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Issue date | Title | Topic | |
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ML18151A386 | 31 October 1995 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Summary of Results | Hot Short Shutdown Margin Time to boil Internal Flooding Probabilistic Risk Assessment Eddy Current Testing Earthquake Fire Watch Fatality Water hammer |
ML20085J280 | 31 May 1995 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry, Unit 1.Evaluation of Severe Accident Risk During Mid-Loop Operations.Main Report | Boric Acid Ultimate heat sink Mission time Internal Flooding Probabilistic Risk Assessment Eddy Current Testing Chernobyl Fatality |
ML18153A755 | 31 May 1995 | Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan. | Hydrostatic VT-2 Incorporated by reference Liquid penetrant |
ML18151A243 | 31 May 1995 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry, Unit 1.Evaluation of Severe Accident Risk During Mid-Loop Operations.Appendices | Probabilistic Risk Assessment B.5.b Fatality Siren |
ML18151A208 | 31 May 1995 | the Probability of Containment Failure by Direct Containment Heating in Surry | |
ML18151A974 | 13 February 1995 | Technical Evaluation Rept on Third 10-Yr Interval ISI Program Plan:Virginia Electric & Power Co,Surry Power Station,Unit 1. | Boric Acid Hydrostatic VT-2 Incorporated by reference |
ML18152A345 | 31 October 1994 | Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:North Anna-1/-2 & Surry-1/-2. | |
ML18151A577 | 31 August 1994 | a Pilot Application of RISK-BASED Methods to Establish Inservice Inspection Priorities for Nuclear Components at Surry Unit 1 Nuclear Power Station | Probabilistic Risk Assessment Nondestructive Examination Earthquake |
ML18151A372 | 31 August 1994 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry, Unit 1.Analysis of Core Damage Frequency from Seismic Events During Mid-Loop Operations.Main Report | Safe Shutdown Earthquake Internal Flooding Probabilistic Risk Assessment Seismically rugged Earthquake |
ML18151A384 | 31 July 1994 | Technical Evaluation Rept Pump & Valve Inservice Testing Program Plant Units 1 & 2. | Boric Acid Stroke time Cold shutdown justification Power-Operated Valves Power Operated Valves Thermography |
ML18151A227 | 31 July 1994 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Analysis of Core Damage Frequency from Internal Fires During Mid-Loop Operations.Main Report | |
ML18151A168 | 31 July 1994 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Analysis of Core Damage Frequency from Internal Floods During Mid-Loop Operations | Safe Shutdown Boric Acid Mission time Fire Barrier Internal Flooding Hydrostatic Probabilistic Risk Assessment Fuel cladding Water hammer |
ML18150A463 | 31 July 1994 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Analysis of Core Damage Frequency from Internal Fires During Mid-Loop Operations.Appendices | |
ML18151A262 | 30 June 1994 | 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 | 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) | |
ML18151A241 | 30 June 1994 | Experiments to Investigate Direct Containment Heating Phenomena with Scaled Models of the Surry Nuclear Power Plant | Grab sample |
ML18151A226 | 30 June 1994 | 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 | Boric Acid Shutdown Margin Reactor Vessel Water Level Mission time Internal Flooding Probabilistic Risk Assessment Earthquake Failure to Scram |
ML18151A207 | 30 June 1994 | 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 | Boric Acid Shutdown Margin Reactor Vessel Water Level Loop seal Packing leak Stroke time Internal Flooding Hydrostatic Probabilistic Risk Assessment Local Leak Rate Testing Integrated leak rate test Eddy Current Testing Control of Heavy Loads Liquid penetrant Unidentified leakage Subsequent actuation Water hammer |
ML18151A149 | 30 June 1994 | 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) | Boric Acid Shutdown Margin Ultimate heat sink Mission time Internal Flooding Probabilistic Risk Assessment Eddy Current Testing Chernobyl Eddy-Current Testing |
ML18150A462 | 30 June 1994 | 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 | 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) | Safe Shutdown Boric Acid Shutdown Margin Ultimate heat sink Mission time Internal Flooding Hydrostatic Probabilistic Risk Assessment Reserve Station Service Transformer Eddy Current Testing Chernobyl Biofouling Loss of condenser vacuum Water hammer |
ML20065E253 | 31 March 1994 | Summary of Melcor 1.8.2 Calculations for Three LOCA Sequences (AG,S2D & S3D) at the Surry Plant | |
ML18151A239 | 30 November 1993 | Assessment of the Potential for High Pressure MELT Ejection Resulting from a Surry Station Blackout Transient | Loop seal Probabilistic Risk Assessment Fuel cladding |
ML20064K802 | 10 August 1993 | Abridged Risk Study During Low Power/Shutdown Operation at Surry | |
ML18151A899 | 31 May 1992 | Summary Rept of :Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Draft Ltr Rept | |
ML18152A050 | 29 May 1992 | Abridged Risk Study During Low Power /Shutdown Operation at Surry, Draft Ltr Rept | Fatality |
ML20028H600 | 31 December 1990 | Analysis of Core Damage Frequency: Surry Power Station,Unit 1 External Events | |
ML20058H759 | 31 October 1990 | Evaluation of Severe Accident Risks: Surry Unit 1.Main Report | |
ML20058H764 | 31 October 1990 | Evaluation of Severe Accident Risks: Surry Unit 1. Appendices | Earthquake |
ML18152A161 | 24 September 1990 | Technical Evaluation Rept Surry Power Station Units 1 & 2,Station Blackout Evaluation, Final Rept | Safe Shutdown Reserve Station Service Transformer |
ML18151A143 | 30 April 1990 | Analysis of Core Damage Frequency:Surry,Unit 1,INTERNAL Events | Safe Shutdown Boric Acid Ultimate heat sink Mission time Probabilistic Risk Assessment Integrated leak rate test Failure to Scram |
ML18150A450 | 30 April 1990 | Analysis of Core Damage Frequency: Surry,Unit 1,INTERNAL Events Appendices | Boric Acid Mission time Probabilistic Risk Assessment B.5.b Biofouling |
ML20058K170 | 30 March 1990 | Pump & Valve Inservice Testing Program,Surry Power Station, Units 1 & 2, Technical Evaluation Rept | |
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 |
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 | |
ML20155K493 | 31 October 1988 | Analyses of Natural Circulation During a Surry Station Blackout Using SCDAP/RELAP5 | Loop seal Fuel cladding |
ML20205N943 | 31 October 1988 | Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 | |
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 |
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 |
ML18040B189 | 31 August 1987 | Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. | |
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 | |
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 | |
ML18153B547 | 31 July 1987 | PRA Applications Program for Insp at Surry Nuclear Power Station,Unit 1, Draft Rept | Boric Acid Probabilistic Risk Assessment Systematic Assessment of Licensee Performance |