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Federal/State Regulatory Permitting Actions in Selected Nuclear Power Station Licensing Cases

Description: Abstract: This report documents the Federal/State regulatory permitting actions in 12 case histories of nuclear power station licensing in nine different states. General observations regarding Federal/State siting roles in the siting process include: new regulations, with the exceptions of those imposed by NEPA, were not found to be the source of significant delay; interventions were the sources of significant delay in only two cases; in only two cases was a local agency a source of delay; no o… more
Date: June 1977
Creator: U.S. Nuclear Regulatory Commission. Office of State Programs.
Partner: UNT Libraries Government Documents Department
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Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, Appendix 1

Description: From introduction: In conventional safety analyses, a suitable design basis, including redundancy, is specified to assure a minimum level of operability of ESFs, and the likelihood or consequences of total failure of ESFs are not considered further. In this study all failures are considered possible, but appropriate probabilities are assigned to them. Thus, many potential accident sequences are described in the following discussions as if they will surely occur, with no reservations expressed a… more
Date: October 1975
Creator: U.S. Nuclear Regulatory Commission
Partner: UNT Libraries Government Documents Department
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Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, Appendices 3 and 4

Description: From section 1: In the quantitative system probability estimates performed in this study, component behavior data in the form of failure rates and repair times are required as inputs to the system models. Since the goal of this study is risk assessment, as opposed to reliability analysis, larger errors (e.g. order of magnitude type accuracy) can be tolerated in the quantified results. This has important implications on the treatment of available data. In standard reliability analysis, point val… more
Date: October 1975
Creator: U.S. Nuclear Regulatory Commission
Partner: UNT Libraries Government Documents Department
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Final Environmental Statement by the U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation for Montague Nuclear Power Station, Units 1 and 2

Description: The proposed project: Pursuant to the Atomic Energy Act, as amended, the U.S. Nuclear Regulatory Commission's regulations in Title 10, Code of Federal Regulations, an application with an accompanying Environmental Report, was filed by Northeast Utilities (hereinafter referred to as the applicant) for construction permits for two generating units designated as the Montague Nuclear Power Station, Units 1 and 2 (Docket Nos. 50-496 and 50-497), each of which is powered by a boiling water reactor (B… more
Date: February 1977
Creator: U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.
Partner: UNT Libraries Government Documents Department
open access

Safety Evaluation Report: Related to the Preliminary Design of the Standard Reference System RESAR-414

Description: From introduction: This Safety Evaluation Report summarizes the results of the technical evaluation of the proposed RESAR-414 design performed by the NRC staff, and delineates the scope of the technical matters considered in evaluating the radiological safety aspects of the RESAR-414 design. Environmental aspects were not considered in our review of RESAR-414, but will be addressed in each utility application for a construction permit which references RESAR-414.
Date: 1978
Creator: U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.
Partner: UNT Libraries Government Documents Department
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Final Environmental Statement by the U.S. Nuclear Regulatory Commission for Greene County Nuclear Power Plant

Description: Abstract: A Final Environmental Statement for the Power Authority of the State of New York for the construction of the Greene County Nuclear Power Plant (Docket No. 50-549) located in Greene County, New York, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission (NRC). This statement provides (1) a summary of environmental impact and adverse effects of the proposed facility, and (2) a consideration of principal alternatives. Also included are comment… more
Date: January 1979
Creator: U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.
Partner: UNT Libraries Government Documents Department
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Nuclear Power Plant Fire Protection

Description: This report examines the adequacy of existing fire-hazards analysis methodology in the context of nuclear power plant safety
Date: September 1979
Creator: Berry, Dennis L. & Minor, Earl E.
Partner: UNT Libraries Government Documents Department
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Appendix B. Test PCM-3 Instrumentation and Associated Uncertainties

Description: Appendix to Test PCM-3 report presenting a description of the "instrumentation and the calibration equations that were used to convert the transducer output to engineering units during the data reduction process." (p. 61)
Date: August 1979
Creator: Owen, Dennis E. & Vinjamuri, Krishna
Partner: UNT Libraries Government Documents Department
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[Appendix C. Test PCM-3 Fuel Rod Power Calibration]

Description: Report presenting the results of thermal heat balance power calibration and neutron flux axial distribution measurements for the Power-Cooling-Mismatch Test PCM-3.
Date: August 1979
Creator: Owen, Dennis E. & Vinjamuri, Krishna
Partner: UNT Libraries Government Documents Department
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[Appendix D. Test PCM-3 Data Plots]

Description: Report presenting data plots for selected parameters measured during Test PCM-3 of the Power-Cooling-Mismatch Test Series.
Date: August 1979
Creator: Owen, Dennis E. & Vinjamuri, Krishna
Partner: UNT Libraries Government Documents Department
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Appendix A. Pretest Fuel Rod Characterization

Description: Report presenting pretest characterization measurements for two of the four Power-Cooling Mismatch Test PCM-3 fuel rods, Rods UTA-0011 and UTA-0013.
Date: August 1979
Creator: Owen, Dennis E. & Vinjamuri, Krishna
Partner: UNT Libraries Government Documents Department
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[Appendix E. Comparison of Calculated and Measured Fuel Rod Behavior for Test PCM-3]

Description: Report to appendix presenting a comparison of the calculated and measured fuel rod behavior determined during steady state power calibration, the onset of departure from nucleate boiling (DNB), and post-DNB test for Power-Cooling Mismatch Test PCM-3. (p. 155)
Date: August 1979
Creator: Owen, Dennis E. & Vinjamuri, Krishna
Partner: UNT Libraries Government Documents Department
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[Appendix F. Cladding Surface Temperature Estimates (Test PCM-3)]

Description: Report presenting estimates of the methods used to establish fuel rod cladding temperatures for Test PCM-3 using three techniques: metallographic examination of the cladding microstructures, isothermal reaction rate correlations, and BUILD5 computer code calculations.
Date: August 1979
Creator: Owen, Dennis E. & Vinjamuri, Krishna
Partner: UNT Libraries Government Documents Department
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Fuel Rod Behavior During Test PCM-4

Description: This report presents and discusses the results from Test PCM-4 of the Power-Cooling-Mismatch Test Series.
Date: August 1979
Creator: Johnson, Roger L.; Lassahn, Pamela L.; Martinson, Zoel R.; Sparks, Daniel T. & Schwieder, David H.
Partner: UNT Libraries Government Documents Department
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[Appendix F. Cladding Surface Temperature Estimates (Test PCM-4)]

Description: "A summary of the methods used to establish fuel rod cladding temperatures associated with the axial region of film boiling for Test PCM-4 and the results of the calculations are presented in this appendix." (p. 219)
Date: August 1979
Creator: Johnson, Roger L.; Lassahn, Pamela L.; Martinson, Zoel R.; Sparks, Daniel T. & Schwieder, David H.
Partner: UNT Libraries Government Documents Department
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Fuel Rod Material Behavior During Test PCM-1

Description: This report presents the analysis of the fuel rod materials behavior based on the postirradiation examination of the Test PCM-1 fuel rod from the Power-Cooling-Mismatch Test Series.
Date: June 1979
Creator: Cook, Beverly A.
Partner: UNT Libraries Government Documents Department
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Appendix G. U0₂ Oxidation Calculation

Description: Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including the U0₂ oxidation calculation.
Date: June 1979
Creator: Cook, Beverly A.
Partner: UNT Libraries Government Documents Department
open access

Appendix F. Cladding Thermal Conductivity Changes

Description: Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including changes in cladding thermal conductivity with oxidation to ZrO₂.
Date: June 1979
Creator: Cook, Beverly A.
Partner: UNT Libraries Government Documents Department
open access

Appendix C. Metallographic Examination

Description: Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including additional metallography illustrating the physical and chemical changes in the cladding and fuel.
Date: June 1979
Creator: Cook, Beverly A.
Partner: UNT Libraries Government Documents Department
open access

Appendix D. Particle Size Analysis

Description: Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including tabulated data from the particle size analysis of the broke fuel rod pieces.
Date: June 1979
Creator: Cook, Beverly A.
Partner: UNT Libraries Government Documents Department
open access

Appendix B. Test Rod Power Profile

Description: Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including a description of the axial power profile.
Date: June 1979
Creator: Cook, Beverly A.
Partner: UNT Libraries Government Documents Department
open access

Appendix E. Microprobe Examination

Description: Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including details of the microprobe examination.
Date: June 1979
Creator: Cook, Beverly A.
Partner: UNT Libraries Government Documents Department
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