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Category:CONTRACTED REPORT - RTA
MONTHYEARML20217F8551999-10-0707 October 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990828-0924 ML20216G4521999-09-0909 September 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA CNWRA, for Fiscal Reporting Period 990731-0827 ML20210G9651999-07-15015 July 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990605-0702 ML20209F2701999-07-0909 July 1999 Review of Submittal in Response to NRC GL 88-20,Suppl 4: 'Ipeees' Fire Submittal Screening Review Technical Evaluation Rept:Three Mile Island,Unit 1,Rev 2,980909 ML20196D2611999-06-17017 June 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990508-0604 ML20206J0871999-04-22022 April 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990313-0409 ML20196K5981999-03-26026 March 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990213-0312 ML20207F2271999-02-26026 February 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990116-0212 ML20202H3281999-01-28028 January 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA for Fiscal Reporting Period,981219-990115 ML20199G3281999-01-0707 January 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,981121-1218 ML20197G6491998-12-0404 December 1998 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,981024-1120 ML20195E7871998-11-0505 November 1998 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,980926-1023 ML20154R5401998-10-0909 October 1998 CNWRA Program Manager Periodic Rept on Activities of CNWRA for Fiscal Reporting Period of 980829-0925 ML20237B7721998-08-14014 August 1998 CNWRA Program Manager'S Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 980704-31 ML20249C5191998-06-19019 June 1998 CNWRA Program Manager'S Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 980509-0605 ML20236S2741998-06-16016 June 1998 CNWRA Program Manager'S Periodic Rept on Activities,For Fiscal Reporting Period 980606-0703 ML20206D4251998-02-26026 February 1998 Rev 0 to Ltr Rept, Technical Review of Gpu Nuclear Three Mile Island Unit 1 Cable Functionality Assessments ML20196K3621998-01-0606 January 1998 Rev 0 to Final Technical Evaluation of Three Mile Island Unit 1 Fire Barrier Ampacity Derating Assessments & RAI Responses ML20140G5041997-04-10010 April 1997 Ltr Rept,Rev 0, Technical Evaluation of Three Mile Island Unit 1 Fire Barrier Ampacity Derating Assessments ML20138G3461996-05-10010 May 1996 Technical Evaluation Rept of IPE Submittal & RAI Responses for Three Mile Island,Unit 1 ML20134G4491995-02-28028 February 1995 Exam of Bolt W/Boric Acid Attack from Three Mile Island Nuclear Generating Station ML20059F1221994-01-30030 January 1994 Lessons Learned from TMI-2 Advisory Panel, Draft Rept for Jan 1994 ML20058F6791993-10-31031 October 1993 Calculations to Estimate Margin to Failure in TMI-2 Vessel ML20058F6911993-10-31031 October 1993 TMI-2 Vessel Investigation Project Integration Rept ML20058F6631993-06-30030 June 1993 Results of Mechanical Tests & Supplementary Microstructural Exams of TMI-2 Lower Head Samples ML20058F6721993-02-28028 February 1993 TMI-2 Intrument Nozzle Exams at Argonne Natl Lab ML20115D9621992-05-31031 May 1992 Technical Evaluation Rept on Second 10 Yr Interval ISI Program Plan:Gpu Nuclear Corp,Tmi Nuclear Station,Unit 1, Docket 50-289 ML20056A6811990-03-31031 March 1990 TMI-2 Vessel Investigation Project (VIP) Metallurgical Program.Progress Report,January-September 1989 ML20011D8241989-11-30030 November 1989 a Review of the Three Mile ISLAND-1 Probabilistic Risk Assessment ML19324A6251989-09-0808 September 1989 Technical Evaluation Rept,TMI-1,Evaluation of Revised TMI-1 Response to Generic Ltr 81-12,Alternate Safe Shutdown Capability. ML20151E0871988-05-31031 May 1988 Rev 2 to Conformance to Reg Guide 1.97:TMI-1, Technical Evaluation Rept ML20150D1321988-02-29029 February 1988 Design Requirements for DSS (Diverse Scram Sys) & AMSAC (ATWS Mitigation Sys Actuation Circuitry), Safety Evaluation of Topical Rept 47-1159091-00 ML20238E9661987-08-31031 August 1987 the Cooldown Aspects of the TMI-2 Accident ML20236G3781987-07-31031 July 1987 Correlation of Radioiodine Resuspension with Temperature at TMI-2 ML20236E2781987-07-31031 July 1987 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components), TMI-1 ML20236P8301987-07-31031 July 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components:TMI-1, Informal Rept ML20235M6301987-06-30030 June 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Three Mile Island-1, Informal Rept ML20235N5251987-06-30030 June 1987 Rev 1 to Final Conformance to Reg Guide 1.97,TMI-1, Informal Rept ML20195G2521987-03-31031 March 1987 Conformance to Reg Guide 1.97,Oconee Nuclear Station,Units 1,2 & 3, Final Informal Rept ML20215J1431987-02-28028 February 1987 Conformance to Reg Guide 1.97,TMI Nuclear Station Unit 1, Informal Rept ML20207S3821987-02-28028 February 1987 Suppl 1 to Supplemental Technical Evaluation Rept,Pump & Valve Inservice Testing Program TMI-1 ML20206F6631986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Coolant System & Systems Decontamination ML20206F2911986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Radioactive Waste and Laundry Shipments ML20206F2351986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Defueling and Disassembly ML20206F2301986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Building Decontamination ML20137V4241985-11-30030 November 1985 Possible Options for Reducing Occupational Dose from the TMI-2 Basement ML20138P7801985-10-31031 October 1985 Conformance to Reg Guide 1.97,TMI-1, Interim Rept ML20137S2571985-08-31031 August 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Arkansas 1,Crystal River 3,Oconee 1,2 & 3,Rancho Seco & TMI-1 ML20209F8151985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Arkansas 1,Crystal River 3,Oconee 1,2 & 3,Rancho Seco & TMI-1 ML20115B1051985-03-0404 March 1985 Evaluation of Detailed Control Room Design Review Suppl II to Summary Rept for TMI-1, Technical Evaluation Rept 1999-09-09
[Table view] Category:QUICK LOOK
MONTHYEARML20217F8551999-10-0707 October 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990828-0924 ML20216G4521999-09-0909 September 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA CNWRA, for Fiscal Reporting Period 990731-0827 ML20210G9651999-07-15015 July 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990605-0702 ML20209F2701999-07-0909 July 1999 Review of Submittal in Response to NRC GL 88-20,Suppl 4: 'Ipeees' Fire Submittal Screening Review Technical Evaluation Rept:Three Mile Island,Unit 1,Rev 2,980909 ML20196D2611999-06-17017 June 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990508-0604 ML20206J0871999-04-22022 April 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990313-0409 ML20196K5981999-03-26026 March 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990213-0312 ML20207F2271999-02-26026 February 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990116-0212 ML20202H3281999-01-28028 January 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA for Fiscal Reporting Period,981219-990115 ML20199G3281999-01-0707 January 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,981121-1218 ML20197G6491998-12-0404 December 1998 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,981024-1120 ML20195E7871998-11-0505 November 1998 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,980926-1023 ML20154R5401998-10-0909 October 1998 CNWRA Program Manager Periodic Rept on Activities of CNWRA for Fiscal Reporting Period of 980829-0925 ML20237B7721998-08-14014 August 1998 CNWRA Program Manager'S Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 980704-31 ML20249C5191998-06-19019 June 1998 CNWRA Program Manager'S Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 980509-0605 ML20236S2741998-06-16016 June 1998 CNWRA Program Manager'S Periodic Rept on Activities,For Fiscal Reporting Period 980606-0703 ML20206D4251998-02-26026 February 1998 Rev 0 to Ltr Rept, Technical Review of Gpu Nuclear Three Mile Island Unit 1 Cable Functionality Assessments ML20196K3621998-01-0606 January 1998 Rev 0 to Final Technical Evaluation of Three Mile Island Unit 1 Fire Barrier Ampacity Derating Assessments & RAI Responses ML20140G5041997-04-10010 April 1997 Ltr Rept,Rev 0, Technical Evaluation of Three Mile Island Unit 1 Fire Barrier Ampacity Derating Assessments ML20138G3461996-05-10010 May 1996 Technical Evaluation Rept of IPE Submittal & RAI Responses for Three Mile Island,Unit 1 ML20134G4491995-02-28028 February 1995 Exam of Bolt W/Boric Acid Attack from Three Mile Island Nuclear Generating Station ML20059F1221994-01-30030 January 1994 Lessons Learned from TMI-2 Advisory Panel, Draft Rept for Jan 1994 ML20058F6791993-10-31031 October 1993 Calculations to Estimate Margin to Failure in TMI-2 Vessel ML20058F6911993-10-31031 October 1993 TMI-2 Vessel Investigation Project Integration Rept ML20058F6631993-06-30030 June 1993 Results of Mechanical Tests & Supplementary Microstructural Exams of TMI-2 Lower Head Samples ML20058F6721993-02-28028 February 1993 TMI-2 Intrument Nozzle Exams at Argonne Natl Lab ML20115D9621992-05-31031 May 1992 Technical Evaluation Rept on Second 10 Yr Interval ISI Program Plan:Gpu Nuclear Corp,Tmi Nuclear Station,Unit 1, Docket 50-289 ML20056A6811990-03-31031 March 1990 TMI-2 Vessel Investigation Project (VIP) Metallurgical Program.Progress Report,January-September 1989 ML20011D8241989-11-30030 November 1989 a Review of the Three Mile ISLAND-1 Probabilistic Risk Assessment ML19324A6251989-09-0808 September 1989 Technical Evaluation Rept,TMI-1,Evaluation of Revised TMI-1 Response to Generic Ltr 81-12,Alternate Safe Shutdown Capability. ML20151E0871988-05-31031 May 1988 Rev 2 to Conformance to Reg Guide 1.97:TMI-1, Technical Evaluation Rept ML20150D1321988-02-29029 February 1988 Design Requirements for DSS (Diverse Scram Sys) & AMSAC (ATWS Mitigation Sys Actuation Circuitry), Safety Evaluation of Topical Rept 47-1159091-00 ML20238E9661987-08-31031 August 1987 the Cooldown Aspects of the TMI-2 Accident ML20236G3781987-07-31031 July 1987 Correlation of Radioiodine Resuspension with Temperature at TMI-2 ML20236E2781987-07-31031 July 1987 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components), TMI-1 ML20236P8301987-07-31031 July 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components:TMI-1, Informal Rept ML20235M6301987-06-30030 June 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Three Mile Island-1, Informal Rept ML20235N5251987-06-30030 June 1987 Rev 1 to Final Conformance to Reg Guide 1.97,TMI-1, Informal Rept ML20195G2521987-03-31031 March 1987 Conformance to Reg Guide 1.97,Oconee Nuclear Station,Units 1,2 & 3, Final Informal Rept ML20215J1431987-02-28028 February 1987 Conformance to Reg Guide 1.97,TMI Nuclear Station Unit 1, Informal Rept ML20207S3821987-02-28028 February 1987 Suppl 1 to Supplemental Technical Evaluation Rept,Pump & Valve Inservice Testing Program TMI-1 ML20206F6631986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Coolant System & Systems Decontamination ML20206F2911986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Radioactive Waste and Laundry Shipments ML20206F2351986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Defueling and Disassembly ML20206F2301986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Building Decontamination ML20137V4241985-11-30030 November 1985 Possible Options for Reducing Occupational Dose from the TMI-2 Basement ML20138P7801985-10-31031 October 1985 Conformance to Reg Guide 1.97,TMI-1, Interim Rept ML20137S2571985-08-31031 August 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Arkansas 1,Crystal River 3,Oconee 1,2 & 3,Rancho Seco & TMI-1 ML20209F8151985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Arkansas 1,Crystal River 3,Oconee 1,2 & 3,Rancho Seco & TMI-1 ML20115B1051985-03-0404 March 1985 Evaluation of Detailed Control Room Design Review Suppl II to Summary Rept for TMI-1, Technical Evaluation Rept 1999-09-09
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20217F8551999-10-0707 October 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990828-0924 ML20216G4521999-09-0909 September 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA CNWRA, for Fiscal Reporting Period 990731-0827 ML20210G9651999-07-15015 July 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990605-0702 ML20209F2701999-07-0909 July 1999 Review of Submittal in Response to NRC GL 88-20,Suppl 4: 'Ipeees' Fire Submittal Screening Review Technical Evaluation Rept:Three Mile Island,Unit 1,Rev 2,980909 ML20196D2611999-06-17017 June 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990508-0604 ML20206J0871999-04-22022 April 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990313-0409 ML20196K5981999-03-26026 March 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990213-0312 ML20207F2271999-02-26026 February 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990116-0212 ML20202H3281999-01-28028 January 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA for Fiscal Reporting Period,981219-990115 ML20199G3281999-01-0707 January 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,981121-1218 ML20197G6491998-12-0404 December 1998 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,981024-1120 ML20195E7871998-11-0505 November 1998 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,980926-1023 ML20154R5401998-10-0909 October 1998 CNWRA Program Manager Periodic Rept on Activities of CNWRA for Fiscal Reporting Period of 980829-0925 ML20237B7721998-08-14014 August 1998 CNWRA Program Manager'S Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 980704-31 ML20249C5191998-06-19019 June 1998 CNWRA Program Manager'S Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 980509-0605 ML20236S2741998-06-16016 June 1998 CNWRA Program Manager'S Periodic Rept on Activities,For Fiscal Reporting Period 980606-0703 ML20206D4251998-02-26026 February 1998 Rev 0 to Ltr Rept, Technical Review of Gpu Nuclear Three Mile Island Unit 1 Cable Functionality Assessments ML20196K3621998-01-0606 January 1998 Rev 0 to Final Technical Evaluation of Three Mile Island Unit 1 Fire Barrier Ampacity Derating Assessments & RAI Responses ML20140G5041997-04-10010 April 1997 Ltr Rept,Rev 0, Technical Evaluation of Three Mile Island Unit 1 Fire Barrier Ampacity Derating Assessments ML20138G3461996-05-10010 May 1996 Technical Evaluation Rept of IPE Submittal & RAI Responses for Three Mile Island,Unit 1 ML20134G4491995-02-28028 February 1995 Exam of Bolt W/Boric Acid Attack from Three Mile Island Nuclear Generating Station ML20059F1221994-01-30030 January 1994 Lessons Learned from TMI-2 Advisory Panel, Draft Rept for Jan 1994 ML20058F6791993-10-31031 October 1993 Calculations to Estimate Margin to Failure in TMI-2 Vessel ML20058F6911993-10-31031 October 1993 TMI-2 Vessel Investigation Project Integration Rept ML20058F6631993-06-30030 June 1993 Results of Mechanical Tests & Supplementary Microstructural Exams of TMI-2 Lower Head Samples ML20058F6721993-02-28028 February 1993 TMI-2 Intrument Nozzle Exams at Argonne Natl Lab ML20115D9621992-05-31031 May 1992 Technical Evaluation Rept on Second 10 Yr Interval ISI Program Plan:Gpu Nuclear Corp,Tmi Nuclear Station,Unit 1, Docket 50-289 ML20056A6811990-03-31031 March 1990 TMI-2 Vessel Investigation Project (VIP) Metallurgical Program.Progress Report,January-September 1989 ML20011D8241989-11-30030 November 1989 a Review of the Three Mile ISLAND-1 Probabilistic Risk Assessment ML19324A6251989-09-0808 September 1989 Technical Evaluation Rept,TMI-1,Evaluation of Revised TMI-1 Response to Generic Ltr 81-12,Alternate Safe Shutdown Capability. ML20151E0871988-05-31031 May 1988 Rev 2 to Conformance to Reg Guide 1.97:TMI-1, Technical Evaluation Rept ML20150D1321988-02-29029 February 1988 Design Requirements for DSS (Diverse Scram Sys) & AMSAC (ATWS Mitigation Sys Actuation Circuitry), Safety Evaluation of Topical Rept 47-1159091-00 ML20238E9661987-08-31031 August 1987 the Cooldown Aspects of the TMI-2 Accident ML20236G3781987-07-31031 July 1987 Correlation of Radioiodine Resuspension with Temperature at TMI-2 ML20236E2781987-07-31031 July 1987 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components), TMI-1 ML20236P8301987-07-31031 July 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components:TMI-1, Informal Rept ML20235M6301987-06-30030 June 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Three Mile Island-1, Informal Rept ML20235N5251987-06-30030 June 1987 Rev 1 to Final Conformance to Reg Guide 1.97,TMI-1, Informal Rept ML20195G2521987-03-31031 March 1987 Conformance to Reg Guide 1.97,Oconee Nuclear Station,Units 1,2 & 3, Final Informal Rept ML20215J1431987-02-28028 February 1987 Conformance to Reg Guide 1.97,TMI Nuclear Station Unit 1, Informal Rept ML20207S3821987-02-28028 February 1987 Suppl 1 to Supplemental Technical Evaluation Rept,Pump & Valve Inservice Testing Program TMI-1 ML20206F6631986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Coolant System & Systems Decontamination ML20206F2911986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Radioactive Waste and Laundry Shipments ML20206F2351986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Defueling and Disassembly ML20206F2301986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Building Decontamination ML20137V4241985-11-30030 November 1985 Possible Options for Reducing Occupational Dose from the TMI-2 Basement ML20138P7801985-10-31031 October 1985 Conformance to Reg Guide 1.97,TMI-1, Interim Rept ML20137S2571985-08-31031 August 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Arkansas 1,Crystal River 3,Oconee 1,2 & 3,Rancho Seco & TMI-1 ML20209F8151985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Arkansas 1,Crystal River 3,Oconee 1,2 & 3,Rancho Seco & TMI-1 ML20115B1051985-03-0404 March 1985 Evaluation of Detailed Control Room Design Review Suppl II to Summary Rept for TMI-1, Technical Evaluation Rept 1999-09-09
[Table view] Category:RESEARCH AND TECHNICAL ASSISTANCE REPORTS
MONTHYEARML20065S7881982-07-31031 July 1982 Tech Specs for Redundant Decay Heat Removal Capability, TMI-1 ML20062A5951982-07-31031 July 1982 TMI Resin Solidification Test Program ML20055A4811982-05-31031 May 1982 Independent Evaluation of TMI Worker Exposure & Personnel Dosimetry, Final Rept for May 1982 ML20054M8791982-04-30030 April 1982 Tech Specs for Redundant Decay Heat Removal Capability, Tmi,Unit 1 (TMI-1), Preliminary Rept ML19347E9181981-04-30030 April 1981 Degraded Grid Protection for Class IE Power Sys,TMI-1, Technical Evaluation Rept ML19341C9931981-01-31031 January 1981 Degraded Grid Protection for Class IE Power Sys,Tmi Nuclear Station,Unit 1, Technical Evaluation Rept ML19351D8971980-10-31031 October 1980 Adequacy of Station Electrical Distribution Sys Voltages, Technical Evaluation Rept,Revision 1 ML19336A5971980-09-30030 September 1980 Technical Evaluation Rept,Adequacy of Station Electrical Distribution Sys Voltages,TMI-1, Interim Rept ML19318B3521980-06-30030 June 1980 Electrical,Instrumentation & Control Aspects of Override of Containment Purge Valve Isolation & Other Safety Feature Signals,TMI-1. 1982-07-31
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20217F8551999-10-0707 October 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990828-0924 ML20216G4521999-09-0909 September 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA CNWRA, for Fiscal Reporting Period 990731-0827 ML20210G9651999-07-15015 July 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990605-0702 ML20209F2701999-07-0909 July 1999 Review of Submittal in Response to NRC GL 88-20,Suppl 4: 'Ipeees' Fire Submittal Screening Review Technical Evaluation Rept:Three Mile Island,Unit 1,Rev 2,980909 ML20196D2611999-06-17017 June 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990508-0604 ML20206J0871999-04-22022 April 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990313-0409 ML20196K5981999-03-26026 March 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990213-0312 ML20207F2271999-02-26026 February 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990116-0212 ML20202H3281999-01-28028 January 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA for Fiscal Reporting Period,981219-990115 ML20199G3281999-01-0707 January 1999 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,981121-1218 ML20197G6491998-12-0404 December 1998 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,981024-1120 ML20195E7871998-11-0505 November 1998 CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,980926-1023 ML20154R5401998-10-0909 October 1998 CNWRA Program Manager Periodic Rept on Activities of CNWRA for Fiscal Reporting Period of 980829-0925 ML20237B7721998-08-14014 August 1998 CNWRA Program Manager'S Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 980704-31 ML20249C5191998-06-19019 June 1998 CNWRA Program Manager'S Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 980509-0605 ML20236S2741998-06-16016 June 1998 CNWRA Program Manager'S Periodic Rept on Activities,For Fiscal Reporting Period 980606-0703 ML20206D4251998-02-26026 February 1998 Rev 0 to Ltr Rept, Technical Review of Gpu Nuclear Three Mile Island Unit 1 Cable Functionality Assessments ML20196K3621998-01-0606 January 1998 Rev 0 to Final Technical Evaluation of Three Mile Island Unit 1 Fire Barrier Ampacity Derating Assessments & RAI Responses ML20140G5041997-04-10010 April 1997 Ltr Rept,Rev 0, Technical Evaluation of Three Mile Island Unit 1 Fire Barrier Ampacity Derating Assessments ML20138G3461996-05-10010 May 1996 Technical Evaluation Rept of IPE Submittal & RAI Responses for Three Mile Island,Unit 1 ML20134G4491995-02-28028 February 1995 Exam of Bolt W/Boric Acid Attack from Three Mile Island Nuclear Generating Station ML20059F1221994-01-30030 January 1994 Lessons Learned from TMI-2 Advisory Panel, Draft Rept for Jan 1994 ML20058F6791993-10-31031 October 1993 Calculations to Estimate Margin to Failure in TMI-2 Vessel ML20058F6911993-10-31031 October 1993 TMI-2 Vessel Investigation Project Integration Rept ML20058F6631993-06-30030 June 1993 Results of Mechanical Tests & Supplementary Microstructural Exams of TMI-2 Lower Head Samples ML20058F6721993-02-28028 February 1993 TMI-2 Intrument Nozzle Exams at Argonne Natl Lab ML20115D9621992-05-31031 May 1992 Technical Evaluation Rept on Second 10 Yr Interval ISI Program Plan:Gpu Nuclear Corp,Tmi Nuclear Station,Unit 1, Docket 50-289 ML20062G6971990-11-16016 November 1990 Notification of Contract Execution,Task Order 13,to Electrical Distribution Functional Insp, Awarded to Aecl Technologies ML20217A2951990-10-23023 October 1990 Mod 13,extending Period of Performance Through 901031,to Test Specimens from Damaged TMI-2 Reactor Bottom Head ML20217A2831990-10-23023 October 1990 Notification of Contract Execution,Mod 13,to Test Specimens from Damaged TMI-2 Reactor Bottom Head. Contractor:Mpr Assoc ML20056A6811990-03-31031 March 1990 TMI-2 Vessel Investigation Project (VIP) Metallurgical Program.Progress Report,January-September 1989 ML20011D8241989-11-30030 November 1989 a Review of the Three Mile ISLAND-1 Probabilistic Risk Assessment ML19324A6251989-09-0808 September 1989 Technical Evaluation Rept,TMI-1,Evaluation of Revised TMI-1 Response to Generic Ltr 81-12,Alternate Safe Shutdown Capability. ML20247P6351989-06-27027 June 1989 Notification of Contract Execution,Mod 6,to Test Specimens from Damaged TMI-2 Reactor Bottom Head. Contractor:Mpr Assocs,Inc ML20247P6441989-06-27027 June 1989 Mod 6,revising Statement of Work & Provisional Indirect Rates for CY89 & Increasing Total Estimated Amount of Contract,To Test Specimens from Damaged TMI-2 Reactor Bottom Head ML20246J8821989-05-0505 May 1989 Notification of Contract Execution,Mod 5,to Test Specimens from Damaged TMI-2 Reactor Bottom Head. Contractor: MPR Assocs ML20246J9441989-05-0505 May 1989 Mod 5,providing Incremental Funding,To Test Specimens from Damaged TMI-2 Reactor Bottom Head ML20154M0021988-09-20020 September 1988 Notification of Contract Execution,Mod 3,to Test Specimens from Damaged TMI-2 Reactor Bottom Head. Contractor:Mpr Assoc,Inc ML20154M0101988-09-20020 September 1988 Mod 3,providing Incremental Funding,To Test Specimens from Damaged TMI-2 Reactor Bottom Head ML20196F4111988-06-23023 June 1988 Notification of Grant Execution: Topical Meeting on TMI-2 Accident Matls Behavior & Plant Recovery Technology Washington,Dc 881031-1104, Awarded to American Nuclear Soc ML20196F4721988-06-23023 June 1988 Grant: Topical Meeting on TMI-2 Accident Matls Behavior & Plant Recovery Technology Washington,Dc 881031-1104, Awarded to American Nuclear Society ML20151E0871988-05-31031 May 1988 Rev 2 to Conformance to Reg Guide 1.97:TMI-1, Technical Evaluation Rept ML20154C4431988-04-28028 April 1988 Mod 2,providing Incremental Funding,To Test Specimens from Damaged TMI-2 Reactor Bottom Head ML20154C4291988-04-28028 April 1988 Notification of Contract Execution,Mod 2,to Test Specimens from Damaged TMI-2 Reactor Bottom Head. Contractor:Mpr Assoc,Inc ML20151E1451988-03-31031 March 1988 Mod 1,providing Incremental Funds,To Test Specimens from Damaged TMI-2 Reactor Bottom Head ML20151E1271988-03-31031 March 1988 Notification of Contract Execution,Mod 1,to Test Specimens from Damaged TMI-2 Reactor Bottom Head. Contractor:Mtr Assoc,Inc ML20150D1321988-02-29029 February 1988 Design Requirements for DSS (Diverse Scram Sys) & AMSAC (ATWS Mitigation Sys Actuation Circuitry), Safety Evaluation of Topical Rept 47-1159091-00 ML20149D7681988-01-15015 January 1988 Contract: Test Specimens from Damaged TMI-2 Reactor Bottom Head, Awarded to MPR Assoc,Inc ML20149D7511988-01-15015 January 1988 Notification of Contract Execution: Test Specimens from Damaged TMI-2 Reactor Bottom Head, Awarded to MPR Assoc, Inc ML20238E9661987-08-31031 August 1987 the Cooldown Aspects of the TMI-2 Accident 1999-09-09
[Table view] |
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. m:a= soao-ase (me, itJs INTERIM REPORT Accession N: B0062600%
Report No. EGG-EA-5167 Contract Program or Project Tit!s:
Electrical, Instrumentation and Control System Support Subject of this Document:
Electrical, Instrumentation and Control Aspects of the Override of Containment Purge Valve Isolation and Other Safety Feature Signals, Three Mile Island - Unit 1, Docket No. 50-289, TAC No. 10205 Type of Document Informal. Report Author (s):
A. C. Udy Det) of Document June 1980 Responsible NRC Individual and NRC Office or Division:
. Paul C. Shemanski, Division of Operating Reactors This document was prepared primarily for preliminary or internal use. it has not received full review and approval. Since there may be substantive changes, this document shouf d not be considered final.
EG&G Idaho, Inc.
Idaho Falls, Idaho 83415
. Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C.
. Under DOE Contract No. DE-AC07-761D01570 NRC FIN No. A6256 INTERIM REPORT ur n n ' '
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June 1980 ELECTRICAL, INSTRUMENTATION AND CONTROL ASPECTS OF i
l THE OVERRIDE OF CONTAINMENT PURGE VALVE ISOLATION AND l
OTHER SAFETY FEATURE SIGNALS, THREE MILE ISLAND -
, UNIT 1, DOCKET NO. 50-289, TAC NO. 10205 A. C. Udy U.S. Department of Energy Idaho Operations Office
- Idaho National Engineering Laboratory w~ nm :-x
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4 TECHNICAL EVALUATION REPORT
- ELECTRICAL, INSTRUMENTATION, AND CONTROL ASPECTS OF-THE OVERRIDE OF CONTAINMENT PURGE VALVE ISOLATION AND OTHER SAFETY FEATURE SIGNALS 4
THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 Docket No. 50-289 TAC No. 10205 a
June 1980-
- A. C. Udy Reliability.and Statistics Branch Engineering Analysis Division EG&G Idaho, Inc.
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s ABSTRACT
, Several instances.have been reported where the' automatic closure of the containment ventilation or purge isolation valves would not have occur-
- red because the_ safety actuation signals were manually overridden or_ blocked during normal plant. operations. This report addresses electrical, instru -
men.tation, and control design aspects for these valves, and.the ability of the unit containment ventilation system to isolate on-several diverse param-
-eters.. Other related systems were' audited to the same guidel'ines.
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FIN No. A6256-EICS Support ii
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, ,.,: - CONTENTS
' 1.0'-[ INTRODUCTION'-.'..'. . . . - . . . -. .. . . . . . . . . . . . . . . . . . . .
1 r
220 EVALUATION 0F THREE MILE ISLAND NUCLEAR STATION, UNIT 1 . . . . . . 2 2.1 Review' Guidelines'. '
2
= 2.2: Containment Ventilation Isolation Circuits Design
. , 1 Description . . . .. .. . . . . . . . . . . . . . . . . . . . . . . . 3 2.3- Containment Ventilation Isolation' System Design Evaluation' -. - - . . - . . . . .
. . . . . . . . - . . . . . . . . . . . 5 2.4 Other-Related Engineered Safeguards Actuation System Circuits. . . . . . . . .. .. . . . . . .. . . . . . . . .
. . . . 6
, 7 3.0
SUMMARY
. . . . - . . . . . . . . . . . . . . . . . . . . . . . . . - . - . - . -. 6
.4.0- REFERENCES . . ' . . -
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. [ TECHNICAL ~ EVALUATION; REPORT _
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ELECTRICAL, INSTRUMENTATION, AND CONTROL ASPECTS' OF -
THE- OVERRRIDE OF L CONTAINMENT PURGE VALVE ISOLATION -
AND OTHER SAFETY FEATURE' SIGNALS'
~
THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1_-
- 1.0~ INTRODUCTION 1 Based on the 'information supplied by: General Public Utilities (GPU),
' this. report addresses the: electrical, instrumentation,.and control systems design ~ aspects of the Containment Ventilativa Isolation ;(CVI) system andL ather related Engineered ~ Safeguards Actuation Syste'm!(ESAS) functions'for.
Three Mile Island--Unit ~ 1.
.Several. instances have been reported where the automatic closure of Ethe. containment ventilation or' purge isolation valves would not have occur-red because the-safety 1 actuation. signals were manually overridden or blocked
.during normal . plant operations. ; These events resulted from a lack of proper
- management controls' ; procedural inadequacies, and circuit design deficien-
~~
. 'cies. .These events'also brought-into question the mechanical operability ~
, of the-valves themselves. These events were determined by the Nuclear
, Regulatory Commission 1(NRC) to be an Abnoanal Occurrence (#78-05) and accordingly', were reported.to Congress..
-As a follow-up of this Abnormal Occurrence, the.NRC is reviewing the' Jelectrical override; aspects and .the mechanical operability aspects of con- -
tainment purging for all operating reactors.- On November 28,-1978, the NRC issued.a letter, " Containment Purging During Normal Plant Operation"I to all Boiling Water Reactor and Pressurized Water Reactor licensees. GPU 2
responded to the~. letter by.a-letter of January 4, 1979 . After discus-sions between GPU.and the NRC, GPU' issued-another letter on this subject on-
! ' April- 3', ~ 1980.3 Additional information is-taken from the Three Mile
-Islan'd--Unit *1 restart report 4 'Section 2.1.1.5, and the Final-Safety (j -
- Analysis Report 1(FSAR). A telephone conference call5 on May 7, 1980,
,. 1 discussed the April'3, 1980-letter.
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~ 2.0. : EVALUATION OF THREE MILE ISLAND NUCLEAR STATION, UNIT :1 .
.2.1 LReviewfG uidelines 1The intentT of this~ evaluation is to determine if the following NRC requirements are met for the safety signals to all ESAS equipment: .
1.. Guideline-No. 1--In keeping with the requirements of -
General Design Criteria 55 and 56, the overridinga og one type of safety actuation signal (e.g., radiation) should not cause the blocking of any other type of safety; actuation signal (e.g., pressure) for~those valves ithat have no function besides containment isolation.
2.- . Guideline No. 2--Sufficient physical features (e.g.,
key lock switches) are to be provided to facilitate adequate administrative controls.
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- 3. -Guideline No. 3--A system level annunciation of the overridden status should be provided for every safety system-impacted when any override is active.
Incidental.to this review, the following additional NRC design guide-lines were used in the evaluation: -
'l. Guideline No. 4--Diverse signals should be provided to initiate isolation of the containment ventilation
, -system. Specifically, containment high radiation, safety injection actuation, and containment high pres .
sure (where containment high pressure is not a. portion of safety injection actuation) should automatically initiate CVI.
- 2. Guideline No. 5--The instrumentation and control systems provided to initiate the ESAS should be designed and qualified as safety grade equipment.
- 3. . Guideline No. 6--the overriding or resetting a of the ESF actuation signal should not cause any valve or damper to change position.
o - a. The following definition is given for clarity of use in this evaluation: .
Override: .The signal is still present, and it~is blocked in order to i
perform a function contrary to the signal.
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. ' Guideline 6 in th'is review applies primarily to other related ESAS circuits because implementation of this guideline for containment isolation will be reviewed by the Lessons Learned Task Force, based on the recommend-ations in NUREG-0578, Section 2 1.4. When containment isolation is not involved, consideration on a case-by-case basis of automatic valve reposi-tioning upon reset may be considered acceptable. Acceptability would be dependent upon system function, design intent, and suitable operating
. procedures.
2.2 Containment Ventilation Isolation Circuits Design Description Three Mile Island--Unit I has two ESAS trains which close, indepen-dently and separately, the inboard and' outboard isolation valves. Each valve can only be opened by a manual control switch if a key-operated per-missive switch has been operated. ' The key is removed once the valve is opened.5 The control system is such that the automatic closure signals will close the valves'even if the control-switch is held in the "open" position.
The resetting of the isolation signal does not cause the opening or repo-sitioning of . any CVI valve.4 Loss of power to the control system or loss of. air to'the solenoid valve closes the solenoid-operated isolation valves.
Motor-operated valves remain in' their last position. Valve position lights, "open" and " closed", are provided on the control console. .
The initiating signals which will close the valves are listed below and in Table 2.1-l':
- 1. Containment pressure high (4 psig)
- a. ' The following definition is given for clarity of use in this evaluat'.on:
Reset: The signal has come and gone, and the circuit is being cleared in order to return it to the normal. condition.
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- 2. ' Reactor. building.exhau'st monitors of radioactivity .
~ level _as. called out in the unit FSAR:
- a. : Air lparticlemonitor
- b. , Iodine monitor
- c. 1 Radioactive gas monitor -
- 3. ' Reactor trip".
The actuation signal resulting from the automatic initiation signal can be reset,_once'the initiation signal is gone, at the ESAS panel or at a
- benchboard to allow manual ~ opening"of the CVI valves. The permissive key
' switch will still'need to be operated before the valves can be opened.
Individual initiation signals can be overridden. An override condition can_only he' established when an accident signal exists, and is automatically
' removed'when the accident signal _is gone. An audible signal informs the operator that his action'has established an override condition.
The inboard and the . outboard CVI valves are controlled by separate ,
ESAS trains,.with the three radiation monitoring channels also able to close<both the inboard and the outboard valves. Once a closure signal has-been received,Jthe valves.cannot be opened until the initiating signal is either overridden or gone'(and the logic then reset by a manual pushbutton switch). There is provision to override an actuation signal-from the radi-2 ation _ channels; this override is annunciated , -A reactor' trip actuation signal can also be overridden, as can the containment pressure signal, to' permit valve opening. These_ override conditions cause an audible signal when established, and are automatically removed when tne initiating condi-
-tion isLgone, i
~The-reactor' trip-signal, defined in Section 2.1.1.5.34 as "antici-
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patory of SFAS and occurs prior .to SFAS initiation," occurs at 1900'psig
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- reactor coolant syst'em'(RCS)-pressure, while the SFAS initiation occurs at 1600.psig-RCS; pressure.
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. .: To-reopen ~theipurge valveslwhen an' isolation condition is present,
- theee actionszarelnecessary for each redundant valve. 1The operator must
~a< tuate the override ~ switch, operate the permissive key switch, and operate.
tha' valve control switch.'
- 2.3 -containment ventilation' Isolation System Design Evaluation E .. .
. ' Guideline ~l~ requires:that-no signal ovarride:can preventfanother safety actuation signal from' functioning. 'The signals can be individually over-J 1 ridden with no affect on'the other. actuation signals;~this conforms-with l this - guideline .
Guideline 2. requires that ~ any reset cn: override switches have physical provisions to aid'in'the' administrative' control of the' switch'es. With key-locked' permissive switches installed in the CVI valve opening logic,
'this guideline is satisfied. The override switches do not' meet the literal intent of this guideline; however, an override can only be established and
~
. maintained when an accident condition-exists. Once the override is-estab-lished, the purge valver cannot be opened without using a key permissive 1'- : switch. This is deemed sufficient to facilitate administrative control.
Guideline T requires: system level annunciation whenever an override-affects the performance of a safety system. Annunciation is provided when
~
a radiation channel is' overridden. Overrides of ESAS signals cause an audible signal'when the override is established. While not in full compli-
~
< ance with the guideline, in- all casesi the operator is -informed by the control system that an override has been established. The override itself 4 does not allow the purge' valves to be opened. A key-locked permissive switch still needs to be operated. Additionally,.the override is automati-4 cally removed when'the' actuating conditiot. is gone Annunciation,.in addi-
-. tion to these design features,-is notLdeemed necessary.
4 Guideline 41 requires that isolation of the CVI system be actuated by
. several diverse signals. -Three Mile ~-Island--Unit I uses a reactor trip
-signal as-anticipatory of a safety-injection. This is acceptable. -With i
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" high radiation.. signals and high containment pressure signals in addition'to -
jthe1 reactor trip signals, this guideline is~ satisfied.
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... - Guideline 5 requires _that_th'e!-isolation actuation signals be: derived
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afrom safety grade. instruments.; Three Mile: Island--Unit 1 actuates' closure fof(thelpurgetvalve's;by'use of signals' derived from safety grade equipment,3 _
except forinon-safety grade radiation channels4 ,5 The'NRC should require
.the_use'of safety grade. radiation channels to initiate. isolation of the.
purge val'vesiat-Three_Mileelsland--UnitJ1.
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GuidelineL6' requires that no resetting of' isolation logic will, of 2
-itself, automatically open th'e is'lation_ valves. The CVI valves have bIeen
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- modified'as Section 2.1'.1.5.3 0 states: " deliberate operator action shall be required.-to reopen selected individual valves." Guideline 6 is satisfied.
- .2.4 OtherJRelated Engineered Safeguard Actuation System Circuits
~0ther ESAS circuits have manual override capabilities. Table 2.1-1 sh'ows these? overrides. Applicable guidelines are complied with for these
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' circuits.
i.
j< No other. manual-overrides have been identified in the review of the material submitted?for this-audit.- -
e . . .
3.0 . .
SUMMARY
i l- ' The1NRC . issued a letter, " Containment Purging During Normal Plant
, Operation," which; requested:GPU to review' purging requirements, controls,
! , and } procedures ~ for^ purging at the Three Mile Island station.
i
'Thel electrical, instrumentation, and control design aspects of the f
containment' ventilation isolation valves and other related ESAS signals for'-
LThree' Mile < Island--Unit l~were= evaluated using the-design guidelines stated- -
~
'in.Section.;2l^of this report. 1&nt unit. design. meets the NRC guidelines ~
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i except that.non-safety grade rzdiation channels are used for automatic
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closure of the purge valves.
The NRC should require GPU to' submit plans to supply.Three Mile Island--Unit I with safety' grade' radiation channels that will initiate closure of the CVI valves.
- . ThelThree Mile Island--Unit'l CVI system is-not in compliance with the literal requirements of guidelines 2 and 3, which require protective covers
. or other - features for the override switches and annunciation when an over-ride is established. The.NRC should accept the present design as adequate as pointed out in Section 2.3 of this report.
4.0 REFERENCES
- 1. NRC/ DOR letter (A. Schwencer) to all BWR and PWR licensees, " Con-tainment Purging During Normal Plant Operation," dated November.28, 1978.
- 2. Met Ed letter (J. G. Herbein).to Director of Nuclear Reactor Regu-lation, "Three Mile Island Nuclear Station, Unit 1 Containment-
. Purging," January 4, 1979, GQL 0007.
. 3. Met'Ed letter (J. G. Herbein) to Director of Nuclear Reactor Regu-lation, " Purge Valves," April 3, 1980, TLL 157.
- 4. Three Mile Island Nuclear Station, Unit 1 Restart Report, Sec-tion 2.1.1.5 and response to NRC question 26. -
- 5. Telecon,'A. C. Udy, EG&G Idaho, Inc., Dominic Dilanni, NRC, G. Sen, J. Korea, and D. Chisholm, GPU, May 7, 1980.
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