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MONTHYEARML0910304582009-04-13013 April 2009 Acceptance Review E-mail, Application for Relief Request B-9 and B-8, and License Amendment Request to Add License Condition for Submittal of Inservice Inspection Info Per WCAP-16168 Project stage: Acceptance Review ML0928706372009-12-22022 December 2009 Relief Request B-9 for Unit 1 and B-8 for Unit 2 to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination Project stage: Other 2009-12-22
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Category:Code Relief or Alternative
MONTHYEARML23198A3212023-07-27027 July 2023 Authorization and Safety Evaluation for Proposed Alternative RV-1 ML23121A2202023-05-0404 May 2023 Proposed Alternative P-1 Regarding Safeguard Building Sump Pumps ML22077A8412022-03-24024 March 2022 Proposed Alternative SNB-3 for the Snubber Inservice Program Third Interval Extension ML21021A1002021-02-0101 February 2021 Proposed Alternative to the Requirements of the ASME OM Code to Extend the Inservice Testing Program Interval for Certain Snubbers (EPID L-2020-LLR-0095 (Covid 19)) ML21013A1282021-01-28028 January 2021 Approval of Proposed Alternative to the Requirements of the ASME Code to Extend the Third Inservice Inspection Interval (EPID L-2020-LLR-0092 (COVID-19)) ML21021A0022021-01-28028 January 2021 Approval of Proposed Alternatives 1A4-1 and 1A4-2 from Certain Requirements of 10 CFR 50.55a for Inservice Inspection of Nuclear Power Plants ML20253A1172020-10-0505 October 2020 Approval of Request for Alternative from Certain Requirements of 10 CFR 50.55a for Operation and Maintenance of Nuclear Power Plants (EPIDs L-2020-LLR-0063, L-2020-LLR-0064, and L-2020-LLR-0065 (COVID-19)) CP-202000431, Relief Request 1A4-1 Supplement - Reactor Vessel (Rv) Upper Head Examinations2020-08-0505 August 2020 Relief Request 1A4-1 Supplement - Reactor Vessel (Rv) Upper Head Examinations ML20196L8232020-07-14014 July 2020 Relief Request SNB-1, Snubber Testing ML20196L8242020-07-14014 July 2020 Relief Request 1A3-2, Inservice Inspection (Isi), Table 1 ML20196L8252020-07-14014 July 2020 Relief Request SNB-1, Snubber Testing, Table 1 ML20196L8262020-07-14014 July 2020 Relief Request V-3, Inservice Testing (IST) ML20196L8292020-07-14014 July 2020 Relief Request 1A3-2, Inservice Inspection (ISI) ML20196L8272020-07-14014 July 2020 Relief Request 1A4-2, Reactor Vessel (Rv) Bottom Mounted Instrumentation (Bmi) Nozzle Penetration Examination ML20196L8302020-07-14014 July 2020 Relief Request V-3, Inservice Testing (Ist), Table 1 CP-202000262, Snubber Testing and Snubber Visual Examinations Relief Request2020-04-10010 April 2020 Snubber Testing and Snubber Visual Examinations Relief Request CP-202000261, Inservice Inspection (ISI) and Inservice Testing (IST) Program Relief Requests2020-04-0707 April 2020 Inservice Inspection (ISI) and Inservice Testing (IST) Program Relief Requests ML17095A2512017-04-0707 April 2017 Request for Alternative 2B3-1 Re Examination of Reactor Vessel Closure Head Penetration Nozzles ML16179A4052016-07-11011 July 2016 Relief Request Nos. B-9, B-3, B-10, and B-11 for Piping Welds, Second 10-year Inservice Inspection Interval ML16074A0012016-03-14014 March 2016 Relief Request 1B3-3, Alternative for Reactor Pressure Vessel Cold Leg Weld Inspection Frequency from Not to Exceed 7 Years to 9 Years for the Third 10-Year Inservice Inspection Interval ML16063A0012016-03-11011 March 2016 Relief Request No. B-15, C-2, and C-4 for Welds in the RPV and Containment Spray and Residual Heat Removal Heat Exchanger Shells, Second 10-year Inservice Inspection Interval ML16011A0732016-01-19019 January 2016 Relief Request T-1; Alternative to the ASME OM Code Frequency Specifications for Inservice Testing for the Third 10-Year IST Interval ML15259A0042015-10-30030 October 2015 Relief Request 1B3-4, Alternative for Reactor Pressure Vessel Head Penetration Weld Inspection Frequency (from 10 to 15 Years), Third 10-Year Inservice Inspection Interval ML15257A2422015-09-18018 September 2015 Relief Request 2A3-1, from ASME Code Section XI Requirements, Risk-Informed Process for Selection of Class 1 and Class 2 Piping Weld Examinations, Third 10-Year Inservice Inspection Interval ML15257A2402015-09-15015 September 2015 Relief Request 2C3-1, from ASME Code, Section XI Requirements Reactor Pressure Vessel Leak-Off Flange for the Third 10-Year Inservice Inspection Interval CP-201500671, Relief Request T-1 for Inservice Testing Program for Application of an Alternative to the ASME OM Code Frequency Specifications, (2007 Edition of ASME Code, Section XI, 2008 Addenda Third Interval Start Date: August 3.2015-06-30030 June 2015 Relief Request T-1 for Inservice Testing Program for Application of an Alternative to the ASME OM Code Frequency Specifications, (2007 Edition of ASME Code, Section XI, 2008 Addenda Third Interval Start Date: August 3. ML15090A1042015-04-0303 April 2015 Relief Requests B-7, B-12, and B-13 - Steam Generator Head-to-Tube Sheet Welds for the Second 10-Year Inservice Inspection Interval ML14087A0662014-04-10010 April 2014 Relief Request No. 1/2E-1 for Containment Electrical Penetrations for the Third 10-Year Inservice Inspection Interval ML14073A5442014-04-0101 April 2014 Relief Request No. B-14 for Reactor Pressure Vessel Hot Leg Nozzle Weld Examinations for the Second 10-Year Inservice Inspection Interval ML13158A0932013-06-26026 June 2013 Relief Request No. E-1 Containment Electrical Penetrations, for the Second 10-Year Inservice Inspection Interval ML13148A4372013-06-26026 June 2013 Relief Request No. P-1 for Pumps and Valves, Third 10-Year Inservice Testing Plan Interval ML13113A3792013-05-0808 May 2013 Relief Request No. V-1, from ASME Code for Operation and Maintenance of Nuclear Power Plants Requirements for Pumps and Valves, for the Third 10-Year Inservice Testing Interval ML13046A3852013-03-19019 March 2013 Relief Request C-2 for the Reactor Pressure Vessel Flange Leak-Off Piping, Third 10-Year Inservice Inspection Interval ML13056A5032013-03-15015 March 2013 Relief Request B-2, Alternative to ASME Code Requirements for Examination of Reactor Vessel Hot-Leg Nozzle Welds, for the Third 10-Year Inservice Inspection Interval CP-201300003, Submittal of Relief Request No. B-2, Third 10 Year ISI Interval from 10CFR50.55a Requirements for Reactor Vessel Hot Leg Nozzle Weld Examinations (Third ISI Interval Start Date August 13, 2010)2013-01-16016 January 2013 Submittal of Relief Request No. B-2, Third 10 Year ISI Interval from 10CFR50.55a Requirements for Reactor Vessel Hot Leg Nozzle Weld Examinations (Third ISI Interval Start Date August 13, 2010) CP-201201384, Response to Request for Additional Information for Relief Request No. E-12012-11-14014 November 2012 Response to Request for Additional Information for Relief Request No. E-1 ML12194A2502012-08-14014 August 2012 Relief Request A-1 for Approval of Risk-Informed Alternative to ASME Code, Section XI for Class 1 and 2 Piping Welds, Third 10-Year Inservice Inspection Interval ML1131100922011-12-19019 December 2011 Relief Request No. C-9, Reactor Pressure Vessel Flange Leak-off Piping Configuration, Second 10-Year Inservice Inspection Interval ML1126500832011-11-10010 November 2011 Approval of Relief Request Nos. B-10 and B-11 for the Second 10-Year Inservice Inspection Interval CP-201001546, Relief Request No. B-11 for the Second 10 Years ISI Interval from 10 CFR 50.55a Inspection Requirements Due to Physical Interferences (Second Interval Start Date: August 13, 2000)2010-12-15015 December 2010 Relief Request No. B-11 for the Second 10 Years ISI Interval from 10 CFR 50.55a Inspection Requirements Due to Physical Interferences (Second Interval Start Date: August 13, 2000) CP-201001544, Relief Request No. C-9 for the Second 10 Year Interval from 10 CFR 50.55a Inspection Requirements Due to Hardship (Second Interval Start Date: August 13, 2000)2010-12-15015 December 2010 Relief Request No. C-9 for the Second 10 Year Interval from 10 CFR 50.55a Inspection Requirements Due to Hardship (Second Interval Start Date: August 13, 2000) CP-201000890, Relief Request No. C-7 for the Second 10 Year ISI Interval from 10 CFR 50.55a Inspection Requirements Due to Physical Interferences (Second Interval Start Date: August 13, 2000)2010-12-15015 December 2010 Relief Request No. C-7 for the Second 10 Year ISI Interval from 10 CFR 50.55a Inspection Requirements Due to Physical Interferences (Second Interval Start Date: August 13, 2000) ML0928706372009-12-22022 December 2009 Relief Request B-9 for Unit 1 and B-8 for Unit 2 to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination CP-200901227, Revision to Request for Relief to Extend the Unit 1 and 2 in Service Inspection Interval for the Reactor Vessel Weld Examination and Withdrawal of License Amendment Request 09-004 to Add License Condition for Submittal of ISI Informatio2009-09-14014 September 2009 Revision to Request for Relief to Extend the Unit 1 and 2 in Service Inspection Interval for the Reactor Vessel Weld Examination and Withdrawal of License Amendment Request 09-004 to Add License Condition for Submittal of ISI Information an ML0916205482009-07-23023 July 2009 Relief Request P-2, Inservice Testing Plan for Pumps and Valves for Second Interval CP-200801132, Relief Request No. P-2 for the Unit 1 and Unit 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 1998 Edition, Through 2000 Addenda; Interval Start Date: August 3, 2004, Second Interval)2008-09-24024 September 2008 Relief Request No. P-2 for the Unit 1 and Unit 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 1998 Edition, Through 2000 Addenda; Interval Start Date: August 3, 2004, Second Interval) ML0821301472008-08-22022 August 2008 Request for Relief B-2 for Second 10-Year Inservice Inspection Interval from 10 CFR 50.55a Inspections Requirements Due to Physical Interferences CP-200800927, (Cpnpp), Relief Request B-8 for Unit 1 Second 10 Year ISI Interval & B-6 for Unit 2 Second 10 Year ISI Interval from 10 CFR 50.55a Requirements for Reactor Vessel Hot & Cold Leg Nozzle Weld Examinations (Unit 1 Second Interval Start..2008-07-10010 July 2008 (Cpnpp), Relief Request B-8 for Unit 1 Second 10 Year ISI Interval & B-6 for Unit 2 Second 10 Year ISI Interval from 10 CFR 50.55a Requirements for Reactor Vessel Hot & Cold Leg Nozzle Weld Examinations (Unit 1 Second Interval Start.. ML0805201952008-03-10010 March 2008 Relief Request B-5 for Second 10-Year ISI Interval from 10 CFR 50.55a Requirements for Class 1 Repair/Replacement of Control Rod Drive Mechanism Canopy Seal Welds ML0804306622008-02-29029 February 2008 Request for Relief No. B-4 from Certain Requirements of ASME Code, Section XI for Implementation of the EPRI-PDI Supplement 11 Program and Application of Weld Overlays 2023-07-27
[Table view] Category:Letter
MONTHYEARCP-202400030, License Renewal Application Revision 0 - Supplement 3, Revision 12024-01-31031 January 2024 License Renewal Application Revision 0 - Supplement 3, Revision 1 IR 05000445/20230042024-01-29029 January 2024 Integrated Inspection Report 05000445/2023004 and 05000446/2023004 CP-202400034, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1)2024-01-29029 January 2024 (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1) ML24024A2102024-01-29029 January 2024 Summary of Regulatory Audit Regarding a License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24025A0052024-01-25025 January 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report ML24023A0242024-01-24024 January 2024 Correction to Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident Methodology ML24018A1072024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000445/2024012 and 05000446/2024012) and Request for Information ML23159A2082023-12-20020 December 2023 Request for Withholding Information from Public Disclosure ML23319A3872023-12-20020 December 2023 Issuance of Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology ML23348A2392023-12-19019 December 2023 Nonacceptance of License Amendment Request to Relocate Technical Specification 3.9.3, Nuclear Instrumentation, to the Technical Requirements Manual CP-202300575, (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 22023-12-13013 December 2023 (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 2 ML23333A0872023-12-13013 December 2023 Transmittal of Dam Safety Inspection Report - Public 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-202300494, License Renewal Application Revision 0, Supplement 32023-12-0606 December 2023 License Renewal Application Revision 0, Supplement 3 ML23313A0732023-12-0606 December 2023 Issuance of Amendment Nos. 184 and 184 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Rev. 1, Improved Roac and CAOC Fq Surveillance Technical Specifications ML23291A4382023-11-30030 November 2023 Notice of Availability of the Draft Plant-Specific Supplement 60, to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Comanche Peak Nuclear Power Plant, Unit Numbers 1 and 2, License Renewal Applica ML23325A0182023-11-30030 November 2023 Schedule Revision for the License Renewal Application Review IR 05000445/20234022023-11-30030 November 2023 NRC Security Inspection Report 05000445/2023402 and 05000446/2023402 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 ML23308A0032023-11-17017 November 2023 Letter to R. Nelson, Executive Director; Achp; Re., Comanche Peak Draft Environmental Impact Statement ML23308A0022023-11-17017 November 2023 Letter to M. Wolfe, Executive Director; Shpo; Re., Comanche Peak Draft Environmental Impact Statement ML23317A3002023-11-13013 November 2023 Letter to R. Sylestine, Chairman, Alabama-Coushatta Tribe of Texas Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2972023-11-13013 November 2023 Letter to R. Martin, President, Tonkawa Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2872023-11-13013 November 2023 Letter to J. Garza, Chairman, Kickapoo Traditional Tribe of Texas Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2832023-11-13013 November 2023 Letter to D. Dotson, President, Delaware Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2852023-11-13013 November 2023 Letter to E. Martinez, President, Mescalero Apache Tribe Regarding Comanche Peak Draft Environmental Impact Statement ML23306A0302023-11-13013 November 2023 Letter to J. Cernek, Chairman; Coushatta Tribe of Louisiana Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2902023-11-13013 November 2023 Letter to M. Pierite, Chairman, Tunica Biloxi Tribe of Louisiana Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2982023-11-13013 November 2023 Letter to R. Morrow, Town King, Thlopthlocco Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2842023-11-13013 November 2023 Letter to D. Kaskaske, Chairman, Kickapoo Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2822023-11-13013 November 2023 Letter to D. Cooper, Chairman, Apache Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2962023-11-13013 November 2023 Letter to M. Woommavovah, Chairman, Comanche Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2812023-11-13013 November 2023 Letter to C. Hoskin, Principal Chief, Cherokee Nation; Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2862023-11-13013 November 2023 Letter to J. Bunch, Chief, United Keetoowah Band of Cherokee Indians Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3032023-11-13013 November 2023 Letter to W. Yargee, Chief, Alabama-Quassarte Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2882023-11-13013 November 2023 Letter to L. Johnson, Chief, Seminole Nation of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3012023-11-13013 November 2023 Letter to S. Yahola, Mekko, Kialegee Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2792023-11-13013 November 2023 Letter to B. Gonzalez, Chairman, Caddo Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3022023-11-13013 November 2023 Letter to T. Parton, President, Wichita and Affiliated Tribes Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2892023-11-13013 November 2023 Letter to L. Spottedbird, Chairman, Kiowa Indian Tribe Regarding Comanche Peak Draft Environmental Impact Statement ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23360A6312023-10-26026 October 2023 FEMA, Submittal of Radiological Emergency Preparedness Final Report for the Comanche Peak Nuclear Power Plant Medical Services Drill Evaluated on August 23, 2023 CP-202300416, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-10-12012 October 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202300432, Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 42023-10-0404 October 2023 Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 4 ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23263A0242023-09-21021 September 2023 Revision of Schedule for the Environmental Review of the Comanche Peak Nuclear Power Plant Units 1 and 2 License Renewal Application 2024-01-31
[Table view] Category:Safety Evaluation
MONTHYEARML23319A3872023-12-20020 December 2023 Issuance of Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology ML23313A0732023-12-0606 December 2023 Issuance of Amendment Nos. 184 and 184 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Rev. 1, Improved Roac and CAOC Fq Surveillance Technical Specifications ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML23198A3212023-07-27027 July 2023 Authorization and Safety Evaluation for Proposed Alternative RV-1 ML22192A0072022-08-22022 August 2022 Issuance of Amendment Nos. 183 and 183 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2 ML22194A0592022-07-14014 July 2022 Correction to Amendment Nos. 182 and 182 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22129A0722022-05-16016 May 2022 Review of Quality Assurance Program Changes ML22077A8412022-03-24024 March 2022 Proposed Alternative SNB-3 for the Snubber Inservice Program Third Interval Extension ML21321A3492022-02-24024 February 2022 Issuance of Amendment Nos. 182 and 182 to Revise Technical Specifications to Adopt TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspections ML21322A1032021-12-0707 December 2021 Proposed Alternative for the Continued Use of a Risk-Informed Process for the Selection of Class 1 and 2 Piping Welds for Inservice Inspection ML21132A0892021-06-0909 June 2021 Issuance of Amendment Nos. 181 and 181 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-567, Rev. 1, Add Containment Sump TS to Address GSI - 191 Issues ML21061A2172021-05-19019 May 2021 Issuance of Amendment Nos. 180 and 180 to Authorize Revision of Certain Emergency Action Levels of the Emergency Plan ML21103A0392021-04-23023 April 2021 Issuance of Amendment Nos. 179 and 179 the Adoption of Technical Specifications Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition (EPID L-2020-0147) ML21015A2122021-02-12012 February 2021 Issuance of Amendment Nos. 178 and 178 Regarding One-Time Revision to Technical Specifications 3.7.8 Station Service Water System (Ssws) and 3.8.1 AC Sources - Operating ML21022A1622021-02-0808 February 2021 Proposed Alternative to the Requirements of the ASME OM Code to Extend the Inservice Testing Program Interval for Certain Check and Relief Valves (EPID L-2020-LLR-0096 (COVID-19)) ML20346A0192021-02-0101 February 2021 Issuance of Amendment Nos. 177 and 177 Regarding Revision to Technical Specifications 3.8.1, AC Sources - Operating ML21021A1002021-02-0101 February 2021 Proposed Alternative to the Requirements of the ASME OM Code to Extend the Inservice Testing Program Interval for Certain Snubbers (EPID L-2020-LLR-0095 (Covid 19)) ML21013A1282021-01-28028 January 2021 Approval of Proposed Alternative to the Requirements of the ASME Code to Extend the Third Inservice Inspection Interval (EPID L-2020-LLR-0092 (COVID-19)) ML21021A0022021-01-28028 January 2021 Approval of Proposed Alternatives 1A4-1 and 1A4-2 from Certain Requirements of 10 CFR 50.55a for Inservice Inspection of Nuclear Power Plants ML20282A7092020-11-17017 November 2020 Proposed Alternative to the Requirements of the ASME Omcode to Extend the Inservice Testing Program Interval for Certain Snubbers (EPID L-2020-LLR-0060 (COVID-19)) ML20281A4722020-11-0404 November 2020 Use of Later Code Edition to the Requirements of the ASME OM Code ML20255A1002020-10-0707 October 2020 Proposed Alternative to the Requirements of the ASME OM Code to Extend the Inservice Test Program Interval for Certain Check and Relief Valves (EPID L-2020-LLR-0061 and EPID L-2020-LLR-0062 (COVID-19)) 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 ML20226A0132020-08-17017 August 2020 Use of Later Code Edition to the Requirements of the ASME Code 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) ML20054A2762020-02-27027 February 2020 Approval of Change to the Quality Assurance Program as Described in the Comanche Peak Nuclear Power Plant Final Safety Analysis Report ML19267A0182019-11-0404 November 2019 Issuance of Amendment Nos. 172 and 172 to Revise Augmentation Times and Emergency Response Organization Staffing for the Emergency Plan ML18304A4872018-11-30030 November 2018 Issuance of Amendments 171 and 171 Regarding Revision to Technical Specifications for Engineered Safety Feature Actuation System Instrumentation 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) ML18221A6322018-08-15015 August 2018 Eicb Safety Evaluation - Comanche Peak Nuclear Power Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.2 Engineered Safety Feature Actuation System Instrumentation Docket/Epid 000976/05000446/L-2018-LLA-0 ML17129A0242017-06-29029 June 2017 Comanche Peak Nuclear Power Plant, Units 1 and 2 - Issuance of Amendment Nos. 169 and 169 Re: Administrative Change to Licensee Name (CAC Nos. MF8933 and MF8934) ML17074A4942017-04-13013 April 2017 Issuance of Amendment Nos. 168 and 168 Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ML17095A2512017-04-0707 April 2017 Request for Alternative 2B3-1 Re Examination of Reactor Vessel Closure Head Penetration Nozzles ML16334A1732016-12-14014 December 2016 Comanche Peak Nuclear Power Plant, Units 1 And 2; Safety Evaluation Regarding Implementation Of Mitigating Strategies And Reliable Spent Fuel Pool Instrumentation Related To Orders EA-12-049 And EA-12-051 ML16179A4052016-07-11011 July 2016 Relief Request Nos. B-9, B-3, B-10, and B-11 for Piping Welds, Second 10-year Inservice Inspection Interval ML16137A0562016-06-14014 June 2016 Issuance of Amendment Nos. 166 and 166, Request to Revise Emergency Action Levels Based on Nuclear Energy Institute (NEI) 99-01, Revision 6 ML16096A2662016-05-0606 May 2016 Redacted Letter, Order, Safety Evaluation, and Draft Conforming Amendments, Application for Order Approving Direct and Indirect Transfer of Licenses and Conforming License Amendments ML16096A2642016-05-0606 May 2016 Draft Conforming Amendments, Application for Order Approving Direct and Indirect Transfer of Licenses and Conforming License Amendments ML16074A0012016-03-14014 March 2016 Relief Request 1B3-3, Alternative for Reactor Pressure Vessel Cold Leg Weld Inspection Frequency from Not to Exceed 7 Years to 9 Years for the Third 10-Year Inservice Inspection Interval ML16063A0012016-03-11011 March 2016 Relief Request No. B-15, C-2, and C-4 for Welds in the RPV and Containment Spray and Residual Heat Removal Heat Exchanger Shells, Second 10-year Inservice Inspection Interval ML16011A0732016-01-19019 January 2016 Relief Request T-1; Alternative to the ASME OM Code Frequency Specifications for Inservice Testing for the Third 10-Year IST Interval 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 ML15259A0042015-10-30030 October 2015 Relief Request 1B3-4, Alternative for Reactor Pressure Vessel Head Penetration Weld Inspection Frequency (from 10 to 15 Years), Third 10-Year Inservice Inspection Interval ML15257A2422015-09-18018 September 2015 Relief Request 2A3-1, from ASME Code Section XI Requirements, Risk-Informed Process for Selection of Class 1 and Class 2 Piping Weld Examinations, Third 10-Year Inservice Inspection Interval ML15257A2402015-09-15015 September 2015 Relief Request 2C3-1, from ASME Code, Section XI Requirements Reactor Pressure Vessel Leak-Off Flange for the Third 10-Year Inservice Inspection Interval ML15090A1042015-04-0303 April 2015 Relief Requests B-7, B-12, and B-13 - Steam Generator Head-to-Tube Sheet Welds for the Second 10-Year Inservice Inspection Interval 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 ML14183A3422014-09-0808 September 2014 Issuance of Amendment Nos. 163 and 163 to Revise License Condition Related to Approval of Revised Cyber Security Plan Implementation Schedule 2023-09-28
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 December 22, 2009 Mr. Rafael Flores Senior Vice President and Chief Nuclear Officer Luminant Generation Company LLC P.O. Box 1002 Glen Rose, TX 76043 SUB..COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 -REQUEST FOR RELIEF TO EXTEND THE INSERVICE INSPECTION INTERVAL FOR THE REACTOR VESSEL WELD EXAMINATION (TAC NOS. ME0777 AND ME0778)
Dear Mr. Flores:
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed and evaluated the information provided by Luminant Generation Company LLC (the licensee) in its letter dated March 4, 2009, as supplemented by letter dated September 14, 2009. The licensee requested approval for the use of the alternative to extend the inservice inspection (lSI) interval for examinations of the reactor pressure vessel Category B-A and Category B-D welds from 10 years to 20 years for Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (Relief Request B-9 for Unit 1 and B-8 for Unit 2). The application dated March 4, 2009, also included an amendment request to add a license condition for submittal of lSI information and analysis requested in paragraph (e) of the final Title 10 of the Code of Federal Regulations (10 CFR), Section 50.61 a, or the proposed rule (October 3, 2007; 72 FR 56275), prior to issuance of the final 10 CFR 50.61 a, following completion of each American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Category B-A and Category B-D Reactor Vessel weld inspection.
By letter dated September 14, 2009, the licensee revised its application for relief request for a one-time extension only and withdrew the proposed amendment and associated license condition.
The NRC staff has completed its review of the submittals for Relief Requests B-9 and B-8 for CPSES, Units 1 and 2 and concludes that extending the current lSI interval for the identified Category B-A and Category B-D components from 10 years to 20 years results in a small and acceptable risk increase.
This conclusion is based on the fact that the plant-specific information provided by the licensee is bounded by the data in the NRC-approved topical report 16168-NP, Revision 2, and the request meets all the conditions and limitations described in the approved topical report and the associated safety evaluation report. Therefore, Relief Requests B-9 and B-8 provide an acceptable level of quality and safety, and the alternative can be authorized pursuant to 10 CFR 50.55a(a)(3)(i) to extend the licensee's current second lSI interval to approximately 2020 for CPSES, Unit 1 and 2023 for CPSES, Unit 2, with the licensee performing the subject examinations in 2019 for CPSES, Unit 1 and 2021 for CPSES, Unit 2.
R. Flores -2 All other ASME Code,Section XI requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
The NRC safety evaluation is enclosed.
If you have any questions, please contact Balwant K. Singal at 301-415-3016 or bye-mail at Balwant.Singal@nrc.gov.
Sincerely, Michael 1. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosure:
As stated cc w/encl: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST NOS. B-9 (UNIT 1) AND B-8 (UNIT 2) SECOND 10-YEAR INSERVICE TESTING INTERVAL LUMINANT GENERATION COMPANY LLC COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446
1.0 INTRODUCTION
By letter dated March 4, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090720583), as supplemented by letter dated September 14, 2009 (ADAMS Accession No. ML092650286), Luminant Generation Company, LLC (the licensee), submitted Relief Requests (RRs) B-9 and B-8 for Comanche Peak Steam Electric Station (CPSES), Unit 1 and Unit 2, respectively.
Specifically, the alternative was requested pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(a)(3)(i) for the use of the alternative to extend the inservice inspection (lSI) interval for examinations of the reactor pressure vessel (RPV) Category B-A and Category B-D welds from 10 years to 20 years. The alternative is based on the U.S. Nuclear Regulatory Commission (NRC) staff's safety evaluation report (SER), dated May 8,2008, of a topical report WCAP-16168-NP, Revision 2, Informed Extension of the Reactor Vessel In-Service Inspection Interval," dated June 2008 (ADAMS Accession No. ML082820046).
The application dated March 4, 2009, also included an amendment request to add a license condition for submittal of lSI information and analysis requested in paragraph (e) of the final Title 10 of the Code of Federal Regulations (10 CFR), Section 50.61 a, or the proposed rule (October 3, 2007; 72 FR 56275), prior to issuance of the final 10 CFR 50.61 a, following completion of each American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Category B-A and Category B-D RPV weld inspections.
By letter dated September 14, 2009, the licensee revised its application for RR for a one-time extension only and withdrew the proposed amendment and associated license condition.
2.0 REGULATORY EVALUATION
In accordance with 10 CFR 50.55a(g)(4), the licensee is required to perform lSI of ASME Code,Section XI, Class 1, 2, and 3 components and system pressure tests during the first 10-year Enclosure
-2 interval and subsequent 1 O-year intervals that comply with the requirements in the latest edition and addenda of Section XI of the ASME Code, incorporated by reference in 10 CFR 50.55a(b), subject to the limitations and modifications listed therein. The current second 10-year lSI interval at CPSES, Unit 1 ends in August 2010, and the current second 1 O-year lSI interval at CPSES, Unit 2 ends in August 2014. The Code of record for the inspection of Class 1, 2, and 3 components for both units isSection XI of the ASME Code 1998 Edition with the 2000 Addenda. The regulation in 10 CFR 50.55a(a)(3) states, in part, that the Director of the Office of Nuclear Reactor Regulation may authorize an alternative to the requirements of 10 CFR 50.55a(g).
For an alternative to be authorized, as per 10 CFR 50.55a(a)(3), the licensee shall demonstrate that (i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The licensee has requested the relief pursuant to 10 CFR 50.55a(a)(3)(i).
3.0 TECHNICAL
EVALUATION The lSI of Category B-A and Category B-D components consists of visual and ultrasonic examinations intended to discover whether flaws have initiated, whether pre-existing flaws have extended, and whether pre-existing flaws may have been missed in prior examinations.
These examinations are required to be performed at regular intervals, as defined in Section XI of the ASME Code. 3.1 Summary ofWCAP-16168-NP In January 2006, the Pressurized Water Reactor Owners Group (PWROG) submitted the WCAP-16168-NP, Revision 1 (ADAMS Accession No. ML060330504) (referred to as WCAP in rest of this document), "Risk-Informed Extension of the Reactor Vessel In-Service Inspection Interval," to the NRC in support of making a risk-informed assessment of extensions to the lSI intervals for Category B-A and Category B-D components.
In the WCAP, the PWROG took data associated with three different pressurized-water reactor (PWR) plants (referred to as the pilot plants), designed respectively by the three main nuclear steam supply system manufacturers for nuclear power plants in the U.S., and performed the necessary studies on each of the pilot plants required to justify the proposed extension for the lSI interval for Category B-A and Category B-D components from 10 to 20 years. The analyses in the WCAP used probabilistic fracture mechanics (PFM) methodology and inputs from the work described in the NRC's pressurized thermal shock (PTS) risk re-evaluation, specifically NUREG-1806, "Technical Basis for Revision of the Pressurized Thermal Shock (PTS) Screening Limit in the PTS Rule (10 CFR 50.61): Summary Report," (ADAMS Accession No. ML061580318), and NUREG-1874, "Recommended Screening Limits for Pressurized Thermal Shock (PTS)," (ADAMS Accession No. ML070860156).
The PWROG analyses incorporated the effects of fatigue crack growth and lSI. Design-basis transient data was used as input to the fatigue crack growth The effects of lSI were modeled consistently with the previously-approved PFM codes contained in WCAP-14572-NP-A, "Westinghouse Owners Group Application of Risk-Informed Methods to Piping Inservice Inspection Topical Report," (ADAMS Accession Nos. ML012630327, ML012630349, and ML012630313).
These
-3 effects were evaluated using the Fracture Analysis of Vessels: Oak Ridge (FAVOR) computer code (ORNLlNRC/LTR04/18 (ADAMS Accession No. ML042960391)).
All other inputs were identical to those used in the PTS risk re-evaluation.
From the results of the studies, the PWROG concluded that the ASME Code,Section XI 10-year inspection interval for Category B-A and Category B-D components in PWR reactor vessels can be safely extended to 20 years. The PWROG's conclusion from the results for the pilot plants was considered applicable to any plant designed by Westinghouse, Combustion Engineering, and Babcock and Wilcox as long as the critical, plant-specific parameters (defined in Appendix A of the WCAP) are bounded by the pilot plants. In June 2008, the PWROG issued WCAP-16168-NP-A, Revision 2 (ADAMS Accession No. ML082820046), which includes the PWROG's responses to the NRC staff's request for additional information and the NRC staff's SER on the WCAP. For simplicity, the NRC staff will characterize the subject methodology as the WCAP-A methodology in the remaining of this safety evaluation. Summary of NRC Safety Evaluation Report ofWCAP-16168-NP The NRC staff's conclusion in its SER for the WCAP indicates that the WCAP-A methodology is acceptable for referencing in requests to implement alternatives to ASME Code inspection requirements for PWR plants in accordance with the limitations and conditions in the SER (ADAMS Accession No. ML081060051).
In addition to showing that the subject plant is bounded by the pilot plants' information from Appendix A in the WCAP, the key points of the SER are summarized below: The dates identified in the request for alternative should be within plus or minus one refueling cycle of the dates identified in the implementation plan contained in PWROG letter, OG-06-356 (ADAMS Accession No. ML08221 0245), to the NRC. Any deviations from the implementation plan should be discussed in detail in the request for alternative lSI interval.
The maximum interval for proposed lSI is 20 years. The request for alternative lSI interval can use any NRC-approved method to calculate the Charpy transition temperature shift at the 30 ft-Ib energy level (b.T 3o) and the fracture resistance against flaws in each RPV material X (RT MAX-X) 1 as defined in the draft and/or final alternative PTS Rule, 10 CFR 50.61 a. However, if the request uses the NUREG-1874 methodology to calculate b.T 3o , then the request should include the analysis described in parqgraph (6) of subsection (f) to the voluntary PTS rule. The analysis should be done for all of the materials in the beltline area with at least three surveillance data points. If the subject plant is a Babcock and Wilcox plant, licensees must 1 RTMAX stands for PTS Reference Temperature.
-4 verify that the fatigue crack growth based on 12 heat-up/cool-down transients per year bounds the fatigue crack growth for all of its design basis transients, and identify the design basis transients that contribute to significant fatigue crack growth. If the subject plant has RPV forgings that are susceptible to underclad cracking or if the RPV includes forgings with RT MAX-FO values exceeding 240 degrees Fahrenheit (OF) then the WCAP analyses are not applicable.
The licensee must submit a plant-specific evaluation for any extension to the 1 O-year inspection interval for ASME Code,Section XI, Category B-A and Category B-D RPV welds. Description of Proposed Alternatives CPSES, Unit 1 In RR B-9, the licensee proposes to postpone performance of the ASME Code required Category B-A and Category B-D weld lSI for the second interval from refueling outage 1 RF14 in 2010 to refueling outage 1 RF20 in 2019. This schedule is consistent with the information in PWROG letter, OG-06-356.
CPSES, Unit 2 In RR B-8, the licensee proposes to postpone performance of the ASME Code required Category B-A and Category B-D weld lSI for the second interval from refueling outage 2RF13 in 2012 to refueling outage 2RF19 in 2021. This schedule is not consistent with the information in PWROG letter, OG-06-356. Component for Which Relief is Requested The affected component is the CPSES, Units 1 and 2 RPVs. The following examination categories and item numbers from IWB-2500 and Table IWB-2500-1 of the ASME Code,Section XI, are addressed in this request: Examination Category Item Number Description B-A B1.11 Circumferential Shell Weld B-A B1.12 Longitudinal Shell Weld B-A B1.21 Lower Head Circumferential Shell Weld B-A B1.22 Lower Head Meridional Weld B-A B1.30 Shell-to-Flange Weld B-D B3.90 Nozzle-to-Vessel Welds B-D B3.100 Nozzle Inner Radius Areas
-3.5 Basis for Proposed Alternatives The methodology used to demonstrate the acceptability of extending the inspection interval for Category B-A and Category B-D welds based on an acceptably small change in risk is contained in WCAP-A. The critical parameters for demonstrating that this pilot plant analysis is applicable on a plant-specific basis, as identified in the WCAP-A, are identified in Table 1 of RRs B-9 and B-8. By demonstrating that each plant-specific parameter is bounded by the corresponding pilot plant parameter, the licensee has established the applicability of the methodology to the CPSES, Units 1 and 2 RPVs. 3.6 Duration of Proposed Alternatives As revised in the September 14, 2009, supplement, this request is applicable to the CPSES, Units 1 and 2 second RPV lSI interval.
3.7 NRC Staff Evaluation The NRC staff has reviewed RRs B-9 and B-8 for CPSES, Units 1 and 2. The "Frequency and Severity of Design Transients" of CPSES, Units 1 and 2 were found to be bounded by the information in WCAP-A. Also, the CPSES, Units 1 and 2 RPVs are single-layer clad and, therefore, bounded by the WCAP-A assumptions.
In its letter dated September 14, 2009, the licensee provided Table 2 for each RR, which includes additional information pertaining to previous RPV inspections and the schedule for future inspections.
The CPSES, Unit 1 RPV has three potential beltline indications in its lSI record. However, all these indications were found to be acceptable in accordance with 3500 of Section XI of the ASME Code. The CPSES, Unit 2 RPV has no recordable indications found in the latest RPV inspection.
The calculation of the 95 th percentile through-wall cracking frequency (TWCF95-TOTAL) due to all relevant beltline materials was performed for each CPSES RPV, as documented in Table 3 of each request for alternative in licensee's letter dated September 14, 2009. The licensee's submittal used the methodology of RG 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," (ADAMS Accession No. ML003740284) to calculate The NRC staff verified these values and found the TWCF95-TOTAL of 7.51 E-15 for CPSES, Unit 1 and 2.73E-16 for CPSES, Unit 2 to be several orders of magnitude lower than the corresponding pilot plants' value of 1.76E-08, demonstrating that CPSES, Units 1 and 2 are bounded by the WCAP-A by a significant margin. It should be noted, however, that the licensee's RT MAX-AW and RT MAX-CW values 2 would create negative arguments for the logarithmic function in the TWCF 95-AX equation for the axial weld and the TWCF 95-CW equation for the circumferential weld. Physically, it means that if the three pilot plants' welds had the CPSES RPVs' RT MAX-AW and RT MAX-CW values, no through-wall cracking would occur in the welds. NUREG-1874 recommends use of zero for the TWCF for such a case. The licensee's approach is conservative and acceptable because its TWCF 95-AX and TWCF 95-CW values are greater than zero. 2 AW and CW stands for axial and circumferential welds
-6 Also, due to the significant margin between the CPSES Units' TWCF95-TOTAL values and the pilot plants, the NRC staff did not seek (1) resolution of the small discrepancies between the chemistry factors reported in Table 3 and those in the NRC's Reactor Vessel Integrity Database for the CPSES units, and (2) confirmation or clarification of the 60 effective full power year (EFPY) fluence used in the licensee's calculations (about 10 percent lower than the NRC staff's estimate based on a direct extrapolation from the current pressure-temperature limits for 36 EFPY). At the time of issuance of the SER for WCAP-A, it was the NRC's intent to establish a process by which licensees could receive approval to implement 20-year lSI intervals for the subject component examinations through the end of their facility's current operating license. This objective led to the provision established in the SER that licensees submit a license condition which would require the licensee to evaluate future volumetric lSI data in accordance with the criteria in the draft and/or final alternative PTS Rule, 10 CFR 50.61 a. However, since that time, further guidance from the NRC's Office of General Counsel has resulted in a modification of this NRC position.
Based on the current guidance, the NRC staff will grant lSI interval extensions for the subject components on an interval-by-interval basis (i.e., only a facility's current lSI interval will be extended for up to 20 years). Licensees will have to submit subsequent requested alternatives, for NRC review and approval, to extend each following lSI interval from 10 years to 20 years, as needed. The requirement in the NRC staff's SER, for a license condition to address the evaluation of future lSI data, is no longer necessary.
In its revised September 14, 2009, submittal, the licensee made two changes. The licensee limited the duration of the proposed alternative for CPSES, Units 1 and 2 to the second RPV lSI interval and withdrew its amendment request for adding the license condition discussed above. Subsequent alternative requests, which seek to extend additional lSI intervals from 10 to 20 years for the subject component examinations, should include the evaluation of a facility's most recent lSI data in accordance with the criteria in the final alternative PTS Rule, 10 CFR 50.61 a, in order to obtain NRC staff approval.
For technical and regulatory consistency, the SER will be revised to reflect these changes in NRC position regarding the implementation of lSI interval extensions.
The NRC staff also reviewed the licensee's proposed schedule as it applies to the second lSI interval at CPSES, Units 1 and 2. The NRC staff concludes that the proposal to perform the SUbject examinations in 2019 for CPSES, Unit 1 are consistent with the information provided in the PWROG letter, OG-06-356 and, therefore, are acceptable.
For CPSES, Unit 2, the licensee, in its letter dated September 14, 2009, revised its proposed date of inspection to 2021 to improve the distribution of plants performing RPV inspections per year. The NRC staff examined the overall PWROG plant examination schedules in the PWROG letter, OG-06-356, and found that there is one plant scheduled to perform RPV examinations in 2021, while there are five plants scheduled to perform RPV examinations in 2012. Therefore, performance of the CPSES, Unit 2 RPV examinations in 2021 enhances yearly distribution of PWROG RPV lSI schedule and is, therefore, acceptable.
In summary, the licensee has demonstrated in the submittal that the RPV components identified under RRs B-9 and B-8 for CPSES, Units 1 and 2 are bounded by the WCAP-A. The submittal demonstrates that the risk associated with extending the current lSI interval for Category B-A and Category B-D components from 10 years to 20 years is acceptably small.
-7
4.0 CONCLUSION
The NRC staff has completed its review of the submittals for RRs B-9 and B-8 for CPSES, Units 1 and 2 and concludes that extending the current lSI interval for the identified Category B-A and Category B-D components from 10 years to 20 years results in a small and acceptable risk increase.
This conclusion is based on the fact that the plant-specific information provided by the licensee is bounded by the data in the NRC-approved topical report 16168-NP, Revision 2, and the request meets all the conditions and limitations described in the approved topical report and the associated safety evaluation report. Therefore, RRs B-9 and 8 provide an acceptable level of quality and safety, and the alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(i) to extend the licensee's current second lSI interval to approximately 2020 for CPSES, Unit 1 and 2023 for CPSES, Unit 2, with the licensee performing the subject examinations in 2019 for CPSES, Unit 1 and 2021 for CPSES, Unit 2. All other ASME Code,Section XI requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor:
S. Sheng Date: December 22, 2009 R. Flores -2 All other ASME Code,Section XI requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
The NRC safety evaluation is enclosed.
If you have any questions, please contact Balwant K. Singal at 301-415-3016 or bye-mail at Balwant.Singal@nrc.gov.
Sincerely, IRN Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrPMComanchePeak Resource LPLIV Reading Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsNrrDciCvib Resource RidsRgn4MailCenter Resource RidsNrrDorlDpr Resource SSheng, NRRIDCI/CVIB RidsNrrDorlLpl4 Resource L Trocine, EDO RIV ADAMS Accession No: ML092870637 OFFICE NRRlLPL4/PM NRR/LPL4/LA DCI/CVIB/BC DRAlAPLAlBC NRR/LPL4/BC NRR/LPL4/PM NAME BSingal JBurkhardt MMitchell DHarrison MMarkley BSingal DATE 12/3/09 11/10109 12/3/09 12/22/09 12/22/09 12/22/09 OFFICIAL AGENCY