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 Issue dateTitleTopic
ML20100C90931 August 1995App a, Technical Evaluation Rept on IPE Front End AnalysisUltimate heat sink
Mission time
Internal Flooding
Probabilistic Risk Assessment
Hardened vent
ML20100D24031 August 1995App B, Plant Technical Evaluation Rept on IPE Back-End AnalysisMission time
Probabilistic Risk Assessment
Containment Hardened Vent
ML20100D24722 August 1995App C, Plant Technical Evaluation Rept on IPE Submittal Human Reliability Analysis,Final ReptInternal Flooding
ML18040A22631 May 1994Technical Evaluation Rept,Technical Basis for Reduction of Torus Shell Condensation Oscillation Loads for Niagra Mohawk Power Corp Nine Mile Point Unit 1.Hydrostatic
ML20085L54130 September 1991Conformance to Reg Guide 1.97:Nine Mile Point-1Reactor Vessel Water Level
Fuel cladding
ML20081K36315 May 1991Final Technical Evaluation Rept Nine Mile Point Nuclear Power Station Unit 1 Station Blackout EvaluationSafe Shutdown
ML20058L04131 August 1990Technical Evaluation Rept,Pump & Valve Inservice Testing ProgramStroke time
Excess Flow Check Valve
Cold shutdown justification
Power-Operated Valves
ML20058K15931 March 1990Final Revised Technical Evaluation Rept on Response from Niagra Mohawk Power Corp to Generic Ltr 88-01 Re Nine Mile Point,Unit 2Weld Overlay
ML20042D17431 October 1989Final Technical Evaluation Rept on Response from Niagara Mohawk Power Corp to Generic Ltr 88-01 Pertaining to Nine Mile Point,Unit 1.Weld Overlay
ML20246B81530 April 1989Rev 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
ML20246L17728 February 1989Conformance to Generic Ltr 83-28,Item 2.2.1-Equipment Classification for All Other Safety-Related Components:Nine Mile Point 1 & 2Safe Shutdown
Systematic Assessment of Licensee Performance
ML20216C23030 April 1987Final 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
ML20214R34231 March 1987Technical Evaluation Rept on Second 10-Yr Internal Inservice Insp Program Plan:Niagara Mohawk Power Corp, Nine Mile Point Nuclear Station Unit 1,Docket Number 50-220Incorporated by reference
Scram Discharge Volume
Liquid penetrant
ML20214H1291 August 1986Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Nine Mile Point Unit 1 Nuclear Generating Station, Supplementary Technical Evaluation Rept
ML20244E19031 July 1986Conformance 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 VrainSafe Shutdown
ML20205E37131 July 1986Conformance 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 ReptSafe Shutdown
ML20214E34331 January 1986Rev 1 to Conformance to Reg Guide 1.97,Nine Mile Point Nuclear Station,Unit 1Reactor Vessel Water Level
Grab sample
Fuel cladding
ML20066H28417 January 1986Technical Review Rept,Nrc Region I Insp 50-410/86-02,Review of Nine Mile Point,Unit 2 Tech Specs, of Onsite Activities Conducted on 860106-17Temporary Modification
ML20151L3314 November 1985Masonry Wall Design, Technical Evaluation ReptTornado Missile
Safe Shutdown Earthquake
Operating Basis Earthquake
Earthquake
ML20198F3434 October 1985Technical Evaluation of Dcrdr for Nine Mile Point Nuclear Station,Unit 1Failure to Scram
ML20244D38710 July 1985Review 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.
ML20244D43830 June 1985Conformance 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
ML20127D73128 February 1985Conformance to Reg Guide 1.97,Nine Mile Point Nuclear Station,Unit 1Grab sample
ML20101T37231 January 1985Control of Heavy Loads,Nine Mile Point Unit 1, Technical Evaluation ReptSafe Shutdown
Control of Heavy Loads
ML20106A57430 September 1984Technical Evaluation of Nine Mile Point Unit 1 Plant-Unique Analysis Rept
ML20106A55226 September 1984Audit for Mark 1 Containment Long-Term Program - Structural Analysis for Operating Reactors, Technical Evaluation ReptFinite Element Analysis
Earthquake
ML20090H76731 July 1983Technical Evaluation of Integrity of Nine Mile Point Unit 1 Rcbp Sys, Technical Evaluation ReptPacking leak
Weld Overlay
Earthquake
Pressure boundary leak
Dissimilar Metal Weld
ML20080A04315 June 1983Adequacy of Station Electric Distribution Sys Voltages for Nine Mile Point Nuclear Station,Unit 1, Technical Evaluation ReptSafe Shutdown
Offsite Circuit
ML20076F2486 April 1983Selected Operating Reactor Issues Program II RCS Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept for Nine Mile Point 1Pressure Boundary Leakage
ML20126E9947 December 1982Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982
ML20077J98917 September 1982Inservice Insp Program, Technical Evaluation ReptHydrostatic
VT-2
Incorporated by reference
Liquid penetrant
ML20027A89926 August 1982Nonproprietary Vols 1 & 2 of, Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SER (F-11 & B-60), Technical Evaluation Rept
ML20062G65431 July 1982Socioeconomic 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
ML20052B83128 February 1982Safety Evaluation Rept,Pumps & Valves Inservice Testing Program,Nine Mile Point Nuclear Station,Unit 1.Stroke time
Hydrostatic
Power-Operated Valves
ML20084P9516 May 1970Preliminary Rept on Meeting Concerning Nine Mile Point Core Spray Nozzles & Related Piping Sys
ML20084Q6335 March 1970Exam & Evaluation of Safe-End from Nozzle N6B on Nine Mile Point Reactor