|
---|
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 ML20058F6911993-10-31031 October 1993 TMI-2 Vessel Investigation Project Integration Rept ML20058F6791993-10-31031 October 1993 Calculations to Estimate Margin to Failure in TMI-2 Vessel 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 ML20206F2301986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Building Decontamination ML20206F2351986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Defueling and Disassembly ML20206F2911986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Radioactive Waste and Laundry Shipments ML20206F6631986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Coolant System & Systems 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 ML20058F6911993-10-31031 October 1993 TMI-2 Vessel Investigation Project Integration Rept ML20058F6791993-10-31031 October 1993 Calculations to Estimate Margin to Failure in TMI-2 Vessel 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 ML20206F2301986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Building Decontamination ML20206F2351986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Defueling and Disassembly ML20206F2911986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Radioactive Waste and Laundry Shipments ML20206F6631986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Coolant System & Systems 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 ML20058F6911993-10-31031 October 1993 TMI-2 Vessel Investigation Project Integration Rept ML20058F6791993-10-31031 October 1993 Calculations to Estimate Margin to Failure in TMI-2 Vessel 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 ML20206F2301986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Building Decontamination ML20206F2351986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Defueling and Disassembly ML20206F2911986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Radioactive Waste and Laundry Shipments ML20206F6631986-05-31031 May 1986 Evaluation of Nuclear Facility Decommissioning Projects. Summary Status Report,Three Mile Island Unit 2,Reactor Coolant System & Systems 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: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 ML20058F6911993-10-31031 October 1993 TMI-2 Vessel Investigation Project Integration Rept ML20058F6791993-10-31031 October 1993 Calculations to Estimate Margin to Failure in TMI-2 Vessel 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 ML20149D7511988-01-15015 January 1988 Notification of Contract Execution: Test Specimens from Damaged TMI-2 Reactor Bottom Head, Awarded to MPR Assoc, Inc ML20149D7681988-01-15015 January 1988 Contract: 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] |
Text
._ _ .-. . . _ _ _ . __
1
~
i MCIT42089-01 l
l l
EXAMINATION OF A BOLT WITII BORIC ACID ATTACK FROM THREE MILE ISLAND NUCLEAR GENERATING STATION
. 1 by Biays S. Bowerman Carl J. Czajkowski Thomas C. Roberts 1
February 1995 Environmental and Waste Technology Center Department of Advanced Technology Brookhaven National Laboratory Upton, New York 11973 9611130204 950227 PDR TOPRP EXIBNL C PDR
l l
TABLE OF CONTENTS i
l Page j 1.
Introductio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 l
- 2. Description of Stud Pieces . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
- 3. Dimensional Characteristics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 i System 21 Test ..............................................2 4 System 22 Test ..............................................2 I
' I
- 4. Hardness testing . . . . . . . . . . : . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 l
- 5. Scanning Electron Microscopy and Visual Inspection of Fracture Faces . . . . . . . . 5 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 i i
I i
1 I
i i
t 1
l l
I l
r L.
l l.
l t
i
.I 1
i 1
i j
i 6
i 1
LIST OF TABLES I Page l
Table 1 Measurements and ANSI /ASME Specifications
- for 5/8-11 Threads j (inc hes) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 l Table 2 Hardness Test Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 ,
l l
l 1
LIST OF FIGURES Page 4
Figure 1 Documentation received with stud pieces. .......................7 4
Figure 2 BNL Drawing of TM1 Stud pieces showing cuts for hardness test and SEM sam pl es. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 Figure 3 Side view of ; re" .tud pieces . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 l
Figure 4 Fracture face of TMI stud piece B. . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 Figure 5 Fracture face of TMI stud piece A. .. . . . . . . . . . . . . . . . . . . . . . . . . . . 11 2
Figure 6 - SEM photomicrograph of stud fracture face B (25 kV,22 x magnification). 12 Figure 7 SEM photomicrograph of stud fracture face A-(25 kV,22 x magnification). 13
- g. g=eemme
., ': l l Examination of a Bolt with Boric Acid Attack 1
From Three Mile Island Nuclear Generating Station i
1
- 1. Introduction The U.S. Nuclear Regulatory Commission (NRC) contracted with Brookhaven i
National Laboratory (BNL) to confirm the root cause analysis of a failed bolt at Three Mile Island Nuclear Generating Station (TMI). The root cause analysis was conducted by TMI.
Supplementary documentation supplied by NRC indicated that the bolt was removed from a 4
valve in the pressurizer at TMI. The bolt was stated to be 5/8 inch diameter, A-193, B7
- material.
BNL testing and analysis was to consist of:
,'l
- measuring the hardness of the bolt, j' *
- determining dimensional characteristics according to System 21 and System 22
- i. of ASME Bl.3M ('Ref.1), and SEM examination of the bolt for its failure mode. j
- 2. Descriotion of Stud Pieces j i
' Two pieces of the " bolt" to be examined were received at BNL, accompanied by the paperwork shown as Figure 1. _According to this document, the pieces were stated to be j item #2 in the drawing having 46,000 disintegrations per minute (dpm) smearable !
contamination and a contact reading of 4 millirem / hour (mrem /hr). The " bolt" was actually ,
a threaded stud, and was covered with rust-colored corrosion. A BNL drawing of the stud - !
pieces "as received" is shown in Figure 2. This figure also indicates the section cuts for the tests described below. ,
The tests for dimensional characteristics require clean materials, so the stud pieces were decontaminated in preparation for thread gaging tests by washing with an alkaline detergent solution (Quick Off, The Quick Chemical Co.) and hand scrubbing with a wire brush. Following this they were soaked in a solution containing ammonium hydroxide, EDTA, and Alconox and wiped off. These activities reduced smearable contamination to less than 100 dpm. Dose rate at contact with both pieces was less than 0.7 mrem /hr.
The bolts were photographed following decontamination, as shown in Figures 3,4 :
and 5. In spite of the cleaning for decontamination purpose, the surfaces of the nut and stud pieces exhibited significant corrosion. Stud piece A (no nut)'showed visual evidence of having been stretched,' with the threads deformed, as if they had been stripped. The threads on the stud piece B with the nut in place were deformed (possibly due to galling) on the side.
of the nut with the fracture face present. (The ASM [Ref. 2] defines galling as " developing a' condition on the rubbing . surface ... where excessive friction between high spots results in 1
e
localized welding with subsequent spalling and a further roughening of the surface.") The threads on the opposing side of the nut appeared to be undamaged, except for the surface corrosion.
- 3. Dimensional Characteristics The two pieces of threaded stud were inspected according to System 21 and System 22, of ANSI /ASME Bl.3M (Ref.1).
l System 21 Test !
System 21 requires testing for GO maximum material, NOT GO functional diameter, and minor diameter. GO and NOT GO threaded ring gages, respectively, can be used for the first two parameters, while an optical comparator can be used for the minor diameter.
GO and NOT GO gages are functional tests, in which a bolt or threaded stud is -
threaded into the gage, which resembles a threaded nut. The GO gage, which determines that maximum material is not exceeded, is passed when the bolt of interest can be threaded through the gage _ and beyond. The NOT GO gage is passed when the bolt of interest can n91 be threaded into the gage for three turns. The NOT GO gage measures functional diameter.
A threaded ring gage, size 5/8-11-UNC(2A) (TG-7, BNIJ IT462, calibration expiration 2/15/95) was used for the GO and NOT GO tests. Stud piece B (with the nut present) was tested on both sides of the nut. On the longer threaded side with the f acture face, the stud failed the GO test. The short threaded side easily fit the GO gage,8 : had insufficient thread to pass all the way through the gage, which constitutes a failus Stud piece A failed the GO gage test, since it could not be threaded all the way thrc 4 the gage. t According to the ANSI standard, the " screw thread of a threaded product shall be acceptable when each of the thread characteristics specified in the designated gaging system )
is found acceptable." The failure to fulfill one characteristic thus constitutes an unacceptable j product. Further tests under System 21 were stopped. I System 22 Test '
System 22 calls for measuring GO maximum material, minimum material, and minor diameter. The test for GO maximum material already failed both stud pieces under System . I 21 above, so there was no need to pursue the test further. However, the optical comparator was used to measure major and minor diameters, and thread depth. These re:;ults and the l
specified values and tolerances for 5/8-11 UNC external threads are shown in Table 1.
The measurements indicate that the only undisturbed threads (starter side of stud piece l
q B, with the nut) are too big for the specified minimum diameter. This could explain the 2
l l
i t
^
galling observed'on the fracture side of the nut, if the nut had been run up the stud and then j backed off.
Following this test, the stud pieces were sectioned for scanning electron microscopy (SEM) and hardness testing.
4 Table 1 l Measurements and ANSI /ASME Specifications
- (inches)
Major Diameter Minor Diameter Thread Depth Stud w/o Nut 0.5993 O.5109 0.0468
- Stud with Nut: 0.6220 0.5210 0.0490 I Starter Side Stud with Nut: 0.5962" 0.5116" 0.0363" l Fracture Side ANSI Specification !
Maximum 0.6234 0.5152 .05413 Minimum -- 0.6113
- Average of two measurements.
- 4. Hardness testine Hardness tests were conducted on the two stud piece ends cut as shown in Figure 2, such that the cut piece was as long as the thickness (5/8 in). Test results are shown in Table 2.
The initial set cf test readings for Section C (stud piece A) were inconsistent, and microhardness measurements were conducted on two separate instruments, after mounting and polishing the samples. After the microhardness measurements, the Rockwell hardness tests were repeated on section C using the polished stud specimen after it was removed from the mounting material.
The Rockwell C values for stud section C are lower as measured using the hardness tester and more scattered. Microhardness values for section C. are more consistent and approximately equal to the values found for Section D (stud piece E). The lower values for the Rockwell C tests reflect the fact that the bulk hardness for piece C is lower.
Microhardness tests measure the hardness of much smaller areas of material, and the resubs 3
.e
can be 'affected by precipitates or harder phases. Rockwell C tests use larger indenters that L measure more material; thus, they can be considered as approaching a bulk measurement.
)
' The consistent microhardness values for stud piece C and Rockwell C values for Section D (stud piece B) fall within the range of 33 to 36 on the Rockwell C scale. The
, i corresponding approximate tensile strengths for these values are 150 to 164 ksi (Ref. 4). l The lower average value on the Rockwell C tester was 25.5, which corresponds to 1
4 approximately 124 ksi. The TMI stud material is stated to be ASTM A193 Class B7. While
! ASTM A193 does not specify maximum hardness values for Class B7, it does specify a minimum tensile strength of 125 ksi for threaded fasteners less than 2.5 inches diameter (Ref. 5). The tensile strength values estimated from hardness measurements indicate that the i bolting material was within specification. ]
l . - -
Table 2 l Hardness Test Results i
Rockwell C Rockwell C Rockwell C Rockwell C Esdness Hardness Hardness Hardness !
i (Knoop)* (Vickers") i Stud Section C l 22 36.3 (363.3) 32 (313.8) 24 .
l 29 35.5 (356.1) 22
, 29- 34.9 (350.1) 30 22 36.2 (362.7) 28 Avg. 25.5 Avg. 35.7 Avg. 26 Stud Section D 33 36.9 (369.3) 35.5 (347.7) Not tested 33 36.8 (368.1) 34 36.6 (366.0) 33 35.9 (359.4)-
Avg. 33.3 Avg. 36.6 First microhardness measurement calibrated as Knoop hardness in parentheses.
Rockwell C values calculated from these.
Second microhardness measurement calibrated on Vickers scale is in parentheses.
Rockwell C value calculated from this.
4
l
! . . . 1 i
1
- 5. Scanning Electron Microscoov and Visual Inspection of Fracture Faces I i Stud pieces A and B were sectioned as shown in Figure 2, to remove the fracture i
faces for scanning electron microscopy (SEM). Figure 3 is a side view of the two pieces before sectioning, and after decontamination. 1 i l
- The visual appearance of the fracture faces (Figures 4 and 5) indicate that the stud pieces were from two separate failed studs. Fracture face B (Figure 4, from the stud piece with the nut) was heavily corroded around the threads, but the fracture face appeared as the
- tip of a relatively intact central core. Fracture face B is relatively flat compared to face A
- (Figure 5) on the other piece. Face A is pointed, being much smaller in area, and is i
surrounded by a larger area of general corrosion. The general corrosion seen in these and the SEM photomicrographs below is consistent with the wastage corrosion seen in other cases
- of component failures due to boric acid attack (Ref. 6).
SEM photomicrographs of the fracture faces are shown in Figures 6 and 7 (both at 22X magnification). Fracture face B (Figure 6) has two areas with ripple marks which suggest a fatigue-assisted failure. The non-corroded portions of both faces A and B indicate ductile rupture. The SEM micrographs of both fracture faces confirm that they are from two separate studs.
- Visual and SEM examination of the two fractures confirm the presence of general corrosion in both pieces which contributed to the failure of the studs. Face A appears to have undergone more corrosion and some wear before failure, which seems to have been induced by tensile stress. In Face A, the wear before failure is evidenced'by the stretched.
and missing threads on the stud. Face B, in addition to the possible fatigue marks in two locations, has indications of a torsional stress in its overall appearance. It may have failed j when the stud was removed, i
- 6. Summary Two stud pieces were tested for physical characteristics and examined for evidence of boric acid attack. Both pieces failed ANSI /ASME gaging tests for dimensional characteristics, indicating that the stud piece did not meet ANSI specifications. Because the ,
gaging tests were conducted on failed stud pieces with obvious corrosion attack, no statement I can be made about stud thread acceptability before the studs were put in service. Tensile strength values estimated from Rockwell C hardness measurements indicate that the stud l pieces were within the tensile specification for A-193, B7 materials. The corroded state of i the stud pieces was consistent with boric acid attack, and SEM examination of the stud fracture faces showed that they failed by ductile rupture.
5
e 1
References
- 1. ANSI /ASME Bl.3M-1992, " Screw Thread Gaging Systems for Dimensional ;
Acceptability - Inch and Metric Screw Threads," American Society for Mechanical ;
Engineers, New York,1993, i
- 2. American Society for Metals, Metals Handbook, 8th ed., Vol.1., Properties and Selection of Metals, Metals Park, Ohio,1961.
- 3. ANSI /ASME D1.1-1989, " Unified Inch Screw Threads," American Society for Mechanical Engineers, New York,1989.
- 4. Nondestnictive Insoection and Ouality Control, Metals Handbook. Rioht Edition. Vol.
11, American Society for Metals, Materials Park, Ohio (1976).
- 5. Fastener Standards. Sixth Edition, Industrial Fasteners Institute, Cleveland, Ohio I (1988).
- 6. C. J. Czajkowski, " Survey of Boric acid Corrosion of Carbon steel Components in ;
Nuclear Plants," NUREG/CR-5576, Brookhaven National Laboratory,1990. )
l 99 M
6
1
- \
\
8 !9 t \s g 3
---__q
)
i g Ly
. c ste xeg s
' ~
s p ! !! !!! j N s j o m m N s a
- ener xx 8 x 8
- o.. .
N s s e.
E j_4..w 5
~
i
.5E5 8 t.:
g i
- :":5a e .
b :::o 1s a t -
8 :ss : 2 eu s
- n. :
- a a.
W ,,
- '::::: it. 3 ,
) 33\ ;,oi-o-,= oc=o 3 m
x D .
wa-
@ s#
5
. ! c_ 1 a
l ...sii:'
" ! l)!!!////////// .///// /// 's i 323"d #
6 8 - . >i.!.il.
c i
.=
8 l p 7 UW///I// ///r@@lu // ,'i -
a e g "piH!!
- datii 5 0 a .: ::""
@f5 8 5dd!Eii! 4 E
l i()/////// ///b5/ // // 0 t.. [
z [ :r v' o
~.
c T*; is o.
@. s
'I a i" , W (//////// / /,,$/ ////// .O
.eP i
s @ g i is35!!c?;m d///////// 4a7/////// / O s u v 1
@c iA: y
[
%. " aq - t ///// /// "I 4//// //// - --
I suun - e 3
d, u
ir g -
A - i a fI j Q<w; i //// /< // //c ~ // ll '
n } ;! e vr l
jh n
- ///////////// TT E
.so a n
b i
' i 33 $5 ; jl l
7 _
~ '
l ~T~M.T Sa ' llune s rud m<sr .
^
hAildd ..
! .A 3 ky j , .3A 4
' ;.j-h Seck ~ C. I F 4./4,o M ri S aT' * " A bilY '
l
/o4/a- u~m+ct
<fobafs/%,,tli ;5.jif i #
{
l@ df n[% cd ' ~ ~ ~ '
lii
- hNdu% r l 4 o.2. ne/A, <a x,
< sasay fen '
Seew D
,Sn,-/4. a-TACT l
t t il 8
Sec7 Iou P.)
- I W -
p Q' io A /A- cosmcr --
$ !j / a g ggg < soo o(/n / /ooen _
I i I
hic 6 ( l 0 % lae canncr
+m
< Goo gg /,gs Figure 2. BNL Drawing of TMI Stud pieces showing cuts for hardness test and SEM samples.
8
i ... .
I i
l i ,..
'^
n.
.m E
g k 3 i a
43 ,
m l3 I s
- k. .
~
E bho E iE .
.,l- l E
2"
! lE ,
e = lE
- m. . n
& E ' . .i E llili d>
N_fSl.Yl'.$h_' .
lE f
armn' n:.. .
.. -se .aa l
l
g ,_ - _ _ . - . _ _ _ _ . . - gy
{ .- ..
q i
1 i
d J ..
. **s, .
i .
\-
),
1 -
1 .
e
- ' Y, , -
l i
,' b
,>v .
77./,y_ ...s, I .
. . .. a
't . ,
. , .y - . . .m ... T& <
l
' * ' i_. ~ . , ' . , ' . , ,
T, ' i I , , ', _.! ',.-
w l
,.4,Q <
l
' .1
, - . . s -
r
. j . .. '
f
(?
\
'e,.
- - , ,K ,_, ,, f
, U , . 3. a s. c. ..
s
, = . .. , .
i -.
f.
x
- - s .
j .
j, . >~~. . _ ;4 _.
~
- ,'. [ } * *
- e
- . .- . < .
j \
-6.,
~ . 4 y es . \ ." *.,_ . ,.,.. ,
-,s
,;- ' .' . . . . .a.'
,'t w %
$ g
, v.
... ..y..-
-e. pa 1
,.j,- ' . , - ' /
y ff.
y
. Q;<,,.' ."l],, .
/~
'.~
e ._- s -
- . ~ . . ; -
r-- ,
~
l l- . ~1 .
7.f.
s.
s., ,
/ .
- < A-
., l c
.v fr .
W
) ^%f ' .
x ..
, [- . , _
Figure 4. Fracture face of TMI stud piece B.
E. . - . . . - . - ,- ,-- ,,. ,. ,, ,.-,.. ,., ,. , , - , - . . , . - - - . . - , . . - - - - , . , . - - - , , . , - - - , .. - . . , ,. i
b .
- _ ~ I. : ~
~, :; -, y h' $_$
l i i.
g g . .) .
,,, 2, ; - ,
9 .-. p
- f',y' i
. D . -h. ., ' 1 . ., ;
.,, . 4 f.
r .(? >
l
_. g
' $, - .? . . ..,
. s [.
. ,f .~ 4 ^
'a' -
- . :.d .
1 ,,g
). - .z. . 'E p 3j. d: , *
, g , , ,. f, ; . ,
Y- m,,.. ;
' A M.).J. ..A h
'lrf -% v . .'5 h.Y. I.s,.
w's:..: y 'f;N4.
I - 4: * $ h . , ..
l,
.. c . 4 :
,, $ .' Ek'k .c,['M,: .m.,[Q- <M:!%,y' .w
- M.;g .
-w( #j l ..L *T b.* "r)4,~l%. [. . ,3g.f,.;?J
. , . . -' y.-,-
t . . . ., _
l . .
^'
..ap ~y
?
a . y ,1. % :4' ~..J : '
, . . _ , ,.}
l f.m.$k '
- n. . %:kr? ~
~
l p.h
,h ), , '*h. -;
t .r
. 9 .,r
, . , . ~ '~._.s y
.s . .'e- . 'i",
i t * , .' ,g. r , ; %v .. . . . .
- f. .*
. ,Yg, % .'.,"4-.,,,, .
. .gl
- 1. . . . . .
.'t, W
.s ym;+>s. $l5 ; M, e r t'
~-
w .'
w.~....- ~
g' g 4 .m ;. .a .
- s. g,.
- f. .' * - ( .- .*,h.
> k. 1..
4 e- . .
.n n b.:
> , c:. .. a k ..
M f \lil
~
o ~
- e. . .. , .,'T.. ,M i. , . .4 f ...
. ape.. . .
I. .s.u. - . . %. ,
,-,: s . .
f,.
(I'l
% ,. fib.$.5 - Y c,. . ,,t..
y*, <.. *'.l _ -' j.
t... ~.; '
&s' -
. f. . '
h'}
k.jf e A t,.h /
hm hg','..o."p.L %,~ .
.t
.z . u -
r.
ny, - &...; .vr. ,;. w : p f ,r #.5. - ., n. , , .,. c . , E, y ;.
,g. . g.
+. ; 9 . ..: i, - ; . ,. r...,,.<.,.- -
.v. , ., . l , a . -
h
' ' -[4. . .. ;$.._
[g v' ,Y,? : .f NN .. . !';' N ~! ^ p..f
-.~; g S.<, n.cn
.. we . t
..n ..
l
.s
,. y.y e.t. c .e c
, . s:
...,t J r .
+
t >
. 4'. ..
.~c.
.. y,s. gL.. s. L.
j
' % . ./ -fp
. -s . - ,,, .~<- .
.I g. '":f,y ^f;- -
, . %5?, , , f
'5 '%
f4 .
y p;p? v ^, > 3 : ;a y
?y;p,y
.:p.f* y
'f ; *e-
~'
t w g-9.>y s. . p' - .
, .. pjptr '- ,p j .
3 -
e , 741p,,. g,.., .. .-
p,gos.g- .
. ;. .c---
. a- .,.,,
W W
.q.
. .E y 7, v .W,, ' .q a.V ,
.g
.r.. , , ., p.. .
. .. . ' m 3
~
., ~6
$.~^ -
.I?. [* ,p.,
g
. ,, .. ; n . . .
% ~
y r ;,b ' ri.' ' d}g
@ [;.
j [.), ,
l .
2 fi ' ,
- Figure 5. Fracture face of TMI stud piece A.
~
11 4
l l f,,
~% w -
5,-
1 41 l :.'
! 7^^' ,,
,f, am -
. r i D _Y '
_. . .: JF25$k i l~ /ERT M .M \$~d5 0 t
- t. .,
, \u ,
h '
4:
l '. ..
l n, , ',. i *$
s
~
l .' -
'\
t j ,.- - _ . _
m 1,000.0 m hh) l
.m l Figure 6. SEM photomicrograph of stud fracture face B (25 kV,22 x magnification) 12
. - - - - - - - - - - - - - - - - - ~ - - - - - ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~
\ : . ~. ~. -- - - - - -
i i*
^^% __ _
^
i j '. .
l
~ l 1 .
l :
p l
l
.t.
(g,.8 . . i 1
.\;;_
,3 N'
1 f_
F
, j;- : :
k e i j,.3 0" t
N E.
-q-lt
' $i c.W . 1
- '1' ','1 N .
- i p.? Q
!i i.
.M.*T.0'.c '
E%1
' ya.. ' ' '.)
.V., _ q y .9 d: . e .<. -
' . 6.i *
( . . , Q-l-'.. , ;fh - . '
~
l^ $M 'I 1,000.0 m
{
'. '-f. i )I
.xln a u ~ ..,. . .
- . , A *. . .
f; Figure 7. SEM photomicrograph of stud fracture face A (25 kV,22 x magnification) 13
__-