Semantic search
Jump to navigation
Jump to search
Issue date | Title | Topic | |
---|---|---|---|
ML20100C909 | 31 August 1995 | App a, Technical Evaluation Rept on IPE Front End Analysis | Ultimate heat sink Mission time Internal Flooding Probabilistic Risk Assessment Hardened vent Manual Operator Action |
ML20100D240 | 31 August 1995 | App B, Plant Technical Evaluation Rept on IPE Back-End Analysis | Mission time Probabilistic Risk Assessment Hardened vent |
ML20100D247 | 22 August 1995 | App C, Plant Technical Evaluation Rept on IPE Submittal Human Reliability Analysis,Final Rept | Internal Flooding Water hammer |
ML18040A226 | 31 May 1994 | Technical Evaluation Rept,Technical Basis for Reduction of Torus Shell Condensation Oscillation Loads for Niagra Mohawk Power Corp Nine Mile Point Unit 1. | Hydrostatic |
ML20085L541 | 30 September 1991 | Conformance to Reg Guide 1.97:Nine Mile Point-1 | Reactor Vessel Water Level Fuel cladding Manual Operator Action |
ML20081K363 | 15 May 1991 | Final Technical Evaluation Rept Nine Mile Point Nuclear Power Station Unit 1 Station Blackout Evaluation | Safe Shutdown |
ML20058L041 | 31 August 1990 | Technical Evaluation Rept,Pump & Valve Inservice Testing Program | Stroke time Excess Flow Check Valve Cold shutdown justification Power-Operated Valves |
ML20058K159 | 31 March 1990 | Final Revised Technical Evaluation Rept on Response from Niagra Mohawk Power Corp to Generic Ltr 88-01 Re Nine Mile Point,Unit 2 | Weld Overlay Unidentified leakage |
ML20042D174 | 31 October 1989 | Final Technical Evaluation Rept on Response from Niagara Mohawk Power Corp to Generic Ltr 88-01 Pertaining to Nine Mile Point,Unit 1. | Weld Overlay Intergranular Stress Corrosion Cracking |
ML20246B815 | 30 April 1989 | Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Duane Arnold,Enrico Fermi-2,Hope Creek,Lasalle County 1 & 2, Limerick 1 & 2,Millstone 1,Monticello,Nine Mile Point 1 & 2 & Oyster Creek, Technical Evaluation Rept | |
ML20246L177 | 28 February 1989 | Conformance to Generic Ltr 83-28,Item 2.2.1-Equipment Classification for All Other Safety-Related Components:Nine Mile Point 1 & 2 | Safe Shutdown Systematic Assessment of Licensee Performance |
ML20216C230 | 30 April 1987 | Final Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Nine Mile Point,Units 1 & 2, Informal Rept | |
ML20214R342 | 31 March 1987 | Technical Evaluation Rept on Second 10-Yr Internal Inservice Insp Program Plan:Niagara Mohawk Power Corp, Nine Mile Point Nuclear Station Unit 1,Docket Number 50-220 | Incorporated by reference Scram Discharge Volume Stress corrosion cracking Liquid penetrant |
ML20214H129 | 1 August 1986 | Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Nine Mile Point Unit 1 Nuclear Generating Station, Supplementary Technical Evaluation Rept | |
ML20244E190 | 31 July 1986 | Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components), Fort Calhoun,Millstone Unit 2,Nine Mile Point Unit 2 & Fort St Vrain | Safe Shutdown |
ML20205E371 | 31 July 1986 | Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components) Fort Calhoun,Millstone Unit 2,Nine Mile Point 2 & Fort St Vrain, Technical Evaluation Rept | Safe Shutdown |
ML20214E343 | 31 January 1986 | Rev 1 to Conformance to Reg Guide 1.97,Nine Mile Point Nuclear Station,Unit 1 | Reactor Vessel Water Level Grab sample Fuel cladding |
ML20066H284 | 17 January 1986 | Technical Review Rept,Nrc Region I Insp 50-410/86-02,Review of Nine Mile Point,Unit 2 Tech Specs, of Onsite Activities Conducted on 860106-17 | Temporary Modification |
ML20151L331 | 4 November 1985 | Masonry Wall Design, Technical Evaluation Rept | Tornado Missile Safe Shutdown Earthquake Operating Basis Earthquake High Energy Line Break Earthquake |
ML20198F343 | 4 October 1985 | Technical Evaluation of Dcrdr for Nine Mile Point Nuclear Station,Unit 1 | Failure to Scram |
ML20244D387 | 10 July 1985 | Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. | |
ML20244D438 | 30 June 1985 | Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities | |
ML20127D731 | 28 February 1985 | Conformance to Reg Guide 1.97,Nine Mile Point Nuclear Station,Unit 1 | Grab sample High Energy Line Break |
ML20101T372 | 31 January 1985 | Control of Heavy Loads,Nine Mile Point Unit 1, Technical Evaluation Rept | Safe Shutdown Control of Heavy Loads |
ML20106A574 | 30 September 1984 | Technical Evaluation of Nine Mile Point Unit 1 Plant-Unique Analysis Rept | |
ML20106A552 | 26 September 1984 | Audit for Mark 1 Containment Long-Term Program - Structural Analysis for Operating Reactors, Technical Evaluation Rept | Finite Element Analysis Earthquake |
ML20090H767 | 31 July 1983 | Technical Evaluation of Integrity of Nine Mile Point Unit 1 Rcbp Sys, Technical Evaluation Rept | Packing leak Weld Overlay Intergranular Stress Corrosion Cracking Stress corrosion cracking Earthquake Pressure boundary leak Dissimilar Metal Weld Unidentified leakage |
ML20080A043 | 15 June 1983 | Adequacy of Station Electric Distribution Sys Voltages for Nine Mile Point Nuclear Station,Unit 1, Technical Evaluation Rept | Safe Shutdown Offsite Circuit |
ML20076F248 | 6 April 1983 | Selected Operating Reactor Issues Program II RCS Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept for Nine Mile Point 1 | Pressure Boundary Leakage |
ML20126E994 | 7 December 1982 | Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 | |
ML20077J989 | 17 September 1982 | Inservice Insp Program, Technical Evaluation Rept | Hydrostatic VT-2 Incorporated by reference Liquid penetrant |
ML20027A899 | 26 August 1982 | Nonproprietary Vols 1 & 2 of, Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SER (F-11 & B-60), Technical Evaluation 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 |
ML20052B831 | 28 February 1982 | Safety Evaluation Rept,Pumps & Valves Inservice Testing Program,Nine Mile Point Nuclear Station,Unit 1. | Stroke time Hydrostatic Power-Operated Valves |
ML20084P951 | 6 May 1970 | Preliminary Rept on Meeting Concerning Nine Mile Point Core Spray Nozzles & Related Piping Sys | |
ML20084Q633 | 5 March 1970 | Exam & Evaluation of Safe-End from Nozzle N6B on Nine Mile Point Reactor | Stress corrosion cracking |