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Issue date | Title | Topic | |
---|---|---|---|
ML20211K768 | 30 July 1999 | Evaluation of Fuel Pin Failure Timing in Boiling Water Reactors | |
ML20216E872 | 13 March 1998 | Rept to NRC Environ Monitoring at Grand Gulf Nuclear Station CY97, Conducted by Contract NRC-29-83-621 | |
ML20101C894 | 16 October 1995 | Plant IPE Insight Support Rept for NUREG-1150 Plants | Internal Flooding Probabilistic Risk Assessment |
ML20087K369 | 31 July 1995 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Summary of Results | Mission time Internal Flooding Probabilistic Risk Assessment Earthquake Fatality |
ML20082D526 | 31 March 1995 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Supporting Melcor Calculations | Ultimate heat sink Internal Flooding Hydrostatic Probabilistic Risk Assessment Fuel cladding |
ML20082B741 | 31 March 1995 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Main Report and Appendices | |
ML20073C367 | 31 August 1994 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf, Unit 1.Analysis of Core Damage Frequency from Seismic Events During Mid-Loop Operations.Main Report | Safe Shutdown Earthquake Internal Flooding Probabilistic Risk Assessment Operating Basis Earthquake Seismically rugged Earthquake |
ML20072D058 | 31 July 1994 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage | Safe Shutdown Fire Barrier Probabilistic Risk Assessment |
ML20072N999 | 31 July 1994 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internally Induced Flooding Events for Plant Operational State 5 During a Refueling. | Mission time Internal Flooding Probabilistic Risk Assessment Earthquake |
ML20071L719 | 30 June 1994 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal | |
ML20071L741 | 30 June 1994 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal | Mission time Internal Flooding Probabilistic Risk Assessment |
ML20071L611 | 30 June 1994 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During Refueling Outage.Internal | |
ML20071L597 | 30 June 1994 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Main Report | |
ML20071L583 | 30 June 1994 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Section 10 | |
ML20071L566 | 30 June 1994 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Sections 1-9 | |
ML20063B550 | 24 January 1994 | Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,Grand Gulf,Unit 1, Technical Evaluation Rept | |
ML20064K051 | 31 October 1993 | Summary Rept Of:Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Final Ltr Rept | |
ML18151A899 | 31 May 1992 | Summary Rept of :Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Draft Ltr Rept | |
ML20066D298 | 31 December 1990 | Evaluation of Severe Accident Risks: Grand Gulf,Unit 1.Main Report | |
ML20066D342 | 31 December 1990 | Evaluation of Severe Accident Risks: Grand Gulf,Unit 1. Appendices | Probabilistic Risk Assessment Fatality |
ML20059N510 | 31 August 1990 | Technical Evaluation Rept on Response from Sys Energy Resources,Inc to Generic Ltr 88-01 Re Grand Gulf Nuclear Plant | Packing leak Weld Overlay Pressure Boundary Leakage |
ML19332G564 | 30 November 1989 | Analysis of Core Damage Frequency: Grand Gulf, Unit 1 Internal Events Appendices.Continuation of Appendix D | Probabilistic Risk Assessment |
ML20248F341 | 30 September 1989 | Analysis of Core Damage Frequency: Grand Gulf, Unit 1 Internal Events Appendices | Reactor Vessel Water Level Probabilistic Risk Assessment |
ML20248F345 | 30 September 1989 | Analysis of Core Damage Frequency: Grand Gulf, Unit 1 Internal Events | Half scram Mission time Probabilistic Risk Assessment Emergency Lighting Pressure boundary leak |
ML19324A623 | 31 May 1989 | Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Grand Gulf-1, Technical Evaluation Rept | |
ML20070Q557 | 31 January 1989 | Nuclear Power Plant Sys Sourcebook,Grand Gulf 1 | Safe Shutdown Ultimate heat sink Scram Discharge Volume |
ML20043B372 | 31 December 1988 | Stability Measurements During Cycle 2. | |
ML19325C158 | 22 February 1988 | Technical Evaluation of Dcrdr. | |
ML20235J229 | 30 September 1987 | Draft PRA-Based Sys Insp Plans | |
ML18040B189 | 31 August 1987 | Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. | |
ML20235A016 | 30 April 1987 | Analysis of Core Damage Frequency from Internal Events:Grand Gulf,Unit 1.Main Report | Ultimate heat sink Probabilistic Risk Assessment |
ML20235A048 | 30 April 1987 | Abslysis of Core Damage Frequency from Internal Events:Grand Gulf,Unit 1.Appendices | |
ML20234B683 | 30 April 1987 | Evaluation of Severe Accident Risks and the Potential for Risk Reduction:Grand Gulf,Unit 1.Draft for Comment | |
ML20214V249 | 30 April 1987 | Containment Event Analysis for Postulated Severe Accidents: Grand Gulf Nuclear Station,Unit 1.Draft for Comment | Probabilistic Risk Assessment Earthquake |
ML20214S346 | 31 March 1987 | Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Grand Gulf 1 & 2, Informal Rept | |
ML20207S520 | 30 November 1986 | Technical Evaluation Rept for River Bend Station on SER Outstanding Issue (8) - Mark III Containment Sys Issues - Humphrey Safety Concerns (Hsc) | |
ML20207S523 | 30 November 1986 | Technical Evaluation Rept for Gessar II Responses for Resolution of Humphrey Safety Concerns (Hsc) Re Mark III Containment Sys | Hydrostatic |
ML20207S507 | 30 September 1986 | Technical Evaluation Rept for Grand Gulf Nuclear Station on SER Outstanding Issue (8) - Mark III Containment Sys Issues - Humphrey Safety Concerns (Hsc) | Hydrostatic |
ML20207S515 | 30 June 1986 | Technical Evaluation Rept for Clinton Power Station on SER Outstanding Issue (8) - Mark III Containment Sys Issues - Humphrey Safety Concerns (Hsc) | Hydrostatic |
ML20155E064 | 8 April 1986 | App D to Evaluation of Licensee-Reported Revs to Process Control Program, Requesting Addl Info | Grab sample Process Control Program |
ML20155D126 | 2 April 1986 | App D to Evaluation of Licensee-Reported Revs to Offsite Dose Calculation Manual | Offsite Dose Calculation Manual |
ML20214G959 | 31 March 1986 | Conformance to Generic Ltr 83-28,Item 2.1 (Part 2) Equipment Qualification (Reactor Trip Sys Components), Selected GE BWR Plants | |
ML20212G359 | 31 March 1986 | Conformance to Reg Guide 1.97,Grand Gulf Nuclear Station, Unit 1 | Squib Fuel cladding |
ML20211F030 | 31 March 1986 | Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (RTS Components) Selected GE BWR Plants (Grand Gulf 1 & 2,Hatch 1 & 2,LaSalle 1 & 2 & Millstone 1) | |
ML20202J455 | 28 March 1986 | First Interval Inservice Insp Program,Grand Gulf Nuclear Station, Technical Evaluation Rept | Hydrostatic VT-2 Incorporated by reference Scram Discharge Volume Liquid penetrant Dissimilar Metal Weld |
ML20136F653 | 31 December 1985 | Review of Tdi Diesel Generator Owners Group Engine Requalification Program,Final Rept, Technical Evaluation Rept | Nondestructive Examination |
ML20207S510 | 30 November 1985 | Technical Evaluation Rept for Perry Nuclear Power Plant on SER Outstanding Issue (8) - Mark III Containment Sys Issues - Humphrey Safety Concerns (Hsc) | Hydrostatic |
ML20138H132 | 31 October 1985 | Conformance to Reg Guide 1.97,Grand Gulf Nuclear Station, Unit 1 | Squib Fuel cladding |
ML20138R898 | 31 October 1985 | Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3,Grand Gulf Units 1 & 2, Technical Evaluation Rept | |
ML20128H779 | 30 June 1985 | Rev 1 to Review of Engine Base & Bearing Caps for Tdi DSRV-12,DSRV-16 & DSRV-20 Diesel Engines, Technical Evaluation Rept |