CPSES-200600084, Annual Report of Changes in Peak Cladding Temperature
From kanterella
Jump to navigation
Jump to search
| ML060190529 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/10/2006 |
| From: | Madden F TXU Power |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CPSES-200600084, TXX-06007 | |
| Download: ML060190529 (3) | |
Similar Documents at Comanche Peak | |
|---|---|
Category:Letter type:CPSES
MONTHYEARCPSES-201001000, Operator Licensing Examination Data, Form 5362010-07-28028 July 2010
[Table view]Operator Licensing Examination Data, Form 536 CPSES-200901377, Operator Licensing Examination Data2009-09-29029 September 2009 Operator Licensing Examination Data CPSES-200701127, Response to Request for Additional Information Related to License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times.2007-11-15015 November 2007 Response to Request for Additional Information Related to License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times. CPSES-200701495, Withdrawal of License Amendment Request (LAR) 06-007, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits2007-10-22022 October 2007 Withdrawal of License Amendment Request (LAR) 06-007, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits CPSES-200701530, Additional Information in Connection with the Indirect Transfer of Facility Operating Licenses and Conforming License Amendments2007-10-0909 October 2007 Additional Information in Connection with the Indirect Transfer of Facility Operating Licenses and Conforming License Amendments CPSES-200701496, Information Required by Order Approving the Indirect Transfer of Facility Operating Licenses and Conforming License Amendments2007-10-0202 October 2007 Information Required by Order Approving the Indirect Transfer of Facility Operating Licenses and Conforming License Amendments CPSES-200701351, Transmittal of First-Half 2007 Fitness-for-Duty Program Performance Data2007-08-29029 August 2007 Transmittal of First-Half 2007 Fitness-for-Duty Program Performance Data 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-200701302, Relief Request B-4 to the Unit 2 Inservice Inspection (ISI) Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date - August 03, 2004, Second Interval)2007-08-22022 August 2007 Relief Request B-4 to the Unit 2 Inservice Inspection (ISI) Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date - August 03, 2004, Second Interval) CPSES-200701324, Supplement to License Amendment Request (LAR) 07-003 Revision to Technical Specification 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, and 5.6.5 B, Core Operating Limits2007-08-16016 August 2007 Supplement to License Amendment Request (LAR) 07-003 Revision to Technical Specification 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, and 5.6.5 B, Core Operating Limits 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.. CPSES-200701279, Mitigation of Alloy 82/182 Pressurizer Butt Welds in 20082007-08-0303 August 2007 Mitigation of Alloy 82/182 Pressurizer Butt Welds in 2008 CPSES-200701284, (Cpses), Operator Licensing Examination Data2007-08-0202 August 2007 (Cpses), Operator Licensing Examination Data CPSES-200701238, Submittal of the CPSES Units 1 and 2 Large and Small Break LOCA Analyses2007-07-31031 July 2007 Submittal of the CPSES Units 1 and 2 Large and Small Break LOCA Analyses CPSES-200701178, Supplement to Application for Order Approving Indirect Transfer of Control of Licenses and License Amendments to Reflect Proposed Licensee Name Change (TAC Nos. MD5289 and MD5280), Enclosures 1, 4, 5, 6 & 72007-07-20020 July 2007 Supplement to Application for Order Approving Indirect Transfer of Control of Licenses and License Amendments to Reflect Proposed Licensee Name Change (TAC Nos. MD5289 and MD5280), Enclosures 1, 4, 5, 6 & 7 CPSES-200701126, Response to Request for Additional Information to License Amendment Request (LAR) 06-007 Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits2007-07-18018 July 2007 Response to Request for Additional Information to License Amendment Request (LAR) 06-007 Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits CPSES-200701174, Submittal of Twelfth Refueling Outage (1RF12) Inservice Inspection Summary Report (1998 Edition of ASME Code Section XI Through 2000 Addenda, Interval Start Date - 08/03/2000, Second Interval)2007-07-17017 July 2007 Submittal of Twelfth Refueling Outage (1RF12) Inservice Inspection Summary Report (1998 Edition of ASME Code Section XI Through 2000 Addenda, Interval Start Date - 08/03/2000, Second Interval) CPSES-200701065, Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.2007-06-21021 June 2007 Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients. CPSES-200700951, (Cpses), Unit 1, Pressurizer Weld Overlay 60 Day Report and Update for Unit 1 Reactor Pressure Vessel Head Replacement Regarding Revised Order EA-03-0092007-06-19019 June 2007 (Cpses), Unit 1, Pressurizer Weld Overlay 60 Day Report and Update for Unit 1 Reactor Pressure Vessel Head Replacement Regarding Revised Order EA-03-009 CPSES-200701059, Submittal of Startup Report, Cycle 132007-06-13013 June 2007 Submittal of Startup Report, Cycle 13 CPSES-200700738, License Amendment Request (LAR) 07-001 Revision to Technical Requirements Surveillance 13.3.33.2 Frequency for the Turbine Stop and Control Valves2007-05-22022 May 2007 License Amendment Request (LAR) 07-001 Revision to Technical Requirements Surveillance 13.3.33.2 Frequency for the Turbine Stop and Control Valves CPSES-200700915, Supplemental Response to Request for Information on Generic Letter 2003-01, Control Room Habitability2007-05-0707 May 2007 Supplemental Response to Request for Information on Generic Letter 2003-01, Control Room Habitability CPSES-200700871, Transmittal of Year 2006 Radioactive Effluent Release Report2007-04-30030 April 2007 Transmittal of Year 2006 Radioactive Effluent Release Report CPSES-200700859, Submittal of the Annual Non-Radiological Environmental Operating Report for 20062007-04-27027 April 2007 Submittal of the Annual Non-Radiological Environmental Operating Report for 2006 CPSES-200700517, Application for Order Approving Indirect Transfer of Control of Licenses and License Amendments to Reflect Proposed Licensee Name Change2007-04-18018 April 2007 Application for Order Approving Indirect Transfer of Control of Licenses and License Amendments to Reflect Proposed Licensee Name Change CPSES-200700719, Nuclear Liability Insurance2007-04-10010 April 2007 Nuclear Liability Insurance CPSES-200700605, License Amendment Request (LAR) 07-003, Revision to Technical Specifications 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, & 5.6.5b, Core Operating Limits Report2007-04-10010 April 2007 License Amendment Request (LAR) 07-003, Revision to Technical Specifications 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, & 5.6.5b, Core Operating Limits Report CPSES-200700708, Evaluation of Pressurizer Weld Overlay Confirmatory Analyses2007-04-0505 April 2007 Evaluation of Pressurizer Weld Overlay Confirmatory Analyses CPSES-200700691, Core Operating Limits Report, Cycle 132007-04-0404 April 2007 Core Operating Limits Report, Cycle 13 CPSES-200700663, Transmittal of the Annual Radiological Environmental Operating Report for 20062007-03-30030 March 2007 Transmittal of the Annual Radiological Environmental Operating Report for 2006 CPSES-200700607, Property Damage Insurance2007-03-29029 March 2007 Property Damage Insurance CPSES-200700606, Decommissioning Report2007-03-29029 March 2007 Decommissioning Report CPSES-200700573, Request to Withdraw Relief Request A-72007-03-22022 March 2007 Request to Withdraw Relief Request A-7 CPSES-200700571, Supplement to License Amendment Request (LAR) 05-06; Revision to Technical Specification 5.6.5 Revise Listing of LOCA and Non-LOCA Analysis Methodologies (TAC Nos. MD0185/0186)2007-03-19019 March 2007 Supplement to License Amendment Request (LAR) 05-06; Revision to Technical Specification 5.6.5 Revise Listing of LOCA and Non-LOCA Analysis Methodologies (TAC Nos. MD0185/0186) CPSES-200700515, Day Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.2007-03-0909 March 2007 Day Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients. 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-200700451, Annual Operating Report for 20062007-02-28028 February 2007 Annual Operating Report for 2006 CPSES-200700422, Response to Request for Additional Information Related to Txu Power'S Request for Review of Previously Submitted Topical Reports2007-02-22022 February 2007 Response to Request for Additional Information Related to Txu Power'S Request for Review of Previously Submitted Topical Reports CPSES-200700414, Transmittal of Inservice Inspection Program Plan, Revision 5 (Unit 1: ASME Code Section XI 1998 Edition, 1999 and 2000 Addenda, Interval Start Date - 08/13/200, Second Interval)2007-02-22022 February 2007 Transmittal of Inservice Inspection Program Plan, Revision 5 (Unit 1: ASME Code Section XI 1998 Edition, 1999 and 2000 Addenda, Interval Start Date - 08/13/200, Second Interval) CPSES-200700391, Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds2007-02-20020 February 2007 Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds CPSES-200700346, Guarantees of Payment of Deferred Premiums, Submits Form 10-Q for the Period Ending September 30, 20062007-02-0808 February 2007 Guarantees of Payment of Deferred Premiums, Submits Form 10-Q for the Period Ending September 30, 2006 CPSES-200700229, Comanche, Response to Request for Additional Information, Relief Request B-6 for the Unit 1 Inservice Inspection (ISI) Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date..2007-02-0202 February 2007 Comanche, Response to Request for Additional Information, Relief Request B-6 for the Unit 1 Inservice Inspection (ISI) Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date.. CPSES-200700169, Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds2007-01-30030 January 2007 Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds CPSES-200700147, Response to Request for Additional Information Regarding Resolution of Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power2007-01-29029 January 2007 Response to Request for Additional Information Regarding Resolution of Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power CPSES-200700127, Submittal of Unit 2 Ninth Refueling Outage (2RF09) Inservice Inspection (ISI) Summary Report (Unit 2: 1998 Edition of ASME Code Section XI, Through 2000 Addenda, Interval Start Date - August 3, 2004, Second Interval)2007-01-24024 January 2007 Submittal of Unit 2 Ninth Refueling Outage (2RF09) Inservice Inspection (ISI) Summary Report (Unit 2: 1998 Edition of ASME Code Section XI, Through 2000 Addenda, Interval Start Date - August 3, 2004, Second Interval) CPSES-200700146, License Amendment Request (LAR) 06-007, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits2007-01-18018 January 2007 License Amendment Request (LAR) 06-007, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits 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 CPSES-200700099, Annual Report of Changes in Peak Cladding Temperature2007-01-10010 January 2007 Annual Report of Changes in Peak Cladding Temperature CPSES-200602339, License Amendment Request (LAR) 06-010, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program.2006-12-19019 December 2006 License Amendment Request (LAR) 06-010, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program. CPSES-200602340, License Amendment Request (LAR) 06-012, Revision to Technical Specification 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources - Operating, & TS 3.8.9, Distribution Systems - Operating.2006-12-19019 December 2006 License Amendment Request (LAR) 06-012, Revision to Technical Specification 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources - Operating, & TS 3.8.9, Distribution Systems - Operating. 2010-07-28 Category:Report MONTHYEARML23355A2682023-12-21021 December 2023
[Table view]NRC Comments - Comanche Peak LRA Supplement 3 (1) CP-202300566, (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation2023-12-12012 December 2023 (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-202300285, Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 12023-07-12012 July 2023 Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 1 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-202200419, (CPNPP) - Unit 1 Refueling Outage 22 (1RF22) Steam Generator 180 Day Report2022-11-0303 November 2022 (CPNPP) - Unit 1 Refueling Outage 22 (1RF22) Steam Generator 180 Day Report 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-202100127, Transmittal of Pressure and Temperature Limits Report, ERX-07-003, Revision 62021-03-16016 March 2021 Transmittal of Pressure and Temperature Limits Report, ERX-07-003, Revision 6 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-201900467, (CPNPP) - Biennial Review of Procedures and Station Operations Review Committee Meetings2019-08-14014 August 2019 (CPNPP) - Biennial Review of Procedures and Station Operations Review Committee Meetings CP-201900378, Transmittal of Seventeenth Refueling Outage (2RF17) Steam Generator 180 Day Report2019-06-10010 June 2019 Transmittal of Seventeenth Refueling Outage (2RF17) Steam Generator 180 Day Report CP-201900126, Special Report 2-SR-19-001-00, Inoperable Post Accident Monitoring Instrumentation Report.2019-02-25025 February 2019 Special Report 2-SR-19-001-00, Inoperable Post Accident Monitoring Instrumentation Report. CP-201800652, Special Report 1-SR-18-001-00, Inoperable Post Accident Monitoring Instrumentation Report2018-09-12012 September 2018 Special Report 1-SR-18-001-00, Inoperable Post Accident Monitoring Instrumentation Report ML18044A0982018-02-0808 February 2018 Solid Waste Registration Number: 33306; Texas Waste Code: 37043902; Reference Number: 15749 CP-201700805, Sixteenth Refueling Outage (2RF16) Steam Generator 180 Day Report2017-10-30030 October 2017 Sixteenth Refueling Outage (2RF16) Steam Generator 180 Day Report CP-201700223, Decommissioning Funding Status Report for Financial Assurance as of 12/31/20162017-03-30030 March 2017 Decommissioning Funding Status Report for Financial Assurance as of 12/31/2016 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-201600097, Westinghouse LTR-PAFM-16-2-NP, Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds.2016-02-29029 February 2016 Westinghouse LTR-PAFM-16-2-NP, Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds. 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 ML16047A3302016-01-20020 January 2016 NEI 12-01 Phase 2 Staffing Assessment, Revision 1 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 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 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 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 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 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 ML14189A4982014-06-19019 June 2014 Stars Response to Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request 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 CP-201400335, . Pressure and Temperature Limits Report2014-04-0808 April 2014 . Pressure and Temperature Limits Report 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 ML13225A5752013-12-19019 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13338A6612013-12-18018 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Comanche Peak Nuclear Power Plant, TAC Nos.: MF0860 and MF0861 ML13309A0272013-10-31031 October 2013 WCAP-17728-NP, Rev. 1, Comanche Peak Nuclear Power Plant Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis 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 2023-08-07 Category:Technical MONTHYEARML23355A2682023-12-21021 December 2023
[Table view]NRC Comments - Comanche Peak LRA Supplement 3 (1) CP-202300285, Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 12023-07-12012 July 2023 Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 1 CP-202200419, (CPNPP) - Unit 1 Refueling Outage 22 (1RF22) Steam Generator 180 Day Report2022-11-0303 November 2022 (CPNPP) - Unit 1 Refueling Outage 22 (1RF22) Steam Generator 180 Day Report CP-202100127, Transmittal of Pressure and Temperature Limits Report, ERX-07-003, Revision 62021-03-16016 March 2021 Transmittal of Pressure and Temperature Limits Report, ERX-07-003, Revision 6 CP-201900467, (CPNPP) - Biennial Review of Procedures and Station Operations Review Committee Meetings2019-08-14014 August 2019 (CPNPP) - Biennial Review of Procedures and Station Operations Review Committee Meetings CP-201900378, Transmittal of Seventeenth Refueling Outage (2RF17) Steam Generator 180 Day Report2019-06-10010 June 2019 Transmittal of Seventeenth Refueling Outage (2RF17) Steam Generator 180 Day Report CP-201900126, Special Report 2-SR-19-001-00, Inoperable Post Accident Monitoring Instrumentation Report.2019-02-25025 February 2019 Special Report 2-SR-19-001-00, Inoperable Post Accident Monitoring Instrumentation Report. CP-201800652, Special Report 1-SR-18-001-00, Inoperable Post Accident Monitoring Instrumentation Report2018-09-12012 September 2018 Special Report 1-SR-18-001-00, Inoperable Post Accident Monitoring Instrumentation Report ML18044A0982018-02-0808 February 2018 Solid Waste Registration Number: 33306; Texas Waste Code: 37043902; Reference Number: 15749 CP-201700805, Sixteenth Refueling Outage (2RF16) Steam Generator 180 Day Report2017-10-30030 October 2017 Sixteenth Refueling Outage (2RF16) Steam Generator 180 Day Report CP-201600097, Westinghouse LTR-PAFM-16-2-NP, Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds.2016-02-29029 February 2016 Westinghouse LTR-PAFM-16-2-NP, Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds. ML16047A3302016-01-20020 January 2016 NEI 12-01 Phase 2 Staffing Assessment, Revision 1 ML14189A4982014-06-19019 June 2014 Stars Response to Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request CP-201400335, . Pressure and Temperature Limits Report2014-04-0808 April 2014 . Pressure and Temperature Limits Report ML13225A5752013-12-19019 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13338A6612013-12-18018 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Comanche Peak Nuclear Power Plant, TAC Nos.: MF0860 and MF0861 ML13309A0272013-10-31031 October 2013 WCAP-17728-NP, Rev. 1, Comanche Peak Nuclear Power Plant Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis ML1029201602010-09-30030 September 2010 WCAP-17269-NP, Revision 0, Analysis of Capsule W from the Comanche Peak Unit No. 2 Reactor Vessel Radiation Surveillance Program. ML0930800082009-10-13013 October 2009 Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 57 of 99 Through Page 89 of 99 ML0930800102009-10-13013 October 2009 Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment E, Page 23 of 49 Through Attachment F CP-200901403, Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Cover Page Through Attachment a, Page 30 of 452009-10-13013 October 2009 Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Cover Page Through Attachment a, Page 30 of 45 CP-200901403, Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment a, Page 31 of 45, Through Attachment B2009-10-13013 October 2009 Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment a, Page 31 of 45, Through Attachment B CP-200901403, Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment C Through Attachment D, Page 20 of 992009-10-13013 October 2009 Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment C Through Attachment D, Page 20 of 99 CP-200901403, Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 21 of 99 Through Page 56 of 992009-10-13013 October 2009 Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 21 of 99 Through Page 56 of 99 CP-200901403, Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 57 of 99 Through Page 89 of 992009-10-13013 October 2009 Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 57 of 99 Through Page 89 of 99 CP-200901403, Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 90 of 99 Through Attachment E, Page 22 of 492009-10-13013 October 2009 Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 90 of 99 Through Attachment E, Page 22 of 49 ML0930800092009-10-13013 October 2009 Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 90 of 99 Through Attachment E, Page 22 of 49 ML0930800072009-10-13013 October 2009 Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 21 of 99 Through Page 56 of 99 ML0930800062009-10-13013 October 2009 Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment C Through Attachment D, Page 20 of 99 ML0930800052009-10-13013 October 2009 Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment a, Page 31 of 45, Through Attachment B CP-200901403, Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Cover Page Through Attachment a, Page 30 of 452009-10-13013 October 2009 Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Cover Page Through Attachment a, Page 30 of 45 CP-200801606, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Introduction Through Attachment a2008-11-26026 November 2008 Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Introduction Through Attachment a ML0835004682008-11-26026 November 2008 Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment B Through Attachment D, Page 20 ML0835004702008-11-26026 November 2008 Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment D, Page 21 Through 57 CP-200801606, Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment D, Page 58 Through 952008-11-26026 November 2008 Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment D, Page 58 Through 95 CP-200801606, Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment D, Page 21 Through 572008-11-26026 November 2008 Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment D, Page 21 Through 57 CP-200801606, Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment B Through Attachment D, Page 202008-11-26026 November 2008 Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment B Through Attachment D, Page 20 CP-200801606, Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Introduction Through Attachment a2008-11-26026 November 2008 Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Introduction Through Attachment a ML0835004722008-11-26026 November 2008 Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment E ML0835004712008-11-26026 November 2008 Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment D, Page 58 Through 95 ML0815600282008-09-0909 September 2008 Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, Proposed Alternative Course of Action ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0826102862008-06-30030 June 2008 WCAP-16827-NP, Addendum 1, Revision 0, Supplement to Comanche Peak, Units 1 and 2, Spent Fuel Pool Criticality Safety Analysis. CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-02-29029 February 2008 Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML0734401502007-12-0303 December 2007 Drill Report 11/06/2007, Final Report - Radiological Emergency Preparedness (REP) Program, 12/03/2007. Draft CPSES-200701238, Submittal of the CPSES Units 1 and 2 Large and Small Break LOCA Analyses2007-07-31031 July 2007 Submittal of the CPSES Units 1 and 2 Large and Small Break LOCA Analyses CPSES-200700708, Evaluation of Pressurizer Weld Overlay Confirmatory Analyses2007-04-0505 April 2007 Evaluation of Pressurizer Weld Overlay Confirmatory Analyses CPSES-200700346, Guarantees of Payment of Deferred Premiums, Submits Form 10-Q for the Period Ending September 30, 20062007-02-0808 February 2007 Guarantees of Payment of Deferred Premiums, Submits Form 10-Q for the Period Ending September 30, 2006 CPSES-200602196, WCAP-16610-NP, Rev. 0, Analysis of Capsule X from the Txu Energy Company Comanche Peak Unit 1 Reactor Vessel Radiation Surveillance Program.2006-09-30030 September 2006 WCAP-16610-NP, Rev. 0, Analysis of Capsule X from the Txu Energy Company Comanche Peak Unit 1 Reactor Vessel Radiation Surveillance Program. CPSES-200600269, Eighth Refueling Outage (2RF08) Steam Generator Twelve Month Report2006-02-14014 February 2006 Eighth Refueling Outage (2RF08) Steam Generator Twelve Month Report 2023-07-12 |
Text
"9Power TXU Power Mike Blevins Comanche Peak Steam Senior Vice President &
Electric Station Chief Nuclear Officer P. O. Box 1002 (EO1) Ref: 10CFR50.46 Glen Rose, TX 76043 Tel: 254 897 5209 Fax: 254 897 6652 mike.blevins~txu.com CPSES- 200600084 Log # TXX-06007 January 10, 2006 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 ANNUAL REPORT OF CHANGES IN PEAK CLADDING TEMPERATURE Gentlemen:
In accordance with the requirements of 10CFR50.46(a)(3)(ii), TXU Generation Company LP (TXU Power) submits the attached peak cladding temperatures (PCT) for CPSES Units 1 and 2. The Large-Break Loss-of-Coolant-Accident and Small-Break Loss-of-Coolant-Accident analysis for Units 1 and 2 were performed by TXU Power with the approved methodologies listed in CPSES Technical Specification 5.6.5. No changes or errors were discovered in the Emergency Core Cooling System (ECCS) evaluation model used to calculate peak cladding temperature (PCT).
This communication contains no new licensing basis commitments regarding CPSES Units 1 and 2.
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak
- Diablo Canyon
- Palo Verde
- South Texas Project
- Wolf Creek
TXX-06007 Page 2 of 2 Should you have any questions, please contact Mr. Jimmy Seawright at (254) 897-0140.
Sincerely, TXU Generation Company LP By: TXU Generation Management Company LLC, Its General Partner Mike Blevins By:
re W. Madden Director, Regulatory Affairs JDS/js Attachment c- B. S. Mallett, Region IV M. C. Thadani, NRR Resident Inspectors, CPSES
Attachment to TXX-06007 Page 1 of 1 CPSES Units 1 and 2 Peak Cladding Temperatures Analysis/Evaluation CPSES Unit 1 CPSES Unit 2 PCT (OF) PCT (0F)
Large Break LOCA 2053 2032
[Limiting]
Small Break LOCA 1841 1802