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Issue date | Title | Topic | |
---|---|---|---|
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 | |
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 |
ML20117D080 | 30 November 1995 | TER on IPE - Back-End Analysis | Probabilistic Risk Assessment |
ML20117D074 | 30 November 1995 | Unit 2-TER on IPE Submittal Human Reliability Analysis - Final Rept | Probabilistic Risk Assessment |
ML20117D068 | 27 November 1995 | NPP TER on IPE Front End Analysis | Safe Shutdown Mission time Internal Flooding Probabilistic Risk Assessment |
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 | |
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 |
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 |
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 | |
ML19332B582 | 30 September 1989 | Conformance to Reg Guide 1.97:Millstone-2, Technical Evaluation Rept | Post Accident Monitoring |
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 | |
ML20067E716 | 31 March 1989 | First Interval ISI Program Millstone Nuclear Power Station Unit 3, Technical Evaluation Rept | |
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 | |
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 |
ML20205N953 | 31 January 1988 | Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 | Safe Shutdown |
ML20205N948 | 31 January 1988 | Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 | Safe Shutdown |
ML20195G527 | 2 October 1987 | Technical Evaluation Rept:Millstone Nuclear Power Station, Unit 1,Post-Fire Shutdown Evaluation,App R | Safe Shutdown Scram Discharge Volume |
ML20237J141 | 17 August 1987 | Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 | |
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 | |
ML20214Q898 | 30 April 1987 | Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Hatch-1 & 2,Millstone-1, Final Rept | |
ML20214R216 | 31 March 1987 | Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, Haddam Neck & Millstone 1,2 &3, Informal Rept | |
ML20214R743 | 31 March 1987 | Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Arkansas Nuclear One-2,Calvert Cliffs 1 & 2,Fort Calhoun, Main Yankee,Millstone 2,Palisades,Palo Verde 1,2 & 3,San Onofre 2 & 3,St Lucie 1 & 2,Waterford 3 & WNP 3 | |
ML20212H371 | 14 January 1987 | Technical Evaluation of Dcrdr for Millstone Nuclear Power Station,Unit 2 | |
ML20210Q448 | 9 January 1987 | Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Arkansas Nuclear One Unit 2,Calvert Cliffs Units 1 & 2,Fort Calhoun,Maine Yankee,Millstone Unit 2, Palisades,Palo Verde Units..., Technical Evaluation Rept | |
ML20211K510 | 30 November 1986 | Input for Ser,Mcguire Nuclear Station Units 1 & 2,Millstone Nuclear Power Station Unit 3,Seabrook Station Units 1 & 2, VC Summer Nuclear Station,Vogtle Electric...Reactor Trip Sys Reliability,Item 4.5.2 of Generic Ltr 83-28 | |
ML20206Q332 | 31 August 1986 | Draft Technical Evaluation Rept,Millstone 2 - Storage of Consolidated Spent Fuel Tech Spec Change | |
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 |
ML20205E399 | 31 July 1986 | Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components) Ginna,Haddam Neck,Millstone 3 & Harris 1 | |
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 |
ML20205T561 | 11 June 1986 | Review of Licensee Responses to SEP Topic III-7.B,'Design Codes,Design Criteria & Loading Combinations,' Technical Evaluation Rept | Safe Shutdown Tornado Missile |
ML20197G593 | 30 April 1986 | a Review of the Millstone 3 Probabilistic Safety Study | Safe Shutdown High winds Ultimate heat sink Mission time Fire Barrier Tornado Missile Safe Shutdown Earthquake Internal Flooding Probabilistic Risk Assessment Reserve Station Service Transformer Earthquake Turbine Missile Failure to Scram |
ML20211F030 | 31 March 1986 | Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (RTS Components) Selected GE BWR Plants (Grand Gulf 1 & 2,Hatch 1 & 2,LaSalle 1 & 2 & Millstone 1) | |
ML20214G959 | 31 March 1986 | Conformance to Generic Ltr 83-28,Item 2.1 (Part 2) Equipment Qualification (Reactor Trip Sys Components), Selected GE BWR Plants | |
ML20214C428 | 15 January 1986 | Site Survey of Millstone Unit 1 Maint Program & Practices, Technical Ltr Rept | Stroke time Systematic Assessment of Licensee Performance Backfit |
ML20140A985 | 6 January 1986 | Review of Millstone Unit 3 Tech Specs, Technical Review Rept for Onsite Activities Conducted 851111-22 | Boric Acid Reactor Vessel Water Level Ultimate heat sink Stroke time |
ML20137A629 | 31 December 1985 | Review of Risk Based Evaluation of Integrated Safety Assessment Program Issues for Millstone Unit 1, Final Rept | Probabilistic Risk Assessment Tornado Missile Protection Backfit |
ML20210K645 | 30 November 1985 | PRA Insights | Safe Shutdown Mission time Tornado Missile Internal Flooding Probabilistic Risk Assessment Earthquake Turbine Missile Fatality |
ML20138R632 | 6 November 1985 | Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28,(Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2..., Technical Evaluation Rept | |
ML20133A648 | 30 September 1985 | Review and Evaluation of the Millstone Unit 3 Probabilistic Safety Study.Containment Failure Modes,Radiological Source- Terms and Offsite Consequences | Safe Shutdown Earthquake Probabilistic Risk Assessment Earthquake |
ML20133A910 | 16 September 1985 | Draft Review of Risk Based Evaluation of Integrated Safety Assessment Program (Isap) Issues for Millstone Unit 1 | Tornado Missile Probabilistic Risk Assessment Tornado Missile Protection Earthquake Biofouling |
ML20134G452 | 30 August 1985 | Draft Review of Operating Experience History Through 1984 of Millstone 1 for NRC Integrated Safety Assessment Program | Safe Shutdown High winds Shutdown Margin Loop seal Ultimate heat sink Emergency Lighting Earthquake Pressure Boundary Leakage Power change Flow Induced Vibration |
ML20135D256 | 15 August 1985 | Review of Risk Based Evaluation of Integrated Safety Assessment (Isap) Issues for Millstone Unit 1 - Phase 2 | |
ML20213F416 | 31 July 1985 | Conformance to Reg Guide 1.97,Millstone Nuclear Power Station,Unit 3 | Boric Acid |
ML20136G188 | 23 July 1985 | Radiological Effluent Tech Spec Implementation,Millstone Point Nuclear Power Station Unit 1, Technical Evaluation Rept | Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program |
ML20135A661 | 19 July 1985 | Review of Millstone Unit 3 Tech Specs,Northeast Nuclear Energy Co, Technical Review Rept | Boric Acid Shutdown Margin Stroke time Backfit |
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. | |
ML20134P985 | 30 June 1985 | Conformance to Generic Ltr 83-28 Items 3.1.3 & 3.2.3 for Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad-Cities Units 1 & 2 |