ML20092H128
From kanterella
| ML20092H128 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/31/1995 |
| From: | Akers D, Menke L IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY |
| To: | NRC (Affiliation Not Assigned) |
| Shared Package | |
| ML20092H099 | List: |
| References | |
| CON-FIN-E-2084 INEL-95-0375, INEL-95-375, NUDOCS 9509200271 | |
| Download: ML20092H128 (26) | |
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|---|---|
Category:CONTRACTED REPORT - RTA
MONTHYEARML20217K4621998-01-30030 January 1998
[Table view]Technical Evaluation Rept on Second 10-Yr Interval ISI Program Plan:Tva,Sequoyah Nuclear Plant,Units 1 & 2 ML20092H1281995-08-31031 August 1995 Evaluation of Sequoyah Nuclear Plant Offsite Dose Calculation Manual,Rev 28 ML20072T9151994-08-31031 August 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Sequoyah-1/-2, Technical Evaluation Rept ML20087A5261991-12-31031 December 1991 Analysis of Bellows Expansion Joints in the Sequoyah Containment ML20085M3861991-10-24024 October 1991 Final Technical Evaluation Rept,Sequoyah Nuclear Plant, Units 1 & 2 Station Blackout Evaluation ML20066D2651990-12-31031 December 1990 Simplified Containment Event Tree Analysis for the Sequoyah Ice Condenser Containment ML20066D2731990-12-31031 December 1990 Evaluation of Severe Accident Risks: Sequoyah,Unit 1.Main Report ML20066D2821990-12-31031 December 1990 Evaluation of Severe Accident Risks: Sequoyah,Unit 1. Appendices ML20059H4591990-07-31031 July 1990 Risk-Based Insp Guide for Sequoyah Nuclear Power Station Final Rept, Informal Rept ML20043A3681990-04-30030 April 1990 Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events ML20043A2811990-04-30030 April 1990 Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events Appendices ML19332C9921989-11-30030 November 1989 Draft Risk-Based Insp Guide for Sequoyah Sequoyah Nuclear Power Station. ML20245J9261989-03-31031 March 1989 TMI Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing Sequoyah Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20154H3271988-08-23023 August 1988 Technical Evaluation Rept Re Requests for Relief,Pump & Valve Inservice Testing Program,Sequoyah Nuclear Plant, Units 1 & 2 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20147C3231987-12-30030 December 1987 Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20236F3471987-09-18018 September 1987 Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20237H0691987-08-10010 August 1987 Rev 1 to Technical Evaluation Rept of Dcrdr for Sequoyah Nuclear Power Plant Units 1 & 2 ML20235T1951987-07-17017 July 1987 Evaluation of Nuclear Safety Review Staff Concerns Requiring Resolution Before & After Restart, Technical Evaluation Rept ML20234D6011987-06-25025 June 1987 Errata to Analysis of Core Damage Frequency from Internal Events:Sequoyah,Unit 1, Forwarding Set of 39 Aperture Cards Which Should Have Been Included W/Original rept.W/39 Oversize Drawings ML20213H0171987-05-11011 May 1987 Conformance to Reg Guide 1.97 Sequoyah Nuclear Plant,Units 1 & 2 ML20215G2781987-03-23023 March 1987 TVA Sequoyah Electrical Medium Voltage Short Circuit Analysis Calculations, Final Technical Evaluation Rept ML20214B2411987-02-28028 February 1987 Containment Event Analysis for Postulated Severe Accidents: Sequoyah Power Station,Unit 1.Draft Report for Comment ML20214B2981987-02-28028 February 1987 Analysis of Core Damage Frequency from Internal Events: Sequoyah,Unit 1 ML20214V4861987-02-28028 February 1987 Evaluation of Severe Accident Risks and the Potential for Risk Reduction:Sequoyah Power Station,Unit 1.Draft for Comment ML20206H1441986-09-0202 September 1986 Direct Containment Heating Analysis W/Contain Computer Code, Ltr Rept ML20215N4281986-08-31031 August 1986 Technical Evaluation Rept Re Welding Concern Program at TVA Sequoyah Units 1 & 2 ML20206H0811986-05-0909 May 1986 Some Sensitivities for Direct Containment Heating Loads ML20197J4641986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Catawba Nuclear Stations 1 & 2,DC Cook Nuclear Power Plants 1 & 2,WB McGuire Nuclear Stations 1 & 2,Sequoyah Nuclear Plants 1 & 2 ML20137D3131985-08-15015 August 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implication of Salem ATWS Events),Item 1.2 'Post-Trip Review:Data & Info Capabilities' for Sequoyah Nuclear Plant,Units 1 & 2 ML20239A6811985-07-31031 July 1985 Crack Propagation in High Strain Regions of Sequoyah Containment ML20244D3871985-07-10010 July 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 Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20106C9961984-07-31031 July 1984 Draft Vol IV, Radionuclide Release Under Specific LWR Accident Conditions,Pwr,Ice Condenser Containment Design ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20065D2831982-09-24024 September 1982 PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),TVA,Sequoyah Nuclear Power Plant Unit 1, Technical Evaluation Rept ML20064N7371982-08-31031 August 1982 Reliability Analysis of Containment Strength.Sequoyah and McGuire Ice Condenser Containments ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20114F8301982-07-16016 July 1982 to Preliminary Assessment of Core Melt Probability in Cold Shutdown Following Postulated LOCA at Sequoyah Nuclear Plant, Final Rept ML20055A4311982-06-14014 June 1982 Control of Heavy Loads, Draft Technical Evaluation Rept ML20040E9561981-12-21021 December 1981 Equipment Environ Qualification Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment, Request for Addl Info ML20040E9641981-12-21021 December 1981 Equipment Environ Qualification Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment, Request for Addl Info ML19345H2931981-04-30030 April 1981 Reactor Safety Study Methodology Applications Program: Sequoyah #1 PWR Power Plant ML19347E1831981-04-30030 April 1981 Analysis of Hydrogen Mitigation for Degraded Core Accidents in the Sequoyah Nuclear Power Plant ML19350B5881980-12-0101 December 1980 Rough Draft, Analysis of Hydrogen Mitigation for Degraded Core Accidents in Sequoyah Nuclear Power Plant, Prepared for Ofc of Nuclear Regulatory Research ML19330C4231980-07-30030 July 1980 Suppl to 800718 Rept, Preliminary Calculations,Ultimate Strength for Hydrogen Explosion,Sequoyah Containment Vessel. 1998-01-30 Category:QUICK LOOK MONTHYEARML20217K4621998-01-30030 January 1998
[Table view]Technical Evaluation Rept on Second 10-Yr Interval ISI Program Plan:Tva,Sequoyah Nuclear Plant,Units 1 & 2 ML20092H1281995-08-31031 August 1995 Evaluation of Sequoyah Nuclear Plant Offsite Dose Calculation Manual,Rev 28 ML20072T9151994-08-31031 August 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Sequoyah-1/-2, Technical Evaluation Rept ML20087A5261991-12-31031 December 1991 Analysis of Bellows Expansion Joints in the Sequoyah Containment ML20085M3861991-10-24024 October 1991 Final Technical Evaluation Rept,Sequoyah Nuclear Plant, Units 1 & 2 Station Blackout Evaluation ML20066D2651990-12-31031 December 1990 Simplified Containment Event Tree Analysis for the Sequoyah Ice Condenser Containment ML20066D2731990-12-31031 December 1990 Evaluation of Severe Accident Risks: Sequoyah,Unit 1.Main Report ML20066D2821990-12-31031 December 1990 Evaluation of Severe Accident Risks: Sequoyah,Unit 1. Appendices ML20059H4591990-07-31031 July 1990 Risk-Based Insp Guide for Sequoyah Nuclear Power Station Final Rept, Informal Rept ML20043A3681990-04-30030 April 1990 Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events ML20043A2811990-04-30030 April 1990 Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events Appendices ML19332C9921989-11-30030 November 1989 Draft Risk-Based Insp Guide for Sequoyah Sequoyah Nuclear Power Station. ML20245J9261989-03-31031 March 1989 TMI Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing Sequoyah Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20154H3271988-08-23023 August 1988 Technical Evaluation Rept Re Requests for Relief,Pump & Valve Inservice Testing Program,Sequoyah Nuclear Plant, Units 1 & 2 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20147C3231987-12-30030 December 1987 Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20236F3471987-09-18018 September 1987 Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20237H0691987-08-10010 August 1987 Rev 1 to Technical Evaluation Rept of Dcrdr for Sequoyah Nuclear Power Plant Units 1 & 2 ML20235T1951987-07-17017 July 1987 Evaluation of Nuclear Safety Review Staff Concerns Requiring Resolution Before & After Restart, Technical Evaluation Rept ML20234D6011987-06-25025 June 1987 Errata to Analysis of Core Damage Frequency from Internal Events:Sequoyah,Unit 1, Forwarding Set of 39 Aperture Cards Which Should Have Been Included W/Original rept.W/39 Oversize Drawings ML20213H0171987-05-11011 May 1987 Conformance to Reg Guide 1.97 Sequoyah Nuclear Plant,Units 1 & 2 ML20215G2781987-03-23023 March 1987 TVA Sequoyah Electrical Medium Voltage Short Circuit Analysis Calculations, Final Technical Evaluation Rept ML20214B2411987-02-28028 February 1987 Containment Event Analysis for Postulated Severe Accidents: Sequoyah Power Station,Unit 1.Draft Report for Comment ML20214B2981987-02-28028 February 1987 Analysis of Core Damage Frequency from Internal Events: Sequoyah,Unit 1 ML20214V4861987-02-28028 February 1987 Evaluation of Severe Accident Risks and the Potential for Risk Reduction:Sequoyah Power Station,Unit 1.Draft for Comment ML20206H1441986-09-0202 September 1986 Direct Containment Heating Analysis W/Contain Computer Code, Ltr Rept ML20215N4281986-08-31031 August 1986 Technical Evaluation Rept Re Welding Concern Program at TVA Sequoyah Units 1 & 2 ML20206H0811986-05-0909 May 1986 Some Sensitivities for Direct Containment Heating Loads ML20197J4641986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Catawba Nuclear Stations 1 & 2,DC Cook Nuclear Power Plants 1 & 2,WB McGuire Nuclear Stations 1 & 2,Sequoyah Nuclear Plants 1 & 2 ML20137D3131985-08-15015 August 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implication of Salem ATWS Events),Item 1.2 'Post-Trip Review:Data & Info Capabilities' for Sequoyah Nuclear Plant,Units 1 & 2 ML20239A6811985-07-31031 July 1985 Crack Propagation in High Strain Regions of Sequoyah Containment ML20244D3871985-07-10010 July 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 Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20106C9961984-07-31031 July 1984 Draft Vol IV, Radionuclide Release Under Specific LWR Accident Conditions,Pwr,Ice Condenser Containment Design ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20065D2831982-09-24024 September 1982 PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),TVA,Sequoyah Nuclear Power Plant Unit 1, Technical Evaluation Rept ML20064N7371982-08-31031 August 1982 Reliability Analysis of Containment Strength.Sequoyah and McGuire Ice Condenser Containments ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20114F8301982-07-16016 July 1982 to Preliminary Assessment of Core Melt Probability in Cold Shutdown Following Postulated LOCA at Sequoyah Nuclear Plant, Final Rept ML20055A4311982-06-14014 June 1982 Control of Heavy Loads, Draft Technical Evaluation Rept ML20040E9561981-12-21021 December 1981 Equipment Environ Qualification Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment, Request for Addl Info ML20040E9641981-12-21021 December 1981 Equipment Environ Qualification Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment, Request for Addl Info ML19345H2931981-04-30030 April 1981 Reactor Safety Study Methodology Applications Program: Sequoyah #1 PWR Power Plant ML19347E1831981-04-30030 April 1981 Analysis of Hydrogen Mitigation for Degraded Core Accidents in the Sequoyah Nuclear Power Plant ML19350B5881980-12-0101 December 1980 Rough Draft, Analysis of Hydrogen Mitigation for Degraded Core Accidents in Sequoyah Nuclear Power Plant, Prepared for Ofc of Nuclear Regulatory Research ML19330C4231980-07-30030 July 1980 Suppl to 800718 Rept, Preliminary Calculations,Ultimate Strength for Hydrogen Explosion,Sequoyah Containment Vessel. 1998-01-30 Category:ETC. (PERIODIC MONTHYEARML20217K4621998-01-30030 January 1998
[Table view]Technical Evaluation Rept on Second 10-Yr Interval ISI Program Plan:Tva,Sequoyah Nuclear Plant,Units 1 & 2 ML20092H1281995-08-31031 August 1995 Evaluation of Sequoyah Nuclear Plant Offsite Dose Calculation Manual,Rev 28 ML20072T9151994-08-31031 August 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Sequoyah-1/-2, Technical Evaluation Rept ML20087A5261991-12-31031 December 1991 Analysis of Bellows Expansion Joints in the Sequoyah Containment ML20085M3861991-10-24024 October 1991 Final Technical Evaluation Rept,Sequoyah Nuclear Plant, Units 1 & 2 Station Blackout Evaluation ML20066D2651990-12-31031 December 1990 Simplified Containment Event Tree Analysis for the Sequoyah Ice Condenser Containment ML20066D2731990-12-31031 December 1990 Evaluation of Severe Accident Risks: Sequoyah,Unit 1.Main Report ML20066D2821990-12-31031 December 1990 Evaluation of Severe Accident Risks: Sequoyah,Unit 1. Appendices ML20059H4591990-07-31031 July 1990 Risk-Based Insp Guide for Sequoyah Nuclear Power Station Final Rept, Informal Rept ML20043A3681990-04-30030 April 1990 Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events ML20043A2811990-04-30030 April 1990 Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events Appendices ML19332C9921989-11-30030 November 1989 Draft Risk-Based Insp Guide for Sequoyah Sequoyah Nuclear Power Station. ML20245J9261989-03-31031 March 1989 TMI Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing Sequoyah Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20154H3271988-08-23023 August 1988 Technical Evaluation Rept Re Requests for Relief,Pump & Valve Inservice Testing Program,Sequoyah Nuclear Plant, Units 1 & 2 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20147C3231987-12-30030 December 1987 Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20236F3471987-09-18018 September 1987 Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20237H0691987-08-10010 August 1987 Rev 1 to Technical Evaluation Rept of Dcrdr for Sequoyah Nuclear Power Plant Units 1 & 2 ML20235T1951987-07-17017 July 1987 Evaluation of Nuclear Safety Review Staff Concerns Requiring Resolution Before & After Restart, Technical Evaluation Rept ML20234D6011987-06-25025 June 1987 Errata to Analysis of Core Damage Frequency from Internal Events:Sequoyah,Unit 1, Forwarding Set of 39 Aperture Cards Which Should Have Been Included W/Original rept.W/39 Oversize Drawings ML20213H0171987-05-11011 May 1987 Conformance to Reg Guide 1.97 Sequoyah Nuclear Plant,Units 1 & 2 ML20215G2781987-03-23023 March 1987 TVA Sequoyah Electrical Medium Voltage Short Circuit Analysis Calculations, Final Technical Evaluation Rept ML20214B2411987-02-28028 February 1987 Containment Event Analysis for Postulated Severe Accidents: Sequoyah Power Station,Unit 1.Draft Report for Comment ML20214B2981987-02-28028 February 1987 Analysis of Core Damage Frequency from Internal Events: Sequoyah,Unit 1 ML20214V4861987-02-28028 February 1987 Evaluation of Severe Accident Risks and the Potential for Risk Reduction:Sequoyah Power Station,Unit 1.Draft for Comment ML20206H1441986-09-0202 September 1986 Direct Containment Heating Analysis W/Contain Computer Code, Ltr Rept ML20215N4281986-08-31031 August 1986 Technical Evaluation Rept Re Welding Concern Program at TVA Sequoyah Units 1 & 2 ML20206H0811986-05-0909 May 1986 Some Sensitivities for Direct Containment Heating Loads ML20197J4641986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Catawba Nuclear Stations 1 & 2,DC Cook Nuclear Power Plants 1 & 2,WB McGuire Nuclear Stations 1 & 2,Sequoyah Nuclear Plants 1 & 2 ML20137D3131985-08-15015 August 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implication of Salem ATWS Events),Item 1.2 'Post-Trip Review:Data & Info Capabilities' for Sequoyah Nuclear Plant,Units 1 & 2 ML20239A6811985-07-31031 July 1985 Crack Propagation in High Strain Regions of Sequoyah Containment ML20244D3871985-07-10010 July 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 Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20106C9961984-07-31031 July 1984 Draft Vol IV, Radionuclide Release Under Specific LWR Accident Conditions,Pwr,Ice Condenser Containment Design ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20065D2831982-09-24024 September 1982 PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),TVA,Sequoyah Nuclear Power Plant Unit 1, Technical Evaluation Rept ML20064N7371982-08-31031 August 1982 Reliability Analysis of Containment Strength.Sequoyah and McGuire Ice Condenser Containments ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20114F8301982-07-16016 July 1982 to Preliminary Assessment of Core Melt Probability in Cold Shutdown Following Postulated LOCA at Sequoyah Nuclear Plant, Final Rept ML20055A4311982-06-14014 June 1982 Control of Heavy Loads, Draft Technical Evaluation Rept ML20040E9561981-12-21021 December 1981 Equipment Environ Qualification Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment, Request for Addl Info ML20040E9641981-12-21021 December 1981 Equipment Environ Qualification Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment, Request for Addl Info ML19345H2931981-04-30030 April 1981 Reactor Safety Study Methodology Applications Program: Sequoyah #1 PWR Power Plant ML19347E1831981-04-30030 April 1981 Analysis of Hydrogen Mitigation for Degraded Core Accidents in the Sequoyah Nuclear Power Plant ML19350B5881980-12-0101 December 1980 Rough Draft, Analysis of Hydrogen Mitigation for Degraded Core Accidents in Sequoyah Nuclear Power Plant, Prepared for Ofc of Nuclear Regulatory Research ML19330C4231980-07-30030 July 1980 Suppl to 800718 Rept, Preliminary Calculations,Ultimate Strength for Hydrogen Explosion,Sequoyah Containment Vessel. 1998-01-30 Category:TEXT-PROCUREMENT & CONTRACTS MONTHYEARML20217K4621998-01-30030 January 1998
[Table view]Technical Evaluation Rept on Second 10-Yr Interval ISI Program Plan:Tva,Sequoyah Nuclear Plant,Units 1 & 2 ML20092H1281995-08-31031 August 1995 Evaluation of Sequoyah Nuclear Plant Offsite Dose Calculation Manual,Rev 28 ML20072T9151994-08-31031 August 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Sequoyah-1/-2, Technical Evaluation Rept ML20087A5261991-12-31031 December 1991 Analysis of Bellows Expansion Joints in the Sequoyah Containment ML20085M3861991-10-24024 October 1991 Final Technical Evaluation Rept,Sequoyah Nuclear Plant, Units 1 & 2 Station Blackout Evaluation ML20066D2821990-12-31031 December 1990 Evaluation of Severe Accident Risks: Sequoyah,Unit 1. Appendices ML20066D2731990-12-31031 December 1990 Evaluation of Severe Accident Risks: Sequoyah,Unit 1.Main Report ML20066D2651990-12-31031 December 1990 Simplified Containment Event Tree Analysis for the Sequoyah Ice Condenser Containment ML20059H4591990-07-31031 July 1990 Risk-Based Insp Guide for Sequoyah Nuclear Power Station Final Rept, Informal Rept ML20059A1311990-07-19019 July 1990 Mod 20,revising Contract to Purchase Addl Training Aids,To Use to TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML20059A1221990-07-19019 July 1990 Notification of Contract Execution,Mod 20,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20043A3681990-04-30030 April 1990 Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events ML20043A2811990-04-30030 April 1990 Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events Appendices ML19332C9921989-11-30030 November 1989 Draft Risk-Based Insp Guide for Sequoyah Sequoyah Nuclear Power Station. 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 ML20245J9261989-03-31031 March 1989 TMI Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing Sequoyah Nuclear Plant Units 1 & 2, Technical Evaluation Rept ML20154H3271988-08-23023 August 1988 Technical Evaluation Rept Re Requests for Relief,Pump & Valve Inservice Testing Program,Sequoyah Nuclear Plant, Units 1 & 2 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20147C3231987-12-30030 December 1987 Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20236F3471987-09-18018 September 1987 Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20237H0691987-08-10010 August 1987 Rev 1 to Technical Evaluation Rept of Dcrdr for Sequoyah Nuclear Power Plant Units 1 & 2 ML20235T1951987-07-17017 July 1987 Evaluation of Nuclear Safety Review Staff Concerns Requiring Resolution Before & After Restart, Technical Evaluation Rept ML20234D6011987-06-25025 June 1987 Errata to Analysis of Core Damage Frequency from Internal Events:Sequoyah,Unit 1, Forwarding Set of 39 Aperture Cards Which Should Have Been Included W/Original rept.W/39 Oversize Drawings ML20214R1481987-05-29029 May 1987 Notification of Contract Execution,Mod 12,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20214R1561987-05-29029 May 1987 Mod 12,providing Incremental Funds & Increasing Ceiling,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML20213H0171987-05-11011 May 1987 Conformance to Reg Guide 1.97 Sequoyah Nuclear Plant,Units 1 & 2 ML20206G5861987-04-0808 April 1987 Notification of Contract Execution,Mod 11,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Brown Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20206G6381987-04-0808 April 1987 Mod 11,recognizing Administrative Changes Due to NRC Reorganization,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML20215G2781987-03-23023 March 1987 TVA Sequoyah Electrical Medium Voltage Short Circuit Analysis Calculations, Final Technical Evaluation Rept ML20214V4861987-02-28028 February 1987 Evaluation of Severe Accident Risks and the Potential for Risk Reduction:Sequoyah Power Station,Unit 1.Draft for Comment ML20214B2411987-02-28028 February 1987 Containment Event Analysis for Postulated Severe Accidents: Sequoyah Power Station,Unit 1.Draft Report for Comment ML20214B2981987-02-28028 February 1987 Analysis of Core Damage Frequency from Internal Events: Sequoyah,Unit 1 ML20211E2601987-02-13013 February 1987 Notification of Contract Execution,Mod 10,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20211E2961987-02-13013 February 1987 Mod 10,providing Addl Work Entailing Training for NRC Inspectors & Supervisors,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry, Sequoyah & Bellefonte Simulators ML20210G4871986-09-19019 September 1986 Notification of Contract Execution,Mod 9,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20210G5571986-09-19019 September 1986 Mod 9,providing Incremental Funds,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML20214T1531986-09-0404 September 1986 Mod 6,providing for Lease of Yellow Creek Model to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML20214T1291986-09-0404 September 1986 Notification of Contract Execution,Mod 6,to Use of TVA Reactor Simulator Facilities of Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20206H1441986-09-0202 September 1986 Direct Containment Heating Analysis W/Contain Computer Code, Ltr Rept ML20215N4281986-08-31031 August 1986 Technical Evaluation Rept Re Welding Concern Program at TVA Sequoyah Units 1 & 2 ML20206M1201986-08-15015 August 1986 Notification of Contract Execution,Mod 7,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20206M1321986-08-15015 August 1986 Mod 7,providing Cost Estimate for Leasing of Simulators for Extended Period of Performance,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on the Browns Ferry,Sequoyah & Bellefonte Simulators ML20205D0081986-08-0606 August 1986 Mod 8,providing Incremental Funds,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML20205C9761986-08-0606 August 1986 Notification of Contract Execution,Mod 8,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20206H0811986-05-0909 May 1986 Some Sensitivities for Direct Containment Heating Loads ML20197J4641986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Catawba Nuclear Stations 1 & 2,DC Cook Nuclear Power Plants 1 & 2,WB McGuire Nuclear Stations 1 & 2,Sequoyah Nuclear Plants 1 & 2 ML20136H6031985-12-23023 December 1985 Notification of Contract Execution,Mod 5,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva 1998-01-30 |
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