ML20072L681
From kanterella
| ML20072L681 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf, 05000000 |
| Issue date: | 06/30/1982 |
| From: | Gasser R BROOKHAVEN NATIONAL LABORATORY |
| To: | NRC |
| Shared Package | |
| ML20072L675 | List: |
| References | |
| FOIA-83-81 NUDOCS 8303310465 | |
| Download: ML20072L681 (247) | |
Similar Documents at Grand Gulf, 05000000 | |
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Category:CONTRACTED REPORT - RTA
MONTHYEARML20211K7681999-07-30030 July 1999
[Table view]Evaluation of Fuel Pin Failure Timing in Boiling Water Reactors ML20216E8721998-03-13013 March 1998 Rept to NRC Environ Monitoring at Grand Gulf Nuclear Station CY97, Conducted by Contract NRC-29-83-621 ML20101C8941995-10-16016 October 1995 Plant IPE Insight Support Rept for NUREG-1150 Plants ML20087K3691995-07-31031 July 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Summary of Results ML20082D5261995-03-31031 March 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Supporting Melcor Calculations ML20082B7411995-03-31031 March 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Main Report and Appendices ML20073C3671994-08-31031 August 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf, Unit 1.Analysis of Core Damage Frequency from Seismic Events During Mid-Loop Operations.Main Report ML20072N9991994-07-31031 July 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internally Induced Flooding Events for Plant Operational State 5 During a Refueling. ML20072D0581994-07-31031 July 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage ML20071L7411994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal ML20071L7191994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal ML20071L6111994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During Refueling Outage.Internal ML20071L5971994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Main Report ML20071L5831994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Section 10 ML20071L5661994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Sections 1-9 ML20063B5501994-01-24024 January 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,Grand Gulf,Unit 1, Technical Evaluation Rept ML20064K0511993-10-31031 October 1993 Summary Rept Of:Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Final Ltr Rept ML18151A8991992-05-31031 May 1992 Summary Rept of :Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Draft Ltr Rept ML20066D3421990-12-31031 December 1990 Evaluation of Severe Accident Risks: Grand Gulf,Unit 1. Appendices ML20066D2981990-12-31031 December 1990 Evaluation of Severe Accident Risks: Grand Gulf,Unit 1.Main Report ML20059N5101990-08-31031 August 1990 Technical Evaluation Rept on Response from Sys Energy Resources,Inc to Generic Ltr 88-01 Re Grand Gulf Nuclear Plant ML19332G5641989-11-30030 November 1989 Analysis of Core Damage Frequency: Grand Gulf, Unit 1 Internal Events Appendices.Continuation of Appendix D 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 ML20248F3411989-09-30030 September 1989 Analysis of Core Damage Frequency: Grand Gulf, Unit 1 Internal Events Appendices ML20248F3451989-09-30030 September 1989 Analysis of Core Damage Frequency: Grand Gulf, Unit 1 Internal Events ML19324A6231989-05-31031 May 1989 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Grand Gulf-1, 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 ML20070Q5571989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Grand Gulf 1 ML20043B3721988-12-31031 December 1988 Stability Measurements During Cycle 2. 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 ML19325C1581988-02-22022 February 1988 Technical Evaluation of Dcrdr. ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 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 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 ML20235J2291987-09-30030 September 1987 Draft PRA-Based Sys Insp Plans 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 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 ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML18052B1931987-06-30030 June 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Calvert Cliffs-1 & -2, Millstone-2 & Palisades, Final Informal Rept ML20235A0161987-04-30030 April 1987 Analysis of Core Damage Frequency from Internal Events:Grand Gulf,Unit 1.Main Report 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 1999-07-30 Category:QUICK LOOK MONTHYEARML20211K7681999-07-30030 July 1999
[Table view]Evaluation of Fuel Pin Failure Timing in Boiling Water Reactors ML20216E8721998-03-13013 March 1998 Rept to NRC Environ Monitoring at Grand Gulf Nuclear Station CY97, Conducted by Contract NRC-29-83-621 ML20101C8941995-10-16016 October 1995 Plant IPE Insight Support Rept for NUREG-1150 Plants ML20087K3691995-07-31031 July 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Summary of Results ML20082D5261995-03-31031 March 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Supporting Melcor Calculations ML20082B7411995-03-31031 March 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Main Report and Appendices ML20073C3671994-08-31031 August 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf, Unit 1.Analysis of Core Damage Frequency from Seismic Events During Mid-Loop Operations.Main Report ML20072N9991994-07-31031 July 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internally Induced Flooding Events for Plant Operational State 5 During a Refueling. ML20072D0581994-07-31031 July 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage ML20071L7411994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal ML20071L7191994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal ML20071L6111994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During Refueling Outage.Internal ML20071L5971994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Main Report ML20071L5831994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Section 10 ML20071L5661994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Sections 1-9 ML20063B5501994-01-24024 January 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,Grand Gulf,Unit 1, Technical Evaluation Rept ML20064K0511993-10-31031 October 1993 Summary Rept Of:Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Final Ltr Rept ML18151A8991992-05-31031 May 1992 Summary Rept of :Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Draft Ltr Rept ML20066D3421990-12-31031 December 1990 Evaluation of Severe Accident Risks: Grand Gulf,Unit 1. Appendices ML20066D2981990-12-31031 December 1990 Evaluation of Severe Accident Risks: Grand Gulf,Unit 1.Main Report ML20059N5101990-08-31031 August 1990 Technical Evaluation Rept on Response from Sys Energy Resources,Inc to Generic Ltr 88-01 Re Grand Gulf Nuclear Plant ML19332G5641989-11-30030 November 1989 Analysis of Core Damage Frequency: Grand Gulf, Unit 1 Internal Events Appendices.Continuation of Appendix D 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 ML20248F3411989-09-30030 September 1989 Analysis of Core Damage Frequency: Grand Gulf, Unit 1 Internal Events Appendices ML20248F3451989-09-30030 September 1989 Analysis of Core Damage Frequency: Grand Gulf, Unit 1 Internal Events ML19324A6231989-05-31031 May 1989 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Grand Gulf-1, 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 ML20070Q5571989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Grand Gulf 1 ML20043B3721988-12-31031 December 1988 Stability Measurements During Cycle 2. 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 ML19325C1581988-02-22022 February 1988 Technical Evaluation of Dcrdr. ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 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 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 ML20235J2291987-09-30030 September 1987 Draft PRA-Based Sys Insp Plans 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 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 ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML18052B1931987-06-30030 June 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Calvert Cliffs-1 & -2, Millstone-2 & Palisades, Final Informal Rept ML20235A0161987-04-30030 April 1987 Analysis of Core Damage Frequency from Internal Events:Grand Gulf,Unit 1.Main Report 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 1999-07-30 Category:ETC. (PERIODIC MONTHYEARML20211K7681999-07-30030 July 1999
[Table view]Evaluation of Fuel Pin Failure Timing in Boiling Water Reactors ML20216E8721998-03-13013 March 1998 Rept to NRC Environ Monitoring at Grand Gulf Nuclear Station CY97, Conducted by Contract NRC-29-83-621 ML20101C8941995-10-16016 October 1995 Plant IPE Insight Support Rept for NUREG-1150 Plants ML20087K3691995-07-31031 July 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Summary of Results ML20082D5261995-03-31031 March 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Supporting Melcor Calculations ML20082B7411995-03-31031 March 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Main Report and Appendices ML20073C3671994-08-31031 August 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf, Unit 1.Analysis of Core Damage Frequency from Seismic Events During Mid-Loop Operations.Main Report ML20072N9991994-07-31031 July 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internally Induced Flooding Events for Plant Operational State 5 During a Refueling. ML20072D0581994-07-31031 July 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage ML20071L7411994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal ML20071L7191994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal ML20071L6111994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During Refueling Outage.Internal ML20071L5971994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Main Report ML20071L5831994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Section 10 ML20071L5661994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Sections 1-9 ML20063B5501994-01-24024 January 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,Grand Gulf,Unit 1, Technical Evaluation Rept ML20064K0511993-10-31031 October 1993 Summary Rept Of:Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Final Ltr Rept ML18151A8991992-05-31031 May 1992 Summary Rept of :Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Draft Ltr Rept ML20066D3421990-12-31031 December 1990 Evaluation of Severe Accident Risks: Grand Gulf,Unit 1. Appendices ML20066D2981990-12-31031 December 1990 Evaluation of Severe Accident Risks: Grand Gulf,Unit 1.Main Report ML20059N5101990-08-31031 August 1990 Technical Evaluation Rept on Response from Sys Energy Resources,Inc to Generic Ltr 88-01 Re Grand Gulf Nuclear Plant ML19332G5641989-11-30030 November 1989 Analysis of Core Damage Frequency: Grand Gulf, Unit 1 Internal Events Appendices.Continuation of Appendix D 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 ML20248F3411989-09-30030 September 1989 Analysis of Core Damage Frequency: Grand Gulf, Unit 1 Internal Events Appendices ML20248F3451989-09-30030 September 1989 Analysis of Core Damage Frequency: Grand Gulf, Unit 1 Internal Events ML19324A6231989-05-31031 May 1989 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Grand Gulf-1, 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 ML20070Q5571989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Grand Gulf 1 ML20043B3721988-12-31031 December 1988 Stability Measurements During Cycle 2. 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 ML19325C1581988-02-22022 February 1988 Technical Evaluation of Dcrdr. ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 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 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 ML20235J2291987-09-30030 September 1987 Draft PRA-Based Sys Insp Plans 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 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 ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML18052B1931987-06-30030 June 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Calvert Cliffs-1 & -2, Millstone-2 & Palisades, Final Informal Rept ML20235A0161987-04-30030 April 1987 Analysis of Core Damage Frequency from Internal Events:Grand Gulf,Unit 1.Main Report 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 1999-07-30 Category:TEXT-PROCUREMENT & CONTRACTS MONTHYEARML20211K7681999-07-30030 July 1999
[Table view]Evaluation of Fuel Pin Failure Timing in Boiling Water Reactors ML20216E8721998-03-13013 March 1998 Rept to NRC Environ Monitoring at Grand Gulf Nuclear Station CY97, Conducted by Contract NRC-29-83-621 ML20101C8941995-10-16016 October 1995 Plant IPE Insight Support Rept for NUREG-1150 Plants ML20087K3691995-07-31031 July 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Summary of Results ML20082D5261995-03-31031 March 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Supporting Melcor Calculations ML20082B7411995-03-31031 March 1995 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage.Main Report and Appendices ML20073C3671994-08-31031 August 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf, Unit 1.Analysis of Core Damage Frequency from Seismic Events During Mid-Loop Operations.Main Report ML20072N9991994-07-31031 July 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internally Induced Flooding Events for Plant Operational State 5 During a Refueling. ML20072D0581994-07-31031 July 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage ML20071L7411994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal ML20071L7191994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Internal ML20071L6111994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During Refueling Outage.Internal ML20071L5971994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Main Report ML20071L5831994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Section 10 ML20071L5661994-06-30030 June 1994 Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Grand Gulf,Unit 1.Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage.Sections 1-9 ML20063B5501994-01-24024 January 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,Grand Gulf,Unit 1, Technical Evaluation Rept ML20064K0511993-10-31031 October 1993 Summary Rept Of:Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Final Ltr Rept ML18151A8991992-05-31031 May 1992 Summary Rept of :Grand Gulf Low Power & Shutdown Abridged Risk Analysis, Draft Ltr Rept ML20066D3421990-12-31031 December 1990 Evaluation of Severe Accident Risks: Grand Gulf,Unit 1. Appendices ML20066D2981990-12-31031 December 1990 Evaluation of Severe Accident Risks: Grand Gulf,Unit 1.Main Report ML20059N5101990-08-31031 August 1990 Technical Evaluation Rept on Response from Sys Energy Resources,Inc to Generic Ltr 88-01 Re Grand Gulf Nuclear Plant ML19332G5641989-11-30030 November 1989 Analysis of Core Damage Frequency: Grand Gulf, Unit 1 Internal Events Appendices.Continuation of Appendix D 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 ML20248F3411989-09-30030 September 1989 Analysis of Core Damage Frequency: Grand Gulf, Unit 1 Internal Events Appendices ML20248F3451989-09-30030 September 1989 Analysis of Core Damage Frequency: Grand Gulf, Unit 1 Internal Events 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 ML19324A6231989-05-31031 May 1989 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Grand Gulf-1, Technical Evaluation Rept 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 ML20070Q5571989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Grand Gulf 1 ML20043B3721988-12-31031 December 1988 Stability Measurements During Cycle 2. 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 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 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 ML19325C1581988-02-22022 February 1988 Technical Evaluation of Dcrdr. ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 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 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 ML20149F1691988-01-11011 January 1988 Contract: Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites, Awarded to New England Bell Telephone Co ML20149F1311988-01-11011 January 1988 Notification of Contract Execution: Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee & Pilgrim & Seabrook Resident Sites, Awarded to New England Bell Telephone Co ML20236T7371987-11-24024 November 1987 Notification of Contract Execution,Mod 7,to Dresden & Perry Simulator. Contractor:Ge ML20236T7461987-11-24024 November 1987 Mod 7,extending Period of Performance Through 880930,adding Addl GE Simulator to Contract & Scheduling Four Simulator Courses Through FY88,to Dresden & Perry Simulator ML20235J2291987-09-30030 September 1987 Draft PRA-Based Sys Insp Plans ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept 1999-07-30 |
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