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 Issue dateTitleTopic
ML20217K46230 January 1998Technical Evaluation Rept on Second 10-Yr Interval ISI Program Plan:Tva,Sequoyah Nuclear Plant,Units 1 & 2Hydrostatic
Nondestructive Examination
VT-2
Incorporated by reference
Pressure boundary leak
Through Wall Leak
Scaffolding
ML20092H12831 August 1995Evaluation of Sequoyah Nuclear Plant Offsite Dose Calculation Manual,Rev 28Offsite Dose Calculation Manual
ML20072T91531 August 1994Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Sequoyah-1/-2, Technical Evaluation Rept
ML20087A52631 December 1991Analysis of Bellows Expansion Joints in the Sequoyah ContainmentHydrostatic
Finite Element Analysis
Earthquake
Flow Induced Vibration
ML20085M38624 October 1991Final Technical Evaluation Rept,Sequoyah Nuclear Plant, Units 1 & 2 Station Blackout EvaluationSafe Shutdown
ML20066D26531 December 1990Simplified Containment Event Tree Analysis for the Sequoyah Ice Condenser Containment
ML20066D27331 December 1990Evaluation of Severe Accident Risks: Sequoyah,Unit 1.Main ReportProbabilistic Risk Assessment
Earthquake
Fatality
Failure to Scram
ML20066D28231 December 1990Evaluation of Severe Accident Risks: Sequoyah,Unit 1. AppendicesTime to boil
Probabilistic Risk Assessment
Fatality
ML20059H45931 July 1990Risk-Based Insp Guide for Sequoyah Nuclear Power Station Final Rept, Informal ReptShutdown Margin
Probabilistic Risk Assessment
ML20043A36830 April 1990Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events
ML20043A28130 April 1990Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events Appendices
ML19332C99230 November 1989Draft Risk-Based Insp Guide for Sequoyah Sequoyah Nuclear Power Station.Shutdown Margin
Probabilistic Risk Assessment
ML20245J92631 March 1989TMI Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing Sequoyah Nuclear Plant Units 1 & 2, Technical Evaluation ReptLoop seal
Anticipated operational occurrence
ML20154H32723 August 1988Technical Evaluation Rept Re Requests for Relief,Pump & Valve Inservice Testing Program,Sequoyah Nuclear Plant, Units 1 & 2
ML20196C1644 February 1988Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131
ML20147C32330 December 1987Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation Rept
ML20236F34718 September 1987Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation ReptStroke time
Power-Operated Valves
Power Operated Valves
ML20237H06910 August 1987Rev 1 to Technical Evaluation Rept of Dcrdr for Sequoyah Nuclear Power Plant Units 1 & 2Safe Shutdown
Emergency Lighting
ML20235T19517 July 1987Evaluation of Nuclear Safety Review Staff Concerns Requiring Resolution Before & After Restart, Technical Evaluation Rept
ML20234D60125 June 1987Errata 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
ML20213H01711 May 1987Conformance to Reg Guide 1.97 Sequoyah Nuclear Plant,Units 1 & 2Boric Acid
ML20215G27823 March 1987TVA Sequoyah Electrical Medium Voltage Short Circuit Analysis Calculations, Final Technical Evaluation ReptSafe Shutdown
ML20214B24128 February 1987Containment Event Analysis for Postulated Severe Accidents: Sequoyah Power Station,Unit 1.Draft Report for CommentProbabilistic Risk Assessment
Earthquake
Failure to Scram
ML20214B29828 February 1987Analysis of Core Damage Frequency from Internal Events: Sequoyah,Unit 1Safe Shutdown
Boric Acid
Ultimate heat sink
Mission time
Internal Flooding
Probabilistic Risk Assessment
Failure to Scram
ML20214V48628 February 1987Evaluation of Severe Accident Risks and the Potential for Risk Reduction:Sequoyah Power Station,Unit 1.Draft for CommentLoop seal
Probabilistic Risk Assessment
Earthquake
Backfit
Fatality
ML20206H1442 September 1986Direct Containment Heating Analysis W/Contain Computer Code, Ltr Rept
ML20215N42831 August 1986Technical Evaluation Rept Re Welding Concern Program at TVA Sequoyah Units 1 & 2Backfit
ML20206H0819 May 1986Some Sensitivities for Direct Containment Heating Loads
ML20197J46430 April 1986Conformance 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
ML20137D31315 August 1985Review 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
ML20239A68131 July 1985Crack Propagation in High Strain Regions of Sequoyah ContainmentFinite Element Analysis
ML20244D38710 July 1985Review 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.
ML20244D43830 June 1985Conformance 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
ML20106C99631 July 1984Draft Vol IV, Radionuclide Release Under Specific LWR Accident Conditions,Pwr,Ice Condenser Containment Design
ML20127A2895 October 1982Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982
ML20065D28324 September 1982PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),TVA,Sequoyah Nuclear Power Plant Unit 1, Technical Evaluation ReptBoric Acid
Shutdown Margin
ML20064N73731 August 1982Reliability Analysis of Containment Strength.Sequoyah and McGuire Ice Condenser ContainmentsFinite Element Analysis
Earthquake
ML20126F25426 August 1982Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982
ML20114F83016 July 1982to Preliminary Assessment of Core Melt Probability in Cold Shutdown Following Postulated LOCA at Sequoyah Nuclear Plant, Final ReptBoric Acid
Shutdown Margin
Ultimate heat sink
Fire Barrier
Time to boil
Safe Shutdown Earthquake
ML20055A43114 June 1982Control of Heavy Loads, Draft Technical Evaluation ReptSafe Shutdown
Coatings
Control of Heavy Loads
ML20040E95621 December 1981Equipment 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
ML20040E96421 December 1981Equipment 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
ML19345H29330 April 1981Reactor Safety Study Methodology Applications Program: Sequoyah #1 PWR Power Plant
ML19347E18330 April 1981Analysis of Hydrogen Mitigation for Degraded Core Accidents in the Sequoyah Nuclear Power PlantSquib
ML19350B5881 December 1980Rough Draft, Analysis of Hydrogen Mitigation for Degraded Core Accidents in Sequoyah Nuclear Power Plant, Prepared for Ofc of Nuclear Regulatory ResearchSquib
ML19330C42330 July 1980Suppl to 800718 Rept, Preliminary Calculations,Ultimate Strength for Hydrogen Explosion,Sequoyah Containment Vessel.