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	Issue date	Title	Topic
ML18039A787	31 January 1999	Technical Evaluation Rept on Second 10-Year Interval Inservice Insp Program Plan, for Browns Ferry Nuclear Plant,Unit 3	Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Dissimilar Metal Weld
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
ML20072E054	30 June 1994	Plant IPE,Front-End Review	Mission time Internal Flooding Probabilistic Risk Assessment
ML20072E122	31 March 1994	Plant Ipe,Submittal Human Reliability Analysis Final Rept	Safe Shutdown Internal Flooding Probabilistic Risk Assessment
ML20059C203	30 September 1993	High Pressure Coolant Injection (HPCI) System RISK-BASED Inspection Guide for Browns Ferry Nuclear Power Station
ML18037A417	31 July 1993	Trip Rept: On-Site Analysis of Human Factors of Event at Browns Ferry 2 on May 11, 1993, Ari/Rpt ESF Actuation Due to Shutdown Overpressurization.	Hydrostatic
ML20058L964	31 July 1993	Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Browns Ferry Nuclear Plant,Units 1,2 & 3	Stroke time Squib Incorporated by reference Cold shutdown justification Power-Operated Valves Power Operated Valves
ML18037A521	31 May 1993	Technical Evaluation Rept on Second 10-Yr Interval Insp Program Plan.	Incorporated by reference Liquid penetrant
ML20072E104	20 January 1993	Plant IPE,Back-End Submittal
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
ML20072R675	31 March 1991	Nuclear Power Plant Sys Source Book - Bellefonte 1 & 2	Safe Shutdown Boric Acid Ultimate heat sink Safe Shutdown Earthquake Reserve Station Service Transformer
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
ML20082S010	13 August 1990	Review of Inservice Testing Program for TVA Nuclear Power Plants	Stroke time Cold shutdown justification Power Operated Valves
ML20059H459	31 July 1990	Risk-Based Insp Guide for Sequoyah Nuclear Power Station Final Rept, Informal Rept	Shutdown Margin Probabilistic Risk Assessment
ML20059A131	19 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
ML20059A122	19 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
ML20043A281	30 April 1990	Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events Appendices
ML20043A368	30 April 1990	Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events
ML18033B395	31 December 1989	Welding-Related Employee Concerns Evaluations, Technical Rept	Non-Destructive Examination Weld Overlay
ML19332C992	30 November 1989	Draft Risk-Based Insp Guide for Sequoyah Sequoyah Nuclear Power Station.	Shutdown Margin Probabilistic Risk Assessment
ML20248E212	16 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
ML20248E219	16 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
ML20247R385	16 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
ML20247R394	16 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..
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
ML20234C112	31 May 1987	Severe Accident Sequence Analysis Program - Anticipated Transient Without Scram Simulations for Browns Ferry Nuclear Plant Unit 1	Safe Shutdown Hydrostatic Probabilistic Risk Assessment Scram Discharge Volume Fuel cladding Coast down Failure to Scram
ML20214R156	29 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
ML20214R148	29 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
ML20213H017	11 May 1987	Conformance to Reg Guide 1.97 Sequoyah Nuclear Plant,Units 1 & 2	Boric Acid
ML20206G638	8 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
ML20206G586	8 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
ML20206D070	31 March 1987	Feedwater Transient and Small Break Loss of Coolant Accident Analyses for the Bellefonte Nuclear Plant	Loop seal Fuel cladding Coast down
ML20213A034	31 March 1987	Demonstration Testing of a Surveillance Robot at Browns Ferry Nuclear Plant.Analysis of Costs and Benefits	High Radiation Area
ML20215G278	23 March 1987	TVA Sequoyah Electrical Medium Voltage Short Circuit Analysis Calculations, Final Technical Evaluation Rept	Safe Shutdown
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
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
ML20214A788	28 February 1987	RAMONA-3B Calculations for Browns Ferry ATWS Study	Hydrostatic Probabilistic Risk Assessment

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