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Issue date | Site | Title | |
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ML22228A253 | 17 August 2022 | 8-17-2022 Public Meeting on Path Forward for Site-Specific Environmental Reviews for Subsequent License Renewal - Slides | |
ML22199A023 | 21 July 2022 | Perry | July 21, 2022, Perry Nuclear Power Plant License Renewal Environmental Pre-application Public Meeting - NRC Slides |
ML093130688 | 5 June 2009 | Oyster Creek | Email from Qte Resource to E. Miller, Request for Technical Editing |
ML18151A262 | 30 June 1994 | Surry | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Analysis of Core Damage Frequency from Internal Events During Mid-Loop Operations.Appendices E (Sections E.9-E.16) |
ML18151A242 | 30 June 1994 | Surry | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Analysis of Core Damage Frequency from Internal Events During Mid-Loop Operations.Appendices E (Sections E.1-E.8) |
ML18151A226 | 30 June 1994 | Surry | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Analysis of Core Damage Frequency from Internal Events During Mid-Loop Operations.Appendices I |
ML18151A207 | 30 June 1994 | Surry | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Analysis of Core Damage Frequency from Internal Events During Mid-Loop Operations.Appendices A-D |
ML18151A149 | 30 June 1994 | Surry | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Analysis of Core Damage Frequency from Internal Events During Mid-Loop Operations.Main Report (Chapters 7-12) |
ML18150A462 | 30 June 1994 | Surry | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Analysis of Core Damage Frequency from Internal Events During Mid-Loop Operations.Appendices F-H |
ML18150A459 | 30 June 1994 | Surry | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Analysis of Core Damage Frequency from Internal Events During Mid-Loop Operations.Main Report (Chapters 1-6) |
ML20126F630 | 31 December 1992 | Special Study Pressure Locking & Thermal Binding of Gate Valves | |
ML20062B110 | 10 October 1990 | Arkansas Nuclear | Forwards AEOD/T90-13, Corrosion & Failure of Svc Water Pump Impeller Snap Rings, of 881111 Event |
ML20062B115 | 10 October 1990 | Arkansas Nuclear | AEOD/T90-13, Corrosion & Failure of Svc Water Pump Impeller Snap Rings, of 881111 Event |
ML20055F811 | 3 July 1990 | Sequoyah | AEOD/E90-06, Potential for RHR Sys Pump Damage |
ML20204J614 | 31 August 1988 | Susquehanna McGuire 05000000 | AEOD/E807, Pump Damage Due to Low Flow Cavitation |
ML20245B573 | 31 March 1987 | Design & Const Problems at Operating Nuclear Plants | |
ML20209B412 | 31 August 1986 | Davis Besse | Operational Experience Involving Turbine Overspeed Trips, Case Study Rept |
ML20210K878 | 30 April 1986 | Operational Experience Involving Turbine Overspeed Trips | |
ML20137N597 | 17 July 1985 | Beaver Valley | Forwards AEOD/T505, Beaver Valley Component Cooling Water Pump Damage, Technical Review Rept.Since Misalignment Can Be Prevented by Proper Administration of Maint Procedures for Motor Assembly,No Addl NRC Action Necessary |
ML20137N607 | 17 July 1985 | Beaver Valley | AEOD/T505, Beaver Valley Component Cooling Water Pump Damage, Technical Review Rept |
ML20129G270 | 20 May 1985 | Brunswick | Forwards Engineering Evaluation Rept AEOD/E506, Valve Stem Susceptibility to IGSCC Due to Improper Heat Treatment |
ML20129G303 | 13 May 1985 | Brunswick | Valve Stem Susceptibility to IGSCC Due to Improper Heat Treatment, Engineering Evaluation Rept |
ML20062P044 | 10 January 1980 | Oconee 05000000 | Discusses B&W Overfeed Transient Analysis Using IRT Deck Simulating Facilities.Figures 1-9 Re Computed Transient Results Encl |
ML19282C208 | 31 January 1979 | Peach Bottom | Thermal-Hydraulic Analysis of Peach Bottom II Turbine Trip Tests, Interim Rept |