Semantic search
Jump to navigation
Jump to search
Issue date | Title | Topic | |
---|---|---|---|
L-94-021, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3 | 30 November 1994 | Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3 | |
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. | |
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. | |
ML19332A751 | 21 July 1980 | Primary Coolant Sys Pressure Isolation Valves,Millstone Unit 2, Technical Evaluation Rept | |
ML19332A780 | 31 July 1980 | Safety Evaluation of Inservice Testing Program for Pumps & Valves, Interim Rept 790426-801025 | Boric Acid Stroke time Exemption Request |
ML19332B582 | 30 September 1989 | Conformance to Reg Guide 1.97:Millstone-2, Technical Evaluation Rept | Post Accident Monitoring |
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 |
ML19350E647 | 18 June 1981 | Equipment Environ Qualification,Millstone Unit 2, Technical Evaluation Rept | Safe Shutdown Boric Acid Shutdown Margin Post Accident Monitoring |
ML20009C374 | 30 June 1981 | Tech Specs for Redundant Decay Heat Removal Capability, Millstone Nuclear Power Station,Unit 2, Technical Evaluation Rept | |
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 | |
ML20023A493 | 17 September 1982 | Radiological Effluent Tech Spec Implementation (A-2), Millstone Nuclear Power Station Unit 2, Technical Evaluation Rept | Boric Acid Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program |
ML20023E178 | 31 May 1983 | Copper in the Intake and Discharge Zones of the Surry and Salem Nuclear Power Stations | |
ML20039G405 | 30 December 1981 | Tech Specs for Redundant Decay Heat Removal Capability, Millstone Nuclear Power Station,Unit 2. | |
ML20041A360 | 16 February 1982 | Tech Specs for Redundant Decay Heat Removal Capability, Millstone Nuclear Power Station,Unit 2, Revised Page | |
ML20041C277 | 31 January 1982 | Snupps Auxiliary Feedwater System Reliability Study Evaluation | |
ML20054F510 | 31 May 1982 | Response of the Zion & Indian Point Containment Buildings to Severe Accident Pressures | |
ML20054K059 | 13 May 1982 | Technical Evaluation Rept on Proposed Design Mods & Tech Spec Changes on Grid Voltage Degradation for Millstone Nuclear Power Station,Unit 1 | |
ML20058D779 | 4 March 1982 | Draft Safety Evaluation, SEP Topic VI-10.A,Testing of RCS & Esf | |
ML20058K973 | 18 July 1990 | Technical Evaluation Rept - Millstone Nuclear Power Station Unit 1,Station Blackout Evaluation, Final Rept | |
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 |
ML20063P933 | 18 July 1990 | Technical Evaluation Rept Millstone Nuclear Power Station Unit 3 Station Blackout Evaluation, Final Rept | Safe Shutdown |
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 |
ML20067E716 | 31 March 1989 | First Interval ISI Program Millstone Nuclear Power Station Unit 3, Technical Evaluation Rept | |
ML20070Q433 | 31 January 1989 | Nuclear Power Plant Sys Sourcebook,Millstone 3 | |
ML20070Q456 | 31 January 1989 | Nuclear Power Plant Sys Sourcebook,Millstone 2 | Safe Shutdown Boric Acid Ultimate heat sink Emergency Lighting Design basis earthquake |
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 | |
ML20071A637 | 31 January 1991 | Trip Rept: Onsite Analysis of Human Factors of Event at Millstone 3 on 901231 (Turbine Bldg Pipe Break) | Through Wall Leak |
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 |
ML20076C403 | 27 January 1983 | ECCS Repts (F-47) TMI Action Plan Requirements,Millstone Nuclear Power Station,Unit 2, Technical Evaluation Rept | |
ML20076C452 | 21 February 1983 | Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Nonproprietary Technical Evaluation Rept | |
ML20076F263 | 2 March 1983 | Selected Operating Reactor Issues Program Ii:Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept | Safe Shutdown Earthquake |
ML20076M335 | 18 July 1983 | Operating Reactor PORV Repts (F-37),TMI Action Plan Requirements,C-E Owners Group (CEN-145), 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 | |
ML20080J661 | 18 August 1983 | Proposed Tech Spec Changes for Inservice Surveillance of Safety-Related Hydraulic & Mechanical Snubbers at Millstone Nuclear Power Station,Unit 2, Technical Evaluation Rept |