Semantic search

Jump to navigation Jump to search
 Issue dateSiteTitle
ML22228A25317 August 20228-17-2022 Public Meeting on Path Forward for Site-Specific Environmental Reviews for Subsequent License Renewal - Slides
ML22199A02321 July 2022PerryJuly 21, 2022, Perry Nuclear Power Plant License Renewal Environmental Pre-application Public Meeting - NRC Slides
ML0931306885 June 2009Oyster CreekEmail from Qte Resource to E. Miller, Request for Technical Editing
ML18151A26230 June 1994SurryEvaluation 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)
ML18151A24230 June 1994SurryEvaluation 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)
ML18151A22630 June 1994SurryEvaluation 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
ML18151A20730 June 1994SurryEvaluation 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
ML18151A14930 June 1994SurryEvaluation 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)
ML18150A46230 June 1994SurryEvaluation 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
ML18150A45930 June 1994SurryEvaluation 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)
ML20126F63031 December 1992Special Study Pressure Locking & Thermal Binding of Gate Valves
ML20062B11010 October 1990Arkansas NuclearForwards AEOD/T90-13, Corrosion & Failure of Svc Water Pump Impeller Snap Rings, of 881111 Event
ML20062B11510 October 1990Arkansas NuclearAEOD/T90-13, Corrosion & Failure of Svc Water Pump Impeller Snap Rings, of 881111 Event
ML20055F8113 July 1990SequoyahAEOD/E90-06, Potential for RHR Sys Pump Damage
ML20204J61431 August 1988Susquehanna
McGuire
05000000
AEOD/E807, Pump Damage Due to Low Flow Cavitation
ML20245B57331 March 1987Design & Const Problems at Operating Nuclear Plants
ML20209B41231 August 1986Davis BesseOperational Experience Involving Turbine Overspeed Trips, Case Study Rept
ML20210K87830 April 1986Operational Experience Involving Turbine Overspeed Trips
ML20137N59717 July 1985Beaver ValleyForwards 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
ML20137N60717 July 1985Beaver ValleyAEOD/T505, Beaver Valley Component Cooling Water Pump Damage, Technical Review Rept
ML20129G27020 May 1985BrunswickForwards Engineering Evaluation Rept AEOD/E506, Valve Stem Susceptibility to IGSCC Due to Improper Heat Treatment
ML20129G30313 May 1985BrunswickValve Stem Susceptibility to IGSCC Due to Improper Heat Treatment, Engineering Evaluation Rept
ML20062P04410 January 1980Oconee
05000000
Discusses B&W Overfeed Transient Analysis Using IRT Deck Simulating Facilities.Figures 1-9 Re Computed Transient Results Encl
ML19282C20831 January 1979Peach BottomThermal-Hydraulic Analysis of Peach Bottom II Turbine Trip Tests, Interim Rept