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| Issue date | Title | Topic | |
|---|---|---|---|
| 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 Earthquake Fire Watch Fatality |
| 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 Chernobyl |
| 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 Mitigating Strategies |
| 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 |
| 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 |
| 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 |
| 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 Control of Heavy Loads Liquid penetrant |
| 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 Chernobyl |
| 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 Chernobyl Biofouling |
| 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 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 Mitigating Strategies 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 |