CPSES-200502282, Technical Specification Reports for Steam Generator Meeting C-3 Category and 15-day Tube Plugging and Repair
ML053200044 | |
Person / Time | |
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Site: | Comanche Peak |
Issue date: | 11/07/2005 |
From: | Madden F TXU Power |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
CPSES-200502282, TXX-05192 | |
Download: ML053200044 (5) | |
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[Table view](Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation CP-202300401, 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 0182023-08-15015 August 2023 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 018 L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments CP-202300263, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-06-15015 June 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202200247, (CPNPP) - 10CFR50.59 Evaluation Summary Report 023, 10CFR72.48 Evaluation Summary Report 008 and Commitment Material Change Evaluation Report 0172022-06-30030 June 2022 (CPNPP) - 10CFR50.59 Evaluation Summary Report 023, 10CFR72.48 Evaluation Summary Report 008 and Commitment Material Change Evaluation Report 017 ML22020A1792021-11-0404 November 2021 Fall 2021 Steam Generator Tube Inspections Discussion Input CP-202000462, Submittal of 10CFR50.59 Evaluation Summary Report 022, 007, and Commitment Material Change Evaluation Report 0162020-09-29029 September 2020 Submittal of 10CFR50.59 Evaluation Summary Report 022, 007, and Commitment Material Change Evaluation Report 016 ML20153A7442020-06-0404 June 2020 Review of the Fall 2018 Steam Generator Tube Inspection Report CP-201700033, Mitigating Strategies Assessment Flood Report, NEI 12-06, Appendix G, Revision 2, G.4.1 Path2017-02-0909 February 2017 Mitigating Strategies Assessment Flood Report, NEI 12-06, Appendix G, Revision 2, G.4.1 Path CP-201600093, Transmittal of 10CFR50.59 Evaluation Summary Report 019, 10CFR72.48 Evaluation Summary Report 004, and Commitment Material Change Evaluation Report 0132016-02-24024 February 2016 Transmittal of 10CFR50.59 Evaluation Summary Report 019, 10CFR72.48 Evaluation Summary Report 004, and Commitment Material Change Evaluation Report 013 ML16014A1252016-01-22022 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force ML15062A0302015-02-25025 February 2015 Work Plan for Completing a Once Through Cooling Water Study for Total Dissolved Solids, Chlorides, and Sulfates CP-201401268, Fourteenth Refueling Outage (2RF14) Steam Generator 180 Day Report2014-10-21021 October 2014 Fourteenth Refueling Outage (2RF14) Steam Generator 180 Day Report CP-201401027, 10CFR50.59 Evaluation Summary Report 018, 10CFR72.48 Evaluation Summary Report 003 and Commitment Material Change Evaluation Report 0122014-08-27027 August 2014 10CFR50.59 Evaluation Summary Report 018, 10CFR72.48 Evaluation Summary Report 003 and Commitment Material Change Evaluation Report 012 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5432014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5372014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5 ML14189A5332014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5 ML14189A5312014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5 ML14189A5002014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 CP-201400324, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-03-27027 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14036A0362014-03-0707 March 2014 Staff Assessments of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident CP-201301238, Sixteenth Refueling Outage (1RF16) Steam Generator 180 Day Report2013-10-15015 October 2013 Sixteenth Refueling Outage (1RF16) Steam Generator 180 Day Report ML12159A2882012-06-11011 June 2012 Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Related to Fukushima Dai-ichi Accident ML12080A1432012-03-0606 March 2012 CPNPP Systems Annual Operator Employment Notices ML12080A1502012-03-0606 March 2012 Submittal of Stc Annual Operator Employment Notices CP-201101257, Submittal of Operator Licensing Examination Data2011-09-21021 September 2011 Submittal of Operator Licensing Examination Data CP-201101169, CFR50.59 Evaluation Summary Report 016, 10CFR72.48 Evaluation Summary Report 001, and Commitment Material Change Evaluation Report 0102011-08-22022 August 2011 CFR50.59 Evaluation Summary Report 016, 10CFR72.48 Evaluation Summary Report 001, and Commitment Material Change Evaluation Report 010 ML1034206512010-09-17017 September 2010 FEMA, Comanche Peak Nuclear Power Plant - After Action Report/Improvement Plan, Drill Date August 18, 2010, Radiological Emergency Preparedness (REP) Program CPSES-201001000, Operator Licensing Examination Data, Form 5362010-07-28028 July 2010 Operator Licensing Examination Data, Form 536 ML1000700042009-12-0303 December 2009 After Action Report/Improvement Plan, Drill Date - December 03, 2009 CP-200901404, Core Operating Limits2009-11-0202 November 2009 Core Operating Limits CP-200900474, Property Damage Insurance, Summary Report2009-03-26026 March 2009 Property Damage Insurance, Summary Report CP-200900127, Guarantees of Payment of Deferred Premiums2009-01-19019 January 2009 Guarantees of Payment of Deferred Premiums CP-200900010, Core Flux Maps Data, Cycle 112009-01-0707 January 2009 Core Flux Maps Data, Cycle 11 CP-200800805, Report of Unusual or Important Environmental Event, Operating License, Appendix B, Environmental Protection Plan (Non Radiological) - Mortality of Avian Species2008-06-0404 June 2008 Report of Unusual or Important Environmental Event, Operating License, Appendix B, Environmental Protection Plan (Non Radiological) - Mortality of Avian Species CP-200800612, Commanche Peak, Units 1 & 2 - Transmittal of Revised Pressure and Temperature Limits Report2008-04-24024 April 2008 Commanche Peak, Units 1 & 2 - Transmittal of Revised Pressure and Temperature Limits Report CP-200800609, Pressurizer Weld Overlay 60 Day Report and Results of the Final Pdi/Ut Examination of Weld Overlays2008-04-24024 April 2008 Pressurizer Weld Overlay 60 Day Report and Results of the Final Pdi/Ut Examination of Weld Overlays CP-200800213, Response to Request for Additional Information2008-02-26026 February 2008 Response to Request for Additional Information CPSES-200700454, Transmittal of Second-Half 2006 Fitness-For-Duty Program Performance Data2007-02-28028 February 2007 Transmittal of Second-Half 2006 Fitness-For-Duty Program Performance Data CPSES-200601738, Transmittal of First-Half 2006 Fitness-For-Duty Program Performance Data2006-08-31031 August 2006 Transmittal of First-Half 2006 Fitness-For-Duty Program Performance Data CPSES-200600154, Transmittal of Unit 2 Inservice Inspection Program Plan, Revision 22006-08-0202 August 2006 Transmittal of Unit 2 Inservice Inspection Program Plan, Revision 2 ML0620500122006-07-17017 July 2006 Attachment 1 to TXX-0612 Response to Requests for Additional Information for the Replacement Steam Generator Supplement to Txu Power'S Large and Small Break Loss of Coolant Accident Analysis Methodologies, Pages 1 Through 74 ML0702303962006-04-10010 April 2006 Report 06-0413 Chart 250-200 ML0702303922006-04-0606 April 2006 Report 06-0413 Chart 7 ML0702303952006-04-0606 April 2006 Report 06-0413 Chart 120-307 2023-08-07 Category:Technical Specifications MONTHYEARML23319A3872023-12-20020 December 2023
[Table view]Issuance of Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology CP-202300349, License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation2023-11-20020 November 2023 License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation CP-202200273, Third Supplement to License Amendment Request (LAR) 20-006 Application to Revise Technical Specifications to Adopt Risk Informed Completion Times, TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative2022-07-20020 July 2022 Third Supplement to License Amendment Request (LAR) 20-006 Application to Revise Technical Specifications to Adopt Risk Informed Completion Times, TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative CP-202200035, Second Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections2022-01-25025 January 2022 Second Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections ML20346A0192021-02-0101 February 2021 Issuance of Amendment Nos. 177 and 177 Regarding Revision to Technical Specifications 3.8.1, AC Sources - Operating ML20168A9242020-11-16016 November 2020 Issuance of Amendment Nos. 176 and 176 Regarding Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation ML20223A3492020-08-31031 August 2020 Issuance of Amendment Nos. 175 and 175 Regarding One-Time Revision to Technical Specification 3.7.19, Safety Chilled Water ML20167A3182020-07-0606 July 2020 Issuance of Amendment Nos. 174 and 174 Regarding Revision to Technical Specifications to Adopt TSTF-563, Revision 0 ML20108E8782020-04-17017 April 2020 Issuance of Amendment Nos. 173 and 173 Revision to TS 5.5.9, Unit 1 Model D76 and Unit 2 Model D5 Steam Generator (SG) Program (Exigent Circumstances) ML18267A3842018-10-25025 October 2018 Issuance of Amendment Nos. 170 and 170 Revision to Technical Specification 3.8.4, DC Sources - Operating, Condition B (Exigent Circumstances) CP-201800659, (Cpnpp), Unit 1 - Response to Request for Additional Information Regarding Exigent License Amendment Request (LAR) 18-001, Revision to Technical Specification 3.8.4, 11DC Sources - Operating, Condition B2018-09-20020 September 2018 (Cpnpp), Unit 1 - Response to Request for Additional Information Regarding Exigent License Amendment Request (LAR) 18-001, Revision to Technical Specification 3.8.4, 11DC Sources - Operating, Condition B CP-201600683, Supplement to License Amendment Request 16-001 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5...2016-06-30030 June 2016 Supplement to License Amendment Request 16-001 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5... ML16096A2642016-05-0606 May 2016 Draft Conforming Amendments, Application for Order Approving Direct and Indirect Transfer of Licenses and Conforming License Amendments ML15309A0732015-12-30030 December 2015 Issuance of Amendment Nos. 165 and 165, Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, to Increase ILRT Test Interval from 10 to 15 Years and Type C Tests from 60 to 75 Mos ML15008A1332015-02-24024 February 2015 Issuance of Amendment Nos. 164 and 164, Revise Technical Specification 3.8.1 for a 14-Day Completion Time for Offsite Circuits ML14160A0352014-07-0101 July 2014 Redacted, Issuance of Amendment No. 162, Revise TS 3.7.16, Fuel Storage Pool Boron Concentration, TS 3.7.17, Spent Fuel Assembly Storage, and TS 5.5, Programs and Manuals ML14042A2232014-02-27027 February 2014 Issuance of Amendment Nos. 161 and 161, Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Consolidated Line Item Improvement Process (TAC MF2651-MF2652) ML14052A2612014-02-19019 February 2014 Supplement to License Amendment Request 13-002 Revision to Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using.. CP-201300738, License Amendment Request 13-002, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item..2013-07-10010 July 2013 License Amendment Request 13-002, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item.. CP-201300257, License Amendment Request (LAR) 13-01, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage, 4.3, Fuel Storage, and 5.5 Programs & Manuals.2013-03-28028 March 2013 License Amendment Request (LAR) 13-01, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage, 4.3, Fuel Storage, and 5.5 Programs & Manuals. CP-201200012, (Cpnpp), Revision to Technical Specification (TS) 5.5.9, Unit 1 D76 and Unit 2 D5 Steam Generator (SG) Program, and TS 5.6.9, Unit 1 D76 and Unit 2 D5 Steam Generator Tube Inspection Report, for a Permanent ....2012-03-28028 March 2012 (Cpnpp), Revision to Technical Specification (TS) 5.5.9, Unit 1 D76 and Unit 2 D5 Steam Generator (SG) Program, and TS 5.6.9, Unit 1 D76 and Unit 2 D5 Steam Generator Tube Inspection Report, for a Permanent .... CP-201101663, License Amendment Request (LAR)11-003 for Adopting of TSTF-491, Rev. 2, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Tech Specs Using Consolidated Line Item Improvement Process.2011-12-13013 December 2011 License Amendment Request (LAR)11-003 for Adopting of TSTF-491, Rev. 2, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Tech Specs Using Consolidated Line Item Improvement Process. CP-201101038, License Amendment Request (LAR) 11-001, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled2011-08-0101 August 2011 License Amendment Request (LAR) 11-001, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled ML1011703672010-02-15015 February 2010 Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2 CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 22010-02-15015 February 2010 Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2 CP-201000144, Revision to License Amendment Request 09-001, Administrative Revision to Operating Licenses and Technical Specifications2010-02-0101 February 2010 Revision to License Amendment Request 09-001, Administrative Revision to Operating Licenses and Technical Specifications CP-200901569, License Amendment Request (LAR) 09-010, for Approval of the Cyber Security Plan2009-11-19019 November 2009 License Amendment Request (LAR) 09-010, for Approval of the Cyber Security Plan ML0927400762009-10-0909 October 2009 Issuance of Amendment Nos. 149 and 149, Modify Technical Specifications to Establish Alternate Repair Criteria (ARC) and Include Reporting Requirements Specific to ARC for Steam Generator Program CP-200901308, Revision to License Amendment Request 09-007 Model D5 Steam Generator Alternate Repair Criteria2009-09-14014 September 2009 Revision to License Amendment Request 09-007 Model D5 Steam Generator Alternate Repair Criteria CP-200901042, Response to Request for Additional Information Regarding License Amendment Request 09-007, Model D5 Steam Generator Alternate Repair Criteria2009-08-20020 August 2009 Response to Request for Additional Information Regarding License Amendment Request 09-007, Model D5 Steam Generator Alternate Repair Criteria CP-200900383, License Amendment Request (LAR) 09-006, for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.2009-04-0101 April 2009 License Amendment Request (LAR) 09-006, for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. CP-200900283, Response to Request for Additional Information Regarding Spent Fuel Pool Criticality License Amendment Request2009-02-17017 February 2009 Response to Request for Additional Information Regarding Spent Fuel Pool Criticality License Amendment Request ML0818400022008-09-12012 September 2008 License and Technical Specifications Pages, Amendment Nos. 147 and 147, Revise Technical Specification 3.6.7, Spray Additive System to Comply with GL-2004-02 ML0815101752008-06-27027 June 2008 License, Appendix B, and Technical Specification Pages, Amendment Nos. 146 and 146, Stretch Power Uprate, Revision to TS 1.0, Use and Application, to Revise Rated Thermal Power from 3458 to 3612 Mwt ML0805800052008-04-0303 April 2008 Tech Spec Pages for Amendment Nos. 145 and 145 Revise TSs 3.1.4, 3.4.10, and 3.7.1 to Reflect Cycle-Specific Safety Analysis Assumptions Re Adoption of Westinghouse Methodologies ML0805100832008-04-0202 April 2008 License and Technical Specifications, Amendment 144 and 144, Changes to TS to Allow Use of Westinghouse-developed/NRC-approved Analytical Methods Used to Establish COLs CP-200800411, Supplement to License Amendment Request (LAR) 07-003 Response to Request for Additional Information Related to Review Associated with Large and Small Break LOCA Analyses2008-03-13013 March 2008 Supplement to License Amendment Request (LAR) 07-003 Response to Request for Additional Information Related to Review Associated with Large and Small Break LOCA Analyses CPSES-200701076, Revision to the Operating License and Technical Specifications 1.0, Use and Application and 3.7.17, Spent Fuel Assembly Storage to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt2007-08-28028 August 2007 Revision to the Operating License and Technical Specifications 1.0, Use and Application and 3.7.17, Spent Fuel Assembly Storage to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt CPSES-200701323, License Amendment Request 07-006, Revision to Technical Specification 3.1.4, Rod Group Alignment Limits, Table 3.3.1-1, Reactor Trip System Instrumentation, Table 3.3.2-1, Engineered Safety Feature Actuation System..2007-08-16016 August 2007 License Amendment Request 07-006, Revision to Technical Specification 3.1.4, Rod Group Alignment Limits, Table 3.3.1-1, Reactor Trip System Instrumentation, Table 3.3.2-1, Engineered Safety Feature Actuation System.. ML0708201932007-04-27027 April 2007 Technical Specifications, Issuance of Amendment Nos. 138 and 138 Revision to Technical Specification 3.8.1, AC Sources - Operating (TAC MD0932 & MD0933) ML0704304542007-03-29029 March 2007 Technical Specifications, Issuance of Amendment Nos. 137 and 137 Reactor Coolant System Specific Activity ML0707700102007-03-26026 March 2007 Technical Specifications, Issuance of Amendment Nos. 135 and 135 Revise Listing of LOCA and Non-LOCA Methodologies ML0707300432007-03-26026 March 2007 Technical Specification, Modify TS Requirements Related to Control Room Envelope Habitability in TS 3.7.10, Control Room Emergency Filtration/Pressurization System (Crefs), and TS Section 5.5, Administrative Controls.... ML0704403712007-02-26026 February 2007 Technical Specifications, Issuance of Amendment Nos. 133 & 133 Revision to TS 3.3.1.2 and 3.3.1.3, Reactor Trip System Instrumentation (TAC Nos. MC9492 & MC9493) ML0703104902007-02-20020 February 2007 Technical Specifications, Issuance of Amendment Nos. 130 & 130 New Methods & Assumptions for Radiological Consequences Calculations (TAC Nos. MC8163 & MC8164) ML0703500472007-02-20020 February 2007 Technical Specifications, Issuance of Amendment Nos. 131 & 131 Technical Specification Changes Related to Unit 1 Steam Generator Replacement Project (TAC Nos. MD0187 & MD0188) CPSES-200700130, License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators2007-01-18018 January 2007 License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators ML0628401022006-10-0505 October 2006 Technical Specification, Revisions to TS 3.3.2, ESFAS Instrumentation; and TS 3.5.2, ECCS - Operating ML0625801172006-09-12012 September 2006 Technical Specifications, Issuance of Amendments Steam Generator Tube Surveillance Program, MC9498 and MC9499 ML0620905292006-07-28028 July 2006 Tech Spec Pages for Amendments 127 & 127 Regarding Revision to Technical Specification 5.5.13, Diesel Fuel Oil Testing Program. 2023-12-20 |
Text
A'A PTXU t9Power TXU Power Mike Blevins Comanche Peak Steam Senior Vice President &
Electric Station Chief Nuclear Officer P. O. Box 1002 (E01)
Glen Rose, TX 76043 Ref: Technical Specification 5.6.10 Tel: 254 897 5209 Fax: 254 897 6652 mike.blevins~txu.com CPSES-200502282 Log #-TXX-05192 November 7, 2005 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
UNIT 1, DOCKET NO. 50-445 TECHNICAL SPECIFICATION REPORTS FOR STEAM GENERATOR MEETING C-3 CATEGORY AND 15-DAY TUBE PLUGGING AND REPAIR Gentlemen:
As Attachment 1 to this letter, TXU Generation Company LP (TXU Power) hereby submits a report pursuant to CPSES Technical Specification 5.6.10.c for Steam Generators (SGs) meeting C-3 conditions during the current refueling outage.
Attachment 2 of this letter submits the 15-day report of tubes plugged, repaired, or designated as an F* tube pursuant to CPSES Technical Specification 5.6.10.a.
Should you require any other additional information please contact Mr. Bob Kidwell at (254) 897-5310.
This communication contains no new licensing basis commitments regarding CPSES Unit 1.
A0oD A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak
- Diablo Canyon
- Palo Verde
- South Texas Project
- Wolf Creek
TXX-05 192 Page 2 of 2 Sincerely, TXU Generation Company LP By: TXU Generation Management Company LLC Its General Partner Mike Blevins By: v )
Fred W. Madden Director, Regulatory Affairs RJK - Report of Steam Generators in Category C3 condition. - Report of Steam Generator Tubes Plugged or Repaired c - B. S. Mallett, Region IV M. C. Thadani, NRR Resident Inspectors, CPSES to TXX-05 192 Page 1 of 2 TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 REPORT OF STEAM GENERATOR IN C-3 CATEGORY The following information meets the reporting requirements of CPSES Technical Specification 5.6.10.c., which states:
"Results of steam generator tube inspections which fall into Category C-3 shall be reported to the Commission in a report within 30 days and prior to resumption of plant operation. This report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence."
Comanche Peak Steam Electric Station (CPSES) Unit 1 was taken off line on October 8, 2005 for the eleventh refueling outage (lRF1 1). As part of the scheduled surveillance requirements of CPSES Technical Specification (TS) 5.5.9, analysis of eddy current testing data on the Steam Generators (SGs) indicated that greater than 1 percent of the total tubes inspected in the #4 SG were defective and the #4 SG fell into Category C-3 of the Technical Specifications.
The majority of the tube defects across all SGs are attributed to circumferential outside diameter stress corrosion cracking (ODSCC) at the hot leg top of tubesheet (TTS) transition.
All defective tubes did meet the criteria of NUREG 1022, Revision 2, for structural integrity.
The extent of the tube degradation found during 1RF 1 was less than predicted by the tube degradation models, largely due to the reduced amount of degradation at the TTS transition in #1, #2 and #3 SGs. Past inspection results and tube degradation prediction models indicated that the degradation of the tubing in the Unit 1 SGs would accelerate as the plant ages. This has generally been true of other plants with original Westinghouse SGs fabricated with Alloy 600 tubing. However, the reduced number of defective tubes found at the TTS transition in the above SGs supports a proposition that the larger populations found in previous outages may have manifested from SCC initiates which originated prior to chemical cleaning. With many of these defects by now having been identified and removed from service, and the potential crevice conditions supporting the development of new initiates mitigated, the number of degraded tube indications at the TTS transition due to ODSCC is displaying a decreasing trend.
to TXX-05 192 Page 2 of 2 TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 REPORT OF STEAM GENERATOR IN C-3 CATEGORY To prevent further degradation of the tubes displaying these defects, TXU Power has plugged all defective tubes identified during the current refueling outage. In addition, TXU Power will continue to follow the requirements of NEI 97-06 and the EPRI guidelines for future cycles of operation. These guidelines include maintaining primary and secondary water chemistry below recommended levels, primary to secondary leakage monitoring, inspection scope and frequency, pressure testing degraded tubes, and performing integrity assessments to ensure tube structural and leakage integrity. The Condition Monitoring and Preliminary Operational Assessment, performed in accordance with the EPRI Integrity Assessment Guidelines during 1RF 11, addresses the as-found condition of the steam generator tubing and justifies operation for the next operating cycle. The assessment is based on degradation identified and conservative analysis to assure tube structural and leakage integrity for the entire cycle length.
to TXX-05 192 Page 1 of 1 TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 1 REPORT OF STEAM GENERATOR TUBES PLUGGED OR REPAIRED The following information meets the reporting requirements of CPSES Technical Specification 5.6.1 O.a., which states:
"Within 15 days following the completion of each inservice inspection of steam generator tubes, the number of tubes plugged, repaired or designated as an F* tube in each steam generator shall be reported to the Commission;"
CPSES Unit I Steam Generator 1
- 17 tubes were plugged in this Steam Generator
- 1 tube was designated as an F* tube (as defined in CPSES TS)
CPSES Unit 1 Steam Generator 2
- 23 tubes were plugged in this Steam Generator CPSES Unit 1 Steam Generator 3
- 33 tubes were plugged in this Steam Generator
- 2 tubes were designated as an F* tube (as defined in CPSES TS)
CPSES Unit 1 Steam Generator 4
- 70 tubes were plugged in this Steam Generator
- 1 tube was designated as an F* tube (as defined in CPSES TS)
No tubes were repaired by sleeving in this outage.