Request for Addl Info Re Equipment Environ Qualification Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment.ML20038B225 |
Person / Time |
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Site: |
Surry |
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Issue date: |
11/30/1981 |
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From: |
FRANKLIN INSTITUTE |
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To: |
NRC |
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Shared Package |
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ML20038B226 |
List: |
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References |
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CON-NRC-03-79-118, CON-NRC-3-79-118, RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM IEB-79-01B, IEB-79-1B, RFI-C5257-482, NUDOCS 8112040391 |
Download: ML20038B225 (14) |
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Similar Documents at Surry |
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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 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 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. 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 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 ML18151A3841994-07-31031 July 1994 Technical Evaluation Rept Pump & Valve Inservice Testing Program Plant Units 1 & 2. 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) 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) 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) 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 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 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 ML20155K4931988-10-31031 October 1988 Analyses of Natural Circulation During a Surry Station Blackout Using SCDAP/RELAP5 ML18153B5471987-07-31031 July 1987 PRA Applications Program for Insp at Surry Nuclear Power Station,Unit 1, Draft Rept ML18150A1221987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 -- Equipment Classification for All Other Safety-Related Components: Surry 1 & 2, Final Informal Rept ML18152A5831987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. ML18150A1191987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept ML18150A1881987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept ML20206F0711987-04-0808 April 1987 Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog ML20206B2041987-03-31031 March 1987 Metallurgical Evaluation of an 18-INCH Feedwater Line Failure at the Surry Unit 2 Power Station ML18150A1261987-03-31031 March 1987 Technical Evaluation Rept TMI Action-NUREG-0737 (II.D.1) Relief & Safety Valve Testing Surry Units 1 & 2, Informal Rept ML20211N5031987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept ML20206C8291986-11-30030 November 1986 Analysis of Core Damage Frequency from Internal Events:Surry Unit 1 ML20206H0811986-05-0909 May 1986 Some Sensitivities for Direct Containment Heating Loads ML20138H2181985-09-30030 September 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Beaver Valley Unit 1,North Anna Units 1 & 2 & Surry Units 1 & 2 ML18142A4011985-05-0303 May 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2 'Post-Trip Review:Data & Info Capabilities' for Surry Power Station,Units 1 & 2.... ML18152A0951985-04-24024 April 1985 Masonry Wall Design,Surry Power Station Units 1 & 2, Technical Evaluation Rept ML20206F0861985-02-28028 February 1985 Draft COBRA-NC Analysis of Station Blackout Transient (Tmlb') for Surry Plant. Inel Viewgraphs Entitled Structural Failure Studies of RCS Also Encl ML18152A5761985-01-31031 January 1985 Conformance to Reg Guide 1.97,Surry Power Station Units 1 & 2. 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 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 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. 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 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 ML18151A3841994-07-31031 July 1994 Technical Evaluation Rept Pump & Valve Inservice Testing Program Plant Units 1 & 2. 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) 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) 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) 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 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 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 ML20155K4931988-10-31031 October 1988 Analyses of Natural Circulation During a Surry Station Blackout Using SCDAP/RELAP5 ML18153B5471987-07-31031 July 1987 PRA Applications Program for Insp at Surry Nuclear Power Station,Unit 1, Draft Rept ML18150A1221987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 -- Equipment Classification for All Other Safety-Related Components: Surry 1 & 2, Final Informal Rept ML18152A5831987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. ML18150A1191987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept ML18150A1881987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept ML20206F0711987-04-0808 April 1987 Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog ML20206B2041987-03-31031 March 1987 Metallurgical Evaluation of an 18-INCH Feedwater Line Failure at the Surry Unit 2 Power Station ML18150A1261987-03-31031 March 1987 Technical Evaluation Rept TMI Action-NUREG-0737 (II.D.1) Relief & Safety Valve Testing Surry Units 1 & 2, Informal Rept ML20211N5031987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept ML20206C8291986-11-30030 November 1986 Analysis of Core Damage Frequency from Internal Events:Surry Unit 1 ML20206H0811986-05-0909 May 1986 Some Sensitivities for Direct Containment Heating Loads ML20138H2181985-09-30030 September 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Beaver Valley Unit 1,North Anna Units 1 & 2 & Surry Units 1 & 2 ML18142A4011985-05-0303 May 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2 'Post-Trip Review:Data & Info Capabilities' for Surry Power Station,Units 1 & 2.... ML18152A0951985-04-24024 April 1985 Masonry Wall Design,Surry Power Station Units 1 & 2, Technical Evaluation Rept ML20206F0861985-02-28028 February 1985 Draft COBRA-NC Analysis of Station Blackout Transient (Tmlb') for Surry Plant. Inel Viewgraphs Entitled Structural Failure Studies of RCS Also Encl ML18152A5761985-01-31031 January 1985 Conformance to Reg Guide 1.97,Surry Power Station Units 1 & 2. 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 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 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. 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 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 ML18151A3841994-07-31031 July 1994 Technical Evaluation Rept Pump & Valve Inservice Testing Program Plant Units 1 & 2. 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) 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) 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) 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 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 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 ML20155K4931988-10-31031 October 1988 Analyses of Natural Circulation During a Surry Station Blackout Using SCDAP/RELAP5 ML18153B5471987-07-31031 July 1987 PRA Applications Program for Insp at Surry Nuclear Power Station,Unit 1, Draft Rept ML18150A1221987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 -- Equipment Classification for All Other Safety-Related Components: Surry 1 & 2, Final Informal Rept ML18152A5831987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. ML18150A1191987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept ML18150A1881987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept ML20206F0711987-04-0808 April 1987 Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog ML20206B2041987-03-31031 March 1987 Metallurgical Evaluation of an 18-INCH Feedwater Line Failure at the Surry Unit 2 Power Station ML18150A1261987-03-31031 March 1987 Technical Evaluation Rept TMI Action-NUREG-0737 (II.D.1) Relief & Safety Valve Testing Surry Units 1 & 2, Informal Rept ML20211N5031987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept ML20206C8291986-11-30030 November 1986 Analysis of Core Damage Frequency from Internal Events:Surry Unit 1 ML20206H0811986-05-0909 May 1986 Some Sensitivities for Direct Containment Heating Loads ML20138H2181985-09-30030 September 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Beaver Valley Unit 1,North Anna Units 1 & 2 & Surry Units 1 & 2 ML18142A4011985-05-0303 May 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2 'Post-Trip Review:Data & Info Capabilities' for Surry Power Station,Units 1 & 2.... ML18152A0951985-04-24024 April 1985 Masonry Wall Design,Surry Power Station Units 1 & 2, Technical Evaluation Rept ML20206F0861985-02-28028 February 1985 Draft COBRA-NC Analysis of Station Blackout Transient (Tmlb') for Surry Plant. Inel Viewgraphs Entitled Structural Failure Studies of RCS Also Encl ML18152A5761985-01-31031 January 1985 Conformance to Reg Guide 1.97,Surry Power Station Units 1 & 2. 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 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 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. 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 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 ML18151A3841994-07-31031 July 1994 Technical Evaluation Rept Pump & Valve Inservice Testing Program Plant Units 1 & 2. 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) 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) 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) 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 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 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 ML20155K4931988-10-31031 October 1988 Analyses of Natural Circulation During a Surry Station Blackout Using SCDAP/RELAP5 ML18153B5471987-07-31031 July 1987 PRA Applications Program for Insp at Surry Nuclear Power Station,Unit 1, Draft Rept ML18150A1221987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 -- Equipment Classification for All Other Safety-Related Components: Surry 1 & 2, Final Informal Rept ML18152A5831987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. ML18150A1191987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept ML18150A1881987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept ML20206F0711987-04-0808 April 1987 Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog ML20206B2041987-03-31031 March 1987 Metallurgical Evaluation of an 18-INCH Feedwater Line Failure at the Surry Unit 2 Power Station ML18150A1261987-03-31031 March 1987 Technical Evaluation Rept TMI Action-NUREG-0737 (II.D.1) Relief & Safety Valve Testing Surry Units 1 & 2, Informal Rept ML20211N5031987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept ML20206C8291986-11-30030 November 1986 Analysis of Core Damage Frequency from Internal Events:Surry Unit 1 ML20206H0811986-05-0909 May 1986 Some Sensitivities for Direct Containment Heating Loads ML20138H2181985-09-30030 September 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Beaver Valley Unit 1,North Anna Units 1 & 2 & Surry Units 1 & 2 ML18142A4011985-05-0303 May 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2 'Post-Trip Review:Data & Info Capabilities' for Surry Power Station,Units 1 & 2.... ML18152A0951985-04-24024 April 1985 Masonry Wall Design,Surry Power Station Units 1 & 2, Technical Evaluation Rept ML20206F0861985-02-28028 February 1985 Draft COBRA-NC Analysis of Station Blackout Transient (Tmlb') for Surry Plant. Inel Viewgraphs Entitled Structural Failure Studies of RCS Also Encl ML18152A5761985-01-31031 January 1985 Conformance to Reg Guide 1.97,Surry Power Station Units 1 & 2. 1995-05-31
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REQUEST FOR ADDITIONAL INFORMATION QUIPMENT EN7IRCNMENTAL QUALIFICATI$N (EQ)
REVIEW OF LICENSEES' RESOLUTION OF OUTSTANDING ISSUES FROM NRC D2UIPMENT ENVIRONMENTAL QUALIFICATION SAFETY EVALUATION REPORTS (SER) AND 'INI ACTICN PLAN INSTALLED EQUIPMENT s Virginia Electric and Power Company Surry Unit 1 NRC Docket No. 50-280 November 30, 1981 NRC TAC No. 42-468 a
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Franklin Research Center A Division of The Franklin institute The Benprmn Frankan Parkway. Phas., Pa. 19103 (215) 448 t000
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RFI-CS257-482 BACKGROUND Franklin Research Center (FRC) of Philadelphia, Pa. is providing assis-tance to the U.S. Nuclear Regulatory Commission (NRC) for the equipment environmental qualification (EEQ) review of operating reactors. FRC will perform an' EEQ review of the Licensee's 90-day response to outstanding issues from the NRC Equipment Environmental Qualification Safety Evaluation Report (SER) and the installed TMI Action Plan equipment. The review will be limited to safety-related equipment potentially exposed to a harsh environment. The results will be presented in the form of a technical evaluation report for each plant.
This request for additional information (RFI) is the result of an evaluation of the information provided by letters dated February 1, 1981 [1]
and December 1, 1980 [2] .
- FRC previously requestei TMI Action Plan information by a telephone memorandum dated August 12, 1981 [3].
In response, VEPCO transmitted the following information on September 10, 1981 [41
- a. Comsip-Delphi Engineering Analysis and Test Report 1035-1 on the containment hydrogen analyzers providing IEEE test results for Model
- KIII and KIV analyzers
- b. Environmental Zone Description Volumes 1-4 for Surry Power Station.
A. FRC REVIEW OF THE LICENSEE'S 90-DAY RESPONSE TO THE NRC EEQ SER Information Requested Date Received by FRC**
- 1. In reference to the Licensee's 90-day response [5] to the NRC SER [6], a legible single copy of each of the following qualification documents is requested in order that the FRC evaluation may proceeds (The numbers in parentheses af ter the letter correspond to the numbers in Section 8 of Reference 5.)
- Numbers in brackets refer to citations found in the list of references.
**This column will be completed by FRC as the requested information is received.
U00A Desumen Franklin Research Center of The Fransen pimense
RFI-C5257-482 Date Received by FRC**
a(2). Environmental Qualification of Reactor Coolant Temperature Detectors and Containment Pressure Transmitters, VEPCO submittal No.
855, November 1, 1979.
b(3). Qualification of Resistance Temperature Detectors, VEPCO submittal No. 855A, for North Anna Power Station Units 1 and 2, November 1, 1979.
c(5) . Learn, J. R., Boston Insulated Wire and Cable Company, to Wright, R. D.,
Stone & Webster Engineering Corporation, 300 V Instrument cables and 600 V Control Cables, January 17, 1972.
d(6) . Limitorque Corporation, Nuclear Qualification Data for Safety Related Service, NQDS, November 1, 1979.
e (7) . Anderson, T. M., Westinghouse Electric Corporation, to Stolz, J. F. ,
Luclear Regulatory Commission, NS-TMA-1950, September 29, 1978.
Possible attachments include Vota, J. L. , Westinghouse Electric Corporation, to Proffitt, W. L.
Virginia Electric Power Company, October 19, 1978, Eicheldinger, C.,
Westinghouss ?lectric Corporation, to Stolz, J. -, Nuclear Regulatory Commission, u ch 23, 1977, Westinghouse Sensor Qualification
?cogram, IEEE 323-1971 Demonstration Program, Final Test for Barton/ITT Modified Pressure Transmitter (Proprietary Class 2) .
nklin Research Center j A Dhenson of The Frennen insuswer
s RFI-C5257-482 Date Received by FRC**
f(9). Anderson, T. M., Westinghouse Electric Corporation, to Stolz, J. F.,
Nuclear Regulatory Commission, NS-TMA-2120, September 14, 1979, Revision A, September 30, 1979.
Possible attachments include:
Westinghouse Supplemental Qualification Testing of Barton Lot 1 Pressure and Differential Pressure Transmitters (Proprietary Class 2) .
g(12). Chapman, L., Stone, J., Tests of Electric Cables Af ter Simulated Post-Accident Reactor Containment Service, Cerro Wire and Cable Company Technical Report NP-04, March 1981.
h(13). Alm, C. A. , Mar th J. R. ,
Qualification of Firewall III Class IE Electric Cables, Rockbestos Company, Rockbestos Report 13-10407-E058-13-2, June 22, 1978, Updated August 22, 1978.
i(18). D. G. O'Brien Incorporated, Environmental Test Report, DGO Report No. C19QA061, February 28, 1972.
k(23). Sheets, M. W. , Topical Report on i General Electric Vertical Induction l Motors, Inside Containment l Recirculation Spray Pump Motors -
Surry Power Station - Second Addendum to Cover Heat Aging, Radiation Exposure, Vibration, and ,
Steam / Chemical Spray Exposure Qualification Tests, NRC Docket Nos.
50-280 and 50-281, June 12, 1973 and July 23, 1973.
l l
nklin Research Center #
A Dameson of The Fransen insamme
, RFI-C5257-482 Date Received by FRC**
1(24). Sheets, M. W., Topical Report on General Electric Vertical Induction Motors, Inside Containment Recirculation Spray Pumps for the Surry and North Anna Stations of Virginia Electric and Power Company, Third Addition to Cover' Rebuilding Motors Using New Bearings, Docket Nos. 50-280 and 50-281, Report No.
491HA689, July 23, 1979.
m(37) . Cerro Wire and Cable Company, Qualification of Firewall III Class IE Electrical Cables, May 1976.
Attachments include: Patterson, W. J.,
Cerro Wire and Cable Company, to Maguire, T. A., Stone & Webster Engineering Corporation, subject:
Identification of cable supplied under dais P.O. as Firewall III, June 9, 1976.
n(38). Schwencer , A., Nuclear Regulatory Commission, to Proffitt, W. L., ,
Virginia Electric and Power Company, subject: Environmental Qualifica-tion Testing of Continental Instrumentation Cable, July 25, 1979.
o(40). Lasky, J. S., Okonite Company, to Bonner, J., Stone & Webster Engineering Corporation, October 15, 1980.
p(42). Ling, T. H., Anaconda Wire and Cable Company, to Bonner, J., Stone &
Webster Engineering Corporation, October 28, 1980.
q(44). Bell, C. E. , General Electric Company, to Bonner, J. , Stone &
Webster Engineering Corporation, subject: Qualification of Inside Recirculation Pump Motors to Withstand a pH of 7-11, October 28, 1980.
~
RFI-C5257-482 Date Received by FRC**
r(45). Drab, J. B. , Limitorque Corporation, to Reilly, P., Stone & Webster Engineering Corporation, subject:
Qualification Information for Limitorque Actuators - Surry Power Station Units 1 & 2, October 8, 1980. Possible attachments include Reilly, P., Stone &
Webster Engineering Corporation, to Drab, J. B., Limitorque Corporation, two letters, September 11, 1980 and September 29, 1980, MacFarlane, I. S.,
Stone & Webster Engineering Corporation, Memo to Whom It May Concern, dated January 28, 1981, MacFarlane, I. S. , Stone & Webster Engineering Corporation, to Drab, J. B.,
Limitorque Corporation ~, Telephone Memorandum dated December 12, 1980, MacFarlane, I. S., Stone & Webster Engineering Corporation, to McQuillan, P., Limitorque Corporation, Telephone Memorandum ,
dated October 27, 1980, Zarandi, V'../CO, to McFarlane, I. S. , Stone & .
Weoster Engineering Corporation, November 7,1980; MacFarlane, I. S. ,
Stone & Webster Engineering Corporation, to Padulla, D. and Smith R., VEPCO, Memo dated November 3,1980, MacFarlane, I. S. , Stone &
Webster Engineering Corporation, to Padulla, D., VEPCO, Memo dated November 4, 1980.
s (47) . Conax Corporation, Engineering Department Certificate to Virginia Electric and Power Company, subject: Compliance of NAS-21 revised May 5, 1972 to equipment ordered under purchase order SN-491, dated December 13, 1972.
t(51). Drab, J. B. , Limitorque Corporation, to Barnhart, J. H., Stone & Webster Engineering Corporation, subject:
Qualification Information for Limitorque Actuators - Surry Power Station Units 1 & 2, two letters,
_nklin Rese_ arch ._ Center
RFI-C5257-482 Date Received by FRC**
t(51). November 13, 1980. Possible Cont. attachments include: Barnhar t, J. H. ,
Stone & Webstet Engineering Corporation, to Limitorque Corporation, November 3,1980.
u(52). Drab, J. B. , ' Limitorque Corporation, to MacFarlane, I. S. , Stone &
Webster Engineering Corporation, subject: Qualification Information for Limitorque Actuators - Surry Power Station Units 1 & 2, November 14, 1980. Possible attachments include: MacFarlane, I. S., Stone &
Webster Engineering Corporation, to Drab, J. B., Limitorque Corporation, Memo -
Subject:
79-OlB Environ-mental Qualification of Equipment, dated November 12, 1980 MacFarlane, I. S.,
Stone & Webster Engineering Corpora-tion, To Whom It May Concern, Memo dated January 28, 1981; MacFarlane, I. S., Stone & Webster Engineering Corporation, to Drab, J. B.,
Limitorque Corporation, Telephone Memorandum dated December 12, 1980.
v(53). Kuster, J. M., Raychem Corporation, to Barnhart, J. H., Stone & Webster Engineering Corporation, subject:
- Flamtrol Wire & Cable, North Anna i
Nuclear Units 3 & 4, Stone & Webster P.O. 3190, November 17, 1980.
I Possible attachments include:
l MacFarlane, I. S., Stone & Webster Engineering Corporation, to Kuster, J. , Raychem Corporation, Telephone Memorandum dated November 18, 1980.
w(54) . Lewicki, R. G., Reliance Electric Company, to Barnhart, J. H. , Stone & I Webster Engineering Corporation, subject: VEPCO/Surry Power Station Units 1 & 2, Motor Bearing Lubricant, Reliance Part No.
482 4-15-A, November 14, 1980.
Anarin ae.ea,ca cente, A Onnesen of The Fransen ansuome
RFI-C5257-482 Date Received by FRC**
x(55). Reliance Electric Company, Nuclear Power Motor Systems, Type Test Support Analysis, Random Wound Motors, Summary Report NUC-9, July 1, 1978. Includes Appendix:
Seismic Report 78-R-33, Justifica-tion for Omission of Routine "End Turn Stress Analsyis" for D.andom Wound Motors, July 10, 1978.
y( 56) . Electric Power Research Institute, Evaluation and Test of Improved
' Fire-Resistant Fluid Lubricants for.
Water Reacter Coolant Pump Hotors, Volume la Fluid Evaluation, Bearing Model Tests, Motor Tests, and Fire Test, Interim Report NP-1447, July 1980.
z(58). Kuster, J. , Raychem Corporation, to
!!acFarlane, I. S., Stone & Webster Engineering Corporation, subject:
IE Bulletin 79-OlB, Environmental Qualification of Equipment, Surry Power Station Units 1 & 2, Additional Qualification of Raychem Flamtrol Wire and Cable, Spec. No.
NAS-3190, December 2, 1980.
aa(60). McGowan, E. J., Raychem Corporation, Raychem-Flamtrol, Continuation of LOCA Simulation Test, Test Report EM
#1403, December 9, 1977. Possible attachments includes Kuster, J.,
Raychem Corporation, to MacFarlane, I. S., Stone & Webster Engineering Corporation, January 27, 1981.
l
, bb ( 61) . Cardello, P. S., Anaconda Ericsson l
Incorporated, to Bonner, J., Stone &
Webster Engineering Corporation, subject: VEPCO Surry Qualification Data, three letters, October 8,
! 1980, October 21, 1980, and December I
10, 1980.
l l
i QOb) 7 ranklin Resea
~ ~,._rch Center e i
RFI-C5257-482 Date Received by FRC**
cc(64). Lasky, J. S., The Okonite Company, to Barnhart, J. H., Stone & Webster Engineering Corporation, subject:
Environmental Qualification of Equipment, Surry Power Station Units 1 & 2, December 17, 1980.
dd(68). Lasky, J. S., The Okonite Company, to Barnhart, J. H., Stone & Webster Engineering Corporation,
Reference:
J. O. No. 12846.44, December 22, 1980. Possible attachments include: Barnhart, J. H. , Stone &
Webster Engineering Corporation, to Lasky, J. S. , Okonite Company, December 17, 1980, MacFarlane, I. S.,
Stone & Webster Engineering Corporation, To Whom It May Concern, Memo dated February 3, 1981.
ee(69). Tolerico, F. A. , Westinghouse Electric Corporation, to Barnhart, J. H., Stone & Webster Engineering Corporation, subject: Surry Power Station 1 & 2, Environmental Qualification of Hydrogen Recombiner, December 8, 1980.
ff(72). Cookinham, J. H., Westinghouse Electric Corporation, to Brown, S. C. ,
Virginia Electric and Power company, subject: North Anna Power Station, NUREG-0588 Equipment Qualification, October 30, 1980. Possible attachments include: Newcomb, R.
C. , Virginia Electric and Power Company, to MacFarlane, I. S., Stone
& Webster Engineering Corporation, Memo dated December 31, 1980.
nklin Research Center A Dhaeson of The Frennen kimumme
- 7 RFI-C5257-482 Date Received Dv FRC**
gg(73). Drab, J. B., Limitorque Corporation, to Reilly, P., Stone & Webster Engineering Corporation, subject:
Qualification Information, North-Anna Power Station Unit 2, September 19, 1980. Possible attachments 4
include: MacFarlane, I. S. , Stone &
Webster Engineering Corporation, To Whom It May Concern, Memo dated January 28, 1981, MacFarlane, I. S.,
Stone & Webster Engineering Corporation, to Drab, J. B.,
Limitorque Corporation, Telephone Memorandum dated December 12, 1980.
hh (76) . Conax Corporation, Design Qualification Test Report for a Conax Low Voltage Control Service Classification Conductor Feedthrough Assembly P/N 7641-21001, Test Report No. IPS-353.2, June 18, 1979.
(Proprietary) 11(77). Federick, W. C.,'Conax Corporation, '
to Reilly, P., Stone & W'bster e
Engineering Corporation, subject:
Environmental Qualification, Electrical Penetrations, North Anna Units 1 & 2, January 8, 1981.
j j (79) . Kushner, J. R., Rockbestos Company, I
to Barnhart, J. H., Stone & Webster Engineering Corporation, subject:
S & W letter of 12/12/80, Items 1.a . (1) and 1.a. (2) , February 24, 1981.
kk(80). Ling, T. H., Anaconda Ericsson, to MacFarlane, I. S., Stone & Webster Engineering Corporation, subject:
600-Volt Power Cable, February 23, 1981.
11(82). Pirrong, J. S., Boston Insulated Wire & Cable Co., to Petty, K.,
Stone & Webster Engineering l Corporation, subject: North Anna j Cables, P.O. NA-265/1265, April 30, i 1981.
I i 000A wFranklin ae Th. rr an in.Research C. enter i
t I
. . . i RFI-C5257-482 Date Received by FRC**
mm(83). Drab, J., Limitorque Corporation, to Barnhart, J. H., Stone & Webster Engineering Corporation, Telex, May 18, 1981.
nn(84) . Drab, J. B., Limitorque Corporation, to Barnhart, J. H., Stone & Webster Engineering Corporation, subject:
Qualification Information for Surry Power Station - Units 1 & 2, May 19, 1981.
oo(85). Technical Report 123-1247 Rev. A dated April 1978.
pp(86). Technical Report 123-204 Rev. A dated March 25, 1975.
qq( 87) . Report No. 23-1268 Rev. dated February 26, 1975.
rr(87). Report No. 123-1269 Rev. dated February 26, 1975.
~
ss(89). Amphenol Design Verification Testing (DVT) Report No. 123-1275.
tt(90). Qualification Report of General Electric Vertical Induction Motors for Class LE Outside Recirculation Spray Pumps.
I uu (91) . Siemens-Allis Inc. (Medium Motor Division) Equipmenc Qualification Random Wound Motcrs for Class IE Safety Related Service.
vv(93). Letter dated August 1, 1969 from Robert H. Dubuc of Cerro Wire &
Cable Company to Mr. Roger Clark of S&W.
ww(94). Cerro Wire & Cable Company l Specification No. RSS-3-701 Issue 4, l November 1, 1968 on Pyro-TROL III, 600 Volt Control Cables.
Ub Franklin Research Center
- a w m. ranen m t
r ~
- - - 4 _ __
=
RFI-C5257-482 Date Received by FRC**
xx(95) . NUS-VEPCO QDR Package 5437-34-01.
yy(97). NUS-VEPCO QDR Package 5437-SOV-01.
22(99). NUS-VEPCO QDR Package 5437-54-01.
aaa (101) . NUS-VEPCO QDR Package 5437-53-01.
i bbb(103). NUS-VEPCO QDR Package 5437-56-01.
ccc(105). NUS-VEPCO QDR Package 5437-51-01.
ddd(107). NUS-VEPCO QDR Package 5437-62-01.
, , eee(109). NUS-VEPCO QDR Package 5437-50-01.
f f f(lll) . NUS-VEPCO QDR Package 5437-57-01.
ggg(ll3). NUS-VEPCO QDR Package 5437-55-01.
' hhh(ll5). NUS-VEPCO QDR Package 5437-57-01.
111(117). NUS-VEPCO QDR Package 5437-49-01.
. jjj(119). NUS-VEPCO QDR Package 5437-59-01.
kkk(121). NUS-VEPCO QDR Package 5437-42-01.
i, 111(124). NUS-VEPCO QDR Package 5437-MOV-1-01.
nnn(126). NUS-VEPCO QDR Package 5437-MOV-1-02.
,[ ooo(127) . NUS-VEPCO QDR Package 5437-62C-01.
I ppp(128) . ' Automatic Dampers (Safety Related)
Qualification Report for Electric Actuators by RCS.
, qqq(134). NUS-VEPCO QDR Package 5437-56-02.
<! rrr(135). NUS-VEPCO QDR Package 5437-61-01.
sss (136) . NUS-VEPCO QDR Package 5437-103-01.
ttt(137). NUS-VEPCO QDR Package 5 43 7-6 2A-01.
uuu(138{. NUS-VEPCO QDR Package 5437-52-01. -
~
) ,
?
- nklin Research Center A Dhemsen of The Fremen sneenme ,
', / -
I
i RFI 5557-{82 Date Received by PRC**
vvv(139) . NUS-VEPCO QDR Package 5437-60-01.
www(140). NUS-VEPCO QDR Package 5437-41-01.
yyy(141). NUS-VEPCO QDR Package 5437-43-01.
xxx(142). NUS-VEPCO QDR Package 5437-8-01.
FRC mailing address is as follows:
Mr. Cyril J. Crane Franklin Research Center The Parkway at Twentieth Street Philadelphia, PA 19103 Telephone No. 215/448-1353 Telecepy No. 215/448-1296 Telecopy Confirmation No. 215/448-1215 a
- v. -
gb ~
NNFranklin Research Center A Dunesen of The Frennen buemme
/
RFI-CSSS7-482 REFERENCES
- 1. Surry Unit 1 - IE Bulletin 79-OlB, TMI Review - Supplement 3, Revision 3 Change Package Virginia Electric & Power Co.,
01-Feb-81
- 2. VEPCO Surry Unit 1 - IE Bulletin 79-01B Revision 2 - Supplement 3 TMI Review Virginia Electric & Power Co.,
01-Dec-80
- 3. Telephone Memorandum C. J. Crane, J. Murphy (FRC) with D. Nabors (NRC-PJM.) ,
R. Newcomb, and J. E. Wromiewicz (VEPCO).
Subject:
RFI for Surry Units 1 and 2 12-Aug-81
- 4. R. H. Leasburg Letter to H. R. Denton and S. A. Varga, NRC.
Subject:
IE Bulletin 79-01B Supplement 3 TMI Review, Surry Power Station Unit Nos. 1 and 2
- September 10, 1981
- 5. R. H. Leasburg Letter to H. R. Denton and S. A. Varga, NRC.
Subject:
Response to Safety Evaluation Report for Environmental Qualification ... IE Bulletin 79-013 90-Day Review; Surry Units 1 and 2 Virginia Electric & Power Co., 24-Aug-81 Serial No. 329
- 6. Office of Nuclear Reactor Regulation Safety Evaluation Report for Surry Unit 1 Environmental Qualification of Safety-Related Electrical Equipment NRC, 21-May-81
- 7. NUREG-0737, " Clarification of TMI Action Plan Requirements" NRC, November 1980
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e A Dennen of The Fransen menswee L -- - .
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