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Issue date | Title | Topic | |
---|---|---|---|
ML17334B033 | 30 November 1986 | Input for Ser,Beaver Valley Power Station Units 1 & 2, Braidwood Station Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Catawba Nuclear Station Units 1..., Reactor Trip Sys Reliability Item 4.5.2 Generic Ltr 83-28. | |
ML17334B072 | 31 March 1987 | Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Cook Units 1 & 2 & Haddam Neck. | |
ML17341B649 | 17 February 1982 | Draft Technical Evaluation of SEP Topic VII-1.A,Isolation of Reactor Protection Sys from Nonsafety Sys. | |
ML17347A593 | 31 July 1987 | Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept | |
ML18040B189 | 31 August 1987 | Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. | |
ML18052B193 | 30 June 1987 | Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Calvert Cliffs-1 & -2, Millstone-2 & Palisades, Final Informal Rept | |
ML18141A305 | 31 December 1983 | Definition of Operable,Kewaunee Nuclear Power Plant. | |
ML18150A119 | 30 April 1987 | Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept | |
ML18150A188 | 30 April 1987 | Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept | |
ML18152A583 | 30 April 1987 | Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. | |
ML19225C453 | 27 April 1979 | Fire Protection in Operating Nuclear Power Stations:Point Beach Units 1 & 2 SER Review, Interim Rept | Fire Protection Program |
ML19323H481 | 30 September 1979 | Technical Evaluation of Electrical Instrumentation & Control Design Aspects of Override Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Point Beach Nuclear Power Station,Units 1 & 2. | |
ML19332B614 | 31 October 1989 | Conformance to Generic Ltr 83-28,Item 2.2.1--Equipment Classification for All Other Safety-Related Components:Quad Cities 1 & 2, Final Technical Evaluation Rept | Safe Shutdown |
ML19341B086 | 31 December 1980 | Instrument Bus Mods,Point Beach Nuclear Plant,Units 1 & 2. | |
ML20009B596 | 31 May 1981 | Technical Evaluation of Licensee Responses to IE Bulletin 80-06,re Engineered Safety Feature Reset Controls for Point Beach Nuclear Power Station,Units 1 & 2 | |
ML20023A486 | 2 September 1982 | Ei Hatch Nuclear Plant Units 1 & 2 Inservice Insp Program, Technical Evaluation Rept | Hydrostatic Nondestructive Examination VT-2 Incorporated by reference |
ML20023A489 | 10 September 1982 | Inservice Insp Program, Technical Evaluation Rept | |
ML20023E178 | 31 May 1983 | Copper in the Intake and Discharge Zones of the Surry and Salem Nuclear Power Stations | |
ML20027D213 | 31 July 1982 | Tech Spec for Redundant DHR Capability,Point Beach,Units 1 & 2. | |
ML20028A734 | 17 August 1982 | Improvements in Training & Requalification Programs as Required by TMI Action Items 1.A.2.1 & II.B.4 for Point Beach Nuclear Plant,Units 1 & 2, Technical Evaluation Rept | Fuel cladding Power change |
ML20041C277 | 31 January 1982 | Snupps Auxiliary Feedwater System Reliability Study Evaluation | |
ML20042D053 | 7 June 1988 | Technical Evaluation Rept of Dcrdr for Point Beach Nuclear Power Plant,Units 1 & 2. | |
ML20052C937 | 28 February 1982 | Tech Specs for Redundant Decay Heat Removal Capability, Point Beach,Units 1 & 2, Preliminary Technical Evaluation Rept | |
ML20054F510 | 31 May 1982 | Response of the Zion & Indian Point Containment Buildings to Severe Accident Pressures | |
ML20054F725 | 21 May 1982 | Quality Group Classification of Components & Sys, Draft Safety Evaluation | |
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 |
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 | |
ML20072K820 | 17 June 1983 | Control of Heavy Loads (C-10),Point Beach Nuclear Plants Units 1 & 2, Draft Final Technical Evaluation Rept | Safe Shutdown Coatings Nondestructive Examination Control of Heavy Loads |
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 | |
ML20076B589 | 30 July 1982 | Inservice Insp Program, Technical Evaluation Rept | Hydrostatic Incorporated by reference Liquid penetrant Dissimilar Metal Weld |
ML20076C378 | 10 December 1982 | ECCS Repts (F 47),TMI Action Plan Requirements,Point Beach Nuclear Plant Units 1 & 2, Technical Evaluation Rept | Boric Acid |
ML20077K670 | 9 February 1983 | Adequacy of Electric Distribution Sys Voltages for Point Beach Nuclear Plant,Units 1 & 2, Technical Evaluation Rept | |
ML20078E047 | 4 October 1994 | TER on Front End IPE Submittal, Task 22,dtd 941004 | Boric Acid Mission time Internal Flooding Probabilistic Risk Assessment |
ML20078E122 | 30 September 1994 | IPE Back-End TER Dtd Sept 1994 | Mission time Internal Flooding Severe Accident Management Guideline |
ML20078E150 | 31 August 1994 | TER of IPE Submittal Human Reliability Analysis, Final Rept, Task 23.Draft Dtd 940131,final Aug 1994 | Internal Flooding Probabilistic Risk Assessment |
ML20079G674 | 28 September 1982 | Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts (F-11 & B-60),Point Beach Nuclear Plant,Unit 1, Technical Evaluation Rept | |
ML20079G683 | 28 September 1982 | Nonproprietary Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60),Point Beach Nuclear Plant Unit 2, Final Technical Evaluation Rept | |
ML20079Q680 | 23 February 1983 | Selected Operating Reactor Issues Program II RCS Sys Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept | |
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 | |
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 |