|
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Category:CONTRACTED REPORT - RTA
MONTHYEARML20210D8461999-06-30030 June 1999 INEEL/EXT-99-00415, Technical Evaluation Rept(Rev 1) on Proposed Alternative to Iwe/Iwl Containment Insp,Comanche Peak Electric Station ML20209G7561999-02-28028 February 1999 Final Rept, Technical Evaluation Rept on 'Submittal-Only' Review of Individual Plant Exam of External Events at Comanche Peak Steam Electric Station,Units 1 & 2 ML20135B3821997-02-24024 February 1997 Exam of Motor-Operated Valve Failures W/Application to Increasing Surveillance Testing Period at Texas Utilities Co. Comanche Peak,Units 1 & 2 ML20135B4331997-01-0606 January 1997 Evaluation of Candidate LSSC Check Valves for Risk Based IST Extension at Comanche Peak Units 1,2 ML20138H9941997-01-0202 January 1997 Technical Evaluation Rept of IPE Submittal & RAI Responses for Comanche Peak Steam Electric Station,Unit 1 ML20117J0121995-11-13013 November 1995 Assessment of Cable Functionality Performance Issues for Tue Comanche Peak Unit 1 Thermo-Lag Fire Endurance Tests, Technical Evaluation Rept L-95-014, TER on First 10-Yr Interval ISI Program Plan:Tuec,Cpses, Unit 21995-04-30030 April 1995 TER on First 10-Yr Interval ISI Program Plan:Tuec,Cpses, Unit 2 ML20126H5491992-12-14014 December 1992 Technical Evaluation Rept, Technical Evaluation of TR RXE-91-002 (Reactivity Anomaly Events Methodology) for Tugc ML20116N9441992-10-31031 October 1992 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Comanche Peak Nuclear Power Plant ML20106D9251992-03-31031 March 1992 Technical Evaluation Rept on First 10-Yr Interval ISI Program Plan:Tuec,Cpses,Unit 1,Docket Number 50-445 ML20095L1051991-12-31031 December 1991 Technical Evaluation Rept TUE-1 Departure from Nucleate Boiling Correlation ML20073M9031991-04-30030 April 1991 Analysis of Flow Stratification in the Surge Line of the Comanche Peak Reactor ML20235B0711988-12-31031 December 1988 Conformance to Reg Guide 1.97:Comanche Peak -1/-2, Technical Evaluation Rept ML20215M1701987-05-31031 May 1987 TMI Action-NUREG-0737 (II.D.1),Comanche Peak Steam Electric Station Unit 1, Informal Technical Evaluation Rept ML20214R4371987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Comanche Peak-1 & -2, Final Informal Technical Evaluation Rept ML20207N2461986-12-16016 December 1986 Technical Assistance to Nrc,Region Iv,For Preservice Insp, Monthly Ltr Rept for Nov 1986 ML17334B0331986-11-30030 November 1986 Input for Ser,Beaver Valley Power Station Units 1 & 2, Braidwood Station Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Catawba Nuclear Station Units 1..., Reactor Trip Sys Reliability Item 4.5.2 Generic Ltr 83-28. ML20215M8911986-10-20020 October 1986 Technical Assistance for Preservice Insp, Monthly Ltr Rept for Aug & Sept 1986 ML20207F1591986-07-0808 July 1986 Energy Technology Engineering Ctr Technical Assistance to NRC for Preservice Insp, Monthly Ltr Rept for June 1986 ML20136F6531985-12-31031 December 1985 Review of Tdi Diesel Generator Owners Group Engine Requalification Program,Final Rept, Technical Evaluation Rept ML20210K6451985-11-30030 November 1985 PRA Insights ML20138M1961985-10-31031 October 1985 Review of Design Review & Quality Revalidation Rept for Tdi Diesel Generators at Comanche Peak Steam Electric Station, Technical Evaluation Rept ML20134A7631985-09-30030 September 1985 Station:Alleged Climate of Intimidation,Supplementary Rept ML20210C6961985-07-29029 July 1985 Executive Summary Technical Evaluation Rept on Comanche Peak Response Team Program Plan & Issue-Specific Action Plans,Rev 2, Books 1 & 2 ML20128H7791985-06-30030 June 1985 Rev 1 to Review of Engine Base & Bearing Caps for Tdi DSRV-12,DSRV-16 & DSRV-20 Diesel Engines, Technical Evaluation Rept ML20126E9861985-05-31031 May 1985 Review of Emergency Diesel Generator Engine & Auxiliary Module Wiring & Terminations, Technical Evaluation Rept ML20127D4431985-03-31031 March 1985 Conformance to Reg Guide 1.97,Comanche Peak Steam Electric Station,Units 1 & 2 ML20100G5771984-10-31031 October 1984 Control of Heavy Loads at Nuclear Power Plants,Comanche Peak Steam Electric Station,Units 1 & 2 (Phase 1) ML20097H6161984-09-30030 September 1984 Review & Evaluation of Tdi Diesel Engine Reliability & Operability - Comanche Peak Steam Electric Station Unit 1, Technical Evaluation Rept ML20097F7281984-09-30030 September 1984 Station,Alleged Climate of Intimidation ML20138C0791984-08-31031 August 1984 Draft Investigation & Assessment of Work Climate at Comanche Peak Electric Station ML20094G8561984-04-30030 April 1984 Control of Heavy Loads (Phase II-NUREG-0612),Comanche Peak Units 1 & 2, Draft Technical Evaluation Rept ML20091B5881984-04-25025 April 1984 Interim Rept on Protective Coatings ML20090K0291984-03-31031 March 1984 Control of Heavy Loads at Nuclear Power Plants,Comanche Peak Steam Electric Station,Unit 1 & 2 (Phase I - Draft) ML20053C3761982-03-31031 March 1982 Control of Heavy Loads at Nuclear Power Plants,Comanche Peak Steam Electric Station,Units 1 & 2, Draft Technical Evaluation Rept 1999-06-30
[Table view] Category:QUICK LOOK
MONTHYEARML20210D8461999-06-30030 June 1999 INEEL/EXT-99-00415, Technical Evaluation Rept(Rev 1) on Proposed Alternative to Iwe/Iwl Containment Insp,Comanche Peak Electric Station ML20209G7561999-02-28028 February 1999 Final Rept, Technical Evaluation Rept on 'Submittal-Only' Review of Individual Plant Exam of External Events at Comanche Peak Steam Electric Station,Units 1 & 2 ML20135B3821997-02-24024 February 1997 Exam of Motor-Operated Valve Failures W/Application to Increasing Surveillance Testing Period at Texas Utilities Co. Comanche Peak,Units 1 & 2 ML20135B4331997-01-0606 January 1997 Evaluation of Candidate LSSC Check Valves for Risk Based IST Extension at Comanche Peak Units 1,2 ML20138H9941997-01-0202 January 1997 Technical Evaluation Rept of IPE Submittal & RAI Responses for Comanche Peak Steam Electric Station,Unit 1 ML20117J0121995-11-13013 November 1995 Assessment of Cable Functionality Performance Issues for Tue Comanche Peak Unit 1 Thermo-Lag Fire Endurance Tests, Technical Evaluation Rept L-95-014, TER on First 10-Yr Interval ISI Program Plan:Tuec,Cpses, Unit 21995-04-30030 April 1995 TER on First 10-Yr Interval ISI Program Plan:Tuec,Cpses, Unit 2 ML20126H5491992-12-14014 December 1992 Technical Evaluation Rept, Technical Evaluation of TR RXE-91-002 (Reactivity Anomaly Events Methodology) for Tugc ML20116N9441992-10-31031 October 1992 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Comanche Peak Nuclear Power Plant ML20106D9251992-03-31031 March 1992 Technical Evaluation Rept on First 10-Yr Interval ISI Program Plan:Tuec,Cpses,Unit 1,Docket Number 50-445 ML20095L1051991-12-31031 December 1991 Technical Evaluation Rept TUE-1 Departure from Nucleate Boiling Correlation ML20073M9031991-04-30030 April 1991 Analysis of Flow Stratification in the Surge Line of the Comanche Peak Reactor ML20235B0711988-12-31031 December 1988 Conformance to Reg Guide 1.97:Comanche Peak -1/-2, Technical Evaluation Rept ML20215M1701987-05-31031 May 1987 TMI Action-NUREG-0737 (II.D.1),Comanche Peak Steam Electric Station Unit 1, Informal Technical Evaluation Rept ML20214R4371987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Comanche Peak-1 & -2, Final Informal Technical Evaluation Rept ML20207N2461986-12-16016 December 1986 Technical Assistance to Nrc,Region Iv,For Preservice Insp, Monthly Ltr Rept for Nov 1986 ML17334B0331986-11-30030 November 1986 Input for Ser,Beaver Valley Power Station Units 1 & 2, Braidwood Station Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Catawba Nuclear Station Units 1..., Reactor Trip Sys Reliability Item 4.5.2 Generic Ltr 83-28. ML20215M8911986-10-20020 October 1986 Technical Assistance for Preservice Insp, Monthly Ltr Rept for Aug & Sept 1986 ML20207F1591986-07-0808 July 1986 Energy Technology Engineering Ctr Technical Assistance to NRC for Preservice Insp, Monthly Ltr Rept for June 1986 ML20136F6531985-12-31031 December 1985 Review of Tdi Diesel Generator Owners Group Engine Requalification Program,Final Rept, Technical Evaluation Rept ML20210K6451985-11-30030 November 1985 PRA Insights ML20138M1961985-10-31031 October 1985 Review of Design Review & Quality Revalidation Rept for Tdi Diesel Generators at Comanche Peak Steam Electric Station, Technical Evaluation Rept ML20134A7631985-09-30030 September 1985 Station:Alleged Climate of Intimidation,Supplementary Rept ML20210C6961985-07-29029 July 1985 Executive Summary Technical Evaluation Rept on Comanche Peak Response Team Program Plan & Issue-Specific Action Plans,Rev 2, Books 1 & 2 ML20128H7791985-06-30030 June 1985 Rev 1 to Review of Engine Base & Bearing Caps for Tdi DSRV-12,DSRV-16 & DSRV-20 Diesel Engines, Technical Evaluation Rept ML20126E9861985-05-31031 May 1985 Review of Emergency Diesel Generator Engine & Auxiliary Module Wiring & Terminations, Technical Evaluation Rept ML20127D4431985-03-31031 March 1985 Conformance to Reg Guide 1.97,Comanche Peak Steam Electric Station,Units 1 & 2 ML20100G5771984-10-31031 October 1984 Control of Heavy Loads at Nuclear Power Plants,Comanche Peak Steam Electric Station,Units 1 & 2 (Phase 1) ML20097H6161984-09-30030 September 1984 Review & Evaluation of Tdi Diesel Engine Reliability & Operability - Comanche Peak Steam Electric Station Unit 1, Technical Evaluation Rept ML20097F7281984-09-30030 September 1984 Station,Alleged Climate of Intimidation ML20138C0791984-08-31031 August 1984 Draft Investigation & Assessment of Work Climate at Comanche Peak Electric Station ML20094G8561984-04-30030 April 1984 Control of Heavy Loads (Phase II-NUREG-0612),Comanche Peak Units 1 & 2, Draft Technical Evaluation Rept ML20091B5881984-04-25025 April 1984 Interim Rept on Protective Coatings ML20090K0291984-03-31031 March 1984 Control of Heavy Loads at Nuclear Power Plants,Comanche Peak Steam Electric Station,Unit 1 & 2 (Phase I - Draft) ML20053C3761982-03-31031 March 1982 Control of Heavy Loads at Nuclear Power Plants,Comanche Peak Steam Electric Station,Units 1 & 2, Draft Technical Evaluation Rept 1999-06-30
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20210D8461999-06-30030 June 1999 INEEL/EXT-99-00415, Technical Evaluation Rept(Rev 1) on Proposed Alternative to Iwe/Iwl Containment Insp,Comanche Peak Electric Station ML20209G7561999-02-28028 February 1999 Final Rept, Technical Evaluation Rept on 'Submittal-Only' Review of Individual Plant Exam of External Events at Comanche Peak Steam Electric Station,Units 1 & 2 ML20135B3821997-02-24024 February 1997 Exam of Motor-Operated Valve Failures W/Application to Increasing Surveillance Testing Period at Texas Utilities Co. Comanche Peak,Units 1 & 2 ML20135B4331997-01-0606 January 1997 Evaluation of Candidate LSSC Check Valves for Risk Based IST Extension at Comanche Peak Units 1,2 ML20138H9941997-01-0202 January 1997 Technical Evaluation Rept of IPE Submittal & RAI Responses for Comanche Peak Steam Electric Station,Unit 1 ML20117J0121995-11-13013 November 1995 Assessment of Cable Functionality Performance Issues for Tue Comanche Peak Unit 1 Thermo-Lag Fire Endurance Tests, Technical Evaluation Rept L-95-014, TER on First 10-Yr Interval ISI Program Plan:Tuec,Cpses, Unit 21995-04-30030 April 1995 TER on First 10-Yr Interval ISI Program Plan:Tuec,Cpses, Unit 2 ML20126H5491992-12-14014 December 1992 Technical Evaluation Rept, Technical Evaluation of TR RXE-91-002 (Reactivity Anomaly Events Methodology) for Tugc ML20116N9441992-10-31031 October 1992 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Comanche Peak Nuclear Power Plant ML20106D9251992-03-31031 March 1992 Technical Evaluation Rept on First 10-Yr Interval ISI Program Plan:Tuec,Cpses,Unit 1,Docket Number 50-445 ML20095L1051991-12-31031 December 1991 Technical Evaluation Rept TUE-1 Departure from Nucleate Boiling Correlation ML20073M9031991-04-30030 April 1991 Analysis of Flow Stratification in the Surge Line of the Comanche Peak Reactor ML20235B0711988-12-31031 December 1988 Conformance to Reg Guide 1.97:Comanche Peak -1/-2, Technical Evaluation Rept ML20215M1701987-05-31031 May 1987 TMI Action-NUREG-0737 (II.D.1),Comanche Peak Steam Electric Station Unit 1, Informal Technical Evaluation Rept ML20214R4371987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Comanche Peak-1 & -2, Final Informal Technical Evaluation Rept ML20207N2461986-12-16016 December 1986 Technical Assistance to Nrc,Region Iv,For Preservice Insp, Monthly Ltr Rept for Nov 1986 ML17334B0331986-11-30030 November 1986 Input for Ser,Beaver Valley Power Station Units 1 & 2, Braidwood Station Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Catawba Nuclear Station Units 1..., Reactor Trip Sys Reliability Item 4.5.2 Generic Ltr 83-28. ML20215M8911986-10-20020 October 1986 Technical Assistance for Preservice Insp, Monthly Ltr Rept for Aug & Sept 1986 ML20207F1591986-07-0808 July 1986 Energy Technology Engineering Ctr Technical Assistance to NRC for Preservice Insp, Monthly Ltr Rept for June 1986 ML20136F6531985-12-31031 December 1985 Review of Tdi Diesel Generator Owners Group Engine Requalification Program,Final Rept, Technical Evaluation Rept ML20210K6451985-11-30030 November 1985 PRA Insights ML20138M1961985-10-31031 October 1985 Review of Design Review & Quality Revalidation Rept for Tdi Diesel Generators at Comanche Peak Steam Electric Station, Technical Evaluation Rept ML20134A7631985-09-30030 September 1985 Station:Alleged Climate of Intimidation,Supplementary Rept ML20210C6961985-07-29029 July 1985 Executive Summary Technical Evaluation Rept on Comanche Peak Response Team Program Plan & Issue-Specific Action Plans,Rev 2, Books 1 & 2 ML20128H7791985-06-30030 June 1985 Rev 1 to Review of Engine Base & Bearing Caps for Tdi DSRV-12,DSRV-16 & DSRV-20 Diesel Engines, Technical Evaluation Rept ML20126E9861985-05-31031 May 1985 Review of Emergency Diesel Generator Engine & Auxiliary Module Wiring & Terminations, Technical Evaluation Rept ML20127D4431985-03-31031 March 1985 Conformance to Reg Guide 1.97,Comanche Peak Steam Electric Station,Units 1 & 2 ML20100G5771984-10-31031 October 1984 Control of Heavy Loads at Nuclear Power Plants,Comanche Peak Steam Electric Station,Units 1 & 2 (Phase 1) ML20097H6161984-09-30030 September 1984 Review & Evaluation of Tdi Diesel Engine Reliability & Operability - Comanche Peak Steam Electric Station Unit 1, Technical Evaluation Rept ML20097F7281984-09-30030 September 1984 Station,Alleged Climate of Intimidation ML20138C0791984-08-31031 August 1984 Draft Investigation & Assessment of Work Climate at Comanche Peak Electric Station ML20094G8561984-04-30030 April 1984 Control of Heavy Loads (Phase II-NUREG-0612),Comanche Peak Units 1 & 2, Draft Technical Evaluation Rept ML20091B5881984-04-25025 April 1984 Interim Rept on Protective Coatings ML20090K0291984-03-31031 March 1984 Control of Heavy Loads at Nuclear Power Plants,Comanche Peak Steam Electric Station,Unit 1 & 2 (Phase I - Draft) ML20053C3761982-03-31031 March 1982 Control of Heavy Loads at Nuclear Power Plants,Comanche Peak Steam Electric Station,Units 1 & 2, Draft Technical Evaluation Rept 1999-06-30
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20210D8461999-06-30030 June 1999 INEEL/EXT-99-00415, Technical Evaluation Rept(Rev 1) on Proposed Alternative to Iwe/Iwl Containment Insp,Comanche Peak Electric Station ML20209G7561999-02-28028 February 1999 Final Rept, Technical Evaluation Rept on 'Submittal-Only' Review of Individual Plant Exam of External Events at Comanche Peak Steam Electric Station,Units 1 & 2 ML20135B3821997-02-24024 February 1997 Exam of Motor-Operated Valve Failures W/Application to Increasing Surveillance Testing Period at Texas Utilities Co. Comanche Peak,Units 1 & 2 ML20135B4331997-01-0606 January 1997 Evaluation of Candidate LSSC Check Valves for Risk Based IST Extension at Comanche Peak Units 1,2 ML20138H9941997-01-0202 January 1997 Technical Evaluation Rept of IPE Submittal & RAI Responses for Comanche Peak Steam Electric Station,Unit 1 ML20117J0121995-11-13013 November 1995 Assessment of Cable Functionality Performance Issues for Tue Comanche Peak Unit 1 Thermo-Lag Fire Endurance Tests, Technical Evaluation Rept L-95-014, TER on First 10-Yr Interval ISI Program Plan:Tuec,Cpses, Unit 21995-04-30030 April 1995 TER on First 10-Yr Interval ISI Program Plan:Tuec,Cpses, Unit 2 ML20126H5491992-12-14014 December 1992 Technical Evaluation Rept, Technical Evaluation of TR RXE-91-002 (Reactivity Anomaly Events Methodology) for Tugc ML20116N9441992-10-31031 October 1992 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Comanche Peak Nuclear Power Plant ML20106D9251992-03-31031 March 1992 Technical Evaluation Rept on First 10-Yr Interval ISI Program Plan:Tuec,Cpses,Unit 1,Docket Number 50-445 ML20095L1051991-12-31031 December 1991 Technical Evaluation Rept TUE-1 Departure from Nucleate Boiling Correlation ML20073M9031991-04-30030 April 1991 Analysis of Flow Stratification in the Surge Line of the Comanche Peak Reactor ML20235B0711988-12-31031 December 1988 Conformance to Reg Guide 1.97:Comanche Peak -1/-2, Technical Evaluation Rept ML20154N9991988-09-23023 September 1988 Notification of Contract Execution,Mod 19,to Review & Evaluation of Commanche Peak Program Plan. Contractor: Teledyne Engineering Svcs ML20154P0131988-09-23023 September 1988 Mod 19,extending Performance Period at No Addl Cost,To Review & Evaluation of Commanche Peak Program Plan ML20153H1851988-04-29029 April 1988 Mod 1,exercising Option to Extend Contract,To NRC Comanche Peak Ofc Complex ML20153H1661988-04-29029 April 1988 Notification of Contract Execution,Mod 1,to NRC Comanche Peak Ofc Complex. Contractor:Texas Utils Electric Co ML20151A0501988-03-29029 March 1988 Notification of Contract Execution,Mod 18,to Review & Evaluation of Comanche Peak Program Plan. Contractor: Teledyne Engineering Svcs ML20151A0641988-03-29029 March 1988 Mod 18,adding Incremental Funds,To Review & Evaluation of Comanche Peak Program Plan ML20147F2351988-01-0404 January 1988 Contract: Review of Retran Computer Code & Plant Specific Info on Steam Generator Overfill for Comanche Peak Steam Electric Station,Units 1 & 2, Awarded to SBA & Intl Technical Svcs,Inc ML20236N6291987-11-0505 November 1987 Notification of Contract Execution,Mod 15,to Review & Evaluation of Comanche Peak Program Plan. Contractor: Teledyne Engineering Svcs ML20236N6441987-11-0505 November 1987 Mod 15,adding Incremental Funds,To Review & Evaluation of Comanche Peak Program Plan ML20237L2171987-08-14014 August 1987 Notification of Contract Execution,Mod 14,to Review & Evaluation of Comanche Peak Program Plan. Contractor: Teledyne Engineering Svc ML20237L2451987-08-14014 August 1987 Mod 14,providing Addl Funds,Revising Estimated Levels of Effort for Four Tasks within Contract,Adding Addl Task & Extending Period of Performance,To Review & Evaluation of Comanche Peak Program Plan ML20215M1701987-05-31031 May 1987 TMI Action-NUREG-0737 (II.D.1),Comanche Peak Steam Electric Station Unit 1, Informal Technical Evaluation Rept ML20214M2361987-05-0808 May 1987 Mod 13,adding Incremental Funds & Changing Monthly Business Ltr Rept for Task Orders,To Review & Evaluation of Comanche Peak Program Plan ML20214M2161987-05-0808 May 1987 Notification of Contract Execution,Mod 13,to Review & Evaluation of Comanche Peak Program Plan. Contractor: Teledyne Engineering Svcs ML20206J0981987-04-0808 April 1987 Notification of Contract Execution,Mod 12,to Review & Evaluation of Comanche Peak Program Plan. Contractor: Teledyne Engineering Svcs ML20206J1051987-04-0808 April 1987 Mod 12,reflecting Administrative Changes Due to NRC Reorganization,To Review & Evaluation of Comanche Peak Program Plan ML20206H8601987-04-0101 April 1987 Notification of Contract Execution,Mod 11,to Review & Evaluation of Comanche Peak Program Plan. Contractor: Teledyne Engineering Svcs ML20206H9421987-04-0101 April 1987 Mod 11,increasing Level of Effort,Adding New Task Areas, Incorporating Task Ordering Procedures & Extending Period of Performance to 870930,to Review & Evaluation of Comanche Peak Program Plan ML20214K1671987-04-0101 April 1987 Notification of Contract Execution: NRC Comanche Peak Ofc Complex, Awarded to Texas Utilities Electric Co ML20214R4371987-03-31031 March 1987 Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Comanche Peak-1 & -2, Final Informal Technical Evaluation Rept ML20207M8301986-12-29029 December 1986 Notification of Contract Execution,Mod 10,to Review & Evaluation of Comanche Peak Program Plan. Contractor: Teledyne Engineering Svcs ML20207M8521986-12-29029 December 1986 Mod 10,extending Period of Performance to 870315,to Review & Evaluation of Comanche Peak Program Plan ML20207N2461986-12-16016 December 1986 Technical Assistance to Nrc,Region Iv,For Preservice Insp, Monthly Ltr Rept for Nov 1986 ML20215D1731986-12-0808 December 1986 Notification of Contract Execution,Mod 9,to Review & Evaluation of Comanche Peak Program Plan. Contractor: Teledyne Engineering Svcs ML20215D1871986-12-0808 December 1986 Mod 9,increasing Level of Effort Under Task 9(i),to Review & Evaluation of Comanche Peak Program Plan ML17334B0331986-11-30030 November 1986 Input for Ser,Beaver Valley Power Station Units 1 & 2, Braidwood Station Units 1 & 2,Byron Station Units 1 & 2, Callaway Plant Unit 1,Catawba Nuclear Station Units 1..., Reactor Trip Sys Reliability Item 4.5.2 Generic Ltr 83-28. ML20215M8911986-10-20020 October 1986 Technical Assistance for Preservice Insp, Monthly Ltr Rept for Aug & Sept 1986 ML20215G4991986-10-0909 October 1986 Mod 8,extending Completion Date to 861130,to Review & Evaluation of Comanche Peak Program Plan ML20215G4921986-10-0909 October 1986 Notification of Contract Execution,Mod 8,to Review & Evaluation of Comanche Peak Program Plan. Contractor: Teledyne Engineering Svcs ML20207F1591986-07-0808 July 1986 Energy Technology Engineering Ctr Technical Assistance to NRC for Preservice Insp, Monthly Ltr Rept for June 1986 ML20199K9311986-07-0303 July 1986 Mod 7,changing Project Officer,To Review & Evaluation of Comanche Peak Program Plan ML20199K9051986-07-0303 July 1986 Notification of Contract Execution,Mod 7,to Review & Evaluation of Comanche Peak Program Plan. Contractor: Teledyne Engineering Svcs ML20155E7951986-03-19019 March 1986 Notification of Contract Execution,Corrected Mod 5, to Review & Evaluation of Comanche Peak Program Plan. Contractor:Teledyne Engineering Svc.Mod 6 Encl ML20141A4121986-03-19019 March 1986 Notification of Contract Execution,Mod 5,to Review & Evaluation of Comanche Peak Program Plan. Contractor: Teledyne Engineering Svcs ML20155E8031986-03-19019 March 1986 Mod 6,extending Completion Date for Task (G) as Addressed in Mod 4,Attachment A,To Review & Evaluation of Comanche Peak Program Plan ML20141A4791986-03-19019 March 1986 Mod 5,revising Task (E) Incorporated by Mod 4 & Increasing Obligated Funding,To Review & Evaluation of Comanche Peak Program Plan ML20136F6531985-12-31031 December 1985 Review of Tdi Diesel Generator Owners Group Engine Requalification Program,Final Rept, Technical Evaluation Rept 1999-06-30
[Table view] |
Text
. - . . . . . . . _ - . . . . . . . - . . . _ _ . - . . - . . - - . - .-
7
- 4. 1 4
A 5
Evaluation af Candidate IASC Check Vahes for Risk Based BT Essession at Ceasanche Peak Units 1,2 e
i i
l 5
1 i
I i
e h-1 l K.L harmh y
! Cak Ridge Nananal%
l Oak Ridge, Tennessee J
s Jennary 6,1997 4
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NRC Job Code W6324 4
4
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l l
2 i
2 I
l j
2 1
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i 9 )o 30 30 0 L/5'
\
Rackground a
l Comanche Peak Suse Eleonic Sabon has nosedy abaiand to the NRC a squam for alief ham the l heervice Ten (IST) innsrvals curready mquimd by the ASME Code for canain check valves based on a pim* analyms d the vehes' impanance to safay, la theory, this analysis methodology usults in i the ranking ofcompensets ineo too basic categories, those dhigh asfay significance and those whh low -
! misty dp*== ne seal is to ensee that the aa=pa==* more imponant a plant safay are to be ented la a meaner that provides a high level of asaramos of their opersbdity. Another goal of the Risk Based approach (RBIST) is e show that IST inservals may be mesaded beyond the surnet seguirements i wkhout resulting in dr=*=*1y incamand safay risks. One comederation in this type danalysis is anaponent informanos history, both Don the specific plant as well as Aos an industry penpsmive.
i I Cansache Peak has repamd IST assasion tem their ament Code aquhansats (esuaDy quarterly) to j se interval d6 years on appradassely 380 " low suisty dphem" (LSSC) check valves. In an aSort to j provide infonastics aseded e evaluate potential cambdate check vahus at Counanche Peak tr masaded
- IST innervals, Oak Ridge Nanomal labonsory (ORNL) has does a brief review of the available perfonnance data for the vahes la question. De hilowing is a sumanary report on that analysis.
l Analysis Rasmits l An analysis was does on check vahe fhilst data obtained tom NPRDS for r'amaaA* Peak Units 1 and j 2 Aom 1990 through 1995. Unit I began comunercial service in 1990, while Unit tegen casamucial 4
speranon in 1993. " Raw" NPRDS hilure marratives were reviewed and characeanand acceeding Io the i
! crusna used in development of the ORNL check valve perfonnance database. De ORNL dnSese itself j l was not used for this analysis sinos it covers only the thee period 1984 through 1992, which would have ,
l hiled to incorporate most of the Comanche Peak operating acpenence Comanske Peak check valve l l
Ailure experience was avmwed acconhas to several parammers, includag seventy of degradanon (to the i valve itself), synsa, failure cause, and aanvaa** myset hilures 'A comparison of valves with failure i socords in NPRDS with the deferral cambdste vahes was.also made. Only 33 tilure records were included in the NPRDS database (as of November 1996) hr hunns oczarring bom 1990 through 1995.
} herefore, due to the anall failure ' population, all records were included in the analysis (i.e., maarnal i
leakage type failuns were included). Also dee to the halted hilure data svailable, a daniled compenson l no omr:11 indusuy perfonnance expensace was not made at this time.
l Cunende J%ek aback eekrfnibwe 3 - * ::-H904M3 _
l i
Of the 33 NPRDS check valve hilure records swallable for 1990-1995, the hilure dutribution acconhng j so scent of degradence is shown in Table 1: -
j Table 1 All Comunche Peak Cheek Vahe FaBarm by Estset of Degradatise 1
. Essest of L., W Mo. Fauures
- hinderate 11 j .
Lenificant 16 Externallankase 6 i
5 i
i 1
1 J
f
- - . . - - - - _ - . .- -.-. .. - . . . . . - - - - -- - . . .._~..- . .-. .. -
Ev:luatirn of Candidate LSSC Check Valves far Risk Based IST Extensi:n ct
, Comanche Peak Units 1,2
" Extent of degradation" refers to the effect of the failme on the ability of the component 13 perform one er more ofits design bW. not to any resultant effect on tmin, system, or plant operadon. For a check
- vaht, therefore, a signyicmt failure would be one in which the vaht either stuck open or stuck closed, exhibited mechanical binding, or had loose or detached internal parts. External leakage (e.g., bonnet or flange leakage) type failures wre not originally included in the ORNL check valve datahaw, but were identified for this analysis for the purpose of provuhng an murall representation of check valve performance at r=anche Peak.
If only moderate and sinai8~a* failures are considered, then for C=anche Peak dunng the study period ;
ofinterest,59% of the check valve failures were si-aiA~a' This compares with an industry avera approximately 35% sigmficant failures for 1991 1992 (excluding external leakage type failul Further extrlaation of the r==ach* Peak failures indacates that many of the significant failures were of the type to be expected in a new plant, however. Table 2 shows the failure distribution by extent of degradation and failure cause.
i Tdk2 l ,
Comanche Peak Check Valve Failure Distribution by Extent of Degradation and Failure Cause l ' Failure Cause No. Moderate Fr br No. Significant Failures l Abnormal wear 1 Abnormal wear, I design problem Abnormal wear, I procedure problem Foreign material 5 Foreign material; 2
~
design problem #
Foreign rnaterial; 5 proadure problem Maintenana problem 1 Procedure problem; 1 improperinstallation Manufacturing defect 4 Unknown 3 2 Normal wear i From Table 2 it is apparent that of the 27 failures involving internals degradation (i.e., excluding external leakage failures), 9 were related to " infant" type problems, including manufacturing defects or maintenance, inen11stion, or design errors. Seven of the sixteen sigmficant failures were related to these causes. Also, in consideration of the length of the IST interval extension requested, it is imponant to note that of the 27 internals-related failures,16 involved some type of age-related failure mecharusm such as debris accumulation or wear. Of the 16 signi6 cant failures,8 were age-related.
in order to provide a more detaded review, Table 3 lists all failures by (- =i-r- at ID and extent of degradation. Repeat failures are also identified. A summary of the significant and repeat failure records is provided (see notes).
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, Yable 3 Comanche Peak Check Valve Fausres by Campesest ID
- j. Composest Valve Type System No. fausres/Estest Espeat Valve se RBIST Notes m erdegradatios a asuurm sendidate (both deferrallist?
units)?
1AF 0086 APW IE Yes
! 1AF4093 AFW IS Yes I i
1AF4098 AFW IM Yes 1AF4101 Swina AFW IS Yes 2 1 3CA4016 Centam 2M Yes Yes 3 l Isolanon 4
ICC4657 Stop CCW IS Yes 4 ICC4831 Uft CCW 2M Yes Yes 9 j ICC 1075 Stop CCW l$ Yes 4 ICC 1076 Stop CCW l$ Yes 4 1CC-1071 Stop CCW IS Yes 4
- ICC4073 Stop CCW IS Yes 4 l __1C!A443 Lift CVCS IM
' 3CT4013 fan *=*===a' IE Yes j 3CT 0047 Cmalan==' IE Yes
! Scroy
- 3CT4063 cane...n.n, IE Yes i IY j ICT4077 cmataianwa' IE Yes i Sorsy -
! ICT 0094 casemn==at 1E Yes i 88m'
- 1DO4258 Diesel Fuel Oil IS Yes Yes 5
! 1FW4076 Tiltina dise Feedwater IS Yes 6 l IFW 0088 Tiltina dise Feedwater IS Yes 7
! 1814968 IJft e n nemin . 2M yes yes 9 leolation l 2CA4016 fameminnmat IM Yes Yes 3 leolanon i 2CC 0831 Uft CCW IS Yes Yes 11
! 2CS4368C IJft CVCS IM Yes i 2DO4258 DieselLube 2S Yes Yes 8
! M 4 2FW 0013 Tiltima dise Feedwater 2S Yes 12 3 2514968 IJft ran*=ia==at 1M,lS Yes Yes 10 l Isolation
- E Emernalleakage, M4daderale, MigntScant i
1 4
3 i
3 l
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=
.- , .v.
- -~-- .___.-.-
1
, Table 3 antes (taken imm NPRDS hihyg narredvest 1
- 1 Valve disc held cif hs sent due a suschanical hearterance between disc counterweight and valve i
body. - - --W defset.
! 2 Crack in valve aest cirammAmestial anal weld. beammhoenring defect.
3 Rapset Adlares due e dehns baudup on valve anst munidag tom moisnue in the system.
4 4 Stop check valve hiled open ese e conesion prodsca --==haaa between ping and bore ,
enring long periods dinactivity, periabe making dvalve was les than adequate Quanarty stroking dvalve had to be initiated to provost mastremos. l 1
] 5 Vahe disc detached teen hinged cosasados a vehe body due toe dupested cychag l j and high mesating pressure. (Osw Corp. "FIO $3").
i 6 Vsedor aspphed vehe with internet angle cisarance, essmag disc to bind on side supports prior
- e 8suy closing 7 landequate assembly procedure manteed la improper insaustion doorsion springs. Disc would l act huy contaca the met. l t
i g Rapset asilens due to wear and sismadag dviton valve sest/gasks on estal analing surface
! sesulting in tsaring of(son) whom seat anstenal " Valve inadequately designed for appucanon."
(Ckm Corp. "FIO $3").
{
1 9 RapsetinternalIsakage hihees.
j 10 Espaat hiluna thee to gethag, sent socimag '
il Stuck opea due to ' tied aest and disc." FaGare cause unknown.
1
! 12 Repeat stuck open biluna. (1) Disc lodged against seat with pivot and retaining pins adsdag l laterference weld escaring the rendaing pin imd.rpaa, u. ins ,w arror. (2) Binding at disc mapcossactanspmestedcaosure -- -
-Q defset.
4
! De 33 check vahe huures were d$trhuted acmas a systems a shown in hble 4. Figure I Blastrates the l bdure distribunos by failure cause and system 1
i Table 4 Distributies af Comanche Peak Cheek Valve Fabares by Systen and Estist inf Degradadse System Emersas u- asad-ste sammh.v m AFW I 1 2
{; CCW 2 6 3 Castabasset Isslatina 6 I
- c=^ ' - -- ' Soray 5
{ WG 2 i Dismi r.si Ou i Disent Lebe 0D 2 Faedwater 4 i
f 4
4 4
t 4
Failure cause i S Abnormal wear S Design dahelency 5Procedwalproblem E Foreign matenal
[ BMaintenance error Blnstallation problem 3 M_ 'm+".ng defect SUnknown j E Normal wear DExtemallenhage a
3a ====
j M-u.
! u-u.
0- t -
t -- - 1 l 1 i AFW CCW Commeuman Camammet CVCB DisedFuel Demellate fundweest
} assineena spesy os os l Pigase 1 Comsanche Peak check valve ingene disesibutism by ineuse amuse and 8F86m j Conclusions l
l Of the 33 dailure reconis recorded in NPRDS for Cansache Punk check vahes thun 1951995, all but 2
{ . af the Adled valves are incinded in the list dlST deistralmaduisses (Table A 1 in the Appseduc lists all i
the deferral maduiste check vahes by unit and system.) Nine of the thirty three Anikses invoked repeat initures (considering both anits). Two indmdual P(2FW4013 and 2004258)had repast signiAmne asilures. Diesel Imbe Oil vahe DO4258 had a antal of three signifkaat initures, considering
, both units.
k is huportant to undermand that des e the anall ammber of dailure isonnis available for Comanche Peak i check valves during the selettvely short analysis period, trw marimwelly asemagfbl nauks an be dermd The data does not, however, a this point suggsa any aboonnal hilsse pansras or omsses By the asse argument, linie data is curready availabic to validate IST interval ensamon or to evahmte the e5ect afisterval edcasion on check valve personnance Further aallar+ian and analysis of perfonnanos dera l over an maanded operating period would be ascesary a more accurately evaluate the sSects of changes i in theist program.
la the review damnant relierrequests kr t'a==* Peak ched valves, k might be prudent to qasstion I both the assure of(and conective messnes taken with regard to) the hilures which have occaned as well
! as the sauros(s) of data that were used e input a risk based a=Im1= ham For ameple,k might be i seasonable to question the Adhus esperience of the CCW stop ched vnhos that invoked the valws' j sicking closed ese e annosion produt -i- berman plug sad bare during long periods of -
Anactivity Periodic stroking of vehe(s) was less than adequate Quenerfy stroidag af(the) valve (s) had i to be inittstad to prevent romanence " Addmoestly, cassiderlag the liased as:ure of Casanache Peak j
eparattag aspenance and data, the sources of aa=Ta==* hilure rutas and othu analysis inputs might be gasseioned.
);
k 1
i l
1 es O
j i 1 Oak Ridge National IJboratory, NUREGCR 5944, Vol. 2,"A Characterization of Check Valve
- Degradation and Failurt Exponence la the Nuclear Power Industry- 1991 Failures," Ady 1995.
1 i 2 Oak Ridge National IJboratory, ORNUNRC/LTR 96/11,"A Characterization of Chad Valve j Degradation and Failurt Expensace la the Nuclear Power Industry - 1992 Failures," June 1996. .
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j . AFFENDIX t
l Table A-1 Causanche Peak Risk Based !ST Beferral Canddste Check Vahes i
Coenasche Peak RBIST Unte(s) Systems Falharesin NFRDS j Baterral Canndate Check (1996 1995)
- Vahes
[ 1,2AF 0014 1,2 MW l 1,2AF4024 1,2 AFW '
l l 1,2AF 0032 1,2 APW j 1,2AF4038 1,2 AFW ,
t 1,2AF 0051 1,2 AFW
} _1,2AF4065 1,2 AFW j 1,2AF 0075 1,2 APW l 1.2AF 0078 1,2 AFW j 1,2M 0083 1,2 AFW
{ 1,2AF 0086 1,2 AFW Unit 1 (IE)
I 1,2AF 0093 1,2 APW Unit I (IS) 1,2AF 0098 1,2 AFW Unit 1 (IM) i 1,2AF 0101 1,2 AFW Unit 1 (IM) i 1,2AF 0106 1,2 AFW j 1AF 0215 1 AFW 1AF 0216 I AFW l 1AF 0217 1 AFW ,
l _1AF 0218 1 APW -
!' ~~
1AF 0219 1 AFW
! . IAF 0220 1 AFW 1,2AF 0221 1,2 AFW
' 1,2AF 0222 1,2 AFW .
1AF4223 1 AFW j 2M 0224 2 AFW j _1AF 0224 , 1 AFW
! 2M 0223 2 AFW
, IAF 0226 1 APW
) 2AF 0227 2 AFW j 1AF4227 1 MW
] 1,2AF4228 1,2 AFW
! 1,2AF 0229 1,2 AFW
) 1AF4230 1 AFW
! 2AF4231 2 AFW
! 1AF4231 1 AFW
! 2AF4230 2 APW f 1,2AF4232 1,2 AFW 1,2AF4233 1,2 APW j , 1.1AF4234 1,2 APW j 1,2AF4235 1,2 AFW i
i i 7 2
l l
)
._ __ . _ _.___..._ __~_ . _ .. _ _ _ . _ _ _ ___._.___ __ _ ___ _ __ _ _ _ ._.
- Cassanche Peak RBIST Bak(s) Syssean Fanuresla NPRDS
. DeferralCandidate Check (1996 1995) l vs.s l 1
1,2CC 0003 1,2 CCW l l
- l. 1,2CC4004 1,2 CCW i 1,2CC4031 j 1,2 CCW i
{ 1,2CC4061 1.2 CCW 2CC4371 2 CCW i l 2CC 0372 2 CCW i 2CC4373
- 2 CCW i 2CC 0374 2 CCW i- 1.2CC4629 1,2 CCW j 1,2CC 0646 1,2 CCW 1,2CC4657 CCW 1.2 Unit 1(IS) l 1,2CC4687 1,2 CCW j ,1,2CC 0694 1,2 CCW i 1,2CC4713 1,2 CCW
! 3,2CC 0831 1,2 CCW Unit 1(2M);
) Unit 2 (IS)
! ICC 1075 1 CCW Unit 1 (IS) l ICC-1076 1 CCW Unit 1 (IS) i ICC-1077 I CCW Unit 1 (IS) i ICC-1078 1 CCW Unit I (IS)
! 3CC-1079 1 CCW f ICC 1080 1 CCW i ICC 1081 1 CCW ,
j ICC-1082 1 CCW -
l 2CC-1091 2 CCW i 2CC-1092 2 CCW 2CC 1093 2 CCW 2CC 1094 2 CCW
- 1,2CH 0300 1,2 famma-m Isolabon
{ 1,2CH4301 1,2 es-t===** Isolation l XCS4037 Comunce CVCS l XCS4039 cm==aa CVCS i XCS 0041 Conuson CVCS
! XCS4044 Comunon CVCS j 1,2CS4180 1,2 CVCS 4 1,2CS4350A 1,2 CVCS l 1,2CS4350B 1,2 CVCS ~~
l 1.2CS4350C 1,2 CVCS l 1,2CS4350D 1,2 CVCS
{ 1,2CS4367A I,2 CVCS l 1,2CS4367B 1,2 CVCS l 1,2CS4367C 1,2 CVCS
- 1,2CS4367D 1,2 CVCS j 1,2CS4368A . 1,2 CVCS
. 1,2CS4368B 1,2 CVCS
- 1,2CS4368C 1.2 CVCS Unh 2 (IM) 1 I
a S
i
, CessanchePeak RBIST Calt(s) System Fausessla NPRDS l,, Deferral Candidate Check (1990 1995) l
, Valves j 1,2CS4368D. 1,2 CVCS j 1,2CS4377 1,2 CVCS 1,24378A 1,2_ CVCS
- 1,24378B 1,2 CVCS l 1,24379A 1,2 CVCS ,
i 1.24379B 1.2 4"VCS -
l 1,24381 1,2 CVCS
} 1,2CS4442 1,2 CVCS l
_1,2CS4473 1,2 CVCS
}- 1,2CS4480A 1,2 - CVCS
- 1,2CS4480B 1,2 CVCS i 1,24481A 1,2 CVCS l 1,2 44818 1,2 CVCS l _1,2CS4487 1,2 CYCS I 1,24497 1,2 CVCS
! 1,2CT4013 1,2 c m aia=am Spray Unit 1 (1E) l
! 1,2CT4020 1,2 rannaia=== Raay i
l _1,2CT4025 1,2 camenia=*at Spray i 1,2CT 003) 1,2 r w n.a===,Sprey
} 1,2CT4042 1,2 camme==== Spray
} 1,2CT 0047 1,2 ca==ia=== Ramy Unit 1 (1E) i 1,2CT 0048 1,2 famenia=== Spray 1,2CT 0063 1,2 camenia=am Spray
' JJait 1 (1E)
_1,2CT 0064 1.2 famaia=== Sprey -
i 1,2CT 0065 ~1,2 raneaia=== Spray
- 1,2CT 0072 1,2 ca=*=ia=== Emmy
) , 1,2C7 0077 1,2 eaa***==== Spray Unit 1 (IE) 1,2CT 0082 1,2 famana==ar Spray
[ 1,2CT 0094 1,2 raataia=== Spray Unit I (IE) i 1,2CT 0142 1,2 famania=*ar Ramy j 1,2CT 0145 , 1,2 cameala=== Spray
) 1,2CT 0148 1,2 Ca=*aia=== Spray
- _1,2CT 0149 1,2 ranemin=*at Spray 2DD4002 2 Deadaaraliand and
{ RansnorMalmup Water j 1,2DD 0006 1,2 Dennasrahand and
- mancearMalmap Waner k
i 2DD4008 2 Deadasrahand and RancearMakeup Water i
i 2DD4009 2 Denmasrahand and massearMalmuy Wasar i
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t
i 1 1, , Commanche Peak RBIST Dak(s) Systemi Faamresim NPRDS
- i . Deferral Candidate Check (1990-1995) ...
j -
Vahes 1,2DD 0016 1,2 Dennasrahand and S '
~
RancearMakamp Water
) l
! 1,2DD4018 1,2 Deadaarahand and '.
l RancearMelump T'vsr y )
{ ..
l XDD4044 Casumen '
l Dennasrahand and RaamorMakeup Waner d
i XDD4048 L
Comumen Duuniseraband and : .-
RancearMakeup Water
[.
l IDD4064 Dumiasrahand and 1
RamsterMakamp Water f '
1DD 0065 k-l
~
1 Danimerahand and j RasclerMakeup Water l' 1DD 0066 1 naminarmh=dand .
RancierMakeup Water
, - -}-)
4
- 1,2DO 0004 1,2 Dunst FuelOil f
! 1,2DO 0005 1,2 Dassel Fuel Oil i 1,2DO 0016 1,2
'I.
R DieselFuelOil ! 1 I
1,2DO 0017 1,2 Diesel Fuel Oil [.; -
1,2DO4049 1,2 DieselFuel00 ~
, IDO 0050 1 DieselFus! Oil i
! 2DO 0052 2 DieselFuel00
} 1,2DO 0058 1,2
.{-
Diesel Fuel Oil ?
! 1,2DO 0059 1,2 Diesel Fuel Oil i' I 1,2DO 0060 1,2 Dissal Fuel Oil l 1,2DO4061 '
1,2 Diesel Fuel 00 I 1,2DO4062 l 1,2DO4063 1,2 1,2 Diesel Fuel 00 ; '
Diesel Fuel 00 - - l 1,2DO4064 1,2 Diesel Fuel Oil l 1,2DO4063 1,2 Diesel Fuel 00 . ..-
j 2DO 0074 2 DissalFuel00 e-2DO4075 2 DieselFuel00
{ 2DO 0076 2 DissalFuel00 i
2DO 0077 1,2DO4104 2
1,2 Dismal Fuel 00 DieselFuel00 f
.--~
, 1,2DO 01$7 1,2 DasselFue!00
! [..
1.2DO4158 1,2 DieselFuel00
- l 1,2DO4204 !J DismalFuel 00 3 l
l 1,2DO4257 1,2 Dieselhast 00 i 1.2DO4258 1,2 DismalFusi00 Uah 1 (15); ,
} Unit 2 (25) .
j i j 10 3 -
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4 Cassamthe Peak RBIST Dmit(s) System Failuresla NPRDS I
DeferralCanadate Check 0 996 1995) j Valves j 3,2FW 0070 1,2 Feedwater
, 1,2FW 0076 1,2 Feedwater Unit I (IS) 1,2FW4082 1,2 Feedwater 1,2FW4088 1,2 Feedweser Unit I (IS) 1,2FW4191 1,2 Feedwater ,e 1.2FW4192 1,2 Pendwater 1,2FW4193 1,2 Feedwater 1,2FW4194 1,2 Feedwater 1,2FW4195 1,2 Feedwater l
! 1,2FW 0196 1,2 Feedweear 1,2FW4197 1,2 Feedwasar 1,2FW4198 1,2 Foseweser
_1,2FW4199 1,2 Feedwater 1 1,2FW4200 1,2 Posewater 1,2FW4201 1,2 Feedweser 1,2FW4202 1,2 Feedwater i 1,2MS4142 - 1,2 Main Sesam 1,2MS4143, 1,2 l Main Sesem 1 2MS 0663 2 Main Sesem l 2MS4664 2 Main Sesam 2MS4665 2 Main Sesam 2MS 0666 2 Main Sesam 2MS 0667 2 Main Sessa .
2MS 0668 2 Main Sesem -
2MS4669 2 Main Seems i 2MS 0670 2 Main Sesam 1MS4680 1 Main Sesam IMS 0681 1 Main Sesam 1MS 0682 1 Main Sesam 1MS 0683 1 Main Seasm IMS 0684 , 1 Main Sesem IMS 0685 1 Main Sesam 1MS 0686 1 Main Sesam 1MS4687 1 Main Sesam 1,24730A -
1,2 RHR 1,24730B 1,2 RHR -
XSF 009 Common SpentFastPool coolina Symem XSF 0004" Cmemon Spent FuelPool
. . Coolins Synom XSF4160 Osammen Spent Past Pool cuties Sysum XSF41SO. Common Space FuelPool coolias Symsm 1,24841A 1,2 RHR IJ484IB 1,2 RHR 11
m Comanche Peak Units 1,2 r-.* Peak RBIST Walt (s) Systems Fallacesla NPRDS
, DderralCandidate Check (1990-1995)
Valves 1,24890A 1,2 1,24890B 1,2 1,2$14900A 1,2 HPSI 1,2SI4900B 1.2 HPSI
_1,2514900C 1,2 HPSI '
1,2SI4900D 1,2 HPSI 1,2SI4905A 1,2 HPSI 1,2SI4905B 1,2 HPSI 1,2SI4905C 1,2 HPSI 1,2SJ490$D 1,2 - HPSI
_1,2SI4919A 1,2 HPSI 1,2SI4919B 1,2 HPSI 1,24922A 1.2 HPSI 1,24922B 1,2 HPSI 1,24949A 1,2 HPSI 1,24949B 1,2 HPSI 1,24949C 1,2 HPSI 1,24949D 1,2 HPSI IJ4958A 1,2 RHR 1,2 49583 1,2 RHR 1,2SI4968 1,2 cameni===e Isolanon Unit 1 (2M);
Unit 2 (IM.1S) 1,24%9A 1,2 HPSI ,
1,24%9B 1,2 HPSI 1,2VD4003 1,2 Vents and Drains 1,2VD 0004 1,2 Vents and Draans 1,2VD 00ll 1,2 Vents and Dnuns 2,2VD 0012 1,2 Vents and Draans 1,2CA 0016 1,2 f*===e taalahaa Unit 1 (2M);
Unit 2 (IM) 1,2CH 0024 , 1,2 fame =*====e Isolanon 1,2CI 0030 1,2 came=*====e Isolanon 1
MN -
5-Signifkant 12 l
l
. - - _ _ _ _