ML19330C423
ML19330C423 | |
Person / Time | |
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Site: | Sequoyah |
Issue date: | 07/30/1980 |
From: | AMES LABORATORY, ENERGY & MINERAL RESOURCES RESEARCH |
To: | Office of Nuclear Reactor Regulation |
Shared Package | |
ML19330C420 | List: |
References | |
CON-FIN-A-4131 NUDOCS 8008080364 | |
Download: ML19330C423 (2) | |
Similar Documents at Sequoyah | |
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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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LJ SUPFLEMENT T0: ' PRELIMINARY CALCULATIONS, ULTIMATE STRENGTH FOR HYDROGEN EXPLOSION, SEQUOYAH CONTAINMENT VESSEL-(submitted 7/18/80)
TO: F. P.~ Schauer, Chief Structural Engineering Branch Division of System Safety Office of Nuclear Reactor Regulation Nuclear Regulatory Commission Washington, DC 20555 BY: Lowell Greimann-Ames Laboratory Iowa State University
'Ames, IA 50011 DATE:- July 30 --1980-Idealized Pressure Loading The dynamic pressures associated with detonation are not significant for two reasons (see pg. 6).
.'The' detonation time is much smaller than the period of motion of the structure
~t d
T , 0.0000025 0.040 = 6.25(10-5)
. The impulse associated with detonation,dI , is negligible with respect to the impulse from the venting pressure, ly ,
I 1. 375(l'0-5)p 0.015 p v = 9.2(10 )
y or, I d
is about 0.1% of Iy .
Ductility Capacity - Lower Bound A lower-bound on the duct.iity capacity of a pressure vessel is D
C.
This ~value is a design recommendation by- the Welding Institute in the United Kingdom'and is. based upon experimental evidence.* Also, the ASME Rolfe & Barsom,4racture and Fatique Control in Structures, Prentice Hall,11977, pp-. 527-530.
8 00 3.06 0M
- x . - - _ _ -
s l- 3:o Boiler.and' Pres ure Vessel Code ** previously defined the collapse
' pressure of a vessel as the pressure at which the displacement is two i
times the displacement at first yieldirg. Note that both of these values are design recommendations. As such, they incorporate some (unspecified)
L factor of safety--probably between 2 and 3. With this conservative value of ductility capacity,'the ultimate venting pressure would be (front page 14) about 31 psi.
'l ,
ASME Boiler' and Pressure Vessel Code,Section III, Division .1, par.1430, Appendix 11,.1974.
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.y. . , , . ., . -.- - --,