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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 ML20072E0541994-06-30030 June 1994 Plant IPE,Front-End Review 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 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 ML20082S0101990-08-13013 August 1990 Review of Inservice Testing Program for TVA Nuclear Power Plants ML18033B3951989-12-31031 December 1989 Welding-Related Employee Concerns Evaluations, Technical Rept ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20234C1121987-05-31031 May 1987 Severe Accident Sequence Analysis Program - Anticipated Transient Without Scram Simulations for Browns Ferry Nuclear Plant Unit 1 ML20213A0341987-03-31031 March 1987 Demonstration Testing of a Surveillance Robot at Browns Ferry Nuclear Plant.Analysis of Costs and Benefits ML20214A7881987-02-28028 February 1987 RAMONA-3B Calculations for Browns Ferry ATWS Study ML20214H1101986-07-17017 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Browns Ferry Nuclear Plant, Supplementary Technical Evaluation Rept ML18029A3541984-12-31031 December 1984 Conformance to Reg Guide 1.97,Browns Ferry Nuclear Plant, Units 1,2 & 3, Interim Rept ML20093E2061984-09-30030 September 1984 Noble Gas,Iodine,And Cesium Transport in a Postulated Loss of Decay Heat Removal Accident at Browns Ferry ML18029A5391984-09-30030 September 1984 Technical Evaluation of Browns Ferry Nuclear Plant, Plant-Unique Analysis Rept. ML20096G6761984-07-31031 July 1984 ATWS at Browns Ferry Unit One - Accident Sequence Analysis ML20090H6281984-03-14014 March 1984 Control of Heavy Loads (C-10),Browns Ferry Nuclear Power Station Units 1,2 & 3, Technical Evaluation Rept ML20090H6211984-03-0101 March 1984 Control of Heavy Loads-Phase Ii,Browns Ferry Nuclear Power Station Units 1,2 & 3, Draft Technical Evaluation Rept ML20080F2981983-10-31031 October 1983 Rept Concerning Effects of Control Sys Failures on Overfill & Overcooling Events at Browns Ferry, Interim Rept ML20081J7021983-10-31031 October 1983 SBLOCA Outside Containment at Browns Ferry Unit One.Volume 2.Iodine,Cesium,And Noble Gas Distribution and Release ML20081J7291983-10-31031 October 1983 the Effect of SMALL-CAPACITY,HIGH-PRESSURE Injection Systems on Tquv Sequences at Browns Ferry Unit One ML20085H8081983-09-26026 September 1983 Masonry Wall Design (B-59),TVA Browns Ferry Nuclear Plant, Units 1,2 & 3, Technical Evaluation Rept ML18094A0781983-08-30030 August 1983 Rev 1 to Technical Evaluation of Integrity of Browns Ferry 1,2 & 3 Reactor Coolant Boundary Piping Sys. ML20072F6591983-06-30030 June 1983 Loss of DHR Sequences at Browns Ferry Unit One - Accident Sequence Analysis ML20080E0211983-05-31031 May 1983 Other Transients Failure Modes & Effects Analysis & Rejected Sys Justification Rept, Preliminary Rept ML20024A0041983-04-0505 April 1983 Control of Heavy Loads (C-10),TVA,Browns Ferry Nuclear Power Station,Units 1,2 & 3, Draft Technical Evaluation Rept ML20126F6151983-02-28028 February 1983 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Feb 1983.Incomplete Progress Rept for Mar 1983 Encl ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20070D1611982-11-30030 November 1982 SBLOCA Outside Containment at Browns Ferry Unit 1-ACCIDENT Sequence Analysis ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20065L9681982-09-30030 September 1982 Station Blackout at Browns Ferry Unit ONE-IODINE and Noble Gas Distribution and Release ML20066B2161982-09-30030 September 1982 Station Blackout Transient at Browns Ferry Unit 1 Plant, Severe Accident Sequence Analysis ML20023A5001982-09-24024 September 1982 ECCS Repts (F-47) TMI Action Plan Requirements, Technical Evaluation Rept.Actual Rept Number TER-C5506-171/172/173 ML18025B8801982-08-31031 August 1982 Interim Reliability Evaluation Program:Analysis of the Browns Ferry,Unit 1,NUCLEAR Plant.Appendix C-Sequence Quantification.Docket No. 50-259.(Tennessee Valley Authority) ML18025B8781982-08-31031 August 1982 Interim Reliability Evaluation Program:Analysis of the Browns Ferry,Unit 1,NUCLEAR Plant.Appendix A-Event Trees. Docket No. 50-259.(Tennessee Valley Authority) ML18025B8771982-08-31031 August 1982 Interim Reliability Evaluation Program:Analysis of the Browns Ferry,Unit 1,NUCLEAR Plant.Appendix B-System Descriptions and Fault Trees.Docket No. 50-259.(Tennessee Valley Authority) ML18025B8761982-08-31031 August 1982 Interim Reliability Evaluation Program:Analysis of the Browns Ferry,Unit 1,NUCLEAR Plant.Docket No. 50-259. (Tennessee Valley Authority) ML20023B0451982-08-31031 August 1982 RELAP5 Analysis of Break in Scram Discharge Vol at Browns Ferry Unit 1 Plant, Interim Rept ML20069D4121982-08-0303 August 1982 Control of Heavy Loads (C-10),Browns Ferry Nuclear Power Station Units 1,2 & 3, Draft Technical Evaluation Rept ML20076B5891982-07-30030 July 1982 Inservice Insp Program, Technical Evaluation Rept ML20062B5281982-07-0707 July 1982 Control of Heavy Loads, Draft Technical Evaluation Rept ML20062H2361982-06-0202 June 1982 RCS Vents, Technical Evaluation Rept ML20041D6471982-02-28028 February 1982 Adequacy of Station Electric Distribution Sys Voltages, Browns Ferry Nuclear Plant,Unit 3, Informal Rept ML20041D6451982-02-28028 February 1982 Degraded Grid Protection for Class IE Power Sys,Browns Ferry Nuclear Plant,Unit 3, Informal Rept ML20039D7001981-11-30030 November 1981 Station Blackout at Browns Ferry Unit One - Accident Sequence Analysis ML19240B9951981-03-31031 March 1981 Proposed Changes for Main Steam Line Isolation & Suppression Chamber Instrumentation Requirements, Technical Evaluation Rept ML20004D2231981-01-31031 January 1981 Equipment Environ Qualification,Browns Ferry Unit 3, Technical Evaluation Rept 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 ML20072E0541994-06-30030 June 1994 Plant IPE,Front-End Review 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 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 ML20082S0101990-08-13013 August 1990 Review of Inservice Testing Program for TVA Nuclear Power Plants ML18033B3951989-12-31031 December 1989 Welding-Related Employee Concerns Evaluations, Technical Rept ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20234C1121987-05-31031 May 1987 Severe Accident Sequence Analysis Program - Anticipated Transient Without Scram Simulations for Browns Ferry Nuclear Plant Unit 1 ML20213A0341987-03-31031 March 1987 Demonstration Testing of a Surveillance Robot at Browns Ferry Nuclear Plant.Analysis of Costs and Benefits ML20214A7881987-02-28028 February 1987 RAMONA-3B Calculations for Browns Ferry ATWS Study ML20214H1101986-07-17017 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Browns Ferry Nuclear Plant, Supplementary Technical Evaluation Rept ML18029A3541984-12-31031 December 1984 Conformance to Reg Guide 1.97,Browns Ferry Nuclear Plant, Units 1,2 & 3, Interim Rept ML20093E2061984-09-30030 September 1984 Noble Gas,Iodine,And Cesium Transport in a Postulated Loss of Decay Heat Removal Accident at Browns Ferry ML18029A5391984-09-30030 September 1984 Technical Evaluation of Browns Ferry Nuclear Plant, Plant-Unique Analysis Rept. ML20096G6761984-07-31031 July 1984 ATWS at Browns Ferry Unit One - Accident Sequence Analysis ML20090H6281984-03-14014 March 1984 Control of Heavy Loads (C-10),Browns Ferry Nuclear Power Station Units 1,2 & 3, Technical Evaluation Rept ML20090H6211984-03-0101 March 1984 Control of Heavy Loads-Phase Ii,Browns Ferry Nuclear Power Station Units 1,2 & 3, Draft Technical Evaluation Rept ML20080F2981983-10-31031 October 1983 Rept Concerning Effects of Control Sys Failures on Overfill & Overcooling Events at Browns Ferry, Interim Rept ML20081J7021983-10-31031 October 1983 SBLOCA Outside Containment at Browns Ferry Unit One.Volume 2.Iodine,Cesium,And Noble Gas Distribution and Release ML20081J7291983-10-31031 October 1983 the Effect of SMALL-CAPACITY,HIGH-PRESSURE Injection Systems on Tquv Sequences at Browns Ferry Unit One ML20085H8081983-09-26026 September 1983 Masonry Wall Design (B-59),TVA Browns Ferry Nuclear Plant, Units 1,2 & 3, Technical Evaluation Rept ML18094A0781983-08-30030 August 1983 Rev 1 to Technical Evaluation of Integrity of Browns Ferry 1,2 & 3 Reactor Coolant Boundary Piping Sys. ML20072F6591983-06-30030 June 1983 Loss of DHR Sequences at Browns Ferry Unit One - Accident Sequence Analysis ML20080E0211983-05-31031 May 1983 Other Transients Failure Modes & Effects Analysis & Rejected Sys Justification Rept, Preliminary Rept ML20024A0041983-04-0505 April 1983 Control of Heavy Loads (C-10),TVA,Browns Ferry Nuclear Power Station,Units 1,2 & 3, Draft Technical Evaluation Rept ML20126F6151983-02-28028 February 1983 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Feb 1983.Incomplete Progress Rept for Mar 1983 Encl ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20070D1611982-11-30030 November 1982 SBLOCA Outside Containment at Browns Ferry Unit 1-ACCIDENT Sequence Analysis ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20065L9681982-09-30030 September 1982 Station Blackout at Browns Ferry Unit ONE-IODINE and Noble Gas Distribution and Release ML20066B2161982-09-30030 September 1982 Station Blackout Transient at Browns Ferry Unit 1 Plant, Severe Accident Sequence Analysis ML20023A5001982-09-24024 September 1982 ECCS Repts (F-47) TMI Action Plan Requirements, Technical Evaluation Rept.Actual Rept Number TER-C5506-171/172/173 ML18025B8801982-08-31031 August 1982 Interim Reliability Evaluation Program:Analysis of the Browns Ferry,Unit 1,NUCLEAR Plant.Appendix C-Sequence Quantification.Docket No. 50-259.(Tennessee Valley Authority) ML18025B8781982-08-31031 August 1982 Interim Reliability Evaluation Program:Analysis of the Browns Ferry,Unit 1,NUCLEAR Plant.Appendix A-Event Trees. Docket No. 50-259.(Tennessee Valley Authority) ML18025B8771982-08-31031 August 1982 Interim Reliability Evaluation Program:Analysis of the Browns Ferry,Unit 1,NUCLEAR Plant.Appendix B-System Descriptions and Fault Trees.Docket No. 50-259.(Tennessee Valley Authority) ML18025B8761982-08-31031 August 1982 Interim Reliability Evaluation Program:Analysis of the Browns Ferry,Unit 1,NUCLEAR Plant.Docket No. 50-259. (Tennessee Valley Authority) ML20023B0451982-08-31031 August 1982 RELAP5 Analysis of Break in Scram Discharge Vol at Browns Ferry Unit 1 Plant, Interim Rept ML20069D4121982-08-0303 August 1982 Control of Heavy Loads (C-10),Browns Ferry Nuclear Power Station Units 1,2 & 3, Draft Technical Evaluation Rept ML20076B5891982-07-30030 July 1982 Inservice Insp Program, Technical Evaluation Rept ML20062B5281982-07-0707 July 1982 Control of Heavy Loads, Draft Technical Evaluation Rept ML20062H2361982-06-0202 June 1982 RCS Vents, Technical Evaluation Rept ML20041D6471982-02-28028 February 1982 Adequacy of Station Electric Distribution Sys Voltages, Browns Ferry Nuclear Plant,Unit 3, Informal Rept ML20041D6451982-02-28028 February 1982 Degraded Grid Protection for Class IE Power Sys,Browns Ferry Nuclear Plant,Unit 3, Informal Rept ML20039D7001981-11-30030 November 1981 Station Blackout at Browns Ferry Unit One - Accident Sequence Analysis ML19240B9951981-03-31031 March 1981 Proposed Changes for Main Steam Line Isolation & Suppression Chamber Instrumentation Requirements, Technical Evaluation Rept ML20004D2231981-01-31031 January 1981 Equipment Environ Qualification,Browns Ferry Unit 3, Technical Evaluation Rept 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 ML20072E0541994-06-30030 June 1994 Plant IPE,Front-End Review 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 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 ML20082S0101990-08-13013 August 1990 Review of Inservice Testing Program for TVA Nuclear Power Plants ML18033B3951989-12-31031 December 1989 Welding-Related Employee Concerns Evaluations, Technical Rept ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20234C1121987-05-31031 May 1987 Severe Accident Sequence Analysis Program - Anticipated Transient Without Scram Simulations for Browns Ferry Nuclear Plant Unit 1 ML20213A0341987-03-31031 March 1987 Demonstration Testing of a Surveillance Robot at Browns Ferry Nuclear Plant.Analysis of Costs and Benefits ML20214A7881987-02-28028 February 1987 RAMONA-3B Calculations for Browns Ferry ATWS Study ML20214H1101986-07-17017 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Browns Ferry Nuclear Plant, Supplementary Technical Evaluation Rept ML18029A3541984-12-31031 December 1984 Conformance to Reg Guide 1.97,Browns Ferry Nuclear Plant, Units 1,2 & 3, Interim Rept ML20093E2061984-09-30030 September 1984 Noble Gas,Iodine,And Cesium Transport in a Postulated Loss of Decay Heat Removal Accident at Browns Ferry ML18029A5391984-09-30030 September 1984 Technical Evaluation of Browns Ferry Nuclear Plant, Plant-Unique Analysis Rept. ML20096G6761984-07-31031 July 1984 ATWS at Browns Ferry Unit One - Accident Sequence Analysis ML20090H6281984-03-14014 March 1984 Control of Heavy Loads (C-10),Browns Ferry Nuclear Power Station Units 1,2 & 3, Technical Evaluation Rept ML20090H6211984-03-0101 March 1984 Control of Heavy Loads-Phase Ii,Browns Ferry Nuclear Power Station Units 1,2 & 3, Draft Technical Evaluation Rept ML20080F2981983-10-31031 October 1983 Rept Concerning Effects of Control Sys Failures on Overfill & Overcooling Events at Browns Ferry, Interim Rept ML20081J7021983-10-31031 October 1983 SBLOCA Outside Containment at Browns Ferry Unit One.Volume 2.Iodine,Cesium,And Noble Gas Distribution and Release ML20081J7291983-10-31031 October 1983 the Effect of SMALL-CAPACITY,HIGH-PRESSURE Injection Systems on Tquv Sequences at Browns Ferry Unit One ML20085H8081983-09-26026 September 1983 Masonry Wall Design (B-59),TVA Browns Ferry Nuclear Plant, Units 1,2 & 3, Technical Evaluation Rept ML18094A0781983-08-30030 August 1983 Rev 1 to Technical Evaluation of Integrity of Browns Ferry 1,2 & 3 Reactor Coolant Boundary Piping Sys. ML20072F6591983-06-30030 June 1983 Loss of DHR Sequences at Browns Ferry Unit One - Accident Sequence Analysis ML20080E0211983-05-31031 May 1983 Other Transients Failure Modes & Effects Analysis & Rejected Sys Justification Rept, Preliminary Rept ML20024A0041983-04-0505 April 1983 Control of Heavy Loads (C-10),TVA,Browns Ferry Nuclear Power Station,Units 1,2 & 3, Draft Technical Evaluation Rept ML20126F6151983-02-28028 February 1983 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Feb 1983.Incomplete Progress Rept for Mar 1983 Encl ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20070D1611982-11-30030 November 1982 SBLOCA Outside Containment at Browns Ferry Unit 1-ACCIDENT Sequence Analysis ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20065L9681982-09-30030 September 1982 Station Blackout at Browns Ferry Unit ONE-IODINE and Noble Gas Distribution and Release ML20066B2161982-09-30030 September 1982 Station Blackout Transient at Browns Ferry Unit 1 Plant, Severe Accident Sequence Analysis ML20023A5001982-09-24024 September 1982 ECCS Repts (F-47) TMI Action Plan Requirements, Technical Evaluation Rept.Actual Rept Number TER-C5506-171/172/173 ML18025B8801982-08-31031 August 1982 Interim Reliability Evaluation Program:Analysis of the Browns Ferry,Unit 1,NUCLEAR Plant.Appendix C-Sequence Quantification.Docket No. 50-259.(Tennessee Valley Authority) ML18025B8781982-08-31031 August 1982 Interim Reliability Evaluation Program:Analysis of the Browns Ferry,Unit 1,NUCLEAR Plant.Appendix A-Event Trees. Docket No. 50-259.(Tennessee Valley Authority) ML18025B8771982-08-31031 August 1982 Interim Reliability Evaluation Program:Analysis of the Browns Ferry,Unit 1,NUCLEAR Plant.Appendix B-System Descriptions and Fault Trees.Docket No. 50-259.(Tennessee Valley Authority) ML18025B8761982-08-31031 August 1982 Interim Reliability Evaluation Program:Analysis of the Browns Ferry,Unit 1,NUCLEAR Plant.Docket No. 50-259. (Tennessee Valley Authority) ML20023B0451982-08-31031 August 1982 RELAP5 Analysis of Break in Scram Discharge Vol at Browns Ferry Unit 1 Plant, Interim Rept ML20069D4121982-08-0303 August 1982 Control of Heavy Loads (C-10),Browns Ferry Nuclear Power Station Units 1,2 & 3, Draft Technical Evaluation Rept ML20076B5891982-07-30030 July 1982 Inservice Insp Program, Technical Evaluation Rept ML20062B5281982-07-0707 July 1982 Control of Heavy Loads, Draft Technical Evaluation Rept ML20062H2361982-06-0202 June 1982 RCS Vents, Technical Evaluation Rept ML20041D6471982-02-28028 February 1982 Adequacy of Station Electric Distribution Sys Voltages, Browns Ferry Nuclear Plant,Unit 3, Informal Rept ML20041D6451982-02-28028 February 1982 Degraded Grid Protection for Class IE Power Sys,Browns Ferry Nuclear Plant,Unit 3, Informal Rept ML20039D7001981-11-30030 November 1981 Station Blackout at Browns Ferry Unit One - Accident Sequence Analysis ML19240B9951981-03-31031 March 1981 Proposed Changes for Main Steam Line Isolation & Suppression Chamber Instrumentation Requirements, Technical Evaluation Rept ML20004D2231981-01-31031 January 1981 Equipment Environ Qualification,Browns Ferry Unit 3, Technical Evaluation Rept 1999-01-31
[Table view] Category:NUREG REPORTS
MONTHYEARML20059C2031993-09-30030 September 1993 High Pressure Coolant Injection (HPCI) System RISK-BASED Inspection Guide for Browns Ferry Nuclear Power Station ML20234C1121987-05-31031 May 1987 Severe Accident Sequence Analysis Program - Anticipated Transient Without Scram Simulations for Browns Ferry Nuclear Plant Unit 1 ML20213A0341987-03-31031 March 1987 Demonstration Testing of a Surveillance Robot at Browns Ferry Nuclear Plant.Analysis of Costs and Benefits ML20214A7881987-02-28028 February 1987 RAMONA-3B Calculations for Browns Ferry ATWS Study ML20093E2061984-09-30030 September 1984 Noble Gas,Iodine,And Cesium Transport in a Postulated Loss of Decay Heat Removal Accident at Browns Ferry ML20096G6761984-07-31031 July 1984 ATWS at Browns Ferry Unit One - Accident Sequence Analysis ML20081J7291983-10-31031 October 1983 the Effect of SMALL-CAPACITY,HIGH-PRESSURE Injection Systems on Tquv Sequences at Browns Ferry Unit One ML20081J7021983-10-31031 October 1983 SBLOCA Outside Containment at Browns Ferry Unit One.Volume 2.Iodine,Cesium,And Noble Gas Distribution and Release ML20072F6591983-06-30030 June 1983 Loss of DHR Sequences at Browns Ferry Unit One - Accident Sequence Analysis ML20070D1611982-11-30030 November 1982 SBLOCA Outside Containment at Browns Ferry Unit 1-ACCIDENT Sequence Analysis ML20065L9681982-09-30030 September 1982 Station Blackout at Browns Ferry Unit ONE-IODINE and Noble Gas Distribution and Release ML18025B8801982-08-31031 August 1982 Interim Reliability Evaluation Program:Analysis of the Browns Ferry,Unit 1,NUCLEAR Plant.Appendix C-Sequence Quantification.Docket No. 50-259.(Tennessee Valley Authority) ML18025B8761982-08-31031 August 1982 Interim Reliability Evaluation Program:Analysis of the Browns Ferry,Unit 1,NUCLEAR Plant.Docket No. 50-259. (Tennessee Valley Authority) ML18025B8771982-08-31031 August 1982 Interim Reliability Evaluation Program:Analysis of the Browns Ferry,Unit 1,NUCLEAR Plant.Appendix B-System Descriptions and Fault Trees.Docket No. 50-259.(Tennessee Valley Authority) ML18025B8781982-08-31031 August 1982 Interim Reliability Evaluation Program:Analysis of the Browns Ferry,Unit 1,NUCLEAR Plant.Appendix A-Event Trees. Docket No. 50-259.(Tennessee Valley Authority) ML20039D7001981-11-30030 November 1981 Station Blackout at Browns Ferry Unit One - Accident Sequence Analysis ML20126D2941980-02-29029 February 1980 Confirmation of Original Qualification Test for Electrical Connectors Used at Facility, Suppl ML19309G2041979-12-31031 December 1979 Confirmation of Original Qualification Test for Electrical Connectors Used at Browns Ferry Nuclear Power Plant Unit 3. ML20126F1581976-02-28028 February 1976 Recommendations Related to Browns Ferry Fire 1993-09-30
[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 ML20072E0541994-06-30030 June 1994 Plant IPE,Front-End Review 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 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 ML20082S0101990-08-13013 August 1990 Review of Inservice Testing Program for TVA Nuclear Power Plants 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 ML18033B3951989-12-31031 December 1989 Welding-Related Employee Concerns Evaluations, Technical 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 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 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.. ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20234C1121987-05-31031 May 1987 Severe Accident Sequence Analysis Program - Anticipated Transient Without Scram Simulations for Browns Ferry Nuclear Plant Unit 1 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 ML20206G6381987-04-0808 April 1987 Mod 11,recognizing Administrative Changes Due to NRC Reorganization,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML20206G5861987-04-0808 April 1987 Notification of Contract Execution,Mod 11,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Brown Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20213A0341987-03-31031 March 1987 Demonstration Testing of a Surveillance Robot at Browns Ferry Nuclear Plant.Analysis of Costs and Benefits ML20214A7881987-02-28028 February 1987 RAMONA-3B Calculations for Browns Ferry ATWS Study ML20211E2601987-02-13013 February 1987 Notification of Contract Execution,Mod 10,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20211E2961987-02-13013 February 1987 Mod 10,providing Addl Work Entailing Training for NRC Inspectors & Supervisors,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry, Sequoyah & Bellefonte Simulators ML20210G4871986-09-19019 September 1986 Notification of Contract Execution,Mod 9,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20210G5571986-09-19019 September 1986 Mod 9,providing Incremental Funds,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML20214T1291986-09-0404 September 1986 Notification of Contract Execution,Mod 6,to Use of TVA Reactor Simulator Facilities of Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20214T1531986-09-0404 September 1986 Mod 6,providing for Lease of Yellow Creek Model to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML20206M1201986-08-15015 August 1986 Notification of Contract Execution,Mod 7,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20206M1321986-08-15015 August 1986 Mod 7,providing Cost Estimate for Leasing of Simulators for Extended Period of Performance,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on the Browns Ferry,Sequoyah & Bellefonte Simulators ML20205D0081986-08-0606 August 1986 Mod 8,providing Incremental Funds,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators ML20205C9761986-08-0606 August 1986 Notification of Contract Execution,Mod 8,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20214H1101986-07-17017 July 1986 Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Browns Ferry Nuclear Plant, Supplementary Technical Evaluation Rept ML20136H6251985-12-23023 December 1985 Mod 5,extending Period of Performance to 880930 & Providing Incremental Funds,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry, Sequoyah & Bellefonte Simulators ML20136H6031985-12-23023 December 1985 Notification of Contract Execution,Mod 5,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20205C2321985-09-11011 September 1985 Notification of Contract Execution,Mod 4,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Brown'S Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML20205C2451985-09-11011 September 1985 Mod 4,increasing Funding to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Brown'S Ferry, Sequoyah & Bellefonte Simulators ML20135J0431985-09-0303 September 1985 Notification of Contract Execution,Mod 3,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva ML18029A3541984-12-31031 December 1984 Conformance to Reg Guide 1.97,Browns Ferry Nuclear Plant, Units 1,2 & 3, Interim Rept ML20093E2061984-09-30030 September 1984 Noble Gas,Iodine,And Cesium Transport in a Postulated Loss of Decay Heat Removal Accident at Browns Ferry ML18029A5391984-09-30030 September 1984 Technical Evaluation of Browns Ferry Nuclear Plant, Plant-Unique Analysis Rept. ML20096G6761984-07-31031 July 1984 ATWS at Browns Ferry Unit One - Accident Sequence Analysis ML20090H6281984-03-14014 March 1984 Control of Heavy Loads (C-10),Browns Ferry Nuclear Power Station Units 1,2 & 3, Technical Evaluation Rept ML20090H6211984-03-0101 March 1984 Control of Heavy Loads-Phase Ii,Browns Ferry Nuclear Power Station Units 1,2 & 3, Draft Technical Evaluation Rept ML20081J7291983-10-31031 October 1983 the Effect of SMALL-CAPACITY,HIGH-PRESSURE Injection Systems on Tquv Sequences at Browns Ferry Unit One ML20081J7021983-10-31031 October 1983 SBLOCA Outside Containment at Browns Ferry Unit One.Volume 2.Iodine,Cesium,And Noble Gas Distribution and Release ML20080F2981983-10-31031 October 1983 Rept Concerning Effects of Control Sys Failures on Overfill & Overcooling Events at Browns Ferry, Interim Rept ML20085H8081983-09-26026 September 1983 Masonry Wall Design (B-59),TVA Browns Ferry Nuclear Plant, Units 1,2 & 3, Technical Evaluation Rept 1999-01-31
[Table view] |
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Prepared for U. S. NUCLEAR REGULATORY COMMISSION
NOTICE This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of su:h use, or any information, apparatus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights.
The views expressed in this report are not necessarily those of the U. S. Nuclear Regulatory Commission.
Available from National Technical Information Service Springfield, VA 22161
i NUREG/CR-1191 SAND 79-2311 RV CONFIRMATION OF THE ORIGINAL QUALIFICATION TEST FOR ELECTRICAL CONNECTORS USED AT BROWNS FERRY NUCLEAR POWER PLANT UNIT 3 Lloyd L. Bonzon William H. Buckalew Douglas W. Dugan Frank V. Thome December 1979 Sandia Laboratories Albuquerque, NM 87185 operated by Sandia Corporation for the U.S. Department of Energy Prepared for Research Support Branch Of fice of Water Reactor Safety Research U.S. Nuclear Regulatory Commission Washington, DC 20555 Under Interagency Agreement DOE 40-550-75 NRC Fin No. A-1051-0 4
3-4
CONTENTS l
Page l
- 1. Background, Program Objective 7
- 2. Test Items Descriptions and Assembly 9
- 3. Description of Test Profiles- 10 3.1 Radiation 11 l 3.2 Temperature Aging 12 3.3 Accident Test 13
- 4. Test Results, Conclusions 15 l
l ILLUSTRATIONS Figure ,
i
- 1. View of Connector Boxes in Irradiation Cell 12 l
- 2. Oven and Associated Controller With Connector Bcxes In-Place in the Oven 14
- 3. Specified BF3-Connector Accident Test Profile and Data From November 1 and 2,1979 Test 16 j
- 4. Posttests Disassembly of 250-Vdc Connectors 17
)
- 5. Posttests Disassembly of 480-Vac Connectors 18 5-6
I CONFIRMATION OF THE ORICINAL QUALIFICATION TEST FOR ELECTRICAL CONNECTORS USED 1 AT BROWNS FERRY NUCLEAR POWER PLANT UNIT 3
- 1. Background , Program Objective Following the Union of Concerned Scientist's petition of November 4, 1977, the NRC Commissioners directed the NRC staff to:
" Arrange for a repeat of the tests to obtain data for the verification of current methodology for environ-mental qualification of electrical canponents. These tests should be performed with a representative sample of commercially available electrical connectors quali-fied in accordance with IEEE-323 (1974) and in use in nuclear power reactor safety systems. When avail- )
able, the test results are to be promptly provided to the Commission." .
The NRC staf f interpreted this action to be aimed at providing information on the methodology of qualification testing using electrical connectors which meet the provisions of IEEE-323. Since no connectors in use at that time had been actually qualified to IEEE-323-1974 (a relatively new standard), the staff responded by directing that electrical connectors previously qualified by licensees for use in operating plants be tested in accordance with the provisions of IEE-323-1971.
To the extent practicable, connector assemblies were to be subjected to the actual aging, radiation, and LOCA-simulation tests for which the ~
connector assemblies had been qualified. In a letter dated May 22, 1978, 7
1 i.
D. G. Mcdonald (SEP/ DOR) to R. Feit (RA/RSR), DOR and IE recommended that the following plants / connectors be considered for testing:
BWR (a) Peach Bottom - Pyle National Connectors; or (b) Browns Ferry - Bendix Connectors PWR (a) Palisade: - Viking Connectors ; or (b) Oconee - Viking Connectors flowever, other plants or connectors would also be appropriate due to ". . .
availability of the connectors to be tested, extensive procurement t ime ,
or other constraints."
From that date, Inspection and En forcement (IE) staf f evaluated some of the various utilities' connector hardware and qualification documents and directed that Sandia proceed with the first test in this series using Browns Ferry-Bendix (BF3) connectors. The principal objective was that the test was to duplicate, as closely as practicable, the actual Browns Ferry Connector tests; it is understood that these original tests were intended to conform to the requirements of IEEE-323-71, with the addition o f a (Browns Ferry specified) thermal aging preconditioning requirement.
The order for the connector hardware was placed through a Bendix-authorized distributor on August- 2,1978 with delivery completed on November 1, 1978. Concurrently, Draf t 1 of' the Sandia-generated impl e-menting test plan was forwarded to NRC staff, for review and approval, on I August 11, 1978. Based on staf f comments, Draft 2 of the plan was sub-l
'mitted on February 16, 1979 followed by Draft 3 on May 1 and Draft 4 on l
l August 30, r
l 8
- r
i The test plan specifically applied to the Browns Ferry Unit 3 (BF3)
, connector assemblies ; the applicable (background) documents for this test plan are:
(a) Tennessee Valley Authority, Purchase Requisition 150639, dated April 18, 1978.
(b) " Assembling Browns Ferry Nuclear Plant Bendix Connectors ,"
dated June 22, 1978.
(c) "Te s t Procedure for Browns Ferry Bendix Connectors, Revision," undated.
i The primary document, which the test plan intended to duplicate is:
1 4
(d) " Qualification Test for Electrical Connectors Used at Browns Ferry Nuclear Power Plant Unit 3," Report 4
No. 43854-2, Wyle Laboratories , March 28, 1978.
i
-2. Test Items Descriptions and Assembly Three each of two different types of electrical connectors were tested. Both types are manufactured by Bendix and used inside containment at Browns Ferry, Unit 3 (BF3), operated by the Tennessee Valley Authority (TVA).
Max im um Operating Identification Operating Current Qty, Manu fac ture r Numbers Voltage (A) 3 Bendix Plug: 250 Vdc 1.0 10-214628-51S Receptacle:
10-214028-51P 3 Bendix Plug: 480 Vac 17.5 10-214636-78S ,
Receptacle: l 10-214036-78P' l l
l These Bendix connectors were purchased by Sandia through a Bendix-authorized distributor. Electric cable was furnished by TVA _ from spare 9
cable of the same type used at BF3. The Bendix 250-Vdc connector assemblies consisted of wire size No. 12 CPJ cable on the plug end and wire size No. 12 Vulkene cable on the receptacle end of the connectors.
The Bendix 480-Vac connector assemblies consisted of wire size No. 10 CPJ cable on the plug end and wire size No. 10 vulkene cable on the receptacle end of the connectors. CPJ and Vulkene cables consist of cross-linked polyethylene with the CPJ cable having a PVC insulating jacket.
Construction of six of each of the connector assemblies was conducted by BF3 staf f using an assembly and potting procedure developed by BF3 staf f (used in field assembling connectors) and approved / certified by IE staff. Initial assembly took place on January 29-30, 1979 at the BF3 site and was completed on February 26-27. All connectors were potted to appro-priate specifications prior to any testing. The actual assembly was observed by IE staff; af ter completion of the assemblies, IE certified that they were acceptably equivalent to the in-place connectors at BF3 before any simulation tests were conducted.
The Bendix 250-Vdc connectors are equipped with 12 pins. Its wiring configuration was such that all pins were used during testing. The Bendix 480-Vac connectors are equipped with 14 pins: 12 were wired into a single-l phase circuit. In each case, the 12 pins were wired to form a series /
parallel circuit that gave a voltage difference between pins within the connector as well as passing current to simulate a load.
Following final assembly, six of each of the wited and potted assemblies were shipped to Sandia Laboratories ( Albuquerque) for emnple-l tion of the entire confirmation-of-qualification test series.
t l
l 3. Description of Test Pro files l
l Three of each of two types of connectors were subjected to the pre-scribed series of tests with the remaining six connector assemblies saved as spares. This test series consisted of the following:
10
a I - Acceptance II - Baseline Functional III - Baseline Mechanical / Dimensional I 3 IV - Radiation V - Postradiation Functional / Mechanical VI - Temperature Aging VII - Postaging Functional / Mechanical VIII - Accident Test IX - Postaccident Functional / Mechanical X - Posttests Inspections 3.1 Radiation The connector assemblies were exposed to Cobalt-60 radiation doses totalling 68.5 Mrads (air) at an averaged dose rate of 0..'6 Mradii. >> ring i the period April 4-9, 1979. By comparison, the specified values were 69 :
Mrad and 0.77 Mrad /h, respectively, to be attained withtn +10%.,
1 The total 90-h irradiation interval was accomplisted in four 22.5-h periods with the specimens rotated to achieve a more ut iform total dose.
Concurrently, selected temperatures were recorded; the maximum measured 1
temperature was 35'C with the temperatures generally r inging between i 30' to 34*C. Figure I shows a view of the connector boxes in place inside the irradiation facility, i
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Figure 1. View of Connector Boxes in Irradiation Cell 3.2 Temperature Aging All of the electrical connectors were subjected to a two-part s im u-lated aging test during the period, April 10 24, 1979. The specified ag-ing times / temperatures / tolerances are shown below; the humidity was not controlled (i.e., was ambient).
Ag ing Aging Temperature Aging Time Atmosphere 217 * +6 *F 60 +0.1 h 8 Air 217* +6*F 180 +0.1 h b Nitrogen d
60 h in air at 217'F is intended to simulate 6 mo in air at 130*F.
b lS0 h is intended to simulate 18 mo in 130*F nitrogen with a maximum of 4% oxygen.
12 -
l Each test item was placed in the temperature chamber (i.e., oven) in a manner to avoid overheating from radiant ef fects from the chamber-heating elements (Figure 2). The temperature chamber was vented to the atmosphere to prevent buildup of outgasing products, particularly chlorine gas, from the test item inside the chamber. The air inside the chamber was distributed uniformly at an average velocity of about 250 f t/ min; pretest flow measurements in an open chamber were made and recorded. The air-aging was conducted for 59 2/3 h at 217' +3*F and was completed on April 13, 1979.
Following the air aging, the oven was purged with flowing nitrogen and the oven chamber brought to, and restabilized at, 217*F. The temperature was maintained (+3*F) for 179 2/3 h and was completed on April 24. During nitrogen-aging, a continuous flow of nitrogen was maintained , averaging i about 1/5 ft 3/m.
During all phases of the aging tests, selected specimen and environ-
, ment temperatures were recorded; the data indicated stabilized tempera-tures ranging between 218' and 220*F.
3.3 Accident Test Programmatic delays in completing the test series were experienced I during the period April 24 to November 1,1979. The delays were a result o f two fac tors. First, it was necessary for NRC staff to define the de-sired test profile so as to envelope both the originally specified and actual test profiles. Second, the necessary steam-generation equipment had to be assembled and a number of demonstration runs conducted to prove that the profile could be attained. During this 6-mo period , the con-nectors were stored in locked cabinets under ambient conditions; Sandia staf f believes that the storage resulted in insignificant additional de-gradation and " age."
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The connector assemblies were installed in the autoclave test chamber on October 31, 1979. Circuit continuity checks were performed and the as-semblies instrumented to load and measure voltage and current. The test chamber was instrumented with numerous temperature and pressure sensors located to provide indications that the environments were correctly at-tained and maintained.
The electrical connector test assemblies were subjected to the acci-dent test profile shown in Figure 3 and as detailed in established test procedures on November 1-2, 1979. The 250-Vdc connector assemblies were energized throughout the entire test. The 480-Vac connector assemblies were energized during the first 5 minutes, between minutes 15 and 18, and between minutes 57 and 60.
All aspects of the test were within the specified tolerances except for a few minutes at approximately 2 h when the tenperature exceeded the desired (110*C) value by +7'C.
4
- 4. Test Results, Conclusions All aspects of the test were considered satisfactorily completed. All connector assemblies passed the specifications of the test series; in particular, the assemblies carried their specified current / voltage loads during the accident-test phase. Posttest inspections (Figures 4 and 5) indicated little or no degradation of the connectors.
It is concluded that the test series completed on the specified BF3 connectors confirms the original qualification tests on the same type connectors as documented in Wyle Laboratories Report No. 43854-2, dated March 28, 1978.
15
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