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Regulatory compliance for a Yucca Mountain Repository: A performance assessment perspective

Description: The U.S. Department of Energy`s Yucca Mountain Site Characterization Project is scheduled to submit a License Application in the year 2002. The License Application is to show compliance with the regulations promulgated by the U.S. Nuclear Regulatory Commission which implement standards promulgated by the U.S. Environmental Protection Agency. These standards are being revised, and it is not certain what their exact nature will be in term of either the performance measure(s) or the time frames that are to be addressed. This paper provides some insights pertaining to this regulatory history, an update on Yucca Mountain performance assessments, and a Yucca Mountain Site Characterization Project perspective on proper standards based on Project experience in performance assessment for its proposed Yucca Mountain Repository system. The Project`s performance assessment based perspective on a proper standard applicable to Yucca Mountain may be summarized as follows: a proper standard should be straight forward and understandable; should be consistent with other standards and regulations; and should require a degree of proof that is scientifically supportable in a licensing setting. A proper standard should have several attributes: (1) propose a reasonable risk level as its basis, whatever the quantitative performance measure is chosen to be, (2) state a definite regulatory time frame for showing compliance with quantitative requirements, (3) explicitly recognize that the compliance calculations are not predictions of actual future risks, (4) define the biosphere to which risk needs to be calculated in such a way as to constrain potentially endless speculation about future societies and future human actions, and (5) have as its only quantitative requirement the risk limit (or surrogate performance measure keyed to risk) for the total system.
Date: February 1, 1997
Creator: Dyer, J. R.; Van Luik, A. E.; Gil, A. V. & Brocoum, S. J.
Partner: UNT Libraries Government Documents Department

Rethinking regulations for disposal criticality

Description: This paper provides the basis for the position that the current U.S. Nuclear Regulatory Commission (NRC) criticality regulation is in need of revision to address problems in implementing it for the postclosure period in a geologic high-level waste repository. The authors believe that the applicant for such a facility should be able to demonstrate that postulated postclosure criticality events will not cause unacceptable risk of deleterious effects on public health and safety. In addition, the applicant should be expected to take practical and feasible measures to reduce the probability of a criticality occurring, even if (as expected) the consequences of such a criticality for repository performance and public health and safety would be negligible. This approach, while recognizing the probabilistic nature of analyses of events and conditions in the distant future, is also arguably consistent with the defense in depth concept that has been successfully applied to nuclear reactor regulation. The authors believe regulations for postclosure criticality control should support this dual approach, rather than require a deterministic prohibition of criticality as does the current rule. The existing rule seems appropriate for the preclosure period, as long as it is clearly specified to apply only to that period.
Date: August 1, 1997
Creator: Scott, M. & Doering, T.
Partner: UNT Libraries Government Documents Department

Yucca Mountain Site Characterization Project technical data catalog quarterly supplement

Description: The Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where the data may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with t requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and distributed in the month following the end of each quarter. A complete revision to the catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to@ previously published reference information. The Technical Data Catalog, dated September 30, 1994, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1995.
Date: March 31, 1995
Partner: UNT Libraries Government Documents Department

Yucca Mountain Site Characterization Project Technical Data Catalog (Quarterly supplement)

Description: The March 21, 1993, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. A complete revision to the Catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to previously published reference information. The Technical Data Catalog, dated September 30, 1993, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1994.
Date: December 31, 1993
Partner: UNT Libraries Government Documents Department

Yucca Mountain Site Characterization Project technical data catalog: Quarterly supplement

Description: The Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where the data may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed-in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and distributed in the month following the end of each quarter. A complete revision to the catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to previously published reference information. The Technical Data Catalog, dated September 30, 1994, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1995.
Date: December 31, 1994
Partner: UNT Libraries Government Documents Department

Occupational radiation dose assessment for a non site specific spent fuel storage facility

Description: To expedite the licensing process of the non site specific Centralized Interim Storage Facility (CISF) the Department of Energy has completed a phase I CISF Topical Safety Analysis Report (TSAR). The TSAR will be used in licensing the phase I CISF if a site is designated. An occupational radiation does assessment of the facility operations is performed as part of the phase I CISF design. The first phase of the CISF has the capability to receive, transfer, and store SNF in dual-purpose cask/canister systems (DPC`s). Currently there are five vendor technologies under consideration. The preliminary dose assessment is based on estimated occupational exposures using traditional power plant ISFSI and transport cask handling processes. The second step in the process is to recommend ALARA techniques to reduce potential exposures. A final dose assessment is completed implementing the ALARA techniques and a review is performed to ensure that the design is in compliance with regulatory criteria. The dose assessment and ALARA evaluation are determined using the following input information: Dose estimates from vendor SAR`s; ISFSI experience with similar systems; Traditional methods of operations; Expected CISF cask receipt rates; and feasible ALARA techniques. 5 refs., 1 tab.
Date: December 1, 1997
Creator: Hadley, J. & Eble, R. G., Jr.
Partner: UNT Libraries Government Documents Department

A preliminary assessment of earthquake ground shaking hazard at Yucca Mountain, Nevada and implications to the Las Vegas region

Description: As part of early design studies for the potential Yucca Mountain nuclear waste repository, the authors have performed a preliminary probabilistic seismic hazard analysis of ground shaking. A total of 88 Quaternary faults within 100 km of the site were considered in the hazard analysis. They were characterized in terms of their probability o being seismogenic, and their geometry, maximum earthquake magnitude, recurrence model, and slip rate. Individual faults were characterized by maximum earthquakes that ranged from moment magnitude (M{sub w}) 5.1 to 7.6. Fault slip rates ranged from a very low 0.00001 mm/yr to as much as 4 mm/yr. An areal source zone representing background earthquakes up to M{sub w} 6 1/4 = 1/4 was also included in the analysis. Recurrence for these background events was based on the 1904--1994 historical record, which contains events up to M{sub w} 5.6. Based on this analysis, the peak horizontal rock accelerations are 0.16, 0.21, 0.28, and 0.50 g for return periods of 500, 1,000, 2,000, and 10,000 years, respectively. In general, the dominant contributor to the ground shaking hazard at Yucca Mountain are background earthquakes because of the low slip rates of the Basin and Range faults. A significant effect on the probabilistic ground motions is due to the inclusion of a new attenuation relation developed specifically for earthquakes in extensional tectonic regimes. This relation gives significantly lower peak accelerations than five other predominantly California-based relations used in the analysis, possibly due to the lower stress drops of extensional earthquakes compared to California events. Because Las Vegas is located within the same tectonic regime as Yucca Mountain, the seismic sources and path and site factors affecting the seismic hazard at Yucca Mountain also have implications to Las Vegas. These implications are discussed in this paper.
Date: December 31, 1996
Creator: Wong, I. G.; Green, R. K.; Sun, J. I.; Pezzopane, S. K.; Abrahamson, N. A. & Quittmeyer, R. C.
Partner: UNT Libraries Government Documents Department

Design basis event consequence analyses for the Yucca Mountain project

Description: Design basis event (DBE) definition and analysis is an ongoing and integrated activity among the design and analysis groups of the Yucca Mountain Project (YMP). DBE`s are those that potentially lead to breach of the waste package and waste form (e.g., spent fuel rods) with consequent release of radionuclides to the environment. A Preliminary Hazards Analysis (PHA) provided a systematic screening of external and internal events that were candidate DBE`s that will be subjected to analyses for radiological consequences. As preparation, pilot consequence analyses for the repository subsurface and surface facilities have been performed to define the methodology, data requirements, and applicable regulatory limits.
Date: February 1, 1997
Creator: Orvis, D. D.; Haas, M. N. & Martin, J. H.
Partner: UNT Libraries Government Documents Department

Effect of repository underground ventilation on emplacement drift temperature control

Description: The repository advanced conceptual design (ACD) is being conducted by the Civilian Radioactive Waste Management System, Management & Operating Contractor. Underground ventilation analyses during ACD have resulted in preliminary ventilation concepts and design methodologies. This paper discusses one of the recent evaluations -- effects of ventilation on emplacement drift temperature management.
Date: February 1, 1996
Creator: Yang, H.; Sun, Y.; McKenzie, D.G. & Bhattacharyya, K.K.
Partner: UNT Libraries Government Documents Department

End effect K{sub eff} bias curve for actinide-only burnup credit casks

Description: A conservative end effect k{sub eff} bias curve for actinide-only burnup credit for spent fuel casks is presented in this paper. The k{sub eff} bias values can be added to the uniform axial burnup analysis to conservatively bound the actinide-only end effect. A normalized axial burnup distribution for the standard Westinghouse 17 x 17 assembly design is used for calculating k{sub eff}. The end effect calculated is a strong function of burnup, and increases as cask size size decreases. The presence of poison plates increases the end effect. The bias curve presented is based on the most limiting cask configuration of a single PWR assembly with completely black poison plates. Therefore, axially uniform criticality calculations with application of the proposed k{sub eff} could eliminate the need for axially burnup dependent analyses. 7 refs., 1 fig.
Date: March 1, 1997
Creator: Kang, C. H. & Lancaster, D. B.
Partner: UNT Libraries Government Documents Department

Humid-air and aqueous corrosion models for corrosion-allowance barrier material

Description: Humid-air and aqueous general and pitting corrosion models (including their uncertainties) for the carbon steel outer containment barrier were developed using the corrosion data from literature for a suite of cast irons and carbon steels which have similar corrosion behaviors to the outer barrier material. The corrosion data include the potential effects of various chemical species present in the testing environments. The atmospheric corrosion data also embed any effects of cyclic wetting and drying and salts that may form on the corroding specimen surface. The humid-air and aqueous general corrosion models are consistent in that the predicted humid-air general corrosion rates at relative humidities between 85 and 100% RH are close to the predicted aqueous general corrosion rates. Using the expected values of the model parameters, the model predicts that aqueous pitting corrosion is the most likely failure mode for the carbon steel outer barrier, and an earliest failure (or initial pit penetration) of the 100-mm thick barrier may occur as early as about 500 years if it is exposed continuously to an aqueous condition at between 60 and 70{degrees}C.
Date: December 31, 1995
Creator: Lee, J. H.; Atkins, J. E. & Andrews, R. W.
Partner: UNT Libraries Government Documents Department

Isotopic and criticality validation for actinide-only burnup credit

Description: The techniques used for actinide-only burnup credit isotopic validation and criticality validation are presented and discussed. Trending analyses have been incorporated into both methodologies, requiring biases and uncertainties to be treated as a function of the trending parameters. The isotopic validation is demonstrated using the SAS2H module of SCALE 4.2, with the 27BURNUPLIB cross section library; correction factors are presented for each of the actinides in the burnup credit methodology. For the criticality validation, the demonstration is performed with the CSAS module of SCALE 4.2 and the 27BURNUPLIB, resulting in a validated upper safety limit.
Date: July 1, 1997
Creator: Fuentes, E.; Lancaster, D. & Rahimi, M.
Partner: UNT Libraries Government Documents Department

Isotopic biases for actinide-only burnup credit

Description: The primary purpose of this paper is to present the new methodology for establishing bias and uncertainty associated with isotopic prediction in spent fuel assemblies for burnup credit analysis. The analysis applies to the design of criticality control systems for spent fuel casks. A total of 54 spent fuel samples were modeled and analyzed using the Shielding Analyses Sequence (SAS2H). Multiple regression analysis and a trending test were performed to develop isotopic correction factors for 10 actinide burnup credit isotopes. 5 refs., 1 tab.
Date: April 1, 1997
Creator: Rahimi, M.; Lancaster, D.; Hoeffer, B. & Nichols, M.
Partner: UNT Libraries Government Documents Department

Appropriate burnup measurements for transportation burnup credit

Description: This paper addresses two of the measurement specifications used in analyzing spent fuel packages to gain burnup credit. The philosophy and calculation of rejection criteria and measurement accuracy are discussed. Any assembly for which the declared measured value and reactor record value deviate by more than 10% will be rejected. Measurement accuracy requirements are established for dependent and independent systems. The requirements have been tested and are achievable, ensuring safe operation without extra cost. 6 refs.
Date: April 1, 1997
Creator: Lancaster, D. & Fuentes, E.
Partner: UNT Libraries Government Documents Department

Criticality validation for burnup credit using recycle Pu criticals

Description: A set of 23 additional critical experiments were analyzed to provide additional input to the criticality validation portion of spent fuel cask analysis. The results of this analyses were combined with the previously analyzed criticals to determine the upper safety limit on k{sub eff}. The combined set of criticals can be used used for criticality validation for burnup credit, and are better suited for the range of isotopics in spent nuclear fuels. A trend observed in the analysis was that the calculated k{sub eff} deviates from the criticals in the positive direction, implying that increased burnup results in increased safety margin. 6 refs., 2 figs., 1 tab.
Date: April 1, 1997
Creator: Fuentes, E. & Lancaster, D.
Partner: UNT Libraries Government Documents Department

Data base for hydraulically stimulated gas wells producing from tight sands formations

Description: A data base was assembled in 1978 consisting of well records from more than 900 hydraulically fractured wells in the Piceance, Uinta, Washakie, Sand Wash, and Denver Basins. The purpose of the present study is to develop a western gas sand computerized data base for hydraulically stimulated gas wells by adapting and expanding the above-mentioned data file. This report describes the data file, tasks accomplished to date, and a sample well record. (DMC)
Date: March 1, 1982
Partner: UNT Libraries Government Documents Department

Final report for TMX-U systems support

Description: This final report is for the TMX-U RF systems development subcontract with Lawrence Livermore National Laboratory (LLNL). This program was initiated on July 1, 1983 and extended through September 30, 1985. This program was concerned with the development of RF systems to meet the objectives of the TMX-U mirror program at LLNL. To accomplish this the following areas were studied during the course of this contract: (1) Ion Cyclotron Heating, (2) Electron Cyclotron Heating, (3) Drift Pumping, (4) Plasma Modeling, (5) Neutral Beam Heating, and (6) Neutral Gas transport and fueling. The key results of these activities are reported.
Date: January 1, 1985
Partner: UNT Libraries Government Documents Department

Alternatives to ceramic bricks and ceramic-brick systems

Description: Alternative materials for use as TES media in electric storage furnaces have been evaluated and selected. Selections were based on: low cost; availability; durability; and energy storage density. The materials selected were: taconite pellets; river gravel; crushed stone; and crushed (air-cooled) blast furnace slag. Essential material properties and energy storage densities were established. A conceptual design for an electric storage furnace using these low-cost materials has been developed. The performance of this conceptual furnace has been characterized by use of an analytical model. A computer code for the model has been developed. Existing performance data for present-day electric storage furnaces have been evaluated, and performance and design comparisons between present-day furnaces and the prototype furnace have been made. With the limited data at this time, a significant cost advantage for the proposed furnace, with equivalent performance, over existing electric storage furnaces cannot be established. Future work required for materials testing and component development has been identified.
Date: January 1, 1981
Creator: MacDonald, J.M.
Partner: UNT Libraries Government Documents Department

Process for license application development for the geologic repository

Description: The Department of Energy (DOE), specifically the Office of Civilian Radioactive Waste Management (OCRWM) has been charged by the US Congress, through the Nuclear Waste Policy Act (NWPA), with the responsibility for obtaining a license to develop a geologic repository. The NRC is the licensing authority for geologic disposal, and its regulations pertinent to construction authorization and license application are specified in 10 CFR Part 60, Disposal of High-Level Radioactive Wastes in Geologic Repositories, {section}60.21ff and {section}60.31ff. This paper discusses the process the Yucca Mountain Site Characterization Project (YMP) will use to identify and apply regulatory and industry guidance to development of the license application (LA) for a geologic repository at Yucca Mountain, Nevada. This guidance will be implemented by the Technical Guidance Document for Preparation of the License Application (TGD), currently in development.
Date: June 1, 1998
Creator: Franks, D. M. & Henderson, N. C.
Partner: UNT Libraries Government Documents Department

TRW technical progress report, February-July 1977. [Energy conservation potential for US]

Description: Progress in a program for identifying methods and policies for improving the effiency of the end use of energy in the US is reported. This program includes evaluation of current and future energy supplies and consumption, energy policy, analysis, and studies of thermal energy storage, fuel cells, potential production of methane from coal beds, and the efficiency of residential space heating equipment. (LCL)
Date: January 1, 1977
Partner: UNT Libraries Government Documents Department

Physics modeling support contract: Final report

Description: This document is the final report for the Physics Modeling Support contract between TRW, Inc. and the Lawrence Livermore National Laboratory for fiscal year 1987. It consists of following projects: TIBER physics modeling and systems code development; advanced blanket modeling task; time dependent modeling; and free electron maser for TIBER II.
Date: September 30, 1987
Partner: UNT Libraries Government Documents Department