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 Issue dateTitleTopic
ML18151A38631 October 1995Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Summary of ResultsHot Short
Shutdown Margin
Time to boil
Internal Flooding
Probabilistic Risk Assessment
Eddy Current Testing
Earthquake
Fire Watch
Fatality
Water hammer
ML20085J28031 May 1995Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry, Unit 1.Evaluation of Severe Accident Risk During Mid-Loop Operations.Main ReportBoric Acid
Ultimate heat sink
Mission time
Internal Flooding
Probabilistic Risk Assessment
Eddy Current Testing
Chernobyl
Fatality
ML18153A75531 May 1995Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan.Hydrostatic
VT-2
Incorporated by reference
Liquid penetrant
ML18151A24331 May 1995Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry, Unit 1.Evaluation of Severe Accident Risk During Mid-Loop Operations.AppendicesProbabilistic Risk Assessment
B.5.b
Fatality
Siren
ML18151A20831 May 1995the Probability of Containment Failure by Direct Containment Heating in Surry
ML18151A97413 February 1995Technical 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
ML18152A34531 October 1994Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:North Anna-1/-2 & Surry-1/-2.
ML18151A57731 August 1994a Pilot Application of RISK-BASED Methods to Establish Inservice Inspection Priorities for Nuclear Components at Surry Unit 1 Nuclear Power StationProbabilistic Risk Assessment
Nondestructive Examination
Earthquake
ML18151A37231 August 1994Evaluation 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 ReportSafe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
Seismically rugged
Earthquake
ML18150A46331 July 1994Evaluation 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
ML18151A16831 July 1994Evaluation 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 OperationsSafe Shutdown
Boric Acid
Mission time
Fire Barrier
Internal Flooding
Hydrostatic
Probabilistic Risk Assessment
Fuel cladding
Water hammer
ML18151A38431 July 1994Technical 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
ML18151A22731 July 1994Evaluation 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
ML18150A45930 June 1994Evaluation 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
ML18150A46230 June 1994Evaluation 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
ML18151A14930 June 1994Evaluation 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
ML18151A26230 June 1994Evaluation 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 1994Evaluation 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)
ML18151A24130 June 1994Experiments to Investigate Direct Containment Heating Phenomena with Scaled Models of the Surry Nuclear Power PlantGrab sample
ML18151A22630 June 1994Evaluation 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 IBoric Acid
Shutdown Margin
Reactor Vessel Water Level
Mission time
Internal Flooding
Probabilistic Risk Assessment
Earthquake
Failure to Scram
ML18151A20730 June 1994Evaluation 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-DBoric 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
ML20065E25331 March 1994Summary of Melcor 1.8.2 Calculations for Three LOCA Sequences (AG,S2D & S3D) at the Surry Plant
ML18151A23930 November 1993Assessment of the Potential for High Pressure MELT Ejection Resulting from a Surry Station Blackout TransientLoop seal
Probabilistic Risk Assessment
Fuel cladding
ML20064K80210 August 1993Abridged Risk Study During Low Power/Shutdown Operation at Surry
ML18151A89931 May 1992Summary Rept of :Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Draft Ltr Rept
ML18152A05029 May 1992Abridged Risk Study During Low Power /Shutdown Operation at Surry, Draft Ltr ReptFatality
ML20028H60031 December 1990Analysis of Core Damage Frequency: Surry Power Station,Unit 1 External Events
ML20058H76431 October 1990Evaluation of Severe Accident Risks: Surry Unit 1. AppendicesEarthquake
ML20058H75931 October 1990Evaluation of Severe Accident Risks: Surry Unit 1.Main Report
ML18152A16124 September 1990Technical Evaluation Rept Surry Power Station Units 1 & 2,Station Blackout Evaluation, Final ReptSafe Shutdown
Reserve Station Service Transformer
ML18150A45030 April 1990Analysis of Core Damage Frequency: Surry,Unit 1,INTERNAL Events AppendicesBoric Acid
Mission time
Probabilistic Risk Assessment
B.5.b
Biofouling
ML18151A14330 April 1990Analysis of Core Damage Frequency:Surry,Unit 1,INTERNAL EventsSafe Shutdown
Boric Acid
Ultimate heat sink
Mission time
Probabilistic Risk Assessment
Integrated leak rate test
Failure to Scram
ML20058K17030 March 1990Pump & Valve Inservice Testing Program,Surry Power Station, Units 1 & 2, Technical Evaluation Rept
ML19332B61431 October 1989Conformance to Generic Ltr 83-28,Item 2.2.1--Equipment Classification for All Other Safety-Related Components:Quad Cities 1 & 2, Final Technical Evaluation ReptSafe Shutdown
ML20248E21916 August 1989Mod 16,reflecting Return of Equipment to Tva,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators
ML20248E21216 August 1989Notification of Contract Execution,Mod 16,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva
ML20247R38516 May 1989Notification of Contract Execution,Mod 15,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn,For Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva
ML20247R39416 May 1989Mod 15,extending Period of Performance,Providing Addl Work Re Training for NRC Inspectors & Supervisors,Changing NRC Project Officer & Adding TVA Project Manager & Increasing Contract Ceiling & Funding to Use of TVA Reactor..
ML20246B81530 April 1989Rev 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
ML20246B97331 March 1989Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation ReptBoric Acid
ML20236B80513 March 1989Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files
ML20205N94331 October 1988Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1
ML20155K49331 October 1988Analyses of Natural Circulation During a Surry Station Blackout Using SCDAP/RELAP5Loop seal
Fuel cladding
ML20155B7391 June 1988Notification of Contract Execution,Mod 1,to Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites. Contractor:New England Telephone Co
ML20155B7531 June 1988Corrected Mod 1,restoring Funds That Was Deobligated & Providing Final Increment of Funding to Contract,To Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee, Pilgrim & Seabrook Resident Sites
ML20150D90917 March 1988Mod 1,deobligating Funds from Total Obligated Amount of Contract & to Correct FIN Number,To Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites
ML20150D90017 March 1988Notification of Contract Execution,Mod 1,to Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites. Contractor:New England Telephone Co
ML20196C1644 February 1988Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131
ML20205N94831 January 1988Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2Safe Shutdown
ML20205N95331 January 1988Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3Safe Shutdown