Category:CONTRACTED REPORT - RTA
MONTHYEARML18151A3861995-10-31031 October 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Summary of Results ML20085J2801995-05-31031 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 ML18151A2081995-05-31031 May 1995 the Probability of Containment Failure by Direct Containment Heating in Surry ML18153A7551995-05-31031 May 1995 Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan. ML18151A2431995-05-31031 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 ML18151A9741995-02-13013 February 1995 Technical Evaluation Rept on Third 10-Yr Interval ISI Program Plan:Virginia Electric & Power Co,Surry Power Station,Unit 1. ML18152A3451994-10-31031 October 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:North Anna-1/-2 & Surry-1/-2. ML18151A3721994-08-31031 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 ML18151A5771994-08-31031 August 1994 a Pilot Application of RISK-BASED Methods to Establish Inservice Inspection Priorities for Nuclear Components at Surry Unit 1 Nuclear Power Station ML18150A4631994-07-31031 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 ML18151A1681994-07-31031 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 ML18151A2271994-07-31031 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 ML18151A3841994-07-31031 July 1994 Technical Evaluation Rept Pump & Valve Inservice Testing Program Plant Units 1 & 2. ML18150A4591994-06-30030 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) ML18150A4621994-06-30030 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 ML18151A1491994-06-30030 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) ML18151A2071994-06-30030 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 ML18151A2261994-06-30030 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 ML18151A2411994-06-30030 June 1994 Experiments to Investigate Direct Containment Heating Phenomena with Scaled Models of the Surry Nuclear Power Plant ML18151A2421994-06-30030 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) ML18151A2621994-06-30030 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) ML20065E2531994-03-31031 March 1994 Summary of Melcor 1.8.2 Calculations for Three LOCA Sequences (AG,S2D & S3D) at the Surry Plant ML18151A2391993-11-30030 November 1993 Assessment of the Potential for High Pressure MELT Ejection Resulting from a Surry Station Blackout Transient ML20064K8021993-08-10010 August 1993 Abridged Risk Study During Low Power/Shutdown Operation at Surry ML18151A8991992-05-31031 May 1992 Summary Rept of :Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Draft Ltr Rept ML18152A0501992-05-29029 May 1992 Abridged Risk Study During Low Power /Shutdown Operation at Surry, Draft Ltr Rept ML20028H6001990-12-31031 December 1990 Analysis of Core Damage Frequency: Surry Power Station,Unit 1 External Events ML20058H7591990-10-31031 October 1990 Evaluation of Severe Accident Risks: Surry Unit 1.Main Report ML20058H7641990-10-31031 October 1990 Evaluation of Severe Accident Risks: Surry Unit 1. Appendices ML18152A1611990-09-24024 September 1990 Technical Evaluation Rept Surry Power Station Units 1 & 2,Station Blackout Evaluation, Final Rept ML18150A4501990-04-30030 April 1990 Analysis of Core Damage Frequency: Surry,Unit 1,INTERNAL Events Appendices ML18151A1431990-04-30030 April 1990 Analysis of Core Damage Frequency:Surry,Unit 1,INTERNAL Events ML20058K1701990-03-30030 March 1990 Pump & Valve Inservice Testing Program,Surry Power Station, Units 1 & 2, Technical Evaluation Rept ML19332B6141989-10-31031 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 ML20246B8151989-04-30030 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 ML20246B9731989-03-31031 March 1989 Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept ML20236B8051989-03-13013 March 1989 Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files ML20155K4931988-10-31031 October 1988 Analyses of Natural Circulation During a Surry Station Blackout Using SCDAP/RELAP5 ML20205N9431988-10-31031 October 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20205N9481988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 ML20205N9531988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. ML20235V1521987-08-31031 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 ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML20236D9181987-07-31031 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 ML18153B5471987-07-31031 July 1987 PRA Applications Program for Insp at Surry Nuclear Power Station,Unit 1, Draft Rept 1995-05-31
[Table view] Category:QUICK LOOK
MONTHYEARML18151A3861995-10-31031 October 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Summary of Results ML20085J2801995-05-31031 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 ML18151A2081995-05-31031 May 1995 the Probability of Containment Failure by Direct Containment Heating in Surry ML18153A7551995-05-31031 May 1995 Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan. ML18151A2431995-05-31031 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 ML18151A9741995-02-13013 February 1995 Technical Evaluation Rept on Third 10-Yr Interval ISI Program Plan:Virginia Electric & Power Co,Surry Power Station,Unit 1. ML18152A3451994-10-31031 October 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:North Anna-1/-2 & Surry-1/-2. ML18151A3721994-08-31031 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 ML18151A5771994-08-31031 August 1994 a Pilot Application of RISK-BASED Methods to Establish Inservice Inspection Priorities for Nuclear Components at Surry Unit 1 Nuclear Power Station ML18150A4631994-07-31031 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 ML18151A1681994-07-31031 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 ML18151A2271994-07-31031 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 ML18151A3841994-07-31031 July 1994 Technical Evaluation Rept Pump & Valve Inservice Testing Program Plant Units 1 & 2. ML18150A4591994-06-30030 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) ML18150A4621994-06-30030 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 ML18151A1491994-06-30030 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) ML18151A2071994-06-30030 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 ML18151A2261994-06-30030 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 ML18151A2411994-06-30030 June 1994 Experiments to Investigate Direct Containment Heating Phenomena with Scaled Models of the Surry Nuclear Power Plant ML18151A2421994-06-30030 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) ML18151A2621994-06-30030 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) ML20065E2531994-03-31031 March 1994 Summary of Melcor 1.8.2 Calculations for Three LOCA Sequences (AG,S2D & S3D) at the Surry Plant ML18151A2391993-11-30030 November 1993 Assessment of the Potential for High Pressure MELT Ejection Resulting from a Surry Station Blackout Transient ML20064K8021993-08-10010 August 1993 Abridged Risk Study During Low Power/Shutdown Operation at Surry ML18151A8991992-05-31031 May 1992 Summary Rept of :Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Draft Ltr Rept ML18152A0501992-05-29029 May 1992 Abridged Risk Study During Low Power /Shutdown Operation at Surry, Draft Ltr Rept ML20028H6001990-12-31031 December 1990 Analysis of Core Damage Frequency: Surry Power Station,Unit 1 External Events ML20058H7591990-10-31031 October 1990 Evaluation of Severe Accident Risks: Surry Unit 1.Main Report ML20058H7641990-10-31031 October 1990 Evaluation of Severe Accident Risks: Surry Unit 1. Appendices ML18152A1611990-09-24024 September 1990 Technical Evaluation Rept Surry Power Station Units 1 & 2,Station Blackout Evaluation, Final Rept ML18150A4501990-04-30030 April 1990 Analysis of Core Damage Frequency: Surry,Unit 1,INTERNAL Events Appendices ML18151A1431990-04-30030 April 1990 Analysis of Core Damage Frequency:Surry,Unit 1,INTERNAL Events ML20058K1701990-03-30030 March 1990 Pump & Valve Inservice Testing Program,Surry Power Station, Units 1 & 2, Technical Evaluation Rept ML19332B6141989-10-31031 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 ML20246B8151989-04-30030 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 ML20246B9731989-03-31031 March 1989 Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept ML20236B8051989-03-13013 March 1989 Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files ML20155K4931988-10-31031 October 1988 Analyses of Natural Circulation During a Surry Station Blackout Using SCDAP/RELAP5 ML20205N9431988-10-31031 October 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20205N9481988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 ML20205N9531988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. ML20235V1521987-08-31031 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 ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML20236D9181987-07-31031 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 ML18153B5471987-07-31031 July 1987 PRA Applications Program for Insp at Surry Nuclear Power Station,Unit 1, Draft Rept 1995-05-31
[Table view] Category:ETC. (PERIODIC
MONTHYEARML18151A3861995-10-31031 October 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Summary of Results ML20085J2801995-05-31031 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 ML18151A2081995-05-31031 May 1995 the Probability of Containment Failure by Direct Containment Heating in Surry ML18153A7551995-05-31031 May 1995 Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan. ML18151A2431995-05-31031 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 ML18151A9741995-02-13013 February 1995 Technical Evaluation Rept on Third 10-Yr Interval ISI Program Plan:Virginia Electric & Power Co,Surry Power Station,Unit 1. ML18152A3451994-10-31031 October 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:North Anna-1/-2 & Surry-1/-2. ML18151A3721994-08-31031 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 ML18151A5771994-08-31031 August 1994 a Pilot Application of RISK-BASED Methods to Establish Inservice Inspection Priorities for Nuclear Components at Surry Unit 1 Nuclear Power Station ML18150A4631994-07-31031 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 ML18151A1681994-07-31031 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 ML18151A2271994-07-31031 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 ML18151A3841994-07-31031 July 1994 Technical Evaluation Rept Pump & Valve Inservice Testing Program Plant Units 1 & 2. ML18150A4591994-06-30030 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) ML18150A4621994-06-30030 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 ML18151A1491994-06-30030 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) ML18151A2071994-06-30030 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 ML18151A2261994-06-30030 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 ML18151A2411994-06-30030 June 1994 Experiments to Investigate Direct Containment Heating Phenomena with Scaled Models of the Surry Nuclear Power Plant ML18151A2421994-06-30030 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) ML18151A2621994-06-30030 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) ML20065E2531994-03-31031 March 1994 Summary of Melcor 1.8.2 Calculations for Three LOCA Sequences (AG,S2D & S3D) at the Surry Plant ML18151A2391993-11-30030 November 1993 Assessment of the Potential for High Pressure MELT Ejection Resulting from a Surry Station Blackout Transient ML20064K8021993-08-10010 August 1993 Abridged Risk Study During Low Power/Shutdown Operation at Surry ML18151A8991992-05-31031 May 1992 Summary Rept of :Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Draft Ltr Rept ML18152A0501992-05-29029 May 1992 Abridged Risk Study During Low Power /Shutdown Operation at Surry, Draft Ltr Rept ML20028H6001990-12-31031 December 1990 Analysis of Core Damage Frequency: Surry Power Station,Unit 1 External Events ML20058H7591990-10-31031 October 1990 Evaluation of Severe Accident Risks: Surry Unit 1.Main Report ML20058H7641990-10-31031 October 1990 Evaluation of Severe Accident Risks: Surry Unit 1. Appendices ML18152A1611990-09-24024 September 1990 Technical Evaluation Rept Surry Power Station Units 1 & 2,Station Blackout Evaluation, Final Rept ML18150A4501990-04-30030 April 1990 Analysis of Core Damage Frequency: Surry,Unit 1,INTERNAL Events Appendices ML18151A1431990-04-30030 April 1990 Analysis of Core Damage Frequency:Surry,Unit 1,INTERNAL Events ML20058K1701990-03-30030 March 1990 Pump & Valve Inservice Testing Program,Surry Power Station, Units 1 & 2, Technical Evaluation Rept ML19332B6141989-10-31031 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 ML20246B8151989-04-30030 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 ML20246B9731989-03-31031 March 1989 Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept ML20236B8051989-03-13013 March 1989 Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files ML20155K4931988-10-31031 October 1988 Analyses of Natural Circulation During a Surry Station Blackout Using SCDAP/RELAP5 ML20205N9431988-10-31031 October 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20205N9481988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 ML20205N9531988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. ML20235V1521987-08-31031 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 ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML20236D9181987-07-31031 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 ML18153B5471987-07-31031 July 1987 PRA Applications Program for Insp at Surry Nuclear Power Station,Unit 1, Draft Rept 1995-05-31
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML18151A3861995-10-31031 October 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Summary of Results ML20085J2801995-05-31031 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 ML18153A7551995-05-31031 May 1995 Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan. ML18151A2081995-05-31031 May 1995 the Probability of Containment Failure by Direct Containment Heating in Surry ML18151A2431995-05-31031 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 ML18151A9741995-02-13013 February 1995 Technical Evaluation Rept on Third 10-Yr Interval ISI Program Plan:Virginia Electric & Power Co,Surry Power Station,Unit 1. ML18152A3451994-10-31031 October 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:North Anna-1/-2 & Surry-1/-2. ML18151A5771994-08-31031 August 1994 a Pilot Application of RISK-BASED Methods to Establish Inservice Inspection Priorities for Nuclear Components at Surry Unit 1 Nuclear Power Station ML18151A3721994-08-31031 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 ML18150A4631994-07-31031 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 ML18151A1681994-07-31031 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 ML18151A3841994-07-31031 July 1994 Technical Evaluation Rept Pump & Valve Inservice Testing Program Plant Units 1 & 2. ML18151A2271994-07-31031 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 ML18150A4591994-06-30030 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) ML18150A4621994-06-30030 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 ML18151A1491994-06-30030 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) ML18151A2071994-06-30030 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 ML18151A2261994-06-30030 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 ML18151A2621994-06-30030 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) ML18151A2421994-06-30030 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) ML18151A2411994-06-30030 June 1994 Experiments to Investigate Direct Containment Heating Phenomena with Scaled Models of the Surry Nuclear Power Plant ML20065E2531994-03-31031 March 1994 Summary of Melcor 1.8.2 Calculations for Three LOCA Sequences (AG,S2D & S3D) at the Surry Plant ML18151A2391993-11-30030 November 1993 Assessment of the Potential for High Pressure MELT Ejection Resulting from a Surry Station Blackout Transient ML20064K8021993-08-10010 August 1993 Abridged Risk Study During Low Power/Shutdown Operation at Surry ML18151A8991992-05-31031 May 1992 Summary Rept of :Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Draft Ltr Rept ML18152A0501992-05-29029 May 1992 Abridged Risk Study During Low Power /Shutdown Operation at Surry, Draft Ltr Rept ML20028H6001990-12-31031 December 1990 Analysis of Core Damage Frequency: Surry Power Station,Unit 1 External Events ML20058H7591990-10-31031 October 1990 Evaluation of Severe Accident Risks: Surry Unit 1.Main Report ML20058H7641990-10-31031 October 1990 Evaluation of Severe Accident Risks: Surry Unit 1. Appendices ML18152A1611990-09-24024 September 1990 Technical Evaluation Rept Surry Power Station Units 1 & 2,Station Blackout Evaluation, Final Rept ML18150A4501990-04-30030 April 1990 Analysis of Core Damage Frequency: Surry,Unit 1,INTERNAL Events Appendices ML18151A1431990-04-30030 April 1990 Analysis of Core Damage Frequency:Surry,Unit 1,INTERNAL Events ML20058K1701990-03-30030 March 1990 Pump & Valve Inservice Testing Program,Surry Power Station, Units 1 & 2, Technical Evaluation Rept ML19332B6141989-10-31031 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 ML20248E2191989-08-16016 August 1989 Mod 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 ML20248E2121989-08-16016 August 1989 Notification 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 ML20247R3941989-05-16016 May 1989 Mod 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.. ML20247R3851989-05-16016 May 1989 Notification 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 ML20246B8151989-04-30030 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 ML20246B9731989-03-31031 March 1989 Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept ML20236B8051989-03-13013 March 1989 Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files ML20155K4931988-10-31031 October 1988 Analyses of Natural Circulation During a Surry Station Blackout Using SCDAP/RELAP5 ML20205N9431988-10-31031 October 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 ML20155B7531988-06-0101 June 1988 Corrected 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 ML20155B7391988-06-0101 June 1988 Notification 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 ML20150D9091988-03-17017 March 1988 Mod 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 ML20150D9001988-03-17017 March 1988 Notification 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 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20205N9481988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 ML20205N9531988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 1995-05-31
[Table view] |