Semantic search
Jump to navigation
Jump to search
| Issue date | Title | Topic | |
|---|---|---|---|
| ML20206M286 | 31 March 1998 | Final Rept, Technical Evaluation Rept on 'Submittal-Only' Review of Individual Plant Exam of External Events at Fort Calhoun Station | Hot Short Safe Shutdown High winds Ultimate heat sink Fire Barrier Tornado Missile Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Tornado-Generated Missile Tornado Missile Protection Earthquake Failure to Scram |
| ML20236U724 | 31 March 1998 | Technical Evaluation Rept on Third 10-Year Interval ISI Program Plan:Nneco Millstone Nuclear Power Station,Unit 2, Dtd Mar 1998 | |
| ML20148D604 | 31 March 1997 | Confirmatory Survey for Fsv Nuclear Station,Psc, Platteville,Co,Final Rept | |
| ML20140G590 | 27 March 1997 | Rev 0 to, Review of Millstone Nuclear Power Station Response to USNRC RAI of 960812 on Fire Barrier Ampacity Derating | Fire Barrier |
| ML20148D586 | 26 March 1997 | Confirmatory Survey Plan for Group E Effluent Discharge Pathway Areas at Fsv Nuclear Station | |
| ML20134C872 | 29 January 1997 | Draft Confirmatory Survey for Fsv Nuclear Station Public Svc Co of Co,Platteville,Co | |
| ML20134D797 | 5 September 1996 | Technical Evaluation Rept on IPE Submittal Human Reliability Analysis, Final Rept | Internal Flooding Probabilistic Risk Assessment Severe Accident Management Guideline |
| ML20134D794 | 13 June 1996 | Technical Evaluation Rept on Individual Plant Examination Front End Analysis | Safe Shutdown Mission time Internal Flooding Probabilistic Risk Assessment Severe Accident Management Guideline Fuel cladding |
| ML20134D803 | 31 May 1996 | Technical Evaluation Rept on Individual Plant Examination Back-End Analysis | Mission time Enforcement Discretion Finite Element Analysis Hardened vent Backfit |
| ML20099L374 | 30 November 1995 | Technical Evaluation Rept on Third 10-Yr Interval ISI Program Plan:Omaha Public Power District Fort Calhoun Station,Unit 1 | Hydrostatic VT-2 Incorporated by reference |
| ML20117D074 | 30 November 1995 | Unit 2-TER on IPE Submittal Human Reliability Analysis - Final Rept | Probabilistic Risk Assessment |
| ML20117D080 | 30 November 1995 | TER on IPE - Back-End Analysis | Probabilistic Risk Assessment |
| ML20117D068 | 27 November 1995 | NPP TER on IPE Front End Analysis | Safe Shutdown Mission time Internal Flooding Probabilistic Risk Assessment |
| 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 |
| ML20100D240 | 31 August 1995 | App B, Plant Technical Evaluation Rept on IPE Back-End Analysis | Mission time Probabilistic Risk Assessment Containment Hardened Vent |
| ML20100D247 | 22 August 1995 | App C, Plant Technical Evaluation Rept on IPE Submittal Human Reliability Analysis,Final Rept | Internal Flooding |
| ML20092G368 | 19 June 1995 | Confirmatory Survey for Repower Area Fsv Platteville,Co, Final Rept | |
| ML20084F393 | 16 May 1995 | Draft Rept, Confirmatory Survey for Repower Area Fsv Platteville,Co | |
| 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 | |
| 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 |
| ML20070M853 | 31 March 1994 | Technical Evaluation Rept,Pump & Valve IST Program,Fort Calhoun Station Unit 1 | Boric Acid Incorporated by reference Cold shutdown justification |
| ML20106A936 | 30 September 1992 | Trip Rept:Onsite Analysis of Human Factors of Event at Fort Calhoun on 920703 (Loss of Instrument Inverter & Subsequent Loss of Coolant) | Shutdown Margin |
| ML20127F270 | 28 September 1992 | Technical Evaluation Rept Fort Calhoun Station Emergency Diesel Generating Max Temp Operating Limits, Interim Rept | |
| ML20126M423 | 31 July 1992 | TER on Third 10-Yr Interval ISI Program Plan:Northeast Utils,Millstone Nuclear Power Station,Unit 1 | Boric Acid Packing leak High Radiation Area Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Liquid penetrant Scaffolding |
| ML20100Q286 | 30 September 1991 | Auxiliary Feedwater Sys Risk-Based Insp Guide for Fort Calhoun Nuclear Power Plant | Probabilistic Risk Assessment |
| ML20085L541 | 30 September 1991 | Conformance to Reg Guide 1.97:Nine Mile Point-1 | Reactor Vessel Water Level Fuel cladding |
| ML20081K363 | 15 May 1991 | Final Technical Evaluation Rept Nine Mile Point Nuclear Power Station Unit 1 Station Blackout Evaluation | Safe Shutdown |
| ML20081E977 | 14 February 1991 | Review of Seismic Analysis for Generating In-Structure Spectra for Fort Calhoun Unit 1 Soil-Structure Interaction, Technical Evaluation Rept | |
| 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 |
| ML20058L041 | 31 August 1990 | Technical Evaluation Rept,Pump & Valve Inservice Testing Program | Stroke time Excess Flow Check Valve Cold shutdown justification Power-Operated Valves |
| ML20063P933 | 18 July 1990 | Technical Evaluation Rept Millstone Nuclear Power Station Unit 3 Station Blackout Evaluation, Final Rept | Safe Shutdown |
| ML20058K973 | 18 July 1990 | Technical Evaluation Rept - Millstone Nuclear Power Station Unit 1,Station Blackout Evaluation, Final Rept | |
| 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 |
| 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 |
| 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 |
| ML19332B582 | 30 September 1989 | Conformance to Reg Guide 1.97:Millstone-2, Technical Evaluation Rept | Post Accident Monitoring |
| ML20247J910 | 30 June 1989 | Rev 1 to Technical Evaluation Rept TMI Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing,Fort Calhoun | Loop seal Anticipated operational occurrence Safe Shutdown Earthquake Design basis earthquake |
| 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 | |
| ML20246B973 | 31 March 1989 | Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept | Boric Acid |
| ML20067E716 | 31 March 1989 | First Interval ISI Program Millstone Nuclear Power Station Unit 3, Technical Evaluation Rept | |
| ML20236B805 | 13 March 1989 | Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files | |
| 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 |
| ML20070Q456 | 31 January 1989 | Nuclear Power Plant Sys Sourcebook,Millstone 2 | Safe Shutdown Boric Acid Ultimate heat sink Emergency Lighting Design basis earthquake |
| ML20070Q433 | 31 January 1989 | Nuclear Power Plant Sys Sourcebook,Millstone 3 | |
| ML20245E660 | 6 January 1989 | Independent Review of Fire Protection Program Plan,Public Svc Co of Co,Fort St Vrain Nuclear Generating Station | Safe Shutdown Fire Barrier Emergency Lighting Exemption Request Fire Protection Program |
| ML20070Q521 | 31 December 1988 | Nuclear Power Plant Sys Sourcebook,Fort Calhoun | |
| ML20245D195 | 31 October 1988 | Integrated Technical Evaluation Rept for Review of Fort St Vrain Tech Spec Upgrade Program | Safe Shutdown Shutdown Margin High Radiation Area Grab sample Offsite Dose Calculation Manual Fire Barrier Coatings Process Control Program Continuous fire watch Fire Protection Program Fire Watch Hourly Fire Watch Backfit |
| ML20205N943 | 31 October 1988 | Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 | |
| ML20154B831 | 30 April 1988 | Rev 1 to EGG-NTA-7895, TMI Action-NUREG-0737 (II.D.1), Technical Evaluation Rept | Loop seal Stroke time Anticipated operational occurrence Earthquake |
| ML20151B003 | 31 March 1988 | Technical Evaluation Rept for Plant Protective Sys Trip Setpoints for Fort St Vrain Nuclear Generating Station, Informal Rept | Unanalyzed Condition |