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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 |
| 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 |
| 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 |
| 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 |
| 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 | |
| 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 | |
| ML20066D342 | 31 December 1990 | Evaluation of Severe Accident Risks: Grand Gulf,Unit 1. Appendices | Probabilistic Risk Assessment Fatality |
| ML20066D298 | 31 December 1990 | Evaluation of Severe Accident Risks: Grand Gulf,Unit 1.Main Report | |
| 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 |
| ML19332B614 | 31 October 1989 | Conformance to Generic Ltr 83-28,Item 2.2.1--Equipment Classification for All Other Safety-Related Components:Quad Cities 1 & 2, Final Technical Evaluation Rept | Safe Shutdown |
| 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 | |
| ML20246B815 | 30 April 1989 | Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Duane Arnold,Enrico Fermi-2,Hope Creek,Lasalle County 1 & 2, Limerick 1 & 2,Millstone 1,Monticello,Nine Mile Point 1 & 2 & Oyster Creek, Technical Evaluation Rept | |
| ML20246B973 | 31 March 1989 | Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept | Boric Acid |
| ML20236B805 | 13 March 1989 | Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files | |
| 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. | |
| ML20205N943 | 31 October 1988 | Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 | |
| ML19325C158 | 22 February 1988 | Technical Evaluation of Dcrdr. | |
| ML20196C164 | 4 February 1988 | Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 | |
| ML20205N953 | 31 January 1988 | Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 | Safe Shutdown |
| ML20205N948 | 31 January 1988 | Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 | Safe Shutdown |
| 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. | |
| ML20235V152 | 31 August 1987 | Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2 | |
| ML20235M359 | 31 August 1987 | Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept | Boric Acid |
| ML20237J062 | 19 August 1987 | Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds | Backfit |
| ML20237J141 | 17 August 1987 | Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 | |
| ML20236D918 | 31 July 1987 | Methodology and Application of Surrogate Plant PRA Analysis to the Rancho Seco Power Plant.Task 1 - Analysis of ANO-1 and Oconee PRAs | Probabilistic Risk Assessment Earthquake |
| ML20236P640 | 31 July 1987 | Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept | |
| ML17347A593 | 31 July 1987 | Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept | |
| ML18052B193 | 30 June 1987 | Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Calvert Cliffs-1 & -2, Millstone-2 & Palisades, Final Informal Rept | |
| ML20235A016 | 30 April 1987 | Analysis of Core Damage Frequency from Internal Events:Grand Gulf,Unit 1.Main Report | Ultimate heat sink Probabilistic Risk Assessment |
| ML18152A583 | 30 April 1987 | Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. | |
| ML18150A119 | 30 April 1987 | Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept | |
| ML18150A188 | 30 April 1987 | Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept |