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Issue date | Title | Topic | |
---|---|---|---|
ML20087A526 | 31 December 1991 | Analysis of Bellows Expansion Joints in the Sequoyah Containment | Hydrostatic Finite Element Analysis Earthquake Flow Induced Vibration |
ML20066D282 | 31 December 1990 | Evaluation of Severe Accident Risks: Sequoyah,Unit 1. Appendices | Time to boil Probabilistic Risk Assessment Fatality |
ML20066D273 | 31 December 1990 | Evaluation of Severe Accident Risks: Sequoyah,Unit 1.Main Report | Probabilistic Risk Assessment Earthquake Fatality Failure to Scram |
ML20066D265 | 31 December 1990 | Simplified Containment Event Tree Analysis for the Sequoyah Ice Condenser Containment | |
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 | |
ML20235T954 | 31 January 1989 | Safety Evaluation Report on Tennessee Valley Authority: Sequoyah Nuclear Performance Plan.Sequoyah Unit 1 Restart | Safe Shutdown Non-Destructive Examination Coatings Condition Adverse to Quality Systematic Assessment of Licensee Performance Integrated leak rate test Battery sizing Earthquake Commercial Grade Power-Operated Valves Fire Protection Program Hourly Fire Watch Siren |
ML20154J429 | 31 May 1988 | Safety Evaluation Report on Tennessee Valley Authority. Sequoyah Nuclear Performance Plan | Safe Shutdown Reactor Vessel Water Level Packing leak Non-Destructive Examination Fire Barrier Anticipated operational occurrence Safe Shutdown Earthquake Internal Flooding Probabilistic Risk Assessment Coatings Reserve Station Service Transformer Nondestructive Examination Emergency Lighting Finite Element Analysis Condition Adverse to Quality High Energy Line Break Thermoset Stress corrosion cracking Systematic Assessment of Licensee Performance Earthquake Commercial Grade Power-Operated Valves Liquid penetrant Fire Watch Backfit Siren Overspeed trip |
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 | |
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 High Energy Line Break Failure to Scram |
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 |
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 |
ML20239A681 | 31 July 1985 | Crack Propagation in High Strain Regions of Sequoyah Containment | Finite Element Analysis |
ML20064N737 | 31 August 1982 | Reliability Analysis of Containment Strength.Sequoyah and McGuire Ice Condenser Containments | Finite Element Analysis Earthquake |
ML19347E183 | 30 April 1981 | Analysis of Hydrogen Mitigation for Degraded Core Accidents in the Sequoyah Nuclear Power Plant | Squib |
ML19345H293 | 30 April 1981 | Reactor Safety Study Methodology Applications Program: Sequoyah #1 PWR Power Plant |