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Accelerating Cleanup: Focus on 2006. Discussion draft

Description: This executive summary addresses the activities associated with the National Transuranic (TRU) Program managed by the Carlsbad Area Office (CAO). The CAO programmatically reports to the Assistant Secretary for Environmental Management and receives administrative support through the Albuquerque Operations Office. The mission of the Carlsbad Area Office (CAO) is to protect human health and the environment by opening and operating the Waste Isolation Pilot Plant for site disposal of TRU waste and by establishing an effective system for management of TRU waste from generation to disposal. It includes personnel assigned to the CAO, the Waste Isolation Pilot Plant (WIPP) site operations, and other activities associated with the National TRU Program. The CAO develops and directs implementation of the program, while the DOE Headquarters establishes policy and guidelines. The CAO assesses compliance with the program guidance, as well as the commonality of activities and assumptions among all the sites. Since the development of the February 28, 1997, database used to develop this Discussion Draft, the opening of the WIPP facility for receipt of Contact Handled waste has been delayed from November 1997 to May 1998. This slippage is significant enough to require a change in the milestones and volumes included in the documents to be reviewed by our stakeholders. Changes have been incorporated into this Discussion Draft and its supporting Project Baseline Summaries (PBSs).
Date: June 1, 1997
Partner: UNT Libraries Government Documents Department

Modeling of Human Intrusion Scenarios at the Waste Isolation Pilot Plant

Description: The Waste Isolation Pilot Plant is a mined, geologic repository designed for permanent disposal of transuranic waste. The facility is owned by the United States Department of Energy, and licensed for operations by the Environmental Protection Agency. Compliance with license requirements dictates that the repository must comply with regulatory stipulations that performance assessment calculations include the effects of resource exploitation on probable releases. Scenarios for these releases incorporate inadvertent penetration of the repository by an exploratory drilling operation. This paper presents the scenarios and models used to predict releases from the repository to the biosphere during. an inadvertent intrusion into the waste disposal regions. A summary of model results and conclusions is also presented.
Date: December 4, 1998
Creator: Gross, M.B.; Hansen, F.D.; Knowles, M.K.; Larson, K.W. & Thompson, T.W.
Partner: UNT Libraries Government Documents Department

Designation of waste receipt assay and storage portions of WRAP as a limited control facility

Description: This evaluation designates the waste receipt, storage, assay, and shiping portions of WRAP I as a Limited Control Facility. The technical basis for this designation comes from CSERs in other facilities The limits and controls for this CSER come from other facilities. This is deemed sufficient, since any fissile material being received at WRAP I, will come from those facilities, and as long as the limits for limited control are maintained, the areas considered in this CSER can be designated appropriately.
Date: September 20, 1996
Creator: Ruben, R.H.
Partner: UNT Libraries Government Documents Department

Hydraulic fracturing tests in anhydrite interbeds in the WIPP, Marker Beds 139 and 140

Description: Hydraulic fracturing tests were integrated with hydrologic tests to estimate the conditions under which gas pressure in the disposal rooms in the Waste Isolation Pilot Plant, Carlsbad, NM (WIPP) will initiate and advance fracturing in nearby anhydrite interbeds. The measurements were made in two marker beds in the Salado formation, MB139 and MB140, to explore the consequences of existing excavations for the extrapolation of results to undisturbed ground. The interpretation of these measurements is based on the pressure-time records in two injection boreholes and several nearby hydrologic observation holes. Data interpretations were aided by post-test borehole video surveys of fracture traces that were made visible by ultraviolet illumination of fluorescent dye in the hydraulic fracturing fluid. The conclusions of this report relate to the upper- and lower-bound gas pressures in the WIPP, the paths of hydraulically and gas-driven fractures in MB139 and MB140, the stress states in MB139 and MB140, and the probable in situ stress states in these interbeds in undisturbed ground far away from the WIPP.
Date: May 1, 1997
Creator: Wawersik, W. R.; Carlson, L. W.; Henfling, J. A.; Borns, D. J.; Howard, C. L. & Roberts, R. M.
Partner: UNT Libraries Government Documents Department

Stability evaluation of the Panel 1 rooms and the E140 drift at WIPP

Description: WIPP, intended for underground permanent disposal of defense transuranic waste, is located 40 km east of Carlsbad at a depth of 655 m in the salt beds of the 600-m thick Permian Salado Formation. It will consist of 56 ``rooms`` each 91.5 m long, 10 m wide, and 4 m high, grouped in 8 ``panels`` of 7 rooms each. About 7.5 km of access drifts will also be provided. Excavation began in 1982 and surface/access/test facilities and one panel were completed by 1988, many years before it could be used. Current plans are to start emplacing waste in WIPP in 1998 and continue for 35 years. The north- south drift E140 is the widest (25 ft) of the four main north-south drifts and is the main north-south passage. Plans to conduct experiments with waste in 1993 were abandoned, and the plan now is to use panel 1 for permanent disposal of waste starting in 1998. The stability evaluation resulted in the conclusion that, while it would be possible to safely use portions of panel 1 for waste emplacement, it would be best to abandon panel 1 and mine a new panel after the decision has been made to use WIPP as a repository and the necessary permits obtained.
Date: August 1, 1996
Creator: Maleki, H. & Chaturvedi, L.
Partner: UNT Libraries Government Documents Department

Guidebook for performance assessment parameters used in the Waste Isolation Pilot Plant compliance certification application. Volume 2: Appendices

Description: The Waste Isolation Pilot Plant (WIPP) Compliance Certification Application (CCA) Performance Assessment (PA) Parameter Database and its ties to supporting information evolved over the course of two years. When the CCA was submitted to the Environmental Protection Agency (EPA) in October 1996, information such as identification of parameter value or distribution source was documented using processes established by Sandia National Laboratories WIPP Quality Assurance Procedures. Reviewers later requested additional supporting documentation, links to supporting information, and/or clarification for many parameters. This guidebook is designed to document a pathway through the complex parameter process and help delineate flow paths to supporting information for all WIPP CCA parameters. In addition, this report is an aid for understanding how model parameters used in the WIPP CCA were developed and qualified. To trace the source information for a particular parameter, a dual-route system was established. The first route uses information from the Parameter Records package as it existed when the CCA calculations were run. The second route leads from the EPA Parameter Database to additional supporting information.
Date: June 1, 1998
Creator: Howarth, S.M.; Martell, M.A.; Weiner, R. & Lattier, C.
Partner: UNT Libraries Government Documents Department

Sealing concepts for the Waste Isolation Pilot Plant (WIPP) site

Description: The Waste Isolation Pilot Plant (WIPP) facility is proposed for development in the southeast portion of the State of New Mexico. The proposed horizon is in bedded salt located approximately 2150 ft below the surface. The purpose of the WIPP is to provide an R&D facility to demonstrate the safe disposal of radioactive wastes resulting from defense activities of the United States. As such, it will include a disposal demonstration for transuranic (TRU) wastes and an experimental area to address issues associated with disposal of defense high level wastes (DHLW) in bedded salt. All DHLW used in the experiments are planned for retrieval at the termination of testing; the TRU waste can be permanently disposed of at the site after the pilot phase is complete. This report addresses only the Plugging and Sealing program, which will result in an adequate and acceptable technology for final sealing and decommissioning of the facility at the WIPP site. The actual plugging operations are intended to be conducted on a commercial industrial basis through contracts issued by the DOE. This report is one in a series that is based on a technical program of modeling, laboratory materials testing and field demonstration which will provide a defensible basis for the actual plugging operations to be conducted by the DOE for final closure of the facility.
Date: September 1, 1982
Creator: Christensen, C.L.; Gulick, C.W. & Lambert, S.J.
Partner: UNT Libraries Government Documents Department

Waste Isolation Pilot Plant borehole data

Description: Data pertaining to all the surface boreholes used at the WIPP site for site characterization hydrological testing and resource evaluation exist in numerous source documents. This project was initiated to develop a comprehensive data base that would include the data on all WIPP related surface boreholes from the Atomic Energy Commission, Waste Isolation Pilot Plant Energy Research and Development Administration, Department of Energy, and Hydrologic Test Borehole Programs. The data compiled from each borehole includes: operator, permit number, location, total depth, type of well, driller, drilling record, casing record, plugging schedule, and stratigraphic summary. There are six groups of boreholes contained in this data base, they are as follows: Commercially Drilled Potash Boreholes, Energy Department Wells, Geologic Exploration Boreholes, Hydrologic Test Boreholes, Potash Boreholes, and Subsurface Exploration Boreholes. There were numerous references which contained borehole data. In some cases the data found in one document was inconsistent with data in another document. In order to ensure consistency and accuracy in the data base, the same references were used for as many of the boreholes as possible. For example, all elevations and locations were taken from Compilation and Comparison of Test-Hole Location Surveys in the Vicinity of the WIPP Site. SAND 88-1065, Table 3-5. There are some sections where a data field is left blank. In this case, the information was either not applicable or was unavailable.
Date: April 1, 1995
Partner: UNT Libraries Government Documents Department

Column Experiments for Radionuclide Adsorption Studies of the Culebra Dolomite: Retardation Parameter Estimation for Non-Eluted Actinide Species

Description: The U.S. Department of Energy (DOE) has been developing a nuclear waste disposal facility, the Waste Isolation Pilot Plant (WIPP), located approximately 42 km east of Carlsbad, New Mexico. The WIPP is designed to demonstrate the safe disposal of transuranic wastes produced by the defense nuclear-weapons program. Performance assessment analyses (U.S. DOE, 1996) indicate that human intrusion by inadvertent and intermittent drilling for resources provide the only credible mechanisms for significant releases of radionuclides horn the disposal system. These releases may occur by five mechanisms: (1) cuttings, (2) cavings, (3) spallings, (4) direct brine releases, and (5) long-term brine releases. The first four mechanisms could result in immediate release of contaminant to the accessible environment. For the last mechanism, migration pathways through the permeable layers of rock above the Salado are important, and major emphasis is placed on the Culebra Member of the Rustler Formation because this is the most transmissive geologic layer in the disposal system. For reasons of initial quantity, half-life, and specific radioactivity, certain isotopes of Th, U, Am, and Pu would dominate calculated releases from the WIPP. In order to help quanti~ parameters for the calculated releases, radionuclide transport experiments have been carried out using five intact-core columns obtained from the Culebra dolomite member of the Rustler Formation within the Waste Isolation Pilot Plant (WIPP) site in southeastern New Mexico. This report deals primarily with results of mathematical analyses related to the retardation of %J%, 24%, and 24'Am in two of these cores (B-Core - VPX26-11A and C-Core - VPX28-6C). All B-Core transport experiments were done using Culebra-simukmt brine relevant to the core recovery location (the WIPP air-intake shaft - AIS). Most experiments with C-Core were done with AIS brine with some admixture of a brine composition (ERDA-6) that simulated deeper formation brines. No significant changes ...
Date: January 1, 1999
Creator: Brown, G.O.; Lucero, D.A. & Perkins, W.G.
Partner: UNT Libraries Government Documents Department

Lessons Learned from WIPP Site Characteriztion, Performance Assessment, and Regulatory Review Related to Radionuclide Migration through Water-Conducting Features

Description: Many lessons have been learned over the past 24 years as the Waste Isolation Pilot Plant (WIPP) project has progressed from initial site characterization to final licensing that may be of relevance to other nuclear-waste-disposal projects. These lessons pertain to the manner in which field and laboratory investigations are planned, how experiments are interpreted, how conceptual and numerical models are developed and simplified~ and how defensibility and credibility are achieved and maintained. These lessons include 1) Site characterization and performance assessment (PA) should evolve together through an iterative process, with neither activity completely dominating the other. 2) Defensibility and credibility require a much greater depth of understanding than can be represented in PA models. 3) Experimentalists should be directly involved in model and parameter abstraction and simplification for PA. 4) External expert review should be incorporated at all stages of a project~ not just after an experiment or modeling activity is completed. 5) Key individuals should be retained for the life of a project or a process must be established to transfer their working knowledge to new individuals. 6) An effective QA program needs to be stable and consistent for the duration of a project and rests on best scientific practices. All of these lessons relate to the key point that consideration must be given from the earliest planning stages to maximizing the defensibility and credibility of all work.
Date: November 11, 1998
Creator: Beauheim, R.L.: Larson. K.W.
Partner: UNT Libraries Government Documents Department

Effects of Spatially Heterogeneous Porosity on Matrix-Diffusion as Investigated by X ray Absorption Imaging

Description: Laboratory experiments were performed to investigate the effects of spatial variation in porosity on matrix-diffusion processes. Four centimeter-scale slabs of Culebra dolomite taken from the Waste Isolation Pilot Plant site were used in the tests. Experiments involved the simple diffusion of iodine into a single edge of each rock slab while X ray absorption imaging was used to measure the resulting two-dmensional solute concentration field as a function of time. X ray imaging was also used to quantify the two-dimensional porosity field of each rock slab. Image analysis provided a unique opportunity to both visuake and quantifj the effects of the spatially variable porosi~ on matrixdMusion. Four key results were obtained. First, significant variation in rates of diffusion were realized over the relatively small length (centimeter) and time scales (months) investigated. Second, clear evidence of diffusion preferentially following zones of relatively higher porosity was noted. Third, rate of difhion was found to vary as tracer diffused into the rock slabs encountering changing porosity conditions. Fourth, strong correlation between porosi~ and the calculated diffusion coefficients was found. In fact, the nature of the correlation can be related to the geometry, position, and orientation of the heterogeneous porosity features populating each rock slab.
Date: October 20, 1998
Creator: Boney, C.; Christian-Frear, T.; Meigs, L. C. & Tidwell, V. C.
Partner: UNT Libraries Government Documents Department

Performance Assessment in Support of the 1996 Compliance Certification Application for the Waste Isolation Pilot Plant

Description: The conceptual and computational structure of a performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP) is described. Important parts of thk structure are @ maintenance of a separation between stochastic (i.e., aleatory) and subjective (i.e., epistemic) uncertain, with stochastic uncefinty arising from the many possible disruptions that could occur over the 10,000 Y regulatory period fiat applies to the WIPP and subjective uncertainty arising from `the imprecision with which many of the quantities rquired in tie `hdysis are known, (ii) use of Latin hypercttbe sampling to incorporate the effects of subjective uncefirtty, (iii) use of Monte Carlo (i.e., random) sampling to incorporate the effects of stochastic uncetinty, and OV) efficient use of tie necessarily limited number of mechanistic calculations that can be performed to SUPPOII the analysis. The WIPP is under development by the U.S. Department of Ener~ (DOE) for the geologic (i.e., deep underground) disposal of transuranic (TRU) waste, with the indicated PA supporting a ~Compliance Certification Application (CCA) by the DOE to the U.S. Environmental Protection Agency (EPA) in October 1996 for tie necessary certifications for the WIPP to begin operation. If certified, the WIPP will be the first operational faciliv in tie United States for the geologic disposal of ra&oactive waste.
Date: October 14, 1998
Creator: Anderson, D.R.; Basabilvazo, G.; Helton, J.C.; Jow, H.-N. & Marietta, M.G.
Partner: UNT Libraries Government Documents Department

Waste Isolation Pilot Plant Biennial Environmental Compliance Report

Description: This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 2000, to March 31, 2002. As required by the WIPP Land Withdrawal Act (LWA)(Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) Carlsbad Field Office's (CBFO) compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico. In the prior BECR, the CBFO and the management and operating contractor (MOC)committed to discuss resolution of a Letter of Violation that had been issued by the New Mexico Environment Department (NMED) in August 1999, which was during the previous BECR reporting period. This Letter of Violation alleged noncompliance with hazardous waste aisle spacing, labeling, a nd tank requirements. At the time of publication of the prior BECR, resolution of the Letter of Violation was pending. On July 7, 2000, the NMED issued a letter noting that the aisle spacing and labeling concerns had been adequately addressed and that they were rescinding the violation alleging that the Exhaust Shaft Catch Basin failed to comply with the requirements for a hazardous waste tank. During the current reporting period, WIPP received a Notice of Violation and a compliance order alleging the violation of the New Mexico Hazardous Waste Regulations and the WIPP Hazardous Waste Facility Permit (HWFP).
Date: September 30, 2002
Creator: Westinghouse TRU Solutions LLC
Partner: UNT Libraries Government Documents Department

2002 WIPP Environmental Monitoring Plan

Description: DOE Order 5400.1, General Environmental Protection Program, requires each DOE | facility to prepare an environmental management plan (EMP). This document is | prepared for WIPP in accordance with the guidance contained in DOE Order 5400.1; DOE Order 5400.5, Radiation Protection of the Public and Environment; applicable sections of Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T; DOE, 1991); and the Title 10 Code of Federal Regulations (CFR) Part 834, ''Radiation Protection of the Public and Environment'' (draft). Many sections of DOE Order 5400.1 have been replaced by DOE Order 231.1, which is the driver for the annual Site Environmental Report (SER) and the guidance source for preparing many environmental program documents. The WIPP Project is operated by Westinghouse TRU Solutions (WTS) for the DOE. This plan defines the extent and scope of WIPP's effluent and environmental | monitoring programs during the facility's operational life and also discusses WIPP's quality assurance/quality control (QA/QC) program as it relates to environmental monitoring. In addition, this plan provides a comprehensive description of environmental activities at WIPP including: A summary of environmental programs, including the status of environmental monitoring activities A description of the WIPP Project and its mission A description of the local environment, including demographics An overview of the methodology used to assess radiological consequences to the public, including brief discussions of potential exposure pathways, routine and accidental releases, and their consequences Responses to the requirements described in the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance.
Date: September 30, 2002
Creator: Westinghouse TRU Solutions LLC
Partner: UNT Libraries Government Documents Department

Waste Isolation Pilot Plant 2001 Site Environmental Report

Description: The United States (U.S.) Department of Energy's (DOE) Carlsbad Field Office (CBFO) and Westinghouse TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2001 Site Environmental Report summarizes environmental data from calendar year (CY) 2001 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above Orders and guidance documents require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED). The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2001. WIPP received its first shipment of waste on March 26, 1999. In 2001, no evidence was found of any adverse effects from WIPP on the surrounding environment.
Date: September 20, 2002
Creator: Westinghouse TRU Solutions, Inc.
Partner: UNT Libraries Government Documents Department

Initial Package Design Concepts Integrated Product Team (IPT) Summary Report

Description: Initially, the question of transporting TRU waste to WIPP was raised as part of the EM Integration activities. The issue was re-examined as part of the system-wide view to re-engineer the TRU waste program. Consequently, the National Transportation Program and the National TRU Waste Program, in a cooperative effort, made a commitment to EM-20 to examine the feasibility of using rail to transport TRU waste material to WIPP. In December of 1999 Mr. Philip Altomare assembled a team of subject matter experts (SME) to define initial concepts for a Type B package capable of shipping TRU waste by rail (see Attachment 1 for a list of team members). This same team of experts also provided input to a preliminary study to determine if shipping TRU waste by rail could offer cost savings or other significant advantages over the current mode of operation using TRUPACT-II packages loaded on truck. As part of the analysis, the team also identified barriers to implementing rail shipments to WIPP and outlined a path forward. This report documents the findings of the study and its initial set of recommendations. As the study progressed, it was expanded to include new packages for truck as well as rail in recognition of the benefits of shipping large boxes and contaminated equipment.
Date: March 1, 2000
Creator: Moss, J. & Luke, Dale Elden
Partner: UNT Libraries Government Documents Department

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

Description: 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.
Date: May 1, 1997
Partner: UNT Libraries Government Documents Department

Basic Data Report for Drillhole SNL-1 (C-2953)

Description: SNL-1 (permitted by the New Mexico State Engineer as C-2953) was drilled to provide geological data and hydrological testing of the Culebra Dolomite Member of the Permian Rustler Formation near the margin of dissolution of halite in the upper Permian Salado Formation in the northeast arm of Nash Draw. SNL-1 is located in the northwest quarter of section 16, T21S, R31E, in eastern Eddy County, New Mexico, and it is adjacent to the tailings pile of Mississippi Potash Incorporated (now Intrepid) East mine to test for the presence of shallow zones that might include brine infiltrated from the tailings pile. SNL-1 was drilled to a total depth of 644 ft below ground level (bgl). Below surface wash, SNL-1 encountered, in order, the Mescalero caliche, Dewey Lake, and Rustler Formations.
Date: January 19, 2005
Creator: Powers, Dennis W. & Services, Washington Regulatory and Environmental
Partner: UNT Libraries Government Documents Department

TRU waste inventory collection and work-off plans for the centralization of TRU waste characterization at INL - on your mark - get set - 9410

Description: The U.S. Department of Energy (DOE) amended the Record of Decision (ROD) for the Waste Management Program: Treatment and Storage ofTransuranic Waste to centralize transuranic (TRU) waste characterization/certification from fourteen TRU waste sites. This centralization will allow for treatment, characterization and certification ofTRU waste from the fourteen sites, thirteen of which are sites with small quantities ofTRU waste, at the Idaho National Laboratory (INL) prior to shipping the waste to the Waste Isolation Pilot Plant (WIPP) for disposal. Centralization ofthis TRU waste will avoid the cost ofbuilding treatment, characterization, certification, and shipping capabilities at each ofthe small quantity sites that currently do not have existing facilities. Advanced Mixed Waste Treatment Project (AMWTP) and Idaho Nuclear Technology and Engineering Center (INTEC) will provide centralized shipping facilities, to WIPP, for all ofthe small quantity sites. Hanford, the one large quantity site identified in the ROD, has a large number ofwaste in containers that are overpacked into larger containers which are inefficient for shipment to and disposal at WIPP. The AMWTP at the INL will reduce the volume ofmuch of the CH waste and make it much more efficient to ship and dispose of at WIPP. In addition, the INTEC has a certified remote handled (RH) TRU waste characterization/certification program at INL to disposition TRU waste from the sites identified in the ROD.
Date: January 1, 2009
Creator: Mctaggert, Jerri Lynne; Lott, Sheila & Gadbury, Casey
Partner: UNT Libraries Government Documents Department

U.S. Department of Energy, Carlsbad Area Office quality assurance program document. Revision 1

Description: Mission of the Carlsbad Area Office (CAO) is to protect human health and the environment by opening and operating the Waste Isolation Pilot Plant (WIPP) for safe disposal of TRU waste, and establishing an effective system for management of TRU waste from generation to disposal. To help in fulfilling this mission and to ensure that risks and environmental impacts are identified and minimized, and that safety, reliability, and performance are optimized, CAO`s policy is to establish and maintain an effective quality assurance (QA) program that supports compliance with applicable Federal, State, and local regulations, and DOE orders and requirements. This document establishes QA program requirements for all programs, projects, and activities sponsored by CAO.
Date: April 1, 1996
Partner: UNT Libraries Government Documents Department

Prediction of dissolved actinide concentrations in concentrated electrolyte solutions: a conceptual model and model results for the Waste Isolation Pilot Plant (WIPP)

Description: The conceptual model for WIPP dissolved concentrations is a description of the complex natural and artificial chemical conditions expected to influence dissolved actinide concentrations in the repository. By a set of physical and chemical assumptions regarding chemical kinetics, sorption substrates, and waste-brine interactions, the system was simplified to be amenable to mathematical description. The analysis indicated that an equilibrium thermodynamic model for describing actinide solubilities in brines would be tractable and scientifically supportable. This paper summarizes the conceptualization and modeling approach and the computational results as used in the WIPP application for certification of compliance with relevant regulations for nuclear waste repositories. The WIPP site contains complex natural brines ranging from sea water to 10x more concentrated than sea water. Data bases for predicting solubility of Am(III) (as well as Pu(III) and Nd(III)), Th(IV), and Np(V) in these brines under potential repository conditions have been developed, focusing on chemical interactions with Na, K, Mg, Cl, SO{sub 4}, and CO{sub 3} ions, and the organic acid anions acetate, citrate, EDTA, and oxalate. The laboratory and modeling effort augmented the Harvie et al. parameterization of the Pitzer activity coefficient model so that it could be applied to the actinides and oxidation states important to the WIPP system.
Date: October 25, 1996
Creator: Novak, C.F.; Moore, R.C. & Bynum, R.V.
Partner: UNT Libraries Government Documents Department

Los Alamos Plutonium Facility newly generated tru waste certification. Final revised version 3/97

Description: This paper presents an overview of the activities being planned and implemented to certify newly generated contact handled transuranic (TRU) waste produced by Los Alamos National Laboratory`s (LANL`s) Plutonium Facility. Certifying waste at the point of generation is the most important cost and labor saving step in the WIPP certification process. The pedigree of a waste item is best known by the originator of the waste and frees a site from many of the expensive characterization activities associated with legacy waste. Through a cooperative agreement with LANLs Waste Management Facility and under the umbrella of LANLs WIPP-related certification and quality assurance documents, the Plutonium Facility will be certifying most of its own newly generated waste. Some of the challenges faced by the Plutonium Facility in preparing to certify TRU waste include the modification and addition of procedures to meet WIPP requirements, standardizing packaging for TRU waste, collecting processing documentation from operations which produce TRU waste, and developing ways to modify waste streams which are not certifiable in their present form.
Date: April 1, 1997
Creator: Gruetzmacher, K.; Montoya, A.; Sinkule, B. & Maez, M.
Partner: UNT Libraries Government Documents Department