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer. The WIPP Hazardous Waste Facility Permit (HWFP) Number NM4890139088-TSDF (treatment, storage, and disposal facility) further requires that the ASER be provided to the New Mexico Environment Department (NMED). The WIPP mission is to safely dispose of transuranic (TRU) radioactive waste generated by the production of nuclear weapons and other activities related to the national defense of the United States. In 2008, 5,265 cubic meters (m3) of TRU waste were disposed of at the WIPP facility, including 5,216 m3 of contact-handled (CH) TRU waste and 49 m3 of remote-handled (RH) TRU waste. From the first receipt of waste in March 1999 through the end of 2008, 57,873 m3 of TRU waste had been disposed of at the WIPP facility.

Washington Regulatory and Enviromnetal Services

2009-09-21T23:59:59.000Z

355

A new DOE standard for transuranic waste nuclear safety analysis  

SciTech Connect (OSTI)

The DOE Office of Environmental Management (EM) observed through onsite assessments and a review of site-specific lessons learned that transuranic (TRU) waste operations could benefit from standardization of assumptions and approaches used to analyze hazards and select controls. EM collected and compared safety analysis information from DOE sites, including a comparison of the type of TRU waste accidents evaluated and controls selected, as well as specific Airborne Release Fractions (ARFs), Respirable Fractions (RFs), and Damage Ratios (DRs) assumed in accident analyses. This paper recounts the efforts by the DOE and its contractors to bring consistency to the safety analysis process supporting TRU waste operations through an integrated re-engineering effort. EM embarked on a process to re-engineer and standardize TRU safety analysis activities complex-wide. The effort involved DOE headquarters, field offices, and contractors. Five teams were formed to analyze and develop the necessary technical basis for a DOE Technical Standard. The teams looked at general issues including Safety Basis (SB), drum integrity and inspection criteria, hazard controls and analysis, safety analysis review and approval process, and implementation of hazard controls. (authors)

Triay, I.; Chung, D. [U.S. Department of Energy, Washington, D.C. (United States); Woody, J. [Atlas Consulting, Knoxville, TN (United States); Foppe, T. [Carlsbad Technical Assistance Contractor, Carlsbad, NM (United States); Mewhinney, C. [Sandia National Laboratories, Carlsbad, NM (United States); Jennings, S. [Los Alamos National Laboratories, Carlsbad, NM (United States)

2007-07-01T23:59:59.000Z

356

PUBLIC AND REGULATORY ACCEPTANCE OF BLENDING OF RADIOACTIVE WASTE VS DILUTION  

SciTech Connect (OSTI)

On April 21, 2009, the Energy Facilities Contractors Group (EFCOG) Waste Management Working Group (WMWG) provided a recommendation to the Department of Energy's Environmental Management program (DOE-EM) concerning supplemental guidance on blending methodologies to use to classify waste forms to determine if the waste form meets the definition of Transuranic (TRU) Waste or can be classified as Low-Level Waste (LLW). The guidance provides specific examples and methods to allow DOE and its Contractors to properly classify waste forms while reducing the generation of TRU wastes. TRU wastes are much more expensive to characterize at the generator's facilities, ship, and then dispose at the Waste Isolation Pilot Plant (WIPP) than Low-Level Radioactive Waste's disposal. Also the reduction of handling and packaging of LLW is inherently less hazardous to the nuclear workforce. Therefore, it is important to perform the characterization properly, but in a manner that minimizes the generation of TRU wastes if at all possible. In fact, the generation of additional volumes of radioactive wastes under the ARRA programs, this recommendation should improve the cost effective implementation of DOE requirements while properly protecting human health and the environment. This paper will describe how the message of appropriate, less expensive, less hazardous blending of radioactive waste is the 'right' thing to do in many cases, but can be confused with inappropriate 'dilution' that is frowned upon by regulators and stakeholders in the public. A proposal will be made in this paper on how to communicate this very complex and confusing technical issue to regulatory bodies and interested stakeholders to gain understanding and approval of the concept. The results of application of the proposed communication method and attempt to change the regulatory requirements in this area will be discussed including efforts by DOE and the NRC on this very complex subject.

Goldston, W.

2010-11-30T23:59:59.000Z

357

Nuclear waste management technical support in the development of nuclear waste form criteria for the NRC. Task 1. Waste package overview  

SciTech Connect (OSTI)

In this report the current state of waste package development for high level waste, transuranic waste, and spent fuel in the US and abroad has been assessed. Specifically, reviewed are recent and on-going research on various waste forms, container materials and backfills and tentatively identified those which are likely to perform most satisfactorily in the repository environment. Radiation effects on the waste package components have been reviewed and the magnitude of these effects has been identified. Areas requiring further research have been identified. The important variables affecting radionuclide release from the waste package have been described and an evaluation of regulatory criteria for high level waste and spent fuel is presented. Finally, for spent fuel, high level, and TRU waste, components which could be used to construct a waste package having potential to meet NRC performance requirements have been described and identified.

Dayal, R.; Lee, B.S.; Wilke, R.J.; Swyler, K.J.; Soo, P.; Ahn, T.M.; McIntyre, N.S.; Veakis, E.

1982-02-01T23:59:59.000Z

358

LM-04-XXXX Office of Legacy Management  

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

LM-04-XXXX LM-04-XXXX Office of Legacy Management Information and Records Management Transition Guidance March 2004 LM Information and Records Management Transition Guidance March 2004 Contents Page ii Table of Contents Page Executive Summary................................................................................................................... iii 1.0 Introduction and Purpose ................................................................................................... 1 2.0 The Life Cycle of Records ................................................................................................... 3 3.0 Organizational Responsibilities.......................................................................................... 4 3.1 Joint Responsibilities.....................................................................................................

359

Legacy Environmental Solutions | Open Energy Information  

Open Energy Info (EERE)

Legacy Environmental Solutions Legacy Environmental Solutions Jump to: navigation, search Logo: Legacy Environmental Solutions Name Legacy Environmental Solutions Address 9878 Main St Suite 105 Place Woodstock, Georgia Zip 30188 Sector Services, Solar Product AET and eShield Therma Reflective Insulation Year founded 2009 Number of employees 1-10 Phone number 678-919-9236 Website http://www.legacyenvironmental Coordinates 34.0809659°, -84.522443° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":34.0809659,"lon":-84.522443,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

360

In Lewes, a legacy of service  

E-Print Network [OSTI]

In Lewes, a legacy of service to agriculture PAGE 31 Bridgeville's Newton family has deep ties offering programs in Bethany Beach. 7 Cape stars. Rebecca Pepper and Jacki Coveleski have taken their love research. Delaware is the number two producer of lima beans in the U.S., and a research project could put

Firestone, Jeremy

Note: This page contains sample records for the topic "legacy tru waste" 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

The Economic Legacy of Mahmoud Ahmadinejad  

E-Print Network [OSTI]

The Economic Legacy of Mahmoud Ahmadinejad Prof. Nader Habibi Mahmoud Ahmadinejad, Iran's sixth and working-class Iranians. His campaign promises regarding redistributing wealth, enlarging economic, during his two terms in office, Ahmadinejad indeed implemented a number of important economic reforms

Snider, Barry B.

362

WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs |  

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

First Remote-Handled Waste Shipment From Sandia Labs First Remote-Handled Waste Shipment From Sandia Labs WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs December 21, 2011 - 12:00pm Addthis Media Contact Deb Gill www.wipp.energy.gov 575-234-7270 CARLSBAD, N.M. - The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) has received the first of eight planned defense-related remote-handled transuranic (RH-TRU) waste shipments from Sandia National Laboratories (SNL) in Albuquerque. The shipment arrived December 16 for permanent disposal in WIPP's underground repository. DOE National TRU Program Director J.R. Stroble said the shipment is significant to WIPP. "Our goal is to reduce the nation's nuclear waste footprint and we routinely receive shipments from around the country,"

363

Waste and Water Top 2013 Accomplishments for Los Alamos EM Program |  

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

Waste and Water Top 2013 Accomplishments for Los Alamos EM Program Waste and Water Top 2013 Accomplishments for Los Alamos EM Program Waste and Water Top 2013 Accomplishments for Los Alamos EM Program December 24, 2013 - 12:00pm Addthis Unusually heavy rain in early September caused flash flooding in canyons surrounding Los Alamos. Unusually heavy rain in early September caused flash flooding in canyons surrounding Los Alamos. LOS ALAMOS, N.M. - Los Alamos National Laboratory's biggest environmental cleanup accomplishments during 2013 centered around waste and water. The laboratory's 3706 TRU Waste Campaign, an accelerated shipping effort spurred by a massive wildfire in 2011, completed another record-breaking year in 2013, removing a cumulative 1,825 cubic meters of transuranic (TRU) waste and exceeding every previous shipping record.

364

RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES | Department of  

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

RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES October 1, 2010 - 12:00pm Addthis RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES Carlsbad, NM - The recent completion of transuranic (TRU) waste cleanup at Vallecitos Nuclear Center (VNC) and Lawrence Livermore National Laboratory (LLNL) Site 300 in California brings the total number of sites cleared of TRU waste to 17. "Recovery Act funding has made this possible," Carlsbad Field Office (CBFO) Recovery Act Federal Project Director Casey Gadbury said of the VNC and LLNL cleanups funded with about $1.6 million in Recovery Act funds. "The cleanup of these and other small-quantity sites has been and will be accelerated because of the available Recovery Act funds."

365

RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES | Department of  

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

RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES October 1, 2010 - 12:00pm Addthis RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES Carlsbad, NM - The recent completion of transuranic (TRU) waste cleanup at Vallecitos Nuclear Center (VNC) and Lawrence Livermore National Laboratory (LLNL) Site 300 in California brings the total number of sites cleared of TRU waste to 17. "Recovery Act funding has made this possible," Carlsbad Field Office (CBFO) Recovery Act Federal Project Director Casey Gadbury said of the VNC and LLNL cleanups funded with about $1.6 million in Recovery Act funds. "The cleanup of these and other small-quantity sites has been and will be accelerated because of the available Recovery Act funds."

366

TRU TeamWorks 7-7-11  

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

7, 2011 7, 2011 WIPP Quick Facts (As of 7-6-11) 9,730 Shipments received since opening (9,234 CH and 496 RH) 75,969 Cubic meters of waste disposed (75,717 CH and 252 RH) 147,852 Containers disposed in the underground (147,357 CH and 495 RH) DOE completes cleanup at New York, California sites "Cleanup of these two sites represents important and continued progress in the

367

CRAD, Safety Basis- Oak Ridge National Laboratory TRU ALPHA LLWT Project  

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 a November 2003 assessment of the Safety Basis portion of an Operational Readiness Review of the Oak Ridge National Laboratory TRU ALPHA LLWT Project.

368

Safety analysis report for packaging (SARP) of the Oak Ridge National Laboratory. TRU curium shipping container  

SciTech Connect (OSTI)

An analytical evaluation of the Oak Ridge National Laboratory Transuranium (TRU) Curium Shipping Container was made to demonstrate its compliance with the regulations governing offsite shipment of packages containing radioactive material. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the container complies with the applicable regulations.

Box, W.D.; Klima, B.B.; Seagren, R.D.; Shappert, L.B.; Aramayo, G.A.

1980-06-01T23:59:59.000Z

369

CRAD, Conduct of Operations- Oak Ridge National Laboratory TRU ALPHA LLWT Project  

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 a November, 2003 assessment of the Conduct of Operations Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory, TRU ALPHA LLWT Project.

370

THe heartTruTH Heart disease is the #1 killer of  

E-Print Network [OSTI]

THe heartTruTH® #12;Heart disease is the #1 killer of women, but many women do not know they are at risk. The Heart Truth® campaign aims to give women a personal and urgent wake-up call about their risk of heart disease. The red Dress® is the national symbol for women and heart disease awareness introduced

Baker, Chris I.

371

CRAD, Radiological Controls- Oak Ridge National Laboratory TRU ALPHA LLWT Project  

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 a November 2003 assessment of the Radiation Protection Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory TRU ALPHA LLWT Project.

372

CRAD, Quality Assurance- Oak Ridge National Laboratory TRU ALPHA LLWT Project  

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 a November 2003 assessment of the Quality Assurance Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory TRU ALPHA LLWT Project.

373

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

SciTech Connect (OSTI)

This report examines the contributing factors to NDA measurement uncertainty at WRAP The significance of each factor on the TMU is analyzed and a final method is given for determining the TMU for NDA measurements at WRAP. As more data becomes available and WRAP gains in operational experience this report will be reviewed semi annually and updated as necessary.

WILLS, C.E.

2000-01-06T23:59:59.000Z

374

TRU TeamWorks - a biweekly e-newsletter for the Waste Isolation...  

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

airborne contamination at WIPP, high efficiency particulate air (HEPA) filters are a safeguard against release to the atmosphere. Today's HEPA filters evolved from German gas...

375

Avoidable waste management costs  

SciTech Connect (OSTI)

This report describes the activity based costing method used to acquire variable (volume dependent or avoidable) waste management cost data for routine operations at Department of Energy (DOE) facilities. Waste volumes from environmental restoration, facility stabilization activities, and legacy waste were specifically excluded from this effort. A core team consisting of Idaho National Engineering Laboratory, Los Alamos National Laboratory, Rocky Flats Environmental Technology Site, and Oak Ridge Reservation developed and piloted the methodology, which can be used to determine avoidable waste management costs. The method developed to gather information was based on activity based costing, which is a common industrial engineering technique. Sites submitted separate flow diagrams that showed the progression of work from activity to activity for each waste type or treatability group. Each activity on a flow diagram was described in a narrative, which detailed the scope of the activity. Labor and material costs based on a unit quantity of waste being processed were then summed to generate a total cost for that flow diagram. Cross-complex values were calculated by determining a weighted average for each waste type or treatability group based on the volume generated. This study will provide DOE and contractors with a better understanding of waste management processes and their associated costs. Other potential benefits include providing cost data for sites to perform consistent cost/benefit analysis of waste minimization and pollution prevention (WMIN/PP) options identified during pollution prevention opportunity assessments and providing a means for prioritizing and allocating limited resources for WMIN/PP.

Hsu, K.; Burns, M.; Priebe, S.; Robinson, P.

1995-01-01T23:59:59.000Z

376

Development and Implementation of a Comprehensive Program to Deal with Canada's Nuclear Legacy Liabilities  

SciTech Connect (OSTI)

The Government of Canada nuclear legacy liabilities have resulted from 60 years of nuclear research and development (R and D) carried out on behalf of Canada by the National Research Council (1944 to 1952) and Atomic Energy of Canada Limited (AECL, 1952 to present). These liabilities are largely located at AECL research sites, and consist of shutdown research buildings (including several prototype and research reactors), a wide variety of buried and stored wastes, and contaminated lands. The shutdown buildings and contaminated lands need to be safely decommissioned to meet federal regulatory requirements, and long-term solutions need to be developed and implemented for management of the wastes. More than half of the liabilities are the result of Cold War activities during the 1940's, 50's and early 60's. The remaining liabilities stem from R and D for medical isotopes and nuclear reactor technology, as well as national science programs. About 70 percent of the liabilities are located at AECL's Chalk River Laboratories (CRL) in Ontario, and a further 20 percent are located at AECL's shutdown Whiteshell Laboratories in Manitoba. The remaining 10 percent relate largely to three shutdown prototype reactors in Ontario and Quebec, which were key to the developmental stage of Canada's CANDU reactor technology. The inventory of legacy waste includes spent fuel, high-level, intermediate-level and low-level solid and liquid radioactive waste, and wastes (largely contaminated soils) from site clean-up work across Canada. Most of the wastes are in raw, unconditioned form, and limited characterization information is available for the wastes generated in past decades. In many cases unique and potentially costly solutions will be required to recover, handle and process the wastes. In conclusion: the Government of Canada has initiated a program to deal with nuclear legacy liabilities dating back to the Cold War and the birth of nuclear technologies and medicine in Canada. The 5-year start-up phase will address immediate health, safety and environmental priorities, as well as provide the facilities, studies and plans required for subsequent phases. Over the next few years, the long-term strategy will be further developed and refined, and public consultations are planned to inform this work and decisions on the next phase of the strategy.

Brown, Peter; Metcalfe, Douglas; Blanchette, Marcia [Natural Resources Canada, 580 Booth Street, Ottawa, Ontario, K1A 0E4 (Canada); Dolinar, George; Halpenny, Steven; Purdy, Chris; Smith, David; Kupferschmidt, William [Atomic Energy of Canada Limited, Chalk River, Ontario, K0J 1J0 (Canada)

2008-01-15T23:59:59.000Z

377

Transuranic waste characterization sampling and analysis methods manual  

SciTech Connect (OSTI)

The Transuranic Waste Characterization Sampling and Analysis Methods Manual (Methods Manual) provides a unified source of information on the sampling and analytical techniques that enable Department of Energy (DOE) facilities to comply with the requirements established in the current revision of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP) Transuranic (TRU) Waste Characterization Program (the Program). This Methods Manual includes all of the testing, sampling, and analytical methodologies accepted by DOE for use in implementing the Program requirements specified in the QAPP.

NONE

1995-05-01T23:59:59.000Z

378

Buried transuranic wastes at ORNL: Review of past estimates and reconciliation with current data  

SciTech Connect (OSTI)

Inventories of buried (generally meaning disposed of) transuranic (TRU) wastes at Oak Ridge National Laboratory (ORNL) have been estimated for site remediation and waste management planning over a period of about two decades. Estimates were required because of inadequate waste characterization and incomplete disposal records. For a variety of reasons, including changing definitions of TRU wastes, differing objectives for the estimates, and poor historical data, the published results have sometimes been in conflict. The purpose of this review was (1) to attempt to explain both the rationale for and differences among the various estimates, and (2) to update the estimates based on more recent information obtained from waste characterization and from evaluations of ORNL waste data bases and historical records. The latter included information obtained from an expert panel`s review and reconciliation of inconsistencies in data identified during preparation of the ORNL input for the third revision of the Baseline Inventory Report for the Waste Isolation Pilot Plant. The results summarize current understanding of the relationship between past estimates of buried TRU wastes and provide the most up-to-date information on recorded burials thereafter. The limitations of available information on the latter and thus the need for improved waste characterization are highlighted.

Trabalka, J.R.

1997-09-01T23:59:59.000Z

379

Investigations to site a radioactive waste repository in Cumbria: Evidence against proceeding to MRWS Stage 4  

E-Print Network [OSTI]

Investigations to site a radioactive waste repository in Cumbria: Evidence against proceeding to MRWS Stage 4 Radioactive waste repository in Cumbria: Evidence against proceeding to MRWS Stage 4 s the UK radioactive waste legacy comprises difficult material which is complex, of mixed origin

380

DOE - Office of Legacy Management -- Piqua  

Office of Legacy Management (LM)

Ohio Ohio Piqua, Ohio, Decommissioned Reactor Site A D&D Program Site piqua_map As part of the DOE Defense Decontamination and Decommissioning (D&D) Program, the Office of Legacy Management manages the Piqua Decommissioned Reactor Site and ensures compliance with applicable federal, state, and local environmental protection laws and regulations, executive orders, and internal DOE policies. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and maintenance, records-related activities, and stakeholder support. For more information about the Piqua site, view the fact sheet. Site Documents and Links Contact Us Inspection/Sampling Schedule Piqua Decommissioned Reactor Site Mapping and Monitoring (GEMS) Last Updated: 6/13/2011

Note: This page contains sample records for the topic "legacy tru waste" 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

DOE - Office of Legacy Management -- Bonus  

Office of Legacy Management (LM)

Puerto Rico Puerto Rico Boiling Nuclear Superheater (BONUS), Puerto Rico, Decommissioned Reactor Site La Antiqua Central Nuclear de Aqua Hirviente Sobrecalentada Reactor Fuera de Servico Activo A D&D Program Site bonus_map3 As part of the DOE Defense Decontamination and Decommissioning (D&D) Program, the Office of Legacy Management manages the Boiling Nuclear Superheater (BONUS) Decommissioned Reactor Site and ensures compliance with applicable federal, state, and local environmental protection laws and regulations, executive orders, and internal DOE policies. The site transferred to the Office of Legacy Management in 2004 and requires routine inspection and maintenance, records-related activities, and stakeholder support. For more information about the BONUS site, view the fact sheet.

382

Categorical Exclusion Determinations: Legacy Management | Department of  

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

May 5, 2011 May 5, 2011 CX-005883: Categorical Exclusion Determination Routine Monitoring, Maintenance, and Administrative Actions at the Salmon, Mississippi Site CX(s) Applied: A8, A9, A11, B3.1 Date: 05/05/2011 Location(s): Salmon, Mississippi Office(s): Legacy Management May 4, 2011 CX-005849: Categorical Exclusion Determination Routine Monitoring, Maintenance, and Administrative Actions at the Gunnison Disposal and Former Processing, Colorado, Sites CX(s) Applied: B1.3, B3.1 Date: 05/04/2011 Location(s): Gunnison, Colorado Office(s): Legacy Management April 14, 2011 CX-005682: Categorical Exclusion Determination Routine Monitoring, Maintenance, Research, General Site, and Administrative Actions at the Shiprock, New Mexico, Disposal Site CX(s) Applied: A1, A8, B1.3, B1.11, B1.20, B3.1

383

Colorado Environmental Coalition v. Office of Legacy Management, Civil  

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

Colorado Environmental Coalition v. Office of Legacy Management, Colorado Environmental Coalition v. Office of Legacy Management, Civil Action No. 08-cv-01624 (October 18, 2011) Colorado Environmental Coalition v. Office of Legacy Management, Civil Action No. 08-cv-01624 (October 18, 2011) U.S. District Court's Order of October 18, 2011, in Colorado Environmental Coalition v. Office of Legacy Management, Civil Action No. 08-cv-01624 (D. Colo.). The Court has issued the injunctive relief described on pages 51-52 of the Order. U.S. District Court's Order of October 18, 2011, in Colorado Environmental Coalition v. Office of Legacy Management, Civil Action No. 08-cv-01624 (D. Colo.). More Documents & Publications Colorado Environmental Coalition v. Office of Legacy Management, Civil Action No. 08-cv-01624 (February 27, 2012)

384

Colorado Environmental Coalition v. Office of Legacy Management, Civil  

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

Colorado Environmental Coalition v. Office of Legacy Management, Colorado Environmental Coalition v. Office of Legacy Management, Civil Action No. 08-cv-01624 (February 27, 2012) Colorado Environmental Coalition v. Office of Legacy Management, Civil Action No. 08-cv-01624 (February 27, 2012) U.S. District Court's Order of February 27, 2012, in Colorado Environmental Coalition v. Office of Legacy Management, Civil Action No. 08-cv-01624 (D. Colo.). U.S. District Court's Order of February 27, 2012, in Colorado Environmental Coalition v. Office of Legacy Management, Civil Action No. 08-cv-01624 (D. Colo.). More Documents & Publications Colorado Environmental Coalition v. Office of Legacy Management, Civil Action No. 08-cv-01624 (October 18, 2011) LG Electronics v. DOE - Defendants' Brief in Opposition to Plaintiff LG

385

Energy Department Awards Small Business Contract for Legacy Management Work  

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

Small Business Contract for Legacy Small Business Contract for Legacy Management Work to S.M. Stoller Corporation Energy Department Awards Small Business Contract for Legacy Management Work to S.M. Stoller Corporation July 2, 2007 - 2:54pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced the award of a prime contract for the Department's Office of Legacy Management (LM) Support Services work to S.M. Stoller Corporation for surveillance and maintenance and technical support at more than 100 of DOE's legacy sites. The three-year contract, with one two-year extension option for a total of five years, is valued at approximately $170 million over the life of the contract and is one of the largest 100% small business contracts within DOE. The contract includes responsibility for legacy sites that have been

386

Environmental impact statement for initiation of transuranic waste disposal at the waste isolation pilot plant  

SciTech Connect (OSTI)

WIPP`s long-standing mission is to demonstrate the safe disposal of TRU waste from US defense activities. In 1980, to comply with NEPA, US DOE completed its first environmental impact statement (EIS) which compared impacts of alternatives for TRU waste disposal. Based on this 1980 analysis, DOE decided to construct WIPP in 1981. In a 1990 decision based on examination of alternatives in a 1990 Supplemental EIS, DOE decided to continue WIPP development by proceeding with a testing program to examine WIPP`s suitability as a TRU waste repository. Now, as DOE`s Carlsbad Area Office (CAO) attempts to complete its regulatory obligations to begin WIPP disposal operations, CAO is developing WIPP`s second supplemental EIS (SEIS-II). To complete the SEIS-II, CAO will have to meet a number of challenges. This paper explores both the past and present EISs prepared to evaluate the suitability of WIPP. The challenges in completing an objective comparison of alternatives, while also finalizing other critical-path compliance documents, controlling costs, and keeping stakeholders involved during the decision-making process are addressed.

Johnson, H.E. [U.S. Dept. of Energy, Carlsbad, NM (United States) Carlsbad Area Office; Whatley, M.E. [Westinghouse Electric Corp., Carlsbad, NM (United States). Waste Isolation Div.

1996-08-01T23:59:59.000Z

387

DOE Seeks Proposals for Management of New Mexico Waste Isolation Pilot  

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

Proposals for Management of New Mexico Waste Isolation Proposals for Management of New Mexico Waste Isolation Pilot Plant DOE Seeks Proposals for Management of New Mexico Waste Isolation Pilot Plant June 20, 2011 - 12:00pm Addthis Media Contact Bill Taylor 513-246-0539 william.taylor@emcbc.doe.gov Cincinnati --The U.S. Department of Energy (DOE) today issued a Final Request for Proposal for management and operations of the Waste Isolation Pilot Plan (WIPP) located in Carlsbad, New Mexico. The successful contractor will manage the WIPP site and DOE's National Transuranic Waste (TRU) program. DOE anticipates awarding a competitive, cost-plus-award-fee contract with an approximate value of $135 million per year, for five years. There will be an option to extend the contract for five additional years. The overall mission of the WIPP and the National TRU program is to protect

388

Microsoft Word - Los Alamos National Laboratory ships remote-handled transuranic waste to WIPP  

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

Los Alamos National Laboratory Ships Remote-Handled Los Alamos National Laboratory Ships Remote-Handled Transuranic Waste to WIPP CARLSBAD, N.M., June 3, 2009 - Cleanup of the nation's defense-related transuranic (TRU) waste has reached an important milestone. Today, the first shipment of remote-handled (RH) TRU waste from Los Alamos National Laboratory (LANL) in New Mexico arrived safely at the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) in the southeast corner of the state. "Shipping this waste to WIPP is important for our national cleanup mission, but this event is especially important for New Mexicans," said DOE Carlsbad Field Office Manager Dave Moody. "It's great to see progress being made right here in our own state." WIPP's mission includes the safe disposal of two types of defense-related

389

Characterization of past and present solid waste streams from the plutonium finishing plant  

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 (WRAP) Facility, and shipped to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico for final disposal. Over 50% of the TRU waste to be retrieved for shipment to the WIPP has been generated at the Plutonium Finishing Plant (PFP), also known as the Plutonium Processing and Storage Facility and Z Plant. The purpose of this report is to characterize the radioactive solid wastes generated by the PFP since its construction in 1947 using process knowledge, existing records, and history-obtained from interviews. The PFP is currently operated by Westinghouse Hanford Company (WHC) for the US Department of Energy (DOE).

Duncan, D R; Mayancsik, B A [Westinghouse Hanford Co., Richland, WA (United States)] [Westinghouse Hanford Co., Richland, WA (United States); Pottmeyer, J A; Vejvoda, E J; Reddick, J A; Sheldon, K M; Weyns, M I [Los Alamos Technical Associates, Kennewick, WA (United States)] [Los Alamos Technical Associates, Kennewick, WA (United States)

1993-02-01T23:59:59.000Z

390

Enhanced Tank Waste Strategy Update  

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

Reduce the life-cycle costs and accelerate the cleanup of the Cold War environmental legacy www.em.doe.gov safety performance cleanup closure E M Environmental Management 1 cleanup of the Cold War environmental legacy Shirley J. Olinger Associate Principal Deputy for Corporate Operations EMAB Presentation June 23, 2011 EM Priorities: Activities to maintain a safe, secure, and compliant posture in the EM complex Radioactive tank waste stabilization, treatment, and disposal Spent (used) nuclear fuel storage, receipt, and disposition "To-Go Life-Cycle Costs" ($185B - $218B as of the FY 2012 Request) Programmatic support activities* 10% Radioactive tank waste stabilization, treatment and disposal 38% Excess facilities decontamination and decommissioning

391

Legacy Management Work Progresses on Defense-Related Uranium...  

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

Most recently, LM visited 84 defense-related legacy uranium mine sites located within 11 uranium mining districts in 6 western states. At these sites, photographs and global...

392

DOE - Office of Legacy Management -- Pinellas Plant General Electric...  

Office of Legacy Management (LM)

Protection FACT SHEET Location of the Pinellas County, Florida, Site Office of Legacy Management Pinellas County, Florida, Site This fact sheet provides information about...

393

DOE - Office of Legacy Management -- Shiprock Mill Site - NM...  

Office of Legacy Management (LM)

Evaluation of the Trench 2 Groundwater Remediation System at the Shiprock, New Mexico, Legacy Management Site March 2009 Supplement to the Baseline Risk Assessment of Ground Water...

394

Energy Department Awards Small Business Contract for Legacy Management...  

Energy Savers [EERE]

the award of a prime contract for the Department's Office of Legacy Management (LM) Support Services work to S.M. Stoller Corporation for surveillance and maintenance and...

395

DOE - Office of Legacy Management -- Hallam Nuclear Power Facility...  

Office of Legacy Management (LM)

was successfully conducted on April 29, 2009. The inspectio FACT SHEET Office of Legacy Management Location of the Hallam Decommissioned Reactor Hallam, Nebraska,...

396

DOE - Office of Legacy Management -- Canonsburg Industrial Park...  

Office of Legacy Management (LM)

Package-October 2008 Groundwater and Surface Water Sampling FACT SHEET Office of Legacy Management Canonsburg, Pennsylvania, Disposal Site Project Plan: Ground Water...

397

DOE - Office of Legacy Management -- Ambrosia Lake Mill Site...  

Office of Legacy Management (LM)

Surveillance Plan (LTSP) for the Ambrosia Lake, New Mexico Site. FACT SHEET Office of Legacy Management Ambrosia Lake, New Mexico, Disposal Site This fact sheet provides...

398

DOE - Office of Legacy Management -- BurrisPark_FUSRAP  

Office of Legacy Management (LM)

by UC-Berkeley require no further remediation. Final Conditions- The DOE Office of Legacy Management assumed maintenance-only responsibility for the remaining contamination in...

399

DOE - Office of Legacy Management -- Maybell Mill Site - CO 0...  

Office of Legacy Management (LM)

Colorado (UMTRCA Title I) Disposal Site Moffat County, Colorado April 2008 Office of Legacy Management Historical documents may contain links which are no longer valid or to...

400

DOE/EIS-0200-SA-01: Supplement Analysis and Determination for the Proposed Characterization for Disposal of Contact-Handled Transuranic Waste at the Waste Isolation Pilot Plant (WIPP) (12/00)  

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

CH-TRU waste may be shipped to WIPP in drums, standard waste boxes, or drum overpacks; 1,250 cubic meters is the CH-TRU waste may be shipped to WIPP in drums, standard waste boxes, or drum overpacks; 1,250 cubic meters is the equivalent of about 6,000 drums (4.8 drums/cubic meter). 1 Supplement Analysis and Determination for the Proposed Characterization for Disposal of Contact-Handled Transuranic Waste at the Waste Isolation Pilot Plant (WIPP) (DOE/EIS- 0200-SA-01) 1.0 Introduction In the Record of Decision for the Department of Energy's Waste Isolation Pilot Plant Disposal Phase Supplemental Environmental Impact Statement (63 Fed. Reg. 3623, January 23, 1998), the Department of Energy (DOE) decided to dispose of transuranic (TRU) waste at WIPP after preparing it to meet WIPP's Waste Acceptance Criteria (WAC). In the Record of Decision for the Department of Energy's Waste Management Program: Treatment and Storage of

Note: This page contains sample records for the topic "legacy tru waste" 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.


401

DOE/EIS-0200-SA-01: Supplement Analysis and Determination for the Proposed Characterization for Disposal of Contact-Handled Transuranic Waste at the Waste Isolation Pilot Plant (WIPP) (12/00)  

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

CH-TRU waste may be shipped to WIPP in drums, standard waste boxes, or drum overpacks; 1,250 cubic meters is the CH-TRU waste may be shipped to WIPP in drums, standard waste boxes, or drum overpacks; 1,250 cubic meters is the equivalent of about 6,000 drums (4.8 drums/cubic meter). 1 Supplement Analysis and Determination for the Proposed Characterization for Disposal of Contact-Handled Transuranic Waste at the Waste Isolation Pilot Plant (WIPP) (DOE/EIS- 0200-SA-01) 1.0 Introduction In the Record of Decision for the Department of Energy's Waste Isolation Pilot Plant Disposal Phase Supplemental Environmental Impact Statement (63 Fed. Reg. 3623, January 23, 1998), the Department of Energy (DOE) decided to dispose of transuranic (TRU) waste at WIPP after preparing it to meet WIPP's Waste Acceptance Criteria (WAC). In the Record of Decision for the Department of Energy's Waste Management Program: Treatment and Storage of

402

Preliminary Notice of Violation, Washington TRU Solutions, LLC - EA-2005-08  

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

5-08 5-08 Preliminary Notice of Violation, Washington TRU Solutions, LLC - EA-2005-08 December 22, 2005 Preliminary Notice of Violation issued to Washington TRU Solutions, LLC, related to Radiological Uptakes at the Mobile Visual Examination and Repackaging Facility at Lawrence Livermore National Laboratory This letter refers to the Department of Energy's (DOE) Office of Price-Anderson Enforcement's (OE) investigation of the Mobile Visual Examination and Repackaging Facility (MOVER) radiological uptakes that occurred from April to August 2004 at the Lawrence Livermore National Laboratory (LLNL). An investigation summary report was issued to you on September 24, 2005. An Enforcement Conference was held on October 26, 2005, in Germantown, Maryland, with you and members of your staff to discuss the

403

Radionuclide inventory for the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

This report updates the information previously submitted in the draft report DOE/WIPP 88-005, Radionuclide Source Term for the WIPP, dated 1987 (reference 1). The information in this report provides the projected radionuclide inventory at the WIPP based on the projected waste receipts through the year 2013. The information is based on the 1991 TRU Program Data submittals for the Integrated Data Base (DOE/RW-0006, Rev. 7) from each of the DOE sites generating or storing TRU waste for shipment to the WIPP. The data is based on existing characterization data on the waste in interim storage, waste estimates based on projected programs during the 1991 through 2013 time period, projected treatment processes required to meet WIPP Waste Acceptance Criteria (WAC), and a projection of the waste that will be declared low level waste when it is assayed as part of the certification program for waste shipments to WIPP. This data will serve as a standard reference for WIPP programs requiring radionuclide data, including safety programs, performance assessment, and regulatory compliance. These projections will continue to be periodically updated as the waste data estimates are refined by the generator sites as they participate in the annual update of the Integrated Data Base (IDB).

Not Available

1991-12-31T23:59:59.000Z

404

Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory TRU Californium Shipping Container  

SciTech Connect (OSTI)

An analytical evaluation of the Oak Ridge National Laboratory TRU Californium Shipping Container was made in order to demonstrate its compliance with the regulations governing off-site shipment of packages that contain radioactive material. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of this evaluation demonstrate that the container complies with the applicable regulations.

Box, W.D.; Shappert, L.B.; Seagren, R.D.; Klima, B.B.; Jurgensen, M.C.; Hammond, C.R.; Watson, C.D.

1980-01-01T23:59:59.000Z

405

E-Print Network 3.0 - arabia environmental legacy Sample Search...  

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

by inherited legacies on environmental... : Evidences from Deforestation Sebastien Marchand Abstract This paper investigates if inherited legacies (i... .e legal origins on law...

406

Annual Transuranic Waste Inventory Report - 2013  

Office of Environmental Management (EM)

ANNUAL TRANSURANIC WASTE INVENTORY REPORT - 2013 (Data Cutoff Date 12/31/2012) DOE/TRU-13-3425 Revision 0 October 2013 U.S. Department of Energy Carlsbad Field Office DOE/TRU-13-3425 Page 1 of 392 This document has been submitted as required to: U.S. Department of Energy Office of Scientific and Technical Information PO Box 62 Oak Ridge, TN 37831 Phone: (865) 576-8401 Additional information about this document may be obtained by calling 1-800-336-9477. Unlimited, publicly available full-text scientific and technical reports produced since 1991 are available online at Information Bridge (www.osti.gov/bridge). U.S. Department of Energy and its contractors may obtain full-text reports produced prior to 1991 in paper form, for a processing fee, from:

407

Assessment of alternatives for management of ORNL retrievable transuranic waste. Nuclear Waste Program: transuranic waste (Activity No. AR 05 15 15 0; ONL-WT04)  

SciTech Connect (OSTI)

Since 1970, solid waste with TRU or U-233 contamination in excess of 10 ..mu..Ci per kilogram of waste has been stored in a retrievable fashion at ORNL, such as in ss drums, concrete casks, and ss-lined wells. This report describes the results of a study performed to identify and evaluate alternatives for management of this waste and of the additional waste projected to be stored through 1995. The study was limited to consideration of the following basic strategies: Strategy 1: Leave waste in place as is; Strategy 2: Improve waste confinement; and Strategy 3: Retrieve waste and process for shipment to a Federal repository. Seven alternatives were identified and evaluated, one each for Strategies 1 and 2 and five for Strategy 3. Each alternative was evaluated from the standpoint of technical feasibility, cost, radiological risk and impact, regulatory factors and nonradiological environmental impact.

Not Available

1980-10-01T23:59:59.000Z

408

EIS-0113: Disposal of Hanford Defense High-Level, Transuranic and Tank Waste, Hanford Site, Richland, Washington  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy developed this EIS to examine the potential environmental impacts of final disposal options for legacy and future radioactive defense wastes stored at the Hanford Site.

409

Final environmental impact statement. Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

In accordance with the National Environmental Policy Act (NEPA) of 1969, the US Department of Energy (DOE) has prepared this document as environmental input to future decisions regarding the Waste Isolation Pilot Plant (WIPP), which would include the disposal of transuranic waste, as currently authorized. The alternatives covered in this document are the following: (1) Continue storing transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) as it is now or with improved confinement. (2) Proceed with WIPP at the Los Medanos site in southeastern New Mexico, as currently authorized. (3) Dispose of TRU waste in the first available repository for high-level waste. The Los Medanos site would be investigated for its potential suitability as a candidate site. This is administration policy and is the alternative preferred by the DOE. (4) Delay the WIPP to allow other candidate sites to be evaluated for TRU-waste disposal. This environmental impact statement is arranged in the following manner: Chapter 1 is an overall summary of the analysis contained in the document. Chapters 2 and 4 set forth the objectives of the national waste-management program and analyze the full spectrum of reasonable alternatives for meeting these objectives, including the WIPP. Chapter 5 presents the interim waste-acceptance criteria and waste-form alternatives for the WIPP. Chapters 6 through 13 provide a detailed description and environmental analysis of the WIPP repository and its site. Chapter 14 describes the permits and approvals necessary for the WIPP and the interactions that have taken place with Federal, State, and local authorities, and with the general public in connection with the repository. Chapter 15 analyzes the many comments received on the DEIS and tells what has been done in this FEIS in response. The appendices contain data and discussions in support of the material in the text.

Not Available

1980-10-01T23:59:59.000Z

410

Compliance status report for the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The US Department of Energy (DOE) is responsible for the disposition of transuranic (TRU) waste generated through national defense-related activities. Approximately 53,700 m{sup 2} of these wastes have been generated and are currently stored at government defense installations across the country. The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico, has been sited and constructed to meet the criteria established by the scientific and regulatory community for the safe, long-term disposal of TRU and TRU-mixed wastes. This Compliance Status Report (CSR) provides an assessment of the progress of the WIPP Program toward compliance with long-term disposal regulations, set forth in Title 40 CFR 191 (EPA, 1993a), Subparts B and C, and Title 40 CFR {section}268.6 (EPA, 1993b), in order to focus on-going and future experimental and engineering activities. The CSR attempts to identify issues associated with the performance of the WIPP as a long-term repository and to focus on the resolution of these issues. This report will serve as a tool to focus project resources on the areas necessary to ensure complete, accurate, and timely submittal of the compliance application. This document is not intended to constitute a statement of compliance or a demonstration of compliance.

Not Available

1994-03-31T23:59:59.000Z

411

DOE/EIS-0305-D; Draft Environmental Impact Statement for Treating Transuranic/Alpha Low-Level Waste at the Oak Ridge National Laboratory Oak Ridge, Tennessee (February 2000)  

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

05-D 05-D DRAFT ENVIRONMENTAL IMPACT STATEMENT (DEIS) FOR TREATING TRANSURANIC (TRU)/ALPHA LOW-LEVEL WASTE AT THE OAK RIDGE NATIONAL LABORATORY OAK RIDGE, TENNESSEE February 2000 TRU Waste Treatment Project, DRAFT Environmental Impact Statement COVER SHEET RESPONSIBLE AGENCY: U.S. Department of Energy (DOE) TITLE: Draft Environmental Impact Statement (EIS) for Treating Transuranic (TRU)/Alpha Low-Level Waste at the Oak Ridge National Laboratory, Oak Ridge, Tennessee CONTACT: For further information on this document, write or call: Dr. Clayton Gist, Waste Management Integration Team Leader U.S. Department of Energy Oak Ridge Operations 55 Jefferson Avenue P. O. Box 2001 Oak Ridge, TN 37831 Telephone: (865) 241-3498 * Facsimile: (865) 576-5333 * E-Mail: gistcs@oro.doe.gov

412

Performance demonstration program plan for RCRA constituent analysis of solidified wastes  

SciTech Connect (OSTI)

Performance Demonstration Programs (PDPS) are designed to help ensure compliance with the Quality Assurance Objectives (QAOs) for the Waste Isolation Pilot Plant (WIPP). The PDPs are intended for use by the Department of Energy (DOE) Carlsbad Area Office (CAO) to assess and approve the laboratories and other measurement facilities supplying services for the characterization of WIPP TRU waste. The PDPs may also be used by CAO in qualifying laboratories proposing to supply additional analytical services that are required for other than waste characterization, such as WIPP site operations. The purpose of this PDP is to test laboratory performance for the analysis of solidified waste samples for TRU waste characterization. This performance will be demonstrated by the successful analysis of blind audit samples of simulated, solidified TRU waste according to the criteria established in this plan. Blind audit samples (hereinafter referred to as PDP samples) will be used as an independent means to assess laboratory performance regarding compliance with the QAOs. The concentration of analytes in the PDP samples will address levels of regulatory concern and will encompass the range of concentrations anticipated in actual waste characterization samples. Analyses that are required by the WIPP to demonstrate compliance with various regulatory requirements and which are included in the PDP must be performed by laboratories that demonstrate acceptable performance in the PDP. These analyses are referred to as WIPP analyses and the samples on which they are performed are referred to as WIPP samples for the balance of this document.

NONE

1995-06-01T23:59:59.000Z

413

Lister at home and abroad: a continuing legacy  

Science Journals Connector (OSTI)

...Hurwitz and Marguerite Dupree Lister at home and abroad: a continuing legacy M. Anne...imperial sentiment, and his legacy is seen at home and abroad through successive generations...Some might travel no farther than their home towns in Scotland and England, but others...

2013-01-01T23:59:59.000Z

414

REMOVAL OF LEGACY PLUTONIUM MATERIALS FROM SWEDEN  

SciTech Connect (OSTI)

U.S. Department of Energys National Nuclear Security Administration (NNSA) Office of Global Threat Reduction (GTRI) recently removed legacy plutonium materials from Sweden in collaboration with AB SVAFO, Sweden. This paper details the activities undertaken through the U.S. re