Category:CONTRACTED REPORT - RTA
MONTHYEARML18039A7871999-01-31031 January 1999 Technical Evaluation Rept on Second 10-Year Interval Inservice Insp Program Plan, for Browns Ferry Nuclear Plant,Unit 3 ML20203J0921998-02-28028 February 1998 Technical Evaluation Rept on 'Submittal-Only' Review of IPEEE at McGuire Nuclear Station,Units 1 & 2, Final Rept ML20217K4621998-01-30030 January 1998 Technical Evaluation Rept on Second 10-Yr Interval ISI Program Plan:Tva,Sequoyah Nuclear Plant,Units 1 & 2 ML20107N0371996-02-29029 February 1996 Submittal-Only Review of McGuire Nuclear Station Individual Plant Exam of External Events, Draft Rept ML20107N0101996-02-29029 February 1996 Submittal-Only Review of Catawba Nuclear Station Individual Plant Exam of External Events, Draft Rept ML20092H1281995-08-31031 August 1995 Evaluation of Sequoyah Nuclear Plant Offsite Dose Calculation Manual,Rev 28 ML20076K9411994-09-30030 September 1994 Technical Evaluation Rept:Pumps & Valves Inservice Testing Program,Mcguire Nuclear Station,Units 1 & 2,Duke Power Co ML20072T9151994-08-31031 August 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Sequoyah-1/-2, Technical Evaluation Rept ML20072E0541994-06-30030 June 1994 Plant IPE,Front-End Review ML20069L8621994-05-31031 May 1994 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Mcguire Nuclear Power Plant ML20080E3711994-05-31031 May 1994 Technical Evaluation Rept on Second Ten-Year Interval Insp Program Plan ML20072E1221994-03-31031 March 1994 Plant Ipe,Submittal Human Reliability Analysis Final Rept ML20059C2031993-09-30030 September 1993 High Pressure Coolant Injection (HPCI) System RISK-BASED Inspection Guide for Browns Ferry Nuclear Power Station ML20071F8851993-08-31031 August 1993 Technical Evaluation Rept McGuire Nuclear Plant Individual Plant Exam Assessment of Human Reliability Analysis,Step 2 Review ML18037A4171993-07-31031 July 1993 Trip Rept: On-Site Analysis of Human Factors of Event at Browns Ferry 2 on May 11, 1993, Ari/Rpt ESF Actuation Due to Shutdown Overpressurization. ML20058L9641993-07-31031 July 1993 Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Browns Ferry Nuclear Plant,Units 1,2 & 3 ML18037A5211993-05-31031 May 1993 Technical Evaluation Rept on Second 10-Yr Interval Insp Program Plan. ML20072E1041993-01-20020 January 1993 Plant IPE,Back-End Submittal ML20087A5261991-12-31031 December 1991 Analysis of Bellows Expansion Joints in the Sequoyah Containment ML20091H0331991-12-10010 December 1991 Final, Technical Evaluation Rept,Mcguire Nuclear Station, Station Blackout Evaluation ML20086G5981991-10-31031 October 1991 Technical Evaluation:Core Thermal-Hydraulic Methodology Using VIPRE-01,Topical Rept DPC-NE-2004 ML20085M3861991-10-24024 October 1991 Final Technical Evaluation Rept,Sequoyah Nuclear Plant, Units 1 & 2 Station Blackout Evaluation ML20077E3661991-05-31031 May 1991 Final Review of LOCA Analysis for Duke Power Co,Catawba & McGuire Units W/B&W Fuel Co Reload Fuel BAW-10174,Rev 1 ML20066D2651990-12-31031 December 1990 Simplified Containment Event Tree Analysis for the Sequoyah Ice Condenser Containment ML20066D2731990-12-31031 December 1990 Evaluation of Severe Accident Risks: Sequoyah,Unit 1.Main Report ML20066D2821990-12-31031 December 1990 Evaluation of Severe Accident Risks: Sequoyah,Unit 1. Appendices ML20059E2841990-08-29029 August 1990 Emergency Preparedness Exercise for 900814-15, Final Rept Per Insp Repts 50-369/90-15 & 50-370/90-15 ML20082S0101990-08-13013 August 1990 Review of Inservice Testing Program for TVA Nuclear Power Plants ML20059H4591990-07-31031 July 1990 Risk-Based Insp Guide for Sequoyah Nuclear Power Station Final Rept, Informal Rept ML20043A2811990-04-30030 April 1990 Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events Appendices ML20043A3681990-04-30030 April 1990 Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events ML18033B3951989-12-31031 December 1989 Welding-Related Employee Concerns Evaluations, Technical Rept ML19332C9921989-11-30030 November 1989 Draft Risk-Based Insp Guide for Sequoyah Sequoyah Nuclear Power Station. ML20063P9121989-10-31031 October 1989 SAIC-88/1943, Technical Evaluation Rept,First Interval Inservice Insp Program,Mcguire Nuclear Station Units 1 & 2 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 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 ML20245J9261989-03-31031 March 1989 TMI Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing Sequoyah Nuclear Plant Units 1 & 2, 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 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 ML20154H3271988-08-23023 August 1988 Technical Evaluation Rept Re Requests for Relief,Pump & Valve Inservice Testing Program,Sequoyah Nuclear Plant, Units 1 & 2 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 ML20147C3231987-12-30030 December 1987 Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20236F3471987-09-18018 September 1987 Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. 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 1999-01-31
[Table view] Category:QUICK LOOK
MONTHYEARML18039A7871999-01-31031 January 1999 Technical Evaluation Rept on Second 10-Year Interval Inservice Insp Program Plan, for Browns Ferry Nuclear Plant,Unit 3 ML20203J0921998-02-28028 February 1998 Technical Evaluation Rept on 'Submittal-Only' Review of IPEEE at McGuire Nuclear Station,Units 1 & 2, Final Rept ML20217K4621998-01-30030 January 1998 Technical Evaluation Rept on Second 10-Yr Interval ISI Program Plan:Tva,Sequoyah Nuclear Plant,Units 1 & 2 ML20107N0371996-02-29029 February 1996 Submittal-Only Review of McGuire Nuclear Station Individual Plant Exam of External Events, Draft Rept ML20107N0101996-02-29029 February 1996 Submittal-Only Review of Catawba Nuclear Station Individual Plant Exam of External Events, Draft Rept ML20092H1281995-08-31031 August 1995 Evaluation of Sequoyah Nuclear Plant Offsite Dose Calculation Manual,Rev 28 ML20076K9411994-09-30030 September 1994 Technical Evaluation Rept:Pumps & Valves Inservice Testing Program,Mcguire Nuclear Station,Units 1 & 2,Duke Power Co ML20072T9151994-08-31031 August 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Sequoyah-1/-2, Technical Evaluation Rept ML20072E0541994-06-30030 June 1994 Plant IPE,Front-End Review ML20069L8621994-05-31031 May 1994 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Mcguire Nuclear Power Plant ML20080E3711994-05-31031 May 1994 Technical Evaluation Rept on Second Ten-Year Interval Insp Program Plan ML20072E1221994-03-31031 March 1994 Plant Ipe,Submittal Human Reliability Analysis Final Rept ML20059C2031993-09-30030 September 1993 High Pressure Coolant Injection (HPCI) System RISK-BASED Inspection Guide for Browns Ferry Nuclear Power Station ML20071F8851993-08-31031 August 1993 Technical Evaluation Rept McGuire Nuclear Plant Individual Plant Exam Assessment of Human Reliability Analysis,Step 2 Review ML18037A4171993-07-31031 July 1993 Trip Rept: On-Site Analysis of Human Factors of Event at Browns Ferry 2 on May 11, 1993, Ari/Rpt ESF Actuation Due to Shutdown Overpressurization. ML20058L9641993-07-31031 July 1993 Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Browns Ferry Nuclear Plant,Units 1,2 & 3 ML18037A5211993-05-31031 May 1993 Technical Evaluation Rept on Second 10-Yr Interval Insp Program Plan. ML20072E1041993-01-20020 January 1993 Plant IPE,Back-End Submittal ML20087A5261991-12-31031 December 1991 Analysis of Bellows Expansion Joints in the Sequoyah Containment ML20091H0331991-12-10010 December 1991 Final, Technical Evaluation Rept,Mcguire Nuclear Station, Station Blackout Evaluation ML20086G5981991-10-31031 October 1991 Technical Evaluation:Core Thermal-Hydraulic Methodology Using VIPRE-01,Topical Rept DPC-NE-2004 ML20085M3861991-10-24024 October 1991 Final Technical Evaluation Rept,Sequoyah Nuclear Plant, Units 1 & 2 Station Blackout Evaluation ML20077E3661991-05-31031 May 1991 Final Review of LOCA Analysis for Duke Power Co,Catawba & McGuire Units W/B&W Fuel Co Reload Fuel BAW-10174,Rev 1 ML20066D2651990-12-31031 December 1990 Simplified Containment Event Tree Analysis for the Sequoyah Ice Condenser Containment ML20066D2731990-12-31031 December 1990 Evaluation of Severe Accident Risks: Sequoyah,Unit 1.Main Report ML20066D2821990-12-31031 December 1990 Evaluation of Severe Accident Risks: Sequoyah,Unit 1. Appendices ML20059E2841990-08-29029 August 1990 Emergency Preparedness Exercise for 900814-15, Final Rept Per Insp Repts 50-369/90-15 & 50-370/90-15 ML20082S0101990-08-13013 August 1990 Review of Inservice Testing Program for TVA Nuclear Power Plants ML20059H4591990-07-31031 July 1990 Risk-Based Insp Guide for Sequoyah Nuclear Power Station Final Rept, Informal Rept ML20043A2811990-04-30030 April 1990 Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events Appendices ML20043A3681990-04-30030 April 1990 Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events ML18033B3951989-12-31031 December 1989 Welding-Related Employee Concerns Evaluations, Technical Rept ML19332C9921989-11-30030 November 1989 Draft Risk-Based Insp Guide for Sequoyah Sequoyah Nuclear Power Station. ML20063P9121989-10-31031 October 1989 SAIC-88/1943, Technical Evaluation Rept,First Interval Inservice Insp Program,Mcguire Nuclear Station Units 1 & 2 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 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 ML20245J9261989-03-31031 March 1989 TMI Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing Sequoyah Nuclear Plant Units 1 & 2, 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 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 ML20154H3271988-08-23023 August 1988 Technical Evaluation Rept Re Requests for Relief,Pump & Valve Inservice Testing Program,Sequoyah Nuclear Plant, Units 1 & 2 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 ML20147C3231987-12-30030 December 1987 Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20236F3471987-09-18018 September 1987 Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. 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 1999-01-31
[Table view] Category:ETC. (PERIODIC
MONTHYEARML18039A7871999-01-31031 January 1999 Technical Evaluation Rept on Second 10-Year Interval Inservice Insp Program Plan, for Browns Ferry Nuclear Plant,Unit 3 ML20203J0921998-02-28028 February 1998 Technical Evaluation Rept on 'Submittal-Only' Review of IPEEE at McGuire Nuclear Station,Units 1 & 2, Final Rept ML20217K4621998-01-30030 January 1998 Technical Evaluation Rept on Second 10-Yr Interval ISI Program Plan:Tva,Sequoyah Nuclear Plant,Units 1 & 2 ML20107N0371996-02-29029 February 1996 Submittal-Only Review of McGuire Nuclear Station Individual Plant Exam of External Events, Draft Rept ML20107N0101996-02-29029 February 1996 Submittal-Only Review of Catawba Nuclear Station Individual Plant Exam of External Events, Draft Rept ML20092H1281995-08-31031 August 1995 Evaluation of Sequoyah Nuclear Plant Offsite Dose Calculation Manual,Rev 28 ML20076K9411994-09-30030 September 1994 Technical Evaluation Rept:Pumps & Valves Inservice Testing Program,Mcguire Nuclear Station,Units 1 & 2,Duke Power Co ML20072T9151994-08-31031 August 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Sequoyah-1/-2, Technical Evaluation Rept ML20072E0541994-06-30030 June 1994 Plant IPE,Front-End Review ML20069L8621994-05-31031 May 1994 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Mcguire Nuclear Power Plant ML20080E3711994-05-31031 May 1994 Technical Evaluation Rept on Second Ten-Year Interval Insp Program Plan ML20072E1221994-03-31031 March 1994 Plant Ipe,Submittal Human Reliability Analysis Final Rept ML20059C2031993-09-30030 September 1993 High Pressure Coolant Injection (HPCI) System RISK-BASED Inspection Guide for Browns Ferry Nuclear Power Station ML20071F8851993-08-31031 August 1993 Technical Evaluation Rept McGuire Nuclear Plant Individual Plant Exam Assessment of Human Reliability Analysis,Step 2 Review ML18037A4171993-07-31031 July 1993 Trip Rept: On-Site Analysis of Human Factors of Event at Browns Ferry 2 on May 11, 1993, Ari/Rpt ESF Actuation Due to Shutdown Overpressurization. ML20058L9641993-07-31031 July 1993 Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Browns Ferry Nuclear Plant,Units 1,2 & 3 ML18037A5211993-05-31031 May 1993 Technical Evaluation Rept on Second 10-Yr Interval Insp Program Plan. ML20072E1041993-01-20020 January 1993 Plant IPE,Back-End Submittal ML20087A5261991-12-31031 December 1991 Analysis of Bellows Expansion Joints in the Sequoyah Containment ML20091H0331991-12-10010 December 1991 Final, Technical Evaluation Rept,Mcguire Nuclear Station, Station Blackout Evaluation ML20086G5981991-10-31031 October 1991 Technical Evaluation:Core Thermal-Hydraulic Methodology Using VIPRE-01,Topical Rept DPC-NE-2004 ML20085M3861991-10-24024 October 1991 Final Technical Evaluation Rept,Sequoyah Nuclear Plant, Units 1 & 2 Station Blackout Evaluation ML20077E3661991-05-31031 May 1991 Final Review of LOCA Analysis for Duke Power Co,Catawba & McGuire Units W/B&W Fuel Co Reload Fuel BAW-10174,Rev 1 ML20066D2651990-12-31031 December 1990 Simplified Containment Event Tree Analysis for the Sequoyah Ice Condenser Containment ML20066D2731990-12-31031 December 1990 Evaluation of Severe Accident Risks: Sequoyah,Unit 1.Main Report ML20066D2821990-12-31031 December 1990 Evaluation of Severe Accident Risks: Sequoyah,Unit 1. Appendices ML20059E2841990-08-29029 August 1990 Emergency Preparedness Exercise for 900814-15, Final Rept Per Insp Repts 50-369/90-15 & 50-370/90-15 ML20082S0101990-08-13013 August 1990 Review of Inservice Testing Program for TVA Nuclear Power Plants ML20059H4591990-07-31031 July 1990 Risk-Based Insp Guide for Sequoyah Nuclear Power Station Final Rept, Informal Rept ML20043A2811990-04-30030 April 1990 Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events Appendices ML20043A3681990-04-30030 April 1990 Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events ML18033B3951989-12-31031 December 1989 Welding-Related Employee Concerns Evaluations, Technical Rept ML19332C9921989-11-30030 November 1989 Draft Risk-Based Insp Guide for Sequoyah Sequoyah Nuclear Power Station. ML20063P9121989-10-31031 October 1989 SAIC-88/1943, Technical Evaluation Rept,First Interval Inservice Insp Program,Mcguire Nuclear Station Units 1 & 2 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 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 ML20245J9261989-03-31031 March 1989 TMI Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing Sequoyah Nuclear Plant Units 1 & 2, 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 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 ML20154H3271988-08-23023 August 1988 Technical Evaluation Rept Re Requests for Relief,Pump & Valve Inservice Testing Program,Sequoyah Nuclear Plant, Units 1 & 2 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 ML20147C3231987-12-30030 December 1987 Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20236F3471987-09-18018 September 1987 Requests for Relief,Pump & Valve Inservice Testing Program, Sequoyah Nuclear Plant,Units 1 & 2, Technical Evaluation Rept ML20235M3591987-08-31031 August 1987 Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept ML18040B1891987-08-31031 August 1987 Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. 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 1999-01-31
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML18039A7871999-01-31031 January 1999 Technical Evaluation Rept on Second 10-Year Interval Inservice Insp Program Plan, for Browns Ferry Nuclear Plant,Unit 3 ML20203J0921998-02-28028 February 1998 Technical Evaluation Rept on 'Submittal-Only' Review of IPEEE at McGuire Nuclear Station,Units 1 & 2, Final Rept ML20217K4621998-01-30030 January 1998 Technical Evaluation Rept on Second 10-Yr Interval ISI Program Plan:Tva,Sequoyah Nuclear Plant,Units 1 & 2 ML20107N0101996-02-29029 February 1996 Submittal-Only Review of Catawba Nuclear Station Individual Plant Exam of External Events, Draft Rept ML20107N0371996-02-29029 February 1996 Submittal-Only Review of McGuire Nuclear Station Individual Plant Exam of External Events, Draft Rept ML20092H1281995-08-31031 August 1995 Evaluation of Sequoyah Nuclear Plant Offsite Dose Calculation Manual,Rev 28 ML20076K9411994-09-30030 September 1994 Technical Evaluation Rept:Pumps & Valves Inservice Testing Program,Mcguire Nuclear Station,Units 1 & 2,Duke Power Co ML20072T9151994-08-31031 August 1994 Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Sequoyah-1/-2, Technical Evaluation Rept ML20072E0541994-06-30030 June 1994 Plant IPE,Front-End Review ML20069L8621994-05-31031 May 1994 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Mcguire Nuclear Power Plant ML20080E3711994-05-31031 May 1994 Technical Evaluation Rept on Second Ten-Year Interval Insp Program Plan ML20072E1221994-03-31031 March 1994 Plant Ipe,Submittal Human Reliability Analysis Final Rept ML20059C2031993-09-30030 September 1993 High Pressure Coolant Injection (HPCI) System RISK-BASED Inspection Guide for Browns Ferry Nuclear Power Station ML20071F8851993-08-31031 August 1993 Technical Evaluation Rept McGuire Nuclear Plant Individual Plant Exam Assessment of Human Reliability Analysis,Step 2 Review ML18037A4171993-07-31031 July 1993 Trip Rept: On-Site Analysis of Human Factors of Event at Browns Ferry 2 on May 11, 1993, Ari/Rpt ESF Actuation Due to Shutdown Overpressurization. ML20058L9641993-07-31031 July 1993 Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Browns Ferry Nuclear Plant,Units 1,2 & 3 ML18037A5211993-05-31031 May 1993 Technical Evaluation Rept on Second 10-Yr Interval Insp Program Plan. ML20072E1041993-01-20020 January 1993 Plant IPE,Back-End Submittal ML20141M2141992-03-23023 March 1992 Notification of Contract Execution,Task Order 2, IPE Reviews,Internal Events,Front End Only:Mcguire. Contractor: Science & Engineering Assocs,Inc ML20087A5261991-12-31031 December 1991 Analysis of Bellows Expansion Joints in the Sequoyah Containment ML20091H0331991-12-10010 December 1991 Final, Technical Evaluation Rept,Mcguire Nuclear Station, Station Blackout Evaluation ML20086G5981991-10-31031 October 1991 Technical Evaluation:Core Thermal-Hydraulic Methodology Using VIPRE-01,Topical Rept DPC-NE-2004 ML20085M3861991-10-24024 October 1991 Final Technical Evaluation Rept,Sequoyah Nuclear Plant, Units 1 & 2 Station Blackout Evaluation ML20077E3661991-05-31031 May 1991 Final Review of LOCA Analysis for Duke Power Co,Catawba & McGuire Units W/B&W Fuel Co Reload Fuel BAW-10174,Rev 1 ML20066D2651990-12-31031 December 1990 Simplified Containment Event Tree Analysis for the Sequoyah Ice Condenser Containment ML20066D2731990-12-31031 December 1990 Evaluation of Severe Accident Risks: Sequoyah,Unit 1.Main Report ML20066D2821990-12-31031 December 1990 Evaluation of Severe Accident Risks: Sequoyah,Unit 1. Appendices ML20059E2841990-08-29029 August 1990 Emergency Preparedness Exercise for 900814-15, Final Rept Per Insp Repts 50-369/90-15 & 50-370/90-15 ML20082S0101990-08-13013 August 1990 Review of Inservice Testing Program for TVA Nuclear Power Plants ML20059H4591990-07-31031 July 1990 Risk-Based Insp Guide for Sequoyah Nuclear Power Station Final Rept, Informal Rept ML20059A1221990-07-19019 July 1990 Notification of Contract Execution,Mod 20,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20059A1311990-07-19019 July 1990 Mod 20,revising Contract to Purchase Addl Training Aids,To Use to TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML20043A2811990-04-30030 April 1990 Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events Appendices ML20043A3681990-04-30030 April 1990 Analysis of Core Damage Frequency: Sequoyah,Unit 1,INTERNAL Events ML18033B3951989-12-31031 December 1989 Welding-Related Employee Concerns Evaluations, Technical Rept ML19332C9921989-11-30030 November 1989 Draft Risk-Based Insp Guide for Sequoyah Sequoyah Nuclear Power Station. ML20063P9121989-10-31031 October 1989 SAIC-88/1943, Technical Evaluation Rept,First Interval Inservice Insp Program,Mcguire Nuclear Station Units 1 & 2 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 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 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 ML20245J9261989-03-31031 March 1989 TMI Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing Sequoyah Nuclear Plant Units 1 & 2, 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 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 ML20154H3271988-08-23023 August 1988 Technical Evaluation Rept Re Requests for Relief,Pump & Valve Inservice Testing Program,Sequoyah Nuclear Plant, Units 1 & 2 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 1999-01-31
[Table view] |