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Revision as of 09:22, 17 April 2018
| ML18040A226 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/31/1994 |
| From: | ECONOMOS C, LEHNER J, LIN C C BROOKHAVEN NATIONAL LABORATORY |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17059A382 | List: |
| References | |
| CON-FIN-L-1331 NUDOCS 9408100168 | |
| Download: ML18040A226 (106) | |
Similar Documents at Nine Mile Point | |
|---|---|
Category:CONTRACTED REPORT - RTA
MONTHYEARML20100C9091995-08-31031 August 1995
[Table view]App a, Technical Evaluation Rept on IPE Front End Analysis ML20100D2401995-08-31031 August 1995 App B, Plant Technical Evaluation Rept on IPE Back-End Analysis ML20100D2471995-08-22022 August 1995 App C, Plant Technical Evaluation Rept on IPE Submittal Human Reliability Analysis,Final Rept ML18040A2261994-05-31031 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. ML20085L5411991-09-30030 September 1991 Conformance to Reg Guide 1.97:Nine Mile Point-1 ML20081K3631991-05-15015 May 1991 Final Technical Evaluation Rept Nine Mile Point Nuclear Power Station Unit 1 Station Blackout Evaluation ML20058L0411990-08-31031 August 1990 Technical Evaluation Rept,Pump & Valve Inservice Testing Program ML20058K1591990-03-31031 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 ML20042D1741989-10-31031 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. 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 ML20246L1771989-02-28028 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 ML20216C2301987-04-30030 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 ML20214R3421987-03-31031 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 ML20214H1291986-08-0101 August 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Nine Mile Point Unit 1 Nuclear Generating Station, Supplementary Technical Evaluation Rept 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 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 ML20214E3431986-01-31031 January 1986 Rev 1 to Conformance to Reg Guide 1.97,Nine Mile Point Nuclear Station,Unit 1 ML20066H2841986-01-17017 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 ML20151L3311985-11-0404 November 1985 Masonry Wall Design, Technical Evaluation Rept ML20198F3431985-10-0404 October 1985 Technical Evaluation of Dcrdr for Nine Mile Point Nuclear Station,Unit 1 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. ML20244D4381985-06-30030 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 ML20127D7311985-02-28028 February 1985 Conformance to Reg Guide 1.97,Nine Mile Point Nuclear Station,Unit 1 ML20101T3721985-01-31031 January 1985 Control of Heavy Loads,Nine Mile Point Unit 1, Technical Evaluation Rept ML20106A5741984-09-30030 September 1984 Technical Evaluation of Nine Mile Point Unit 1 Plant-Unique Analysis Rept ML20106A5521984-09-26026 September 1984 Audit for Mark 1 Containment Long-Term Program - Structural Analysis for Operating Reactors, Technical Evaluation Rept ML20090H7671983-07-31031 July 1983 Technical Evaluation of Integrity of Nine Mile Point Unit 1 Rcbp Sys, Technical Evaluation Rept ML20080A0431983-06-15015 June 1983 Adequacy of Station Electric Distribution Sys Voltages for Nine Mile Point Nuclear Station,Unit 1, Technical Evaluation Rept ML20076F2481983-04-0606 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 ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20077J9891982-09-17017 September 1982 Inservice Insp Program, Technical Evaluation Rept ML20027A8991982-08-26026 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 ML20062G6541982-07-31031 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) ML20052B8311982-02-28028 February 1982 Safety Evaluation Rept,Pumps & Valves Inservice Testing Program,Nine Mile Point Nuclear Station,Unit 1. ML20084P9511970-05-0606 May 1970 Preliminary Rept on Meeting Concerning Nine Mile Point Core Spray Nozzles & Related Piping Sys ML20084Q6331970-03-0505 March 1970 Exam & Evaluation of Safe-End from Nozzle N6B on Nine Mile Point Reactor 1995-08-31 Category:QUICK LOOK MONTHYEARML20100C9091995-08-31031 August 1995
[Table view]App a, Technical Evaluation Rept on IPE Front End Analysis ML20100D2401995-08-31031 August 1995 App B, Plant Technical Evaluation Rept on IPE Back-End Analysis ML20100D2471995-08-22022 August 1995 App C, Plant Technical Evaluation Rept on IPE Submittal Human Reliability Analysis,Final Rept ML18040A2261994-05-31031 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. ML20085L5411991-09-30030 September 1991 Conformance to Reg Guide 1.97:Nine Mile Point-1 ML20081K3631991-05-15015 May 1991 Final Technical Evaluation Rept Nine Mile Point Nuclear Power Station Unit 1 Station Blackout Evaluation ML20058L0411990-08-31031 August 1990 Technical Evaluation Rept,Pump & Valve Inservice Testing Program ML20058K1591990-03-31031 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 ML20042D1741989-10-31031 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. 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 ML20246L1771989-02-28028 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 ML20216C2301987-04-30030 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 ML20214R3421987-03-31031 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 ML20214H1291986-08-0101 August 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Nine Mile Point Unit 1 Nuclear Generating Station, Supplementary Technical Evaluation Rept 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 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 ML20214E3431986-01-31031 January 1986 Rev 1 to Conformance to Reg Guide 1.97,Nine Mile Point Nuclear Station,Unit 1 ML20066H2841986-01-17017 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 ML20151L3311985-11-0404 November 1985 Masonry Wall Design, Technical Evaluation Rept ML20198F3431985-10-0404 October 1985 Technical Evaluation of Dcrdr for Nine Mile Point Nuclear Station,Unit 1 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. ML20244D4381985-06-30030 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 ML20127D7311985-02-28028 February 1985 Conformance to Reg Guide 1.97,Nine Mile Point Nuclear Station,Unit 1 ML20101T3721985-01-31031 January 1985 Control of Heavy Loads,Nine Mile Point Unit 1, Technical Evaluation Rept ML20106A5741984-09-30030 September 1984 Technical Evaluation of Nine Mile Point Unit 1 Plant-Unique Analysis Rept ML20106A5521984-09-26026 September 1984 Audit for Mark 1 Containment Long-Term Program - Structural Analysis for Operating Reactors, Technical Evaluation Rept ML20090H7671983-07-31031 July 1983 Technical Evaluation of Integrity of Nine Mile Point Unit 1 Rcbp Sys, Technical Evaluation Rept ML20080A0431983-06-15015 June 1983 Adequacy of Station Electric Distribution Sys Voltages for Nine Mile Point Nuclear Station,Unit 1, Technical Evaluation Rept ML20076F2481983-04-0606 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 ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20077J9891982-09-17017 September 1982 Inservice Insp Program, Technical Evaluation Rept ML20027A8991982-08-26026 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 ML20062G6541982-07-31031 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) ML20052B8311982-02-28028 February 1982 Safety Evaluation Rept,Pumps & Valves Inservice Testing Program,Nine Mile Point Nuclear Station,Unit 1. ML20084P9511970-05-0606 May 1970 Preliminary Rept on Meeting Concerning Nine Mile Point Core Spray Nozzles & Related Piping Sys ML20084Q6331970-03-0505 March 1970 Exam & Evaluation of Safe-End from Nozzle N6B on Nine Mile Point Reactor 1995-08-31 Category:ETC. (PERIODIC MONTHYEARML20100C9091995-08-31031 August 1995
[Table view]App a, Technical Evaluation Rept on IPE Front End Analysis ML20100D2401995-08-31031 August 1995 App B, Plant Technical Evaluation Rept on IPE Back-End Analysis ML20100D2471995-08-22022 August 1995 App C, Plant Technical Evaluation Rept on IPE Submittal Human Reliability Analysis,Final Rept ML18040A2261994-05-31031 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. ML20085L5411991-09-30030 September 1991 Conformance to Reg Guide 1.97:Nine Mile Point-1 ML20081K3631991-05-15015 May 1991 Final Technical Evaluation Rept Nine Mile Point Nuclear Power Station Unit 1 Station Blackout Evaluation ML20058L0411990-08-31031 August 1990 Technical Evaluation Rept,Pump & Valve Inservice Testing Program ML20058K1591990-03-31031 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 ML20042D1741989-10-31031 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. 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 ML20246L1771989-02-28028 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 ML20216C2301987-04-30030 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 ML20214R3421987-03-31031 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 ML20214H1291986-08-0101 August 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Nine Mile Point Unit 1 Nuclear Generating Station, Supplementary Technical Evaluation Rept 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 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 ML20214E3431986-01-31031 January 1986 Rev 1 to Conformance to Reg Guide 1.97,Nine Mile Point Nuclear Station,Unit 1 ML20066H2841986-01-17017 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 ML20151L3311985-11-0404 November 1985 Masonry Wall Design, Technical Evaluation Rept ML20198F3431985-10-0404 October 1985 Technical Evaluation of Dcrdr for Nine Mile Point Nuclear Station,Unit 1 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. ML20244D4381985-06-30030 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 ML20127D7311985-02-28028 February 1985 Conformance to Reg Guide 1.97,Nine Mile Point Nuclear Station,Unit 1 ML20101T3721985-01-31031 January 1985 Control of Heavy Loads,Nine Mile Point Unit 1, Technical Evaluation Rept ML20106A5741984-09-30030 September 1984 Technical Evaluation of Nine Mile Point Unit 1 Plant-Unique Analysis Rept ML20106A5521984-09-26026 September 1984 Audit for Mark 1 Containment Long-Term Program - Structural Analysis for Operating Reactors, Technical Evaluation Rept ML20090H7671983-07-31031 July 1983 Technical Evaluation of Integrity of Nine Mile Point Unit 1 Rcbp Sys, Technical Evaluation Rept ML20080A0431983-06-15015 June 1983 Adequacy of Station Electric Distribution Sys Voltages for Nine Mile Point Nuclear Station,Unit 1, Technical Evaluation Rept ML20076F2481983-04-0606 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 ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20077J9891982-09-17017 September 1982 Inservice Insp Program, Technical Evaluation Rept ML20027A8991982-08-26026 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 ML20062G6541982-07-31031 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) ML20052B8311982-02-28028 February 1982 Safety Evaluation Rept,Pumps & Valves Inservice Testing Program,Nine Mile Point Nuclear Station,Unit 1. ML20084P9511970-05-0606 May 1970 Preliminary Rept on Meeting Concerning Nine Mile Point Core Spray Nozzles & Related Piping Sys ML20084Q6331970-03-0505 March 1970 Exam & Evaluation of Safe-End from Nozzle N6B on Nine Mile Point Reactor 1995-08-31 Category:TEXT-PROCUREMENT & CONTRACTS MONTHYEARML20100C9091995-08-31031 August 1995
[Table view]App a, Technical Evaluation Rept on IPE Front End Analysis ML20100D2401995-08-31031 August 1995 App B, Plant Technical Evaluation Rept on IPE Back-End Analysis ML20100D2471995-08-22022 August 1995 App C, Plant Technical Evaluation Rept on IPE Submittal Human Reliability Analysis,Final Rept ML18040A2261994-05-31031 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. ML20085L5411991-09-30030 September 1991 Conformance to Reg Guide 1.97:Nine Mile Point-1 ML20081K3631991-05-15015 May 1991 Final Technical Evaluation Rept Nine Mile Point Nuclear Power Station Unit 1 Station Blackout Evaluation ML20058L0411990-08-31031 August 1990 Technical Evaluation Rept,Pump & Valve Inservice Testing Program ML20058K1591990-03-31031 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 ML20042D1741989-10-31031 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. 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 ML20246L1771989-02-28028 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 ML20216C2301987-04-30030 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 ML20214R3421987-03-31031 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 ML20214H1291986-08-0101 August 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Nine Mile Point Unit 1 Nuclear Generating Station, Supplementary Technical Evaluation Rept 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 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 ML20214E3431986-01-31031 January 1986 Rev 1 to Conformance to Reg Guide 1.97,Nine Mile Point Nuclear Station,Unit 1 ML20066H2841986-01-17017 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 ML20151L3311985-11-0404 November 1985 Masonry Wall Design, Technical Evaluation Rept ML20198F3431985-10-0404 October 1985 Technical Evaluation of Dcrdr for Nine Mile Point Nuclear Station,Unit 1 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. ML20244D4381985-06-30030 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 ML20127D7311985-02-28028 February 1985 Conformance to Reg Guide 1.97,Nine Mile Point Nuclear Station,Unit 1 ML20101T3721985-01-31031 January 1985 Control of Heavy Loads,Nine Mile Point Unit 1, Technical Evaluation Rept ML20106A5741984-09-30030 September 1984 Technical Evaluation of Nine Mile Point Unit 1 Plant-Unique Analysis Rept ML20106A5521984-09-26026 September 1984 Audit for Mark 1 Containment Long-Term Program - Structural Analysis for Operating Reactors, Technical Evaluation Rept ML20090H7671983-07-31031 July 1983 Technical Evaluation of Integrity of Nine Mile Point Unit 1 Rcbp Sys, Technical Evaluation Rept ML20080A0431983-06-15015 June 1983 Adequacy of Station Electric Distribution Sys Voltages for Nine Mile Point Nuclear Station,Unit 1, Technical Evaluation Rept ML20076F2481983-04-0606 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 ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20077J9891982-09-17017 September 1982 Inservice Insp Program, Technical Evaluation Rept ML20027A8991982-08-26026 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 ML20062G6541982-07-31031 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) ML20052B8311982-02-28028 February 1982 Safety Evaluation Rept,Pumps & Valves Inservice Testing Program,Nine Mile Point Nuclear Station,Unit 1. ML20084P9511970-05-0606 May 1970 Preliminary Rept on Meeting Concerning Nine Mile Point Core Spray Nozzles & Related Piping Sys ML20084Q6331970-03-0505 March 1970 Exam & Evaluation of Safe-End from Nozzle N6B on Nine Mile Point Reactor 1995-08-31 |
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