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Genesis of an environmental statement: nuclear power reactor

Description: Over the past four years a procedure has been developed and instituted by the AEC through which the requirements of the National Environmental Policy Act of 1969 are fully realized. The procedure insures an independent assessment of the Applicant's Environmental Report by scientists and engineers in contractor laboratories, and through extensive interfacing with the Applicant, local and federal government agencies. The procedure permits intervenors as well as advocates to be heard, and finally permits an independent board to make an overall assessment of the environmental and safety issues and make recommendations to the AEC for appropriate action. The process is time- consuming, yet assures the protection of the environment and people in the environment of the nuclear facility. Progress is being made to shorten the procedure through use of more standard reactor designs and stressing the unique features which may require unusually detailed assessment. (auth)
Date: December 1, 1973
Creator: Schwendiman, L.C.
Partner: UNT Libraries Government Documents Department

DEVELOPMENT OF HUMAN FACTORS ENGINEERING GUIDANCE FOR SAFETY EVALUATIONS OF ADVANCED REACTORS.

Description: Advanced reactors are expected to be based on a concept of operations that is different from what is currently used in today's reactors. Therefore, regulatory staff may need new tools, developed from the best available technical bases, to support licensing evaluations. The areas in which new review guidance may be needed and the efforts underway to address the needs will be discussed. Our preliminary results focus on some of the technical issues to be addressed in three areas for which new guidance may be developed: automation and control, operations under degraded conditions, and new human factors engineering methods and tools.
Date: October 1, 2006
Creator: O'HARA, J.; PERSENSKY, J. & SZABO, A.
Partner: UNT Libraries Government Documents Department

Nuclear power plant Generic Aging Lessons Learned (GALL). Main report and appendix A

Description: The purpose of this generic aging lessons learned (GALL) review is to provide a systematic review of plant aging information in order to assess materials and component aging issues related to continued operation and license renewal of operating reactors. Literature on mechanical, structural, and thermal-hydraulic components and systems reviewed consisted of 97 Nuclear Plant Aging Research (NPAR) reports, 23 NRC Generic Letters, 154 Information Notices, 29 Licensee Event Reports (LERs), 4 Bulletins, and 9 Nuclear Management and Resources Council Industry Reports (NUMARC IRs) and literature on electrical components and systems reviewed consisted of 66 NPAR reports, 8 NRC Generic Letters, 111 Information Notices, 53 LERs, 1 Bulletin, and 1 NUMARC IR. More than 550 documents were reviewed. The results of these reviews were systematized using a standardized GALL tabular format and standardized definitions of aging-related degradation mechanisms and effects. The tables are included in volume s 1 and 2 of this report. A computerized data base has also been developed for all review tables and can be used to expedite the search for desired information on structures, components, and relevant aging effects. A survey of the GALL tables reveals that all ongoing significant component aging issues are currently being addressed by the regulatory process. However, the aging of what are termed passive components has been highlighted for continued scrutiny. This document is Volume 1, consisting of the executive summary, summary and observations, and an appendix listing the GALL literature review tables.
Date: December 1996
Creator: Kaza, K. E.; Diercks, D. R.; Holland, J. W. & Choi, S. U.
Partner: UNT Libraries Government Documents Department

Nuclear power plant Generic Aging Lessons Learned (GALL). Appendix B

Description: The purpose of this generic aging lessons learned (GALL) review is to provide a systematic review of plant aging information in order to assess materials and component aging issues related to continued operation and license renewal of operating reactors. Literature on mechanical, structural, and thermal-hydraulic components and systems reviewed consisted of 97 Nuclear Plant Aging Research (NPAR) reports, 23 NRC Generic Letters, 154 Information Notices, 29 Licensee Event Reports (LERs), 4 Bulletins, and 9 Nuclear Management and Resources Council Industry Reports (NUMARC IRs) and literature on electrical components and systems reviewed consisted of 66 NPAR reports, 8 NRC Generic Letters, 111 Information Notices, 53 LERs, 1 Bulletin, and 1 NUMARC IR. More than 550 documents were reviewed. The results of these reviews were systematized using a standardized GALL tabular format and standardized definitions of aging-related degradation mechanisms and effects. The tables are included in volume s 1 and 2 of this report. A computerized data base has also been developed for all review tables and can be used to expedite the search for desired information on structures, components, and relevant aging effects. A survey of the GALL tables reveals that all ongoing significant component aging issues are currently being addressed by the regulatory process. However, the aging of what are termed passive components has been highlighted for continued scrutiny. This report consists of Volume 2, which consists of the GALL literature review tables for the NUMARC Industry Reports reviewed for the report.
Date: December 1996
Creator: Kasza, K. E.; Diercks, D. R.; Holland, J. W. & Choi, S. U.
Partner: UNT Libraries Government Documents Department

NRC antitrust licensing actions, 1978--1996

Description: NUREG-0447, Antitrust Review of Nuclear Power Plants, was published in May 1978 and includes a compilation and discussion of U.S. Nuclear Regulatory Commission (NRC) proceedings and activity involving the NRC`s competitive review program through February 1978, NUREG-0447 is an update of an earlier discussion of the NRC`s antitrust review of nuclear power plants, NR-AIG-001, The US Nuclear Regulatory Commission`s Antitrust Review of Nuclear Power Plants: The Conditioning of Licenses, which reviewed the Commission`s antitrust review function from its inception in December 1970 through April 1976. This report summarizes the support provided to NRC staff in updating the compilation of the NRC`s antitrust licensing review activities for commercial nuclear power plants that have occurred since February 1978. 4 refs., 4 tabs.
Date: September 1, 1997
Creator: Mayer, S.J. & Simpson, J.J.
Partner: UNT Libraries Government Documents Department

Licensing issues associated with the use of mixed-oxide fuel in US commercial nuclear reactors

Description: On January 14, 1997, the Department of Energy, as part of its Record of Decision on the storage and disposition of surplus nuclear weapons materials, committed to pursue the use of excess weapons-usable plutonium in the fabrication of mixed-oxide (MOX) fuel for consumption in existing commercial nuclear power plants. Domestic use of MOX fuel has been deferred since the late 1970s, principally due to nuclear proliferation concerns. This report documents a review of past and present literature (i.e., correspondence, reports, etc.) on the domestic use of MOX fuel and provides discussion on the technical and regulatory issues that must be addressed by DOE (and the utility/consortia selected by DOE to effect the MOX fuel consumption strategy) in obtaining approval from the Nuclear Regulatory Commission to use MOX fuel in one or a group of existing commercial nuclear power plants.
Date: April 1, 1997
Creator: Williams, D.L. Jr.
Partner: UNT Libraries Government Documents Department

Title list of documents made publicly available, December 1-31, 1997

Description: This report includes the information received and published by the U.S. Nuclear Regulatory Commission (NRC) in December 1997. It includes: (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. This series of documents is indexed by author, corporate source, and report number. This report includes six docketed items and 24 non-docketed items.
Date: February 1, 1998
Partner: UNT Libraries Government Documents Department

Standard technical specifications, Westinghouse Plants: Bases (Sections 2.0--3.3). Volume 2, Revision 1

Description: This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the Westinghouse Owners Group (WOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency.
Date: April 1, 1995
Partner: UNT Libraries Government Documents Department

Standard technical specifications, Westinghouse Plants: Specifications. Volume 1, Revision 1

Description: This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the Westinghouse Owners Group (WOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency.
Date: April 1, 1995
Partner: UNT Libraries Government Documents Department

Advances in HFE Methods and Their Implications for Regulatory Reviews.

Description: There is renewed interest in the United States (U.S.) to construct new Generation III and III+ reactors within the next decade and Generation IV reactors in the future. Licensing by the U.S. Nuclear Regulatory Commission (NRC) is a significant consideration and these new plants may pose new challenges. One such challenge is the advances in human factors engineering (HFE) methods that are used. These methods are used to design and evaluate the HFE aspects of a plant, such as the human-system interface (HSI). These methods are important because NRC HFE reviews are design process oriented, thus, the criteria are mostly technology neutral with regard to reactor design.[1] However, the HFE review criteria are not neutral with respect to the HFE methods that are used as part of the design process This will be important for new reactor reviews because the diversity of reactor types, HSIs, and operational concepts will increase, especially for Generation III+ and IV plants. Thus the NRC is conducting research to identify advances in HFE methods and to develop additional guidance to address their review.
Date: March 21, 2006
Creator: O'hara, J.; Persensky, J. & Szabo, A.
Partner: UNT Libraries Government Documents Department

Seismic requirements for design of nuclear power plants and test facilities

Description: Engineering requirements for the design of nuclear power plants and test facilities to accommodate the vibratory effects of earthquakes are presented. This standard is applicable to the containment, all components within and including the reactor coolant pressure boundary, engineered safety features, and to all systems or components that are required to permit continued operation. (JWR)
Date: January 1, 1974
Partner: UNT Libraries Government Documents Department

Age-Related Degradation of Nuclear Power Plant Structures and Components

Description: This paper summarizes and highlights the results of the initial phase of a research project on the assessment of aged and degraded structures and components important to the safe operation of nuclear power plants (NPPs). A review of age-related degradation of structures and passive components at NPPs was performed. Instances of age-related degradation have been collected and reviewed. Data were collected from plant generated documents such as Licensing Event Reports, NRC generic communications, NUREGs and industry reports. Applicable cases of degradation occurrences were reviewed and then entered into a computerized database. The results obtained from the review of degradation occurrences are summarized and discussed. Various trending analyses were performed to identify which structures and components are most affected, whether degradation occurrences are worsening, and what was the most common aging mechanisms. The paper also discusses potential aging issues and degradation-susceptible structures and passive components which would have the greatest impact on plant risk.
Date: March 29, 1999
Creator: Braverman, J.; Chang, T.-Y.; Chokshi, N.; Hofmayer, C.; Morante, R. & Shteyngart, S.
Partner: UNT Libraries Government Documents Department

Nuclear Regulatory Commission Issuances

Description: This report contains the issuances received during the specified period from the Atomic Safety and Licensing Board only. The two issuances included relate to: (1) suspension of byproduct material license for Eastern Testing and Inspection, Inc., and (2) license renewal for the Georgia Tech research reactor.
Date: May 1, 1996
Partner: UNT Libraries Government Documents Department

Nuclear Regulatory Commission issuances. Volume 44, Number 2

Description: This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Decision on Petitions for Rulemaking (DPRM). The topics of this publication include the dismissal of a suit brought against Georgia Power Company in the transfer of Vogtle Electric Generating Plant, units 1 and 2 to Southern Nuclear; and denial of a petition to review the entire licensing process for Watts Bar Nuclear Plant, Unit 1 operated by the Tennessee Valley Authority.
Date: August 1, 1996
Partner: UNT Libraries Government Documents Department

Application of bridging methods for standard HTGR [High-Temperature Gas-Cooled Reactor] licensing bases

Description: A review of the bridging methods is accomplished by providing an application of the process to the standard HTGR. A representative PRA, of limited range, is used in the process, and representative deterministic licensing bases are obtained. The PRA is presented as a risk plot, and the characteristics of the events and the equipment in the PRA are used in the bridging application. Representative licensing basis events are identified consisting of anticipated operational occurrences, design basis events, and emergency planning basis events. Representative safety-related functions and safety-related structures, systems and components are identified. The licensing basis events and safety-related functions and equipment are representative of the deterministic licensing bases that will be included in the PSID and SARs. A response is requested from NRC on the acceptability of the application of the method, considering the range of the representative PRA presented.
Date: February 1, 1986
Creator: Houghton, W.J. & Parme, L.L.
Partner: UNT Libraries Government Documents Department