ML20093C533
From kanterella
| ML20093C533 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna, 05000000 |
| Issue date: | 03/30/1984 |
| From: | Bacanskas V, Jerome Murphy FRANKLIN INSTITUTE |
| To: | Bettenhausen L, Mccabe E NRC |
| Shared Package | |
| ML20093C531 | List: |
| References | |
| CON-NRC-03-81-130, CON-NRC-3-81-130 TER-C5506-524, NUDOCS 8404040098 | |
| Download: ML20093C533 (26) | |
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|---|---|
Category:CONTRACTED REPORT - RTA
MONTHYEARML20206D3411999-12-31031 December 1999
[Table view]Suppl Technical Evaluation Rept Based on Review of Addl Responses & Site Audit of Individual Plant Exam of External Events at Susquehanna Steam Electric Station,Units 1 & 2 ML17164A6901998-07-31031 July 1998 Site Audit Rept for Step 2 Review of IPEEE at Susquehanna Steam Electric Station Units 1 & 2. Site Audit Plan, Jul 1998 ML18026A2931998-02-28028 February 1998 Technical Evaluation Rept on Submittal Only Review of IPEEE at Susquehanna Steam Electric Station Units 1 & 2. Final Rept,Feb 1998 ML20212F1921997-03-31031 March 1997 Rev 1 to, Review & Evaluation of PP&L Fire Protection Review Rept,Rev 4 Susquehanna Steam Electric Station Safe Shutdown Capability-10CFR50,App R, 'Post-Fire Safe Shutdown Methodology & Analysis of Associated Circuits.' ML18026A2741995-10-31031 October 1995 Technical Evaluation Rept on Second 10-Yr ISI Program Plan for Units 1 & 2. ML20080L6861995-02-28028 February 1995 Technical Evaluation Rept:Pp&L,Susquehanna Steam Electric Station,Pump & Valve Inservice Testing Program,Rev 10,Unit 1 Second 10-Yr Interval,Rev 7,Unit 2 Second 10-Yr Interval ML20091J1151991-10-0101 October 1991 Final Technical Evaluation Rept,Susquehanna Steam Electric Station Units 1 & 2,Station Blackout Evaluation ML20082Q8271991-08-31031 August 1991 Evaluation of 9 by 9 Fuel Impact on Stability of Susquehanna-2 at End of Cycle 4 ML18040B2611989-10-31031 October 1989 Technical Evaluation Rept on Response from Pennsylvania Power & Light to Generic Ltr 88-01 Pertaining to Susquehanna Steam Electric Station Unit 2, Final Rept ML19332B6141989-10-31031 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 ML18040A9461989-09-30030 September 1989 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Susquehanna-1/-2, Final Technical Evaluation Rept ML20245F0471989-06-22022 June 1989 Fire Protection Review Rept Evaluation 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 ML20246B9731989-03-31031 March 1989 Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept ML20236B8051989-03-13013 March 1989 Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files ML18040A9251988-12-31031 December 1988 Conformance to Generic Ltr 83-28,Item 2.1 (Part 2),Reactor Trip Sys Vendor Interface,Susquehanna Steam Electric Station Units 1 & 2, Technical Evaluation Rept.Salp Input Also Encl ML18040A9221988-12-31031 December 1988 Conformance to Generic Ltr 83-28,Item 4.5.2,Susquehanna Steam Electric Station Units 1 & 2, Technical Evaluation Rept 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 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 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 ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML20235V1521987-08-31031 August 1987 Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2 ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML20236D9181987-07-31031 July 1987 Methodology and Application of Surrogate Plant PRA Analysis to the Rancho Seco Power Plant.Task 1 - Analysis of ANO-1 and Oconee PRAs 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 ML20214R0681987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Arnold,Brunswick-1 & 2, Informal Rept ML18150A1881987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept ML18150A1191987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept ML18152A5831987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. 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 ML20206F0711987-04-0808 April 1987 Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog 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 ML17334B0721987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Cook Units 1 & 2 & Haddam Neck. ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 ML20214R8651987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Cook-1 & -2,Haddam Neck, Final 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 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 ML20211N5031987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept ML20210A0051986-12-31031 December 1986 Environ Radioactivity Survey for 1986 ML20210A0131986-12-31031 December 1986 BWR Environ Radioactivity Survey for 1986 ML20207N2461986-12-16016 December 1986 Technical Assistance to Nrc,Region Iv,For Preservice Insp, Monthly Ltr Rept for Nov 1986 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 ML17334B0331986-11-30030 November 1986 Input for Ser,Beaver Valley Power Station Units 1 & 2, Braidwood Station Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Catawba Nuclear Station Units 1..., Reactor Trip Sys Reliability Item 4.5.2 Generic Ltr 83-28. ML18040B1671986-11-30030 November 1986 First Interval Inservice Insp Program,Susquehanna Steam Electric Station Unit 2, Technical Evaluation Rept 1999-12-31 Category:QUICK LOOK MONTHYEARML20206D3411999-12-31031 December 1999
[Table view]Suppl Technical Evaluation Rept Based on Review of Addl Responses & Site Audit of Individual Plant Exam of External Events at Susquehanna Steam Electric Station,Units 1 & 2 ML17164A6901998-07-31031 July 1998 Site Audit Rept for Step 2 Review of IPEEE at Susquehanna Steam Electric Station Units 1 & 2. Site Audit Plan, Jul 1998 ML18026A2931998-02-28028 February 1998 Technical Evaluation Rept on Submittal Only Review of IPEEE at Susquehanna Steam Electric Station Units 1 & 2. Final Rept,Feb 1998 ML20212F1921997-03-31031 March 1997 Rev 1 to, Review & Evaluation of PP&L Fire Protection Review Rept,Rev 4 Susquehanna Steam Electric Station Safe Shutdown Capability-10CFR50,App R, 'Post-Fire Safe Shutdown Methodology & Analysis of Associated Circuits.' ML18026A2741995-10-31031 October 1995 Technical Evaluation Rept on Second 10-Yr ISI Program Plan for Units 1 & 2. ML20080L6861995-02-28028 February 1995 Technical Evaluation Rept:Pp&L,Susquehanna Steam Electric Station,Pump & Valve Inservice Testing Program,Rev 10,Unit 1 Second 10-Yr Interval,Rev 7,Unit 2 Second 10-Yr Interval ML20091J1151991-10-0101 October 1991 Final Technical Evaluation Rept,Susquehanna Steam Electric Station Units 1 & 2,Station Blackout Evaluation ML20082Q8271991-08-31031 August 1991 Evaluation of 9 by 9 Fuel Impact on Stability of Susquehanna-2 at End of Cycle 4 ML18040B2611989-10-31031 October 1989 Technical Evaluation Rept on Response from Pennsylvania Power & Light to Generic Ltr 88-01 Pertaining to Susquehanna Steam Electric Station Unit 2, Final Rept ML19332B6141989-10-31031 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 ML18040A9461989-09-30030 September 1989 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Susquehanna-1/-2, Final Technical Evaluation Rept ML20245F0471989-06-22022 June 1989 Fire Protection Review Rept Evaluation 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 ML20246B9731989-03-31031 March 1989 Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept ML20236B8051989-03-13013 March 1989 Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files ML18040A9251988-12-31031 December 1988 Conformance to Generic Ltr 83-28,Item 2.1 (Part 2),Reactor Trip Sys Vendor Interface,Susquehanna Steam Electric Station Units 1 & 2, Technical Evaluation Rept.Salp Input Also Encl ML18040A9221988-12-31031 December 1988 Conformance to Generic Ltr 83-28,Item 4.5.2,Susquehanna Steam Electric Station Units 1 & 2, Technical Evaluation Rept 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 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 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 ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML20235V1521987-08-31031 August 1987 Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2 ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML20236D9181987-07-31031 July 1987 Methodology and Application of Surrogate Plant PRA Analysis to the Rancho Seco Power Plant.Task 1 - Analysis of ANO-1 and Oconee PRAs 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 ML20214R0681987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Arnold,Brunswick-1 & 2, Informal Rept ML18150A1881987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept ML18150A1191987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept ML18152A5831987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. 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 ML20206F0711987-04-0808 April 1987 Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog 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 ML17334B0721987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Cook Units 1 & 2 & Haddam Neck. ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 ML20214R8651987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Cook-1 & -2,Haddam Neck, Final 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 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 ML20211N5031987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept ML20210A0051986-12-31031 December 1986 Environ Radioactivity Survey for 1986 ML20210A0131986-12-31031 December 1986 BWR Environ Radioactivity Survey for 1986 ML20207N2461986-12-16016 December 1986 Technical Assistance to Nrc,Region Iv,For Preservice Insp, Monthly Ltr Rept for Nov 1986 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 ML17334B0331986-11-30030 November 1986 Input for Ser,Beaver Valley Power Station Units 1 & 2, Braidwood Station Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Catawba Nuclear Station Units 1..., Reactor Trip Sys Reliability Item 4.5.2 Generic Ltr 83-28. ML18040B1671986-11-30030 November 1986 First Interval Inservice Insp Program,Susquehanna Steam Electric Station Unit 2, Technical Evaluation Rept 1999-12-31 Category:ETC. (PERIODIC MONTHYEARML20206D3411999-12-31031 December 1999
[Table view]Suppl Technical Evaluation Rept Based on Review of Addl Responses & Site Audit of Individual Plant Exam of External Events at Susquehanna Steam Electric Station,Units 1 & 2 ML17164A6901998-07-31031 July 1998 Site Audit Rept for Step 2 Review of IPEEE at Susquehanna Steam Electric Station Units 1 & 2. Site Audit Plan, Jul 1998 ML18026A2931998-02-28028 February 1998 Technical Evaluation Rept on Submittal Only Review of IPEEE at Susquehanna Steam Electric Station Units 1 & 2. Final Rept,Feb 1998 ML20212F1921997-03-31031 March 1997 Rev 1 to, Review & Evaluation of PP&L Fire Protection Review Rept,Rev 4 Susquehanna Steam Electric Station Safe Shutdown Capability-10CFR50,App R, 'Post-Fire Safe Shutdown Methodology & Analysis of Associated Circuits.' ML18026A2741995-10-31031 October 1995 Technical Evaluation Rept on Second 10-Yr ISI Program Plan for Units 1 & 2. ML20080L6861995-02-28028 February 1995 Technical Evaluation Rept:Pp&L,Susquehanna Steam Electric Station,Pump & Valve Inservice Testing Program,Rev 10,Unit 1 Second 10-Yr Interval,Rev 7,Unit 2 Second 10-Yr Interval ML20091J1151991-10-0101 October 1991 Final Technical Evaluation Rept,Susquehanna Steam Electric Station Units 1 & 2,Station Blackout Evaluation ML20082Q8271991-08-31031 August 1991 Evaluation of 9 by 9 Fuel Impact on Stability of Susquehanna-2 at End of Cycle 4 ML18040B2611989-10-31031 October 1989 Technical Evaluation Rept on Response from Pennsylvania Power & Light to Generic Ltr 88-01 Pertaining to Susquehanna Steam Electric Station Unit 2, Final Rept ML19332B6141989-10-31031 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 ML18040A9461989-09-30030 September 1989 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Susquehanna-1/-2, Final Technical Evaluation Rept ML20245F0471989-06-22022 June 1989 Fire Protection Review Rept Evaluation 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 ML20246B9731989-03-31031 March 1989 Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept ML20236B8051989-03-13013 March 1989 Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files ML18040A9251988-12-31031 December 1988 Conformance to Generic Ltr 83-28,Item 2.1 (Part 2),Reactor Trip Sys Vendor Interface,Susquehanna Steam Electric Station Units 1 & 2, Technical Evaluation Rept.Salp Input Also Encl ML18040A9221988-12-31031 December 1988 Conformance to Generic Ltr 83-28,Item 4.5.2,Susquehanna Steam Electric Station Units 1 & 2, Technical Evaluation Rept 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 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 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 ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML20235V1521987-08-31031 August 1987 Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2 ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML20236D9181987-07-31031 July 1987 Methodology and Application of Surrogate Plant PRA Analysis to the Rancho Seco Power Plant.Task 1 - Analysis of ANO-1 and Oconee PRAs 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 ML20214R0681987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Arnold,Brunswick-1 & 2, Informal Rept ML18150A1881987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept ML18150A1191987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept ML18152A5831987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. 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 ML20206F0711987-04-0808 April 1987 Flow-Pattern Results for Tmlb' Accident Sequence in Surry Plant Using Melprog 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 ML17334B0721987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Cook Units 1 & 2 & Haddam Neck. ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 ML20214R8651987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Cook-1 & -2,Haddam Neck, Final 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 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 ML20211N5031987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept ML20210A0051986-12-31031 December 1986 Environ Radioactivity Survey for 1986 ML20210A0131986-12-31031 December 1986 BWR Environ Radioactivity Survey for 1986 ML20207N2461986-12-16016 December 1986 Technical Assistance to Nrc,Region Iv,For Preservice Insp, Monthly Ltr Rept for Nov 1986 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 ML17334B0331986-11-30030 November 1986 Input for Ser,Beaver Valley Power Station Units 1 & 2, Braidwood Station Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Catawba Nuclear Station Units 1..., Reactor Trip Sys Reliability Item 4.5.2 Generic Ltr 83-28. ML18040B1671986-11-30030 November 1986 First Interval Inservice Insp Program,Susquehanna Steam Electric Station Unit 2, Technical Evaluation Rept 1999-12-31 Category:TEXT-PROCUREMENT & CONTRACTS MONTHYEARML20206D3411999-12-31031 December 1999
[Table view]Suppl Technical Evaluation Rept Based on Review of Addl Responses & Site Audit of Individual Plant Exam of External Events at Susquehanna Steam Electric Station,Units 1 & 2 ML17164A6901998-07-31031 July 1998 Site Audit Rept for Step 2 Review of IPEEE at Susquehanna Steam Electric Station Units 1 & 2. Site Audit Plan, Jul 1998 ML18026A2931998-02-28028 February 1998 Technical Evaluation Rept on Submittal Only Review of IPEEE at Susquehanna Steam Electric Station Units 1 & 2. Final Rept,Feb 1998 ML20212F1921997-03-31031 March 1997 Rev 1 to, Review & Evaluation of PP&L Fire Protection Review Rept,Rev 4 Susquehanna Steam Electric Station Safe Shutdown Capability-10CFR50,App R, 'Post-Fire Safe Shutdown Methodology & Analysis of Associated Circuits.' ML18026A2741995-10-31031 October 1995 Technical Evaluation Rept on Second 10-Yr ISI Program Plan for Units 1 & 2. ML20080L6861995-02-28028 February 1995 Technical Evaluation Rept:Pp&L,Susquehanna Steam Electric Station,Pump & Valve Inservice Testing Program,Rev 10,Unit 1 Second 10-Yr Interval,Rev 7,Unit 2 Second 10-Yr Interval ML20091J1151991-10-0101 October 1991 Final Technical Evaluation Rept,Susquehanna Steam Electric Station Units 1 & 2,Station Blackout Evaluation ML20082Q8271991-08-31031 August 1991 Evaluation of 9 by 9 Fuel Impact on Stability of Susquehanna-2 at End of Cycle 4 ML18040B2611989-10-31031 October 1989 Technical Evaluation Rept on Response from Pennsylvania Power & Light to Generic Ltr 88-01 Pertaining to Susquehanna Steam Electric Station Unit 2, Final Rept ML19332B6141989-10-31031 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 ML18040A9461989-09-30030 September 1989 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Susquehanna-1/-2, Final Technical Evaluation Rept ML20248E2191989-08-16016 August 1989 Mod 16,reflecting Return of Equipment to Tva,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML20248E2121989-08-16016 August 1989 Notification of Contract Execution,Mod 16,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20245F0471989-06-22022 June 1989 Fire Protection Review Rept Evaluation ML20247R3941989-05-16016 May 1989 Mod 15,extending Period of Performance,Providing Addl Work Re Training for NRC Inspectors & Supervisors,Changing NRC Project Officer & Adding TVA Project Manager & Increasing Contract Ceiling & Funding to Use of TVA Reactor.. ML20247R3851989-05-16016 May 1989 Notification of Contract Execution,Mod 15,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn,For Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva 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 ML20246B9731989-03-31031 March 1989 Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept ML20236B8051989-03-13013 March 1989 Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files ML18040A9251988-12-31031 December 1988 Conformance to Generic Ltr 83-28,Item 2.1 (Part 2),Reactor Trip Sys Vendor Interface,Susquehanna Steam Electric Station Units 1 & 2, Technical Evaluation Rept.Salp Input Also Encl ML18040A9221988-12-31031 December 1988 Conformance to Generic Ltr 83-28,Item 4.5.2,Susquehanna Steam Electric Station Units 1 & 2, Technical Evaluation Rept 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 ML20155B7531988-06-0101 June 1988 Corrected Mod 1,restoring Funds That Was Deobligated & Providing Final Increment of Funding to Contract,To Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee, Pilgrim & Seabrook Resident Sites ML20155B7391988-06-0101 June 1988 Notification of Contract Execution,Mod 1,to Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites. Contractor:New England Telephone Co ML20150D9091988-03-17017 March 1988 Mod 1,deobligating Funds from Total Obligated Amount of Contract & to Correct FIN Number,To Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites ML20150D9001988-03-17017 March 1988 Notification of Contract Execution,Mod 1,to Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites. Contractor:New England Telephone Co ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 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 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 ML20149F1691988-01-11011 January 1988 Contract: Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee,Pilgrim & Seabrook Resident Sites, Awarded to New England Bell Telephone Co ML20149F1311988-01-11011 January 1988 Notification of Contract Execution: Local Telephone Svc for Yankee Rowe,Vermont Yankee,Maine Yankee & Pilgrim & Seabrook Resident Sites, Awarded to New England Bell Telephone Co ML20236T7461987-11-24024 November 1987 Mod 7,extending Period of Performance Through 880930,adding Addl GE Simulator to Contract & Scheduling Four Simulator Courses Through FY88,to Dresden & Perry Simulator ML20236T7371987-11-24024 November 1987 Notification of Contract Execution,Mod 7,to Dresden & Perry Simulator. Contractor:Ge ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML20235V1521987-08-31031 August 1987 Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2 ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20237J1411987-08-17017 August 1987 Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 ML20236P2181987-08-10010 August 1987 Mod 1,increasing Total Amount of Contract,To Local Telephone Svc for Yankee Rowe,Vermont Yankee,Main Yankee, Pilgrim & Seabrook Resident Sites ML20236P2051987-08-10010 August 1987 Notification of Contract Execution,Mod 1,to Local Telephone Svc for Yankee Rowe,Vermont Yankee,Main Yankee,Pilgrim & Seabrook Resident Sites. Contractor:New England Bell Telephone Co ML17347A5931987-07-31031 July 1987 Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept ML20236P6401987-07-31031 July 1987 Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept ML20236D9181987-07-31031 July 1987 Methodology and Application of Surrogate Plant PRA Analysis to the Rancho Seco Power Plant.Task 1 - Analysis of ANO-1 and Oconee PRAs 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 ML20214R1481987-05-29029 May 1987 Notification of Contract Execution,Mod 12,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20214R1561987-05-29029 May 1987 Mod 12,providing Incremental Funds & Increasing Ceiling,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML18152A5831987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. ML20214R0681987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Arnold,Brunswick-1 & 2, 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 ML18150A1191987-04-30030 April 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2, Final Informal Rept 1999-12-31 |
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