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Issue date | Title | Topic | |
---|---|---|---|
ML20027A616 | 31 August 1980 | Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Features for St Lucie Nuclear Generating Plant. | |
ML20041C277 | 31 January 1982 | Snupps Auxiliary Feedwater System Reliability Study Evaluation | |
ML20052B534 | 28 February 1982 | Tech Specs for Redundant Decay Heat Removal Capability, St Lucie,Unit 1, Technical Evaluation Rept | |
ML20054F510 | 31 May 1982 | Response of the Zion & Indian Point Containment Buildings to Severe Accident Pressures | |
ML20058K870 | 9 July 1990 | Rev 2 to Technical Evaluation Rept,Maine Yankee Atomic Power Station,Station Blackout Evaluation | |
ML20062A937 | 30 April 1982 | Control of Heavy Loads at Nuclear Power Plants,Waterford Generating Station,Unit 3, Draft Technical Evaluation Rept | Safe Shutdown Control of Heavy Loads |
ML20062E204 | 31 July 1982 | Socioeconomic Impacts of Nuclear Generating Stations:Saint Lucie Case Study.Docket Nos. 50-335 and 50-389.(Florida Power and Light Company) | Ultimate heat sink |
ML20062G654 | 31 July 1982 | Socioeconomic Impacts of Nuclear Generating Stations:Nine Mile Plant and Fitzpatrick Case Study.Docket Nos. 50-220, 50-410 & 50-333.(Niagara Mohawk Power Corporation and Power Authority of the State of New York) | Earthquake |
ML20064K078 | 30 June 1980 | Impure Water in Steam Generators & Isolation Generators, Informal Rept for Limited Distribution | |
ML20064N737 | 31 August 1982 | Reliability Analysis of Containment Strength.Sequoyah and McGuire Ice Condenser Containments | Finite Element Analysis Earthquake |
ML20065C358 | 31 July 1982 | Control of Heavy Loads at Nuclear Power Plants,Byron Units 1 & 2 & Braidwood Units 1 & 2, Draft Technical Evaluation Rept | Safe Shutdown Overtravel Control of Heavy Loads |
ML20065D290 | 30 September 1982 | Evaluation of the Prompt Alerting Systems at Four Nuclear Power Stations | Siren |
ML20065U235 | 31 October 1982 | Technical Evaluation Rept of Overpressure Mitigation Sys for St Lucie,Unit 1 | |
ML20066B323 | 31 August 1982 | Audit of Environ Qualification of Safety-Related Electrical Equipment at St Lucie Unit 2 Nuclear Generating Station, Interim Rept | Anchor Darling |
ML20069B808 | 31 January 1982 | Tech Specs for Redundant Decay Heat Removal Capability, St Lucie,Unit 1, Technical Evaluation Rept | |
ML20070Q680 | 8 October 1982 | Evaluation of Procedures Proposed by Detroit Edison Co in Emergency Plans to Consider Meteorological Conditions in Enrico Fermi Site Coastal Environ | |
ML20070Q688 | 8 October 1982 | Evaluation of Procedures Proposed by PG&E in Emergency Plans to Consider Meteorological Conditions in Diablo Canyon Plant Coastal Environ | |
ML20070Q767 | 31 December 1988 | Nuclear Power Plant Sys Sourcebook,Waterford 3 | Safe Shutdown Boric Acid Ultimate heat sink Emergency Lighting B.5.b Mitigating Strategies |
ML20072L681 | 30 June 1982 | Assessment of Postulated Degraded Core Accidents in Grand Gulf Reactor Plant, Draft Informal Rept | |
ML20072L689 | 31 August 1982 | Analysis of Full Core Meltdown Accidents in Grand Gulf Reactor Plant, Draft Informal Rept | |
ML20076A768 | 31 May 1983 | Draft Control of Heavy Loads at Nuclear Power Plants, Waterford Generating Station,Unit 3,Louisiana Power & Lighting Co (Phase 1), Technical Evaluation Rept | Safe Shutdown Boric Acid Coatings Control of Heavy Loads |
ML20076B589 | 30 July 1982 | Inservice Insp Program, Technical Evaluation Rept | Hydrostatic Incorporated by reference Liquid penetrant Dissimilar Metal Weld |
ML20080E071 | 13 January 1984 | Evaluations of Detailed Control Room Design Reviews for St Lucie Units 1 & 2 & Turkey Point Units 3 & 4, Technical Evaluation Rept | Backfit |
ML20080J309 | 17 April 1981 | Metallurgical,Stress & Fracture Mechanics Analyses of Cracked Steam Generator Manway Studs from Oconee Unit 3 of Duke Power Co | |
ML20080J321 | 17 April 1981 | Attachment 1 to Stress Analysis of Failed Steam Generator Manway Studs from Oconee Unit 3,Duke Power Co | |
ML20082N092 | 18 June 1991 | Draft Assessment of Intersystem LOCA Risks - Methodology & Application:C-E Plant | |
ML20082S937 | 30 September 1991 | Trip Rept:Onsite Analysis of Human Factors of Event at Waterford 3 on 910624 (Manual Reactor Trip W/Excess Steam Demand) | Boric Acid Stroke time |
ML20083D085 | 30 November 1983 | Review of the Byron/Braidwood Units 1 and 2 Auxiliary Feedwater System Reliability Analysis | |
ML20083Q711 | 4 March 1983 | Preliminary Investigation of Interconnected Sys Interactions for Safety Injection Sys of Indian Point 3 | Boric Acid Fuel cladding |
ML20084B612 | 22 June 1972 | Rept of Preliminary Investigation Failure of Hanger Bolts on Suppression Chamber Suction Header at Quad Cities Nuclear Station,Unit 2 | |
ML20084L930 | 8 May 1984 | Const Insps at Midland & Zimmer Nuclear Power Plants, Monthly Progress Rept for Apr 1984 | |
ML20085F252 | 19 May 1983 | Evaluation of McGuire Units 1 & 2 Undervoltage Trip Attachment Failures, Interim Technical Evaluation Rept | |
ML20085K488 | 19 September 1983 | QA Case Study Working Paper Case C, Revised Draft Working Paper | Earthquake |
ML20086S620 | 30 April 1981 | Systems Interaction Evaluation Procedure for Application to Indian POINT-3 | Boric Acid Ultimate heat sink Scram Discharge Volume Earthquake |
ML20086S648 | 15 June 1981 | Review of PASNY Sys Interaction Study | Safe Shutdown Ultimate heat sink |
ML20086S661 | 1 March 1982 | Review of PASNY Sys Interaction Study | |
ML20087Q085 | 13 July 1983 | Evaluation of McGuire Units 1 & 2 Undervoltage Trip Attachment Failures, Technical Evaluation Rept | |
ML20093C533 | 30 March 1984 | Audit of Susquehanna Unit 2 Tech Specs, Technical Evaluation Rept | Reactor Vessel Water Level Half scram Stroke time Hydrostatic Anchor Darling Backfit |
ML20097F020 | 31 August 1984 | Technical Assistance in Conduct of Insp Program at Various Region III Nuclear Power Plants, Monthly Progress Rept for Aug 1984 | |
ML20105C435 | 18 November 1983 | Evaluation of Diesel Generator Failure at Shoreham Unit 1, Interim Rept on Phase 1,Failure Cause Evaluation, Interim Technical Evaluation Rept | |
ML20105D087 | 31 August 1992 | Auxiliary Feedwater System RISK-BASED Inspection Guide for the St. Lucie Unit 1 Nuclear Power Generation Station | Probabilistic Risk Assessment |
ML20107H673 | 16 April 1984 | Review of Waterford III Basemat Analysis | Finite Element Analysis Earthquake |
ML20107H732 | 21 June 1984 | Review of Waterford III Basemat Analysis | Finite Element Analysis Earthquake |
ML20107H755 | 18 July 1984 | Review of Waterford III Basemat Analysis | Finite Element Analysis Earthquake |
ML20107K934 | 10 July 1984 | Draft Control of Heavy Loads - Phase Ii,Indian Point Nuclear Power Plant Unit 2, Technical Evaluation Rept | Safe Shutdown Control of Heavy Loads Fuel cladding |
ML20112G245 | 31 October 1984 | Northwest Us Subduction Zone Seismic Risk Assessment, Rept for Oct 1983 - Oct 1984 | Earthquake |
ML20112G277 | 7 February 1975 | Topical Rept on Exams of Portions of Reactor Bldg Spray Sys Piping from Arkansas Nuclear Plant 1 | |
ML20112J145 | 31 July 1983 | Audit of Environ Qualification of Safety-Related Electrical Equipment at Byron Units 1 & 2 & Braidwood Units 1 & 2 | Boric Acid Anchor Darling |
ML20112J410 | 31 March 1983 | Audit of Environ Qualification of Safety-Related Electrical Equipment at Waterford Steam Electric Station,Unit 3 | |
ML20112J431 | 31 March 1983 | Audit of Environ Qualification of Safety-Related Electrical Equipment at Midland Nuclear Plant (Units 1 & 2) |