ML20126F659
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| ML20126F659 | |
| Person / Time | |
|---|---|
| Site: | Surry, Crystal River, 05000000 |
| Issue date: | 06/30/1983 |
| From: | Naus D OAK RIDGE NATIONAL LABORATORY |
| To: | Arndt G NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| Shared Package | |
| ML20126E434 | List: |
| References | |
| CON-FIN-B-0489, CON-FIN-B-489, FOIA-85-143 NUDOCS 8506170575 | |
| Download: ML20126F659 (2) | |
Category:CONTRACTED REPORT - RTA
MONTHYEARML20140G5481997-03-0707 March 1997
[Table view]Rev 0 to, Initial Review of Florida Power Crystal River Ampacity Derating Test Rept 95NK17030NC1973 ML20140F3841997-01-13013 January 1997 Rev to Technical Evaluation Rept of IPE Submittal & RAI Responses for Crystal River Power Station,Unit 3 ML18151A3861995-10-31031 October 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Summary of Results 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 ML18151A2081995-05-31031 May 1995 the Probability of Containment Failure by Direct Containment Heating in Surry 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 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. L-94-025, Ter,Audit of Plant Specific License Conversion to STS: Crystal River Unit 31994-12-31031 December 1994 Ter,Audit of Plant Specific License Conversion to STS: Crystal River Unit 3 ML20077A0211994-10-31031 October 1994 Audit of Plant Specific License Conversions to Sts,Unit 3, TER ML18152A3451994-10-31031 October 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:North Anna-1/-2 & Surry-1/-2. ML20077E9451994-09-30030 September 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Crystal River-3 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 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 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 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 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 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 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 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) 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 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) 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 ML20096H3601992-03-17017 March 1992 Supplemental TER Crystal River Unit 3 Station Blackout Evaluation ML20091S0871992-01-31031 January 1992 Trip Rept: Onsite Analysis of Human Factors of Event at Crystal River Unit-3,911208,(Pressurizer Spray Valve Failure ML20095C0511991-12-31031 December 1991 Technical Evaluation Rept on Second 10-Yr Interval Inservice Insp Program Plan ML20079D3281991-06-30030 June 1991 RISK-BASED Inspection Guide for Crystal River Unit 3 Nuclear Power Plant 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 ML18151A1431990-04-30030 April 1990 Analysis of Core Damage Frequency:Surry,Unit 1,INTERNAL Events ML18150A4501990-04-30030 April 1990 Analysis of Core Damage Frequency: Surry,Unit 1,INTERNAL Events Appendices 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 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 ML20155K4931988-10-31031 October 1988 Analyses of Natural Circulation During a Surry Station Blackout Using SCDAP/RELAP5 ML20245D6841988-08-31031 August 1988 Rev 1 to Technical Evaluation Rept,Tmi Action-NUREG-0737 (II.D.1),Relief & Safety Valve Testing,Crystal River Unit 3 ML20151C7101988-07-12012 July 1988 Technical Evaluation Rept of Dcrdr for Florida Power Corp Crystal River 3 Generating Station 1997-03-07 Category:QUICK LOOK MONTHYEARML20140G5481997-03-0707 March 1997
[Table view]Rev 0 to, Initial Review of Florida Power Crystal River Ampacity Derating Test Rept 95NK17030NC1973 ML20140F3841997-01-13013 January 1997 Rev to Technical Evaluation Rept of IPE Submittal & RAI Responses for Crystal River Power Station,Unit 3 ML18151A3861995-10-31031 October 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Summary of Results 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 ML18151A2081995-05-31031 May 1995 the Probability of Containment Failure by Direct Containment Heating in Surry 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 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. L-94-025, Ter,Audit of Plant Specific License Conversion to STS: Crystal River Unit 31994-12-31031 December 1994 Ter,Audit of Plant Specific License Conversion to STS: Crystal River Unit 3 ML20077A0211994-10-31031 October 1994 Audit of Plant Specific License Conversions to Sts,Unit 3, TER ML18152A3451994-10-31031 October 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:North Anna-1/-2 & Surry-1/-2. ML20077E9451994-09-30030 September 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Crystal River-3 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 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 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 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 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 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 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 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) 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 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) 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 ML20096H3601992-03-17017 March 1992 Supplemental TER Crystal River Unit 3 Station Blackout Evaluation ML20091S0871992-01-31031 January 1992 Trip Rept: Onsite Analysis of Human Factors of Event at Crystal River Unit-3,911208,(Pressurizer Spray Valve Failure ML20095C0511991-12-31031 December 1991 Technical Evaluation Rept on Second 10-Yr Interval Inservice Insp Program Plan ML20079D3281991-06-30030 June 1991 RISK-BASED Inspection Guide for Crystal River Unit 3 Nuclear Power Plant 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 ML18151A1431990-04-30030 April 1990 Analysis of Core Damage Frequency:Surry,Unit 1,INTERNAL Events ML18150A4501990-04-30030 April 1990 Analysis of Core Damage Frequency: Surry,Unit 1,INTERNAL Events Appendices 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 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 ML20155K4931988-10-31031 October 1988 Analyses of Natural Circulation During a Surry Station Blackout Using SCDAP/RELAP5 ML20245D6841988-08-31031 August 1988 Rev 1 to Technical Evaluation Rept,Tmi Action-NUREG-0737 (II.D.1),Relief & Safety Valve Testing,Crystal River Unit 3 ML20151C7101988-07-12012 July 1988 Technical Evaluation Rept of Dcrdr for Florida Power Corp Crystal River 3 Generating Station 1997-03-07 Category:ETC. (PERIODIC MONTHYEARML20140G5481997-03-0707 March 1997
[Table view]Rev 0 to, Initial Review of Florida Power Crystal River Ampacity Derating Test Rept 95NK17030NC1973 ML20140F3841997-01-13013 January 1997 Rev to Technical Evaluation Rept of IPE Submittal & RAI Responses for Crystal River Power Station,Unit 3 ML18151A3861995-10-31031 October 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Summary of Results 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 ML18151A2081995-05-31031 May 1995 the Probability of Containment Failure by Direct Containment Heating in Surry 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 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. L-94-025, Ter,Audit of Plant Specific License Conversion to STS: Crystal River Unit 31994-12-31031 December 1994 Ter,Audit of Plant Specific License Conversion to STS: Crystal River Unit 3 ML20077A0211994-10-31031 October 1994 Audit of Plant Specific License Conversions to Sts,Unit 3, TER ML18152A3451994-10-31031 October 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:North Anna-1/-2 & Surry-1/-2. ML20077E9451994-09-30030 September 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Crystal River-3 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 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 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 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 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 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 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 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) 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 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) 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 ML20096H3601992-03-17017 March 1992 Supplemental TER Crystal River Unit 3 Station Blackout Evaluation ML20091S0871992-01-31031 January 1992 Trip Rept: Onsite Analysis of Human Factors of Event at Crystal River Unit-3,911208,(Pressurizer Spray Valve Failure ML20095C0511991-12-31031 December 1991 Technical Evaluation Rept on Second 10-Yr Interval Inservice Insp Program Plan ML20079D3281991-06-30030 June 1991 RISK-BASED Inspection Guide for Crystal River Unit 3 Nuclear Power Plant 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 ML18151A1431990-04-30030 April 1990 Analysis of Core Damage Frequency:Surry,Unit 1,INTERNAL Events ML18150A4501990-04-30030 April 1990 Analysis of Core Damage Frequency: Surry,Unit 1,INTERNAL Events Appendices 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 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 ML20155K4931988-10-31031 October 1988 Analyses of Natural Circulation During a Surry Station Blackout Using SCDAP/RELAP5 ML20245D6841988-08-31031 August 1988 Rev 1 to Technical Evaluation Rept,Tmi Action-NUREG-0737 (II.D.1),Relief & Safety Valve Testing,Crystal River Unit 3 ML20151C7101988-07-12012 July 1988 Technical Evaluation Rept of Dcrdr for Florida Power Corp Crystal River 3 Generating Station 1997-03-07 Category:TEXT-PROCUREMENT & CONTRACTS MONTHYEARML20140G5481997-03-0707 March 1997
[Table view]Rev 0 to, Initial Review of Florida Power Crystal River Ampacity Derating Test Rept 95NK17030NC1973 ML20140F3841997-01-13013 January 1997 Rev to Technical Evaluation Rept of IPE Submittal & RAI Responses for Crystal River Power Station,Unit 3 ML18151A3861995-10-31031 October 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Summary of Results 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 ML18151A2081995-05-31031 May 1995 the Probability of Containment Failure by Direct Containment Heating in Surry 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 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. L-94-025, Ter,Audit of Plant Specific License Conversion to STS: Crystal River Unit 31994-12-31031 December 1994 Ter,Audit of Plant Specific License Conversion to STS: Crystal River Unit 3 ML20077A0211994-10-31031 October 1994 Audit of Plant Specific License Conversions to Sts,Unit 3, TER ML18152A3451994-10-31031 October 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:North Anna-1/-2 & Surry-1/-2. ML20077E9451994-09-30030 September 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Crystal River-3 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 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 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 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 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 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 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 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) 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 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) 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 ML20096H3601992-03-17017 March 1992 Supplemental TER Crystal River Unit 3 Station Blackout Evaluation ML20091S0871992-01-31031 January 1992 Trip Rept: Onsite Analysis of Human Factors of Event at Crystal River Unit-3,911208,(Pressurizer Spray Valve Failure ML20095C0511991-12-31031 December 1991 Technical Evaluation Rept on Second 10-Yr Interval Inservice Insp Program Plan ML20079D3281991-06-30030 June 1991 RISK-BASED Inspection Guide for Crystal River Unit 3 Nuclear Power Plant 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 ML18151A1431990-04-30030 April 1990 Analysis of Core Damage Frequency:Surry,Unit 1,INTERNAL Events ML18150A4501990-04-30030 April 1990 Analysis of Core Damage Frequency: Surry,Unit 1,INTERNAL Events Appendices 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 1997-03-07 |
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- 3 OAK RIDGE NATIONAL LABORATORY M'irdch OPERATED BY 'd'lt b ill, UNtoN CARBIDE CORPORATION NUCLEAR Divist0N OM e-e,-
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June 30,1983 j Mr. Gunter Arndt Mechanical / Structural Engineering Branch Division of Engineering Technology NL 238 Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Gunter:
This letter sumarizes our progress on the Containment Leak Rate Testing investigations (Fin. No. B0489) for the month of June 1983.
Technical Highlights One difference between the ANSI standard and the proposed revision to Appendix J that has not yet been discussed concerns the acceptability criterion for the results of Type B and C tests. To be acceptable the ANSI standard requires the combined leakage rate (including the upper confidence limit) of Type B and C tests to be less than 75 percent of the maximun allowable leakage rate. The proposed revision to Appendix J states that the combined leakage rate of all Type B and C tests must be less than 60 percent of the maximum allowable leakage rate at all <
times. The differences in these criteria are two-fold. The ANSI stand-ard includes an tupper confidence limit on the combined leakages determined by adding the standard deviation of the leakage rate to the leakage rate, while the proposed revision to Appendix J does not. The second difference regards the 75 percent versus 60 percent criterion. ,
i The inclusion of the measurement error through the use of the standard deviation is very worthwhile. Presentation of the leakage rate data in this manner provides a better indication of the accuracy of the Type B and C leak tests. Because the ANSI standard uses 75 percent with a confidence limit and the proposed revision to Appendix J uses 60 percent without a confidence limit, the only way the two could provide the same result is if the standard deviatirn of the combined leakages is 15 per-cent of the maximum allowable leak rate. With the sophisticated instru-mentation available today such a large standard deviation is very un-likely which means the criteria in the proposed revision to Appendix J are more conservative than the ANSI criteria.
8506170575 850325 FOIA PDR REYTBLAB5-143 PDR [
f Mr. Gunter Arndt 2 June 30,1983 The remaining question concerns the degree of conservatism to use in evaluating the results (i.e., what percentage of the maximum allowable leak rate). Recog-nizing the poor performance of Type A tests following the successful completion of local leak testing programs, no reason is evident to justify relaxing the currently enforced 60 percent rule. In fact, except for the knowledge of potential changes elsewhere in the local leak testing programs, the 60 per-cent criterion should probably be more strict. The 60 percent rule should stand until the effects of potential changes in the local leak testing pro-grams can be evaluated.
A computerized literature search of the DOE energy data base and Nuclear Science Abstracts has been initiated to uncover sources of information concerning the leakage characteristics of containment valves with respect to temperature and seating time. Both domestic and foreign sources are being examined but noth-ing of value has been obtained yet.
Plant visits to observe leak testing have been tentatively scheduled for the middle of July at Crystal River and the end of July at Surry.
Expenditures Oct. Nov. Dec. Jan. Feb. Mar. Apr. M June Expenditure ($K) 7.2 8.9 7.8 8.9 9.2 9.4 7.5 8.7 8.7* I Cumulative ($K)** 14.2 23.1 30.9 39.8 49.0 58.4 65.9 74.6 83.3
- Estimated
- Program Total Sincerely, D. J. Naus DJN:ege cc: J. R. Dougan
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