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Issue date | Title | Topic | |
---|---|---|---|
ML20217K462 | 30 January 1998 | Technical Evaluation Rept on Second 10-Yr Interval ISI Program Plan:Tva,Sequoyah Nuclear Plant,Units 1 & 2 | Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Pressure boundary leak Through Wall Leak Scaffolding |
ML20092H128 | 31 August 1995 | Evaluation of Sequoyah Nuclear Plant Offsite Dose Calculation Manual,Rev 28 | Offsite Dose Calculation Manual |
ML20072T915 | 31 August 1994 | Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Sequoyah-1/-2, Technical Evaluation Rept | |
ML20087A526 | 31 December 1991 | Analysis of Bellows Expansion Joints in the Sequoyah Containment | Hydrostatic Finite Element Analysis Earthquake Flow Induced Vibration |
ML20085M386 | 24 October 1991 | Final Technical Evaluation Rept,Sequoyah Nuclear Plant, Units 1 & 2 Station Blackout Evaluation | Safe Shutdown |
ML20066D265 | 31 December 1990 | Simplified Containment Event Tree Analysis for the Sequoyah Ice Condenser Containment | |
ML20066D273 | 31 December 1990 | Evaluation of Severe Accident Risks: Sequoyah,Unit 1.Main Report | Probabilistic Risk Assessment Earthquake Fatality Failure to Scram |
ML20066D282 | 31 December 1990 | Evaluation of Severe Accident Risks: Sequoyah,Unit 1. Appendices | Time to boil Probabilistic Risk Assessment Fatality |
ML20059H459 | 31 July 1990 | Risk-Based Insp Guide for Sequoyah Nuclear Power Station Final Rept, Informal Rept | Shutdown Margin Probabilistic Risk Assessment |
ML20043A368 | 30 April 1990 | Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events | |
ML20043A281 | 30 April 1990 | Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events Appendices | |
ML19332C992 | 30 November 1989 | Draft Risk-Based Insp Guide for Sequoyah Sequoyah Nuclear Power Station. | Shutdown Margin Probabilistic Risk Assessment |
ML20245J926 | 31 March 1989 | TMI Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing Sequoyah Nuclear Plant Units 1 & 2, Technical Evaluation Rept | Loop seal Anticipated operational occurrence |
ML20154H327 | 23 August 1988 | Technical Evaluation Rept Re Requests for Relief,Pump & Valve Inservice Testing Program,Sequoyah Nuclear Plant, Units 1 & 2 | |
ML20196C164 | 4 February 1988 | Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 | |
ML20147C323 | 30 December 1987 | Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation Rept | |
ML20236F347 | 18 September 1987 | Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation Rept | Stroke time Power-Operated Valves Power Operated Valves |
ML20237H069 | 10 August 1987 | Rev 1 to Technical Evaluation Rept of Dcrdr for Sequoyah Nuclear Power Plant Units 1 & 2 | Safe Shutdown Emergency Lighting |
ML20235T195 | 17 July 1987 | Evaluation of Nuclear Safety Review Staff Concerns Requiring Resolution Before & After Restart, Technical Evaluation Rept | |
ML20234D601 | 25 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 | |
ML20213H017 | 11 May 1987 | Conformance to Reg Guide 1.97 Sequoyah Nuclear Plant,Units 1 & 2 | Boric Acid |
ML20215G278 | 23 March 1987 | TVA Sequoyah Electrical Medium Voltage Short Circuit Analysis Calculations, Final Technical Evaluation Rept | Safe Shutdown |
ML20214B241 | 28 February 1987 | Containment Event Analysis for Postulated Severe Accidents: Sequoyah Power Station,Unit 1.Draft Report for Comment | Probabilistic Risk Assessment Earthquake Failure to Scram |
ML20214B298 | 28 February 1987 | Analysis of Core Damage Frequency from Internal Events: Sequoyah,Unit 1 | Safe Shutdown Boric Acid Ultimate heat sink Mission time Internal Flooding Probabilistic Risk Assessment Failure to Scram |
ML20214V486 | 28 February 1987 | Evaluation of Severe Accident Risks and the Potential for Risk Reduction:Sequoyah Power Station,Unit 1.Draft for Comment | Loop seal Probabilistic Risk Assessment Earthquake Backfit Fatality |
ML20206H144 | 2 September 1986 | Direct Containment Heating Analysis W/Contain Computer Code, Ltr Rept | |
ML20215N428 | 31 August 1986 | Technical Evaluation Rept Re Welding Concern Program at TVA Sequoyah Units 1 & 2 | Backfit |
ML20206H081 | 9 May 1986 | Some Sensitivities for Direct Containment Heating Loads | |
ML20197J464 | 30 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 | |
ML20137D313 | 15 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 | |
ML20239A681 | 31 July 1985 | Crack Propagation in High Strain Regions of Sequoyah Containment | Finite Element Analysis |
ML20244D387 | 10 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. | |
ML20244D438 | 30 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 | |
ML20106C996 | 31 July 1984 | Draft Vol IV, Radionuclide Release Under Specific LWR Accident Conditions,Pwr,Ice Condenser Containment Design | |
ML20127A289 | 5 October 1982 | Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 | |
ML20065D283 | 24 September 1982 | PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),TVA,Sequoyah Nuclear Power Plant Unit 1, Technical Evaluation Rept | Boric Acid Shutdown Margin |
ML20064N737 | 31 August 1982 | Reliability Analysis of Containment Strength.Sequoyah and McGuire Ice Condenser Containments | Finite Element Analysis Earthquake |
ML20126F254 | 26 August 1982 | Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 | |
ML20114F830 | 16 July 1982 | to Preliminary Assessment of Core Melt Probability in Cold Shutdown Following Postulated LOCA at Sequoyah Nuclear Plant, Final Rept | Boric Acid Shutdown Margin Ultimate heat sink Fire Barrier Time to boil Safe Shutdown Earthquake |
ML20055A431 | 14 June 1982 | Control of Heavy Loads, Draft Technical Evaluation Rept | Safe Shutdown Coatings Control of Heavy Loads |
ML20040E956 | 21 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 | |
ML20040E964 | 21 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 | |
ML19345H293 | 30 April 1981 | Reactor Safety Study Methodology Applications Program: Sequoyah #1 PWR Power Plant | |
ML19347E183 | 30 April 1981 | Analysis of Hydrogen Mitigation for Degraded Core Accidents in the Sequoyah Nuclear Power Plant | Squib |
ML19350B588 | 1 December 1980 | Rough Draft, Analysis of Hydrogen Mitigation for Degraded Core Accidents in Sequoyah Nuclear Power Plant, Prepared for Ofc of Nuclear Regulatory Research | Squib |
ML19330C423 | 30 July 1980 | Suppl to 800718 Rept, Preliminary Calculations,Ultimate Strength for Hydrogen Explosion,Sequoyah Containment Vessel. |