ML20195G527
From kanterella
| ML20195G527 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/02/1987 |
| From: | SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY |
| To: | NRC |
| Shared Package | |
| ML20151M066 | List: |
| References | |
| CON-NRC-03-87-029, CON-NRC-3-87-29 SAIC-87-3084, TAC-60188, NUDOCS 8710060577 | |
| Download: ML20195G527 (17) | |
Similar Documents at Millstone | |
|---|---|
Category:CONTRACTED REPORT - RTA
MONTHYEARML20236U7241998-03-31031 March 1998
[Table view]Technical Evaluation Rept on Third 10-Year Interval ISI Program Plan:Nneco Millstone Nuclear Power Station,Unit 2, Dtd Mar 1998 ML20140G5901997-03-27027 March 1997 Rev 0 to, Review of Millstone Nuclear Power Station Response to USNRC RAI of 960812 on Fire Barrier Ampacity Derating ML20117D0801995-11-30030 November 1995 TER on IPE - Back-End Analysis ML20117D0741995-11-30030 November 1995 Unit 2-TER on IPE Submittal Human Reliability Analysis - Final Rept ML20117D0681995-11-27027 November 1995 NPP TER on IPE Front End Analysis L-94-021, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-31994-11-30030 November 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3 ML20126M4231992-07-31031 July 1992 TER on Third 10-Yr Interval ISI Program Plan:Northeast Utils,Millstone Nuclear Power Station,Unit 1 ML20071A6371991-01-31031 January 1991 Trip Rept: Onsite Analysis of Human Factors of Event at Millstone 3 on 901231 (Turbine Bldg Pipe Break) ML20063P9331990-07-18018 July 1990 Technical Evaluation Rept Millstone Nuclear Power Station Unit 3 Station Blackout Evaluation, Final Rept ML20058K9731990-07-18018 July 1990 Technical Evaluation Rept - Millstone Nuclear Power Station Unit 1,Station Blackout Evaluation, Final Rept ML19332B5821989-09-30030 September 1989 Conformance to Reg Guide 1.97:Millstone-2, Technical Evaluation Rept ML20246B8151989-04-30030 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 ML20067E7161989-03-31031 March 1989 First Interval ISI Program Millstone Nuclear Power Station Unit 3, Technical Evaluation Rept ML20070Q4561989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Millstone 2 ML20070Q4331989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Millstone 3 ML20205N9431988-10-31031 October 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 ML20154B8311988-04-30030 April 1988 Rev 1 to EGG-NTA-7895, TMI Action-NUREG-0737 (II.D.1), Technical Evaluation Rept ML20205N9531988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 ML20205N9481988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 ML20195G5271987-10-0202 October 1987 Technical Evaluation Rept:Millstone Nuclear Power Station, Unit 1,Post-Fire Shutdown Evaluation,App R ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML18052B1931987-06-30030 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 ML20214Q8981987-04-30030 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 ML20214R2161987-03-31031 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 ML20214R7431987-03-31031 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 ML20212H3711987-01-14014 January 1987 Technical Evaluation of Dcrdr for Millstone Nuclear Power Station,Unit 2 ML20210Q4481987-01-0909 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 ML20211K5101986-11-30030 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 ML20206Q3321986-08-31031 August 1986 Draft Technical Evaluation Rept,Millstone 2 - Storage of Consolidated Spent Fuel Tech Spec Change ML20205E3711986-07-31031 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 ML20205E3991986-07-31031 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 ML20244E1901986-07-31031 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 ML20205T5611986-06-11011 June 1986 Review of Licensee Responses to SEP Topic III-7.B,'Design Codes,Design Criteria & Loading Combinations,' Technical Evaluation Rept ML20197G5931986-04-30030 April 1986 a Review of the Millstone 3 Probabilistic Safety Study ML20211F0301986-03-31031 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) ML20214G9591986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 2) Equipment Qualification (Reactor Trip Sys Components), Selected GE BWR Plants ML20214C4281986-01-15015 January 1986 Site Survey of Millstone Unit 1 Maint Program & Practices, Technical Ltr Rept ML20140A9851986-01-0606 January 1986 Review of Millstone Unit 3 Tech Specs, Technical Review Rept for Onsite Activities Conducted 851111-22 ML20137A6291985-12-31031 December 1985 Review of Risk Based Evaluation of Integrated Safety Assessment Program Issues for Millstone Unit 1, Final Rept ML20210K6451985-11-30030 November 1985 PRA Insights ML20138R6321985-11-0606 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 ML20133A6481985-09-30030 September 1985 Review and Evaluation of the Millstone Unit 3 Probabilistic Safety Study.Containment Failure Modes,Radiological Source- Terms and Offsite Consequences ML20133A9101985-09-16016 September 1985 Draft Review of Risk Based Evaluation of Integrated Safety Assessment Program (Isap) Issues for Millstone Unit 1 ML20134G4521985-08-30030 August 1985 Draft Review of Operating Experience History Through 1984 of Millstone 1 for NRC Integrated Safety Assessment Program ML20135D2561985-08-15015 August 1985 Review of Risk Based Evaluation of Integrated Safety Assessment (Isap) Issues for Millstone Unit 1 - Phase 2 ML20213F4161985-07-31031 July 1985 Conformance to Reg Guide 1.97,Millstone Nuclear Power Station,Unit 3 ML20136G1881985-07-23023 July 1985 Radiological Effluent Tech Spec Implementation,Millstone Point Nuclear Power Station Unit 1, Technical Evaluation Rept ML20135A6611985-07-19019 July 1985 Review of Millstone Unit 3 Tech Specs,Northeast Nuclear Energy Co, Technical Review Rept ML20244D3871985-07-10010 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. ML20134P9851985-06-30030 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 1998-03-31 Category:QUICK LOOK MONTHYEARML20236U7241998-03-31031 March 1998
[Table view]Technical Evaluation Rept on Third 10-Year Interval ISI Program Plan:Nneco Millstone Nuclear Power Station,Unit 2, Dtd Mar 1998 ML20140G5901997-03-27027 March 1997 Rev 0 to, Review of Millstone Nuclear Power Station Response to USNRC RAI of 960812 on Fire Barrier Ampacity Derating ML20117D0801995-11-30030 November 1995 TER on IPE - Back-End Analysis ML20117D0741995-11-30030 November 1995 Unit 2-TER on IPE Submittal Human Reliability Analysis - Final Rept ML20117D0681995-11-27027 November 1995 NPP TER on IPE Front End Analysis L-94-021, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-31994-11-30030 November 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3 ML20126M4231992-07-31031 July 1992 TER on Third 10-Yr Interval ISI Program Plan:Northeast Utils,Millstone Nuclear Power Station,Unit 1 ML20071A6371991-01-31031 January 1991 Trip Rept: Onsite Analysis of Human Factors of Event at Millstone 3 on 901231 (Turbine Bldg Pipe Break) ML20063P9331990-07-18018 July 1990 Technical Evaluation Rept Millstone Nuclear Power Station Unit 3 Station Blackout Evaluation, Final Rept ML20058K9731990-07-18018 July 1990 Technical Evaluation Rept - Millstone Nuclear Power Station Unit 1,Station Blackout Evaluation, Final Rept ML19332B5821989-09-30030 September 1989 Conformance to Reg Guide 1.97:Millstone-2, Technical Evaluation Rept ML20246B8151989-04-30030 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 ML20067E7161989-03-31031 March 1989 First Interval ISI Program Millstone Nuclear Power Station Unit 3, Technical Evaluation Rept ML20070Q4561989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Millstone 2 ML20070Q4331989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Millstone 3 ML20205N9431988-10-31031 October 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 ML20154B8311988-04-30030 April 1988 Rev 1 to EGG-NTA-7895, TMI Action-NUREG-0737 (II.D.1), Technical Evaluation Rept ML20205N9531988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 ML20205N9481988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 ML20195G5271987-10-0202 October 1987 Technical Evaluation Rept:Millstone Nuclear Power Station, Unit 1,Post-Fire Shutdown Evaluation,App R ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML18052B1931987-06-30030 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 ML20214Q8981987-04-30030 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 ML20214R2161987-03-31031 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 ML20214R7431987-03-31031 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 ML20212H3711987-01-14014 January 1987 Technical Evaluation of Dcrdr for Millstone Nuclear Power Station,Unit 2 ML20210Q4481987-01-0909 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 ML20211K5101986-11-30030 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 ML20206Q3321986-08-31031 August 1986 Draft Technical Evaluation Rept,Millstone 2 - Storage of Consolidated Spent Fuel Tech Spec Change ML20205E3711986-07-31031 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 ML20205E3991986-07-31031 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 ML20244E1901986-07-31031 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 ML20205T5611986-06-11011 June 1986 Review of Licensee Responses to SEP Topic III-7.B,'Design Codes,Design Criteria & Loading Combinations,' Technical Evaluation Rept ML20197G5931986-04-30030 April 1986 a Review of the Millstone 3 Probabilistic Safety Study ML20211F0301986-03-31031 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) ML20214G9591986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 2) Equipment Qualification (Reactor Trip Sys Components), Selected GE BWR Plants ML20214C4281986-01-15015 January 1986 Site Survey of Millstone Unit 1 Maint Program & Practices, Technical Ltr Rept ML20140A9851986-01-0606 January 1986 Review of Millstone Unit 3 Tech Specs, Technical Review Rept for Onsite Activities Conducted 851111-22 ML20137A6291985-12-31031 December 1985 Review of Risk Based Evaluation of Integrated Safety Assessment Program Issues for Millstone Unit 1, Final Rept ML20210K6451985-11-30030 November 1985 PRA Insights ML20138R6321985-11-0606 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 ML20133A6481985-09-30030 September 1985 Review and Evaluation of the Millstone Unit 3 Probabilistic Safety Study.Containment Failure Modes,Radiological Source- Terms and Offsite Consequences ML20133A9101985-09-16016 September 1985 Draft Review of Risk Based Evaluation of Integrated Safety Assessment Program (Isap) Issues for Millstone Unit 1 ML20134G4521985-08-30030 August 1985 Draft Review of Operating Experience History Through 1984 of Millstone 1 for NRC Integrated Safety Assessment Program ML20135D2561985-08-15015 August 1985 Review of Risk Based Evaluation of Integrated Safety Assessment (Isap) Issues for Millstone Unit 1 - Phase 2 ML20213F4161985-07-31031 July 1985 Conformance to Reg Guide 1.97,Millstone Nuclear Power Station,Unit 3 ML20136G1881985-07-23023 July 1985 Radiological Effluent Tech Spec Implementation,Millstone Point Nuclear Power Station Unit 1, Technical Evaluation Rept ML20135A6611985-07-19019 July 1985 Review of Millstone Unit 3 Tech Specs,Northeast Nuclear Energy Co, Technical Review Rept ML20244D3871985-07-10010 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. ML20134P9851985-06-30030 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 1998-03-31 Category:ETC. (PERIODIC MONTHYEARML20236U7241998-03-31031 March 1998
[Table view]Technical Evaluation Rept on Third 10-Year Interval ISI Program Plan:Nneco Millstone Nuclear Power Station,Unit 2, Dtd Mar 1998 ML20140G5901997-03-27027 March 1997 Rev 0 to, Review of Millstone Nuclear Power Station Response to USNRC RAI of 960812 on Fire Barrier Ampacity Derating ML20117D0801995-11-30030 November 1995 TER on IPE - Back-End Analysis ML20117D0741995-11-30030 November 1995 Unit 2-TER on IPE Submittal Human Reliability Analysis - Final Rept ML20117D0681995-11-27027 November 1995 NPP TER on IPE Front End Analysis L-94-021, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-31994-11-30030 November 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3 ML20126M4231992-07-31031 July 1992 TER on Third 10-Yr Interval ISI Program Plan:Northeast Utils,Millstone Nuclear Power Station,Unit 1 ML20071A6371991-01-31031 January 1991 Trip Rept: Onsite Analysis of Human Factors of Event at Millstone 3 on 901231 (Turbine Bldg Pipe Break) ML20063P9331990-07-18018 July 1990 Technical Evaluation Rept Millstone Nuclear Power Station Unit 3 Station Blackout Evaluation, Final Rept ML20058K9731990-07-18018 July 1990 Technical Evaluation Rept - Millstone Nuclear Power Station Unit 1,Station Blackout Evaluation, Final Rept ML19332B5821989-09-30030 September 1989 Conformance to Reg Guide 1.97:Millstone-2, Technical Evaluation Rept ML20246B8151989-04-30030 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 ML20067E7161989-03-31031 March 1989 First Interval ISI Program Millstone Nuclear Power Station Unit 3, Technical Evaluation Rept ML20070Q4561989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Millstone 2 ML20070Q4331989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Millstone 3 ML20205N9431988-10-31031 October 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 ML20154B8311988-04-30030 April 1988 Rev 1 to EGG-NTA-7895, TMI Action-NUREG-0737 (II.D.1), Technical Evaluation Rept ML20205N9531988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 ML20205N9481988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 ML20195G5271987-10-0202 October 1987 Technical Evaluation Rept:Millstone Nuclear Power Station, Unit 1,Post-Fire Shutdown Evaluation,App R ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML18052B1931987-06-30030 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 ML20214Q8981987-04-30030 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 ML20214R2161987-03-31031 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 ML20214R7431987-03-31031 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 ML20212H3711987-01-14014 January 1987 Technical Evaluation of Dcrdr for Millstone Nuclear Power Station,Unit 2 ML20210Q4481987-01-0909 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 ML20211K5101986-11-30030 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 ML20206Q3321986-08-31031 August 1986 Draft Technical Evaluation Rept,Millstone 2 - Storage of Consolidated Spent Fuel Tech Spec Change ML20205E3711986-07-31031 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 ML20205E3991986-07-31031 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 ML20244E1901986-07-31031 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 ML20205T5611986-06-11011 June 1986 Review of Licensee Responses to SEP Topic III-7.B,'Design Codes,Design Criteria & Loading Combinations,' Technical Evaluation Rept ML20197G5931986-04-30030 April 1986 a Review of the Millstone 3 Probabilistic Safety Study ML20211F0301986-03-31031 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) ML20214G9591986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 2) Equipment Qualification (Reactor Trip Sys Components), Selected GE BWR Plants ML20214C4281986-01-15015 January 1986 Site Survey of Millstone Unit 1 Maint Program & Practices, Technical Ltr Rept ML20140A9851986-01-0606 January 1986 Review of Millstone Unit 3 Tech Specs, Technical Review Rept for Onsite Activities Conducted 851111-22 ML20137A6291985-12-31031 December 1985 Review of Risk Based Evaluation of Integrated Safety Assessment Program Issues for Millstone Unit 1, Final Rept ML20210K6451985-11-30030 November 1985 PRA Insights ML20138R6321985-11-0606 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 ML20133A6481985-09-30030 September 1985 Review and Evaluation of the Millstone Unit 3 Probabilistic Safety Study.Containment Failure Modes,Radiological Source- Terms and Offsite Consequences ML20133A9101985-09-16016 September 1985 Draft Review of Risk Based Evaluation of Integrated Safety Assessment Program (Isap) Issues for Millstone Unit 1 ML20134G4521985-08-30030 August 1985 Draft Review of Operating Experience History Through 1984 of Millstone 1 for NRC Integrated Safety Assessment Program ML20135D2561985-08-15015 August 1985 Review of Risk Based Evaluation of Integrated Safety Assessment (Isap) Issues for Millstone Unit 1 - Phase 2 ML20213F4161985-07-31031 July 1985 Conformance to Reg Guide 1.97,Millstone Nuclear Power Station,Unit 3 ML20136G1881985-07-23023 July 1985 Radiological Effluent Tech Spec Implementation,Millstone Point Nuclear Power Station Unit 1, Technical Evaluation Rept ML20135A6611985-07-19019 July 1985 Review of Millstone Unit 3 Tech Specs,Northeast Nuclear Energy Co, Technical Review Rept ML20244D3871985-07-10010 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. ML20134P9851985-06-30030 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 1998-03-31 Category:TEXT-PROCUREMENT & CONTRACTS MONTHYEARML20236U7241998-03-31031 March 1998
[Table view]Technical Evaluation Rept on Third 10-Year Interval ISI Program Plan:Nneco Millstone Nuclear Power Station,Unit 2, Dtd Mar 1998 ML20140G5901997-03-27027 March 1997 Rev 0 to, Review of Millstone Nuclear Power Station Response to USNRC RAI of 960812 on Fire Barrier Ampacity Derating ML20117D0801995-11-30030 November 1995 TER on IPE - Back-End Analysis ML20117D0741995-11-30030 November 1995 Unit 2-TER on IPE Submittal Human Reliability Analysis - Final Rept ML20117D0681995-11-27027 November 1995 NPP TER on IPE Front End Analysis L-94-021, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-31994-11-30030 November 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3 ML20126M4231992-07-31031 July 1992 TER on Third 10-Yr Interval ISI Program Plan:Northeast Utils,Millstone Nuclear Power Station,Unit 1 ML20071A6371991-01-31031 January 1991 Trip Rept: Onsite Analysis of Human Factors of Event at Millstone 3 on 901231 (Turbine Bldg Pipe Break) ML20063P9331990-07-18018 July 1990 Technical Evaluation Rept Millstone Nuclear Power Station Unit 3 Station Blackout Evaluation, Final Rept ML20058K9731990-07-18018 July 1990 Technical Evaluation Rept - Millstone Nuclear Power Station Unit 1,Station Blackout Evaluation, Final Rept ML19332B5821989-09-30030 September 1989 Conformance to Reg Guide 1.97:Millstone-2, Technical Evaluation Rept ML20246B8151989-04-30030 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 ML20067E7161989-03-31031 March 1989 First Interval ISI Program Millstone Nuclear Power Station Unit 3, Technical Evaluation Rept ML20070Q4561989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Millstone 2 ML20070Q4331989-01-31031 January 1989 Nuclear Power Plant Sys Sourcebook,Millstone 3 ML20205N9431988-10-31031 October 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 ML20154B8311988-04-30030 April 1988 Rev 1 to EGG-NTA-7895, TMI Action-NUREG-0737 (II.D.1), Technical Evaluation Rept ML20205N9531988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 ML20205N9481988-01-31031 January 1988 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 ML20195G5271987-10-0202 October 1987 Technical Evaluation Rept:Millstone Nuclear Power Station, Unit 1,Post-Fire Shutdown Evaluation,App R ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML18052B1931987-06-30030 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 ML20214Q8981987-04-30030 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 ML20214R2161987-03-31031 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 ML20214R7431987-03-31031 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 ML20212H3711987-01-14014 January 1987 Technical Evaluation of Dcrdr for Millstone Nuclear Power Station,Unit 2 ML20210Q4481987-01-0909 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 ML20211K5101986-11-30030 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 ML20206Q3321986-08-31031 August 1986 Draft Technical Evaluation Rept,Millstone 2 - Storage of Consolidated Spent Fuel Tech Spec Change ML20205E3711986-07-31031 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 ML20205E3991986-07-31031 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 ML20244E1901986-07-31031 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 ML20205T5611986-06-11011 June 1986 Review of Licensee Responses to SEP Topic III-7.B,'Design Codes,Design Criteria & Loading Combinations,' Technical Evaluation Rept ML20197G5931986-04-30030 April 1986 a Review of the Millstone 3 Probabilistic Safety Study ML20211F0301986-03-31031 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) ML20214G9591986-03-31031 March 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 2) Equipment Qualification (Reactor Trip Sys Components), Selected GE BWR Plants ML20214C4281986-01-15015 January 1986 Site Survey of Millstone Unit 1 Maint Program & Practices, Technical Ltr Rept ML20140A9851986-01-0606 January 1986 Review of Millstone Unit 3 Tech Specs, Technical Review Rept for Onsite Activities Conducted 851111-22 ML20137A6291985-12-31031 December 1985 Review of Risk Based Evaluation of Integrated Safety Assessment Program Issues for Millstone Unit 1, Final Rept ML20210K6451985-11-30030 November 1985 PRA Insights ML20138R6321985-11-0606 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 ML20133A6481985-09-30030 September 1985 Review and Evaluation of the Millstone Unit 3 Probabilistic Safety Study.Containment Failure Modes,Radiological Source- Terms and Offsite Consequences ML20133A9101985-09-16016 September 1985 Draft Review of Risk Based Evaluation of Integrated Safety Assessment Program (Isap) Issues for Millstone Unit 1 ML20134G4521985-08-30030 August 1985 Draft Review of Operating Experience History Through 1984 of Millstone 1 for NRC Integrated Safety Assessment Program ML20135D2561985-08-15015 August 1985 Review of Risk Based Evaluation of Integrated Safety Assessment (Isap) Issues for Millstone Unit 1 - Phase 2 ML20213F4161985-07-31031 July 1985 Conformance to Reg Guide 1.97,Millstone Nuclear Power Station,Unit 3 ML20136G1881985-07-23023 July 1985 Radiological Effluent Tech Spec Implementation,Millstone Point Nuclear Power Station Unit 1, Technical Evaluation Rept ML20135A6611985-07-19019 July 1985 Review of Millstone Unit 3 Tech Specs,Northeast Nuclear Energy Co, Technical Review Rept ML20244D3871985-07-10010 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. ML20134P9851985-06-30030 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 1998-03-31 |
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