Letter Sequence Response to RAI |
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MONTHYEARML12264A5312012-09-20020 September 2012 Acceptance Review E-mail, Relief Request No. E-1 Containment Electrical Penetrations, for the Second 10-Year Inservice Inspection Interval Project stage: Acceptance Review ML12296A2702012-10-22022 October 2012 Request for Additional Information Email, Relief Request No. E-1 Containment Electrical Penetrations, for the Second 10-Year Inservice Inspection Interval Project stage: RAI ML12272A2892012-11-0505 November 2012 G20120727/LTR-12-0541 - Ltr to Christine Kehoe from Chairman Macfarlane Follow-up to NRC 4/9/12 Letter to Senator Christine Kehoe San Onofre Generating Nuclear Station Issues Project stage: Other 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 Project stage: Response to RAI ML13158A0932013-06-26026 June 2013 Relief Request No. E-1 Containment Electrical Penetrations, for the Second 10-Year Inservice Inspection Interval Project stage: Acceptance Review 2012-11-05
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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 type:CP
MONTHYEARCP-202400030, License Renewal Application Revision 0 - Supplement 3, Revision 12024-01-31031 January 2024 License Renewal Application Revision 0 - Supplement 3, Revision 1 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) 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 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 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-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 CP-202300442, (CPNPP) - Request to Use Later Code Edition for Inservice Inspection (ISI) Program2023-09-15015 September 2023 (CPNPP) - Request to Use Later Code Edition for Inservice Inspection (ISI) Program CP-202300391, (CPNPP) - Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2023-08-24024 August 2023 (CPNPP) - Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule CP-202300411, (Cpnpp), Inservice Inspection (ISI) Owner'S Activity Reports (OAR-1 Forms) for Unit 2 Refueling Outage 20 (2RF20)2023-08-17017 August 2023 (Cpnpp), Inservice Inspection (ISI) Owner'S Activity Reports (OAR-1 Forms) for Unit 2 Refueling Outage 20 (2RF20) CP-202300361, (CPNPP) - Unit 2 Refueling Outage 20 (2RF20) Steam Generator 180 Day Report2023-08-17017 August 2023 (CPNPP) - Unit 2 Refueling Outage 20 (2RF20) Steam Generator 180 Day Report 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 CP-202300358, (Cpnpp), Transmittal of Electronic Licensing Basis Documents Including Certified FSAR Amendment 1122023-08-0101 August 2023 (Cpnpp), Transmittal of Electronic Licensing Basis Documents Including Certified FSAR Amendment 112 CP-202300322, Response to Requests for Additional Information Regarding Review of the License Renewal Application Sets 2 and 32023-07-27027 July 2023 Response to Requests for Additional Information Regarding Review of the License Renewal Application Sets 2 and 3 CP-202300348, (Cpnpp), Transmittal of Revised Emergency Plan (Revision 48)2023-07-18018 July 2023 (Cpnpp), Transmittal of Revised Emergency Plan (Revision 48) 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-202300262, Response to Request for Confirmation of Information Regarding Review of the License Renewal Application - Set 22023-06-20020 June 2023 Response to Request for Confirmation of Information Regarding Review of the License Renewal Application - Set 2 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-202300248, Response to Request for Additional Information Regarding License Renewal Application - Set 12023-06-13013 June 2023 Response to Request for Additional Information Regarding License Renewal Application - Set 1 CP-202300209, Response to Request for Additional Information - License Renewal Application Environmental Review2023-06-0606 June 2023 Response to Request for Additional Information - License Renewal Application Environmental Review CP-202300207, Revision to Comanche Peak Nuclear Power Plant'S Response to Notice of Violation (NOV) 05000445/2021011-052023-05-25025 May 2023 Revision to Comanche Peak Nuclear Power Plant'S Response to Notice of Violation (NOV) 05000445/2021011-05 CP-202300182, Response to Requests for Confirmation of Information Regarding the Environmental Review of the License Renewal Application2023-05-0808 May 2023 Response to Requests for Confirmation of Information Regarding the Environmental Review of the License Renewal Application CP-202300201, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 0)2023-05-0404 May 2023 (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 0) CP-202300160, (Cpnpp), 2022 Annual Radiological Environmental Operating Report2023-04-27027 April 2023 (Cpnpp), 2022 Annual Radiological Environmental Operating Report CP-202300159, (Cpnpp), 2022 Annual Radiological Effluent Release Report2023-04-27027 April 2023 (Cpnpp), 2022 Annual Radiological Effluent Release Report CP-202300165, License Renewal Application Revision 0 - Supplement 22023-04-24024 April 2023 License Renewal Application Revision 0 - Supplement 2 CP-202300175, Submittal of 2022 Annual Environmental Operating Report (Non-Radiological)2023-04-20020 April 2023 Submittal of 2022 Annual Environmental Operating Report (Non-Radiological) CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments CP-202300096, License Amendment Request (LAR) 23-002 Application Regarding GDC-5 Shared Systems Requirements2023-04-20020 April 2023 License Amendment Request (LAR) 23-002 Application Regarding GDC-5 Shared Systems Requirements CP-202300140, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors. LAR 23-0012023-04-19019 April 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors. LAR 23-001 CP-202300157, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-14014 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments CP-202300135, License Renewal Application Revision 0 - Supplement 12023-04-0606 April 2023 License Renewal Application Revision 0 - Supplement 1 CP-202300144, (CPNPP) - Decommissioning Report2023-03-30030 March 2023 (CPNPP) - Decommissioning Report CP-202300139, (CPNPP) - Property Damage Insurance2023-03-30030 March 2023 (CPNPP) - Property Damage Insurance CP-202300098, (Cpnpp), Annual Report of Changes in Peak Cladding Temperature2023-03-16016 March 2023 (Cpnpp), Annual Report of Changes in Peak Cladding Temperature CP-202200481, Response to Request for Additional Information - Relief Request Application P-1, Inservice Testing (IST)2022-12-0707 December 2022 Response to Request for Additional Information - Relief Request Application P-1, Inservice Testing (IST) CP-202200454, (Cpnpp), Reply to a Notice of Violation Transmitted Via NRC Letter from Gregory Werner to Ken Peters Dated 11/01/2022, Comanche Peak Nuclear Power Plant, Units 1 and 2 Integrated Inspection Report 05000445/2022003 .2022-12-0101 December 2022 (Cpnpp), Reply to a Notice of Violation Transmitted Via NRC Letter from Gregory Werner to Ken Peters Dated 11/01/2022, Comanche Peak Nuclear Power Plant, Units 1 and 2 Integrated Inspection Report 05000445/2022003 . CP-202200355, Application to Revise Technical Specifications to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model LAR 22-0022022-11-21021 November 2022 Application to Revise Technical Specifications to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model LAR 22-002 CP-202200380, (CPNPP) - Non-Voluntary License Amendment Request to Revise Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications2022-11-21021 November 2022 (CPNPP) - Non-Voluntary License Amendment Request to Revise Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications CP-202200450, (CPNPP) - Registration of Dry Spent Fuel Storage Canisters2022-11-16016 November 2022 (CPNPP) - Registration of Dry Spent Fuel Storage Canisters CP-202200435, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2022-11-0808 November 2022 (Cpnpp), Registration of Dry Spent Fuel Storage Canisters 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-202200357, (CPNPP) Unit 2 - Response to Request for Additional Information, Fall 2021 (2RF19) Steam Generator Tube Inspection Report2022-09-14014 September 2022 (CPNPP) Unit 2 - Response to Request for Additional Information, Fall 2021 (2RF19) Steam Generator Tube Inspection Report CP-202200358, (CPNPP) - Transmittal of Revised Emergency Plan (Revision 46)2022-09-14014 September 2022 (CPNPP) - Transmittal of Revised Emergency Plan (Revision 46) CP-202200246, Evacuation Time Estimate Analysis2022-08-25025 August 2022 Evacuation Time Estimate Analysis CP-202200306, (CPNPP) - Inservice Inspection (ISI) Owner'S Activity Reports (OAR-1 Forms) for Unit 1 Refueling Outage 22 (1RF22)2022-08-11011 August 2022 (CPNPP) - Inservice Inspection (ISI) Owner'S Activity Reports (OAR-1 Forms) for Unit 1 Refueling Outage 22 (1RF22) 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-202200276, (CPNPP) - Relief Request Application P-1, Inservice Testing (IST)2022-07-20020 July 2022 (CPNPP) - Relief Request Application P-1, Inservice Testing (IST) 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 2024-01-31
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Rafael Flores Luminant Power Senior Vice President P 0 Box 1002
&Chief Nuclear Officer 6322 North FM 56 Rafael.Flores@Luminant.com Glen Rose, TX 76043 Luminant T 254 897 5550 C 817 559 0403 F 254 897 6652 CP-201201384 Ref. # 10CFR50.55a Log # TXX-12162 November 14, 2012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NO. 50-445 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST NO. E-1 (TAC NOS. ME9261 AND ME9262)
REFERENCES:
- 1. Letter logged TXX-12118 dated August 16, 2012 from Rafael Flores to the NRC submitting Relief Request No. E-1 for Containment Electrical Penetrations (Second IWE Interval End Date: September 9, 2011).
- 2. Email dated October 22, 2012 from Balwant Singal of the NRC to Timothy Hope of Luminant Power requesting additional information regarding Relief Request No. E-1 (TAC Nos. ME9261 and ME9262).
Dear Sir or Madam:
Per reference 1, Luminant Generation Company LLC (Luminant Power) previously submitted a request for relief for containment electrical penetrations. Per reference 2, the NRC provided a request for additional information regarding the subject relief request.
Luminant Power has provided the information requested per reference 2 in the Attachments 1 and 2 to this letter.
This communication contains no new commitment regarding Comanche Peak Units 1 and 2.
Should you have any questions, please contact Mr. Jack Hicks at (254) 897-6725.
I A member of the STARS Alliance ý F Callaway
U. S. Nuclear Regulatory Commission TXX-12162 Page 2 of 2 Sincerely, Luminant Generation Company LLC Rafael Flores By: <2. ,*,
Fred W. Madden Director, Oversight & Regulatory Affairs Attachment I Response to Request for Additional Information for Relief Request E-1 Local Leak Rate (Type B) Results c- E. E. Collins, Region IV Luis Ponce B. K. Singal, NRR Texas Department of Licensing and Regulation Resident Inspectors, Comanche Peak P. 0. Box 12157 Jack Ballard, ANII, Comanche Peak Austin, Texas 78711-2332 to TXX-12162 Page 1 of 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST NUMBER E-1 FOR THE UNITS 1 AND 2 SECOND 10 YEAR IWE INTERVAL (SECOND INTERVAL END DATE: SEPTEMBER 9,2011) (TAC NOS. ME9261 AND ME9262)
The following questions were provided to Luminant Power in the email dated October 22, 2012, from Balwant Singal of the NRC to Timothy Hope of Luminant Power (reference 2) requesting additional information regarding Relief Request No. E-1:
NRC Question 1:
Section 4 of your application for RR E-1 stated that the surfaces of 20 electrical penetrations are covered with radiant energy shielding material. Section 6 of your application stated that the carbon steel containment liner, mechanical penetrations and the remaining stainless steel electrical penetrations (66 in CPNPP, Unit 1 and 64 in CPNPP, Unit 2) have all been examined each period during the second interval without any degradation or corrosion identified.
Please provide clarification that RR E-1 pertains to the visual examination of electrical penetration stainless steel assemblies and confirm that the containment liner in the local area of those electrical penetrations included in RR E-1 (total of 20 penetrations, 9 in CPNPP, Unit 1 and 11 in CPNPP, Unit 2) have been examined and no degradation or corrosion have been identified.
Luminant Power's Response to Question 1:
Relief Request E-1 pertains to the visual examination of 20 stainless steel electrical penetration assemblies covered with radiant energy shielding material that were not visually examined each period (3) during the second interval. The local areas of the containment liner around the 20 unexamined electrical penetrations were visually examined each period during the second interval, with no degradation or corrosion identified to the liner.
NRC Question 2:
Please provide the results of Title 10 of the Code of FederalRegulations (10 CFR), Part 50, Appendix J containment integrated leak rate test (Type A) and their comparison with the allowable leakage rate specified in the plant Technical Specifications (TSs).
Luminant Power's Response to Question 2:
Reference T.S. 5.5.16.c & 5.5.16.d.1 & T.S. Bases 3.6.1:
Allowable leakage rate (La) of 0.1% of containment air weight per day.
The As-found Type A test surveillance acceptance criteria is leakage rate less than or equal to 1.0 La. In addition the As-left Type A test surveillance acceptance criteria is leakage rate less than or equal to 0.75 La prior to entering the mode in which containment operability is required (Mode 4).
Unit 1Type A test results performed in April 2007:
" The As-found leakage rate was 0.063019% weight per day which met the As-found surveillance criteria of 0.1% weight per day.
- The As-left leakage rate was 0.0630% weight per day which met the As-left surveillance criteria of 0.075% weight per day.
to TXX-12162 Page 2 of 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST NUMBER E-1 FOR THE UNITS 1 AND 2 SECOND 10 YEAR IWE INTERVAL (SECOND INTERVAL END DATE: SEPTEMBER 9,2011) (TAC NOS. ME9261 AND ME9262)
Unit 2 Type A test results performed in October 2012:
- The As-found leakage rate was 0.0595% weight per day which met the As-found surveillance criteria of 0.1% weight per day.
" The As-left leakage rate was 0.0594% weight per day which met the As-left surveillance criteria of 0.075% weight per day.
NRC Question 3:
Please provide the results of Type B leakage test of those electrical penetrations included in RR E-1 (total of 20 penetrations, 9 in CPNPP, Unit 1 and 11 in CPNPP, Unit 2) and discuss the acceptability of leakage test results and the performance history of Type B leakage testing of these electrical penetrations.
Luminant Power's Response to Question 3:
The electrical penetrations are tested in groupings by elevation. The electrical penetrations in question are part of the overall groupings categorized as follows:
Unit 1:
" 852-ELEC-PEN includes E-0006, E-0009, E-0016, & E-0018
- 832-ELEC-PEN includes E-0029, E-0039, & E-0040
- 810-ELEC-PEN includes E-0056 & E-0060 Unit 2:
- 2-852-ELEC-PEN includes 2-E-0006, 2-E-0009, 2-E-0015, 2-E-0016, & 2-E-0018
- 2-832-ELEC-PEN includes 2-E-0039, 2-E-0040, & 2-E-0045
" 2-810-ELEC-PEN includes 2-E-0056, 2-E-0060, & 2-E-0066 See Attachment 2 for the Local Leak Rate (Type B) Results for each grouping. There have been no previous failures for these penetrations for Unit 1 or Unit 2. The results listed in Attachment 2 are in standard cubic centimeters per minute (sccm). The administrative limit for each test is 100 sccm.
However, the Unit 1 tests performed in 1991 had an administrative limit of 25 sccm. The two tests that exceeded 25 sccm had a technical evaluation performed which documented the acceptability of the test results via Technical Evaluation (TE) 91-2683.
ATTACHMENT 2 to TXX-12162 Local Leak Rate (Type B) Results
NMMLR07 TU ELECTRIC Page: 1 of CPSES LOCAL LEAK RATE TEST Date : 11/06/2012 Past Performance History Report Time: 13:32:19 Unit/ Pene. No : 852-ELEC-PEN SystemlService: ELEC. PEN ASSY Procedure : OPT-860A/ RT 504952 Current Interval : 3660 sf j Test Type C
ý,; U rM3 ,9; ý0*'( Passed
- 1,.0
- .*:,,*'*:,:Pene. Status P Left:. :;*91.=,3j, (Ab .;, Next Test Due : 10/29/2015 Valve/Boundary : 852-ELEC-TC Inside/Oustide *Outside Concurrently Tested Valve(s)/Boundary(s) Admin. Limit , 100 No Related Tag(s)
Test Leak Work Order As Left Test Date Rate Number Entered? Status AS FOUND 10/21/2005 91.30 5-05-504952-AA Passed AS LEFT 10/21/2005 91.30 5-05-504952-AA Yes Passed AS FOUND 10/01/2002 2.00 5-02-504952-AA Passed AS LEFT 10/01/2002 2.00 5-02-504952-AA Yes Passed AS FOUND 03/04/1995 17.00 5-94-501651-AA Passed AS LEFT 03/04/1995 17.00 5-94-501651-AA Yes Passed AS FOUND 04/14/1993 20.00 5-92-501651-AA Passed AS LEFT 04/14/1993 20.00 5-92-501651-AA Yes Passed AS FOUND 09/12/1991 68.00 S-91-00008 -25 Passed AF Comments: SEE TE 91-2683 AS LEFT 09/12/1991 68.00 S-91-00008 -25 Yes Passed
- ENVD OF HISTORY REPORT FOR : 852-ELEC-PEN
NMMLR07 TU ELECTRIC Page: 1 of I CPSES LOCAL LEAK RATE TEST Date : 11/06/2012 Past Performance History Report Time 13:34:16 Unit/Pene. No : 832-ELEC-PEN SystemlService: ELEC.PEN Procedure
- OPT-859A / RT 504951 Current Interval 3660
_ .0 Test Type C A'"u6nd(iF -
- 2'V-*!.!*:*,* Pene. Status P AsLeft,' 1012912015JA~i
- i Next Test Due : 10/25/2015 Valve/Boundary :832-ELEC-TC Inside/Oustide Outside Concurrently Tested Valve(s)/Boundary(s) Admin. Limit : 100 No Related Tag(s)
Test Leak Work Order As Left Test Date Rate Number Entered? Status AS FOUND 10/21/2005 20.00 5-05-504951-AA Passed AS LEFT 10/21/2005 20.00 5-05-504951-AA Yes Passed AS FOUND 02/22/2005 58.50 5-99-504951-AA Passed AS LEFT 02/22/2005 58.50 5-99-504951-AA Yes Passed, AS FOUND 03/04/1995 20.00 5-94-501376-AA Passed AS LEFT 03/04/1995 20.00 5-94-501376-AA Yes Passed AS FOUND 04/15/1993 20.00 5-92-501376-AA Passed AS LEFT 04/15/1993 20.00 5-92-501376-AA Yes Passed AS FOUND 09/13/1991 3.50 S-91-00008 -24 Passed AS LEFT 09/13/1991 3.50 S-91-00008 -24 Yes Passed
- END OF HISTORY REPORT FOR : 832-ELEC-PEN
NMMLR07 TU ELECTRIC Page: of I CPSES LOCAL LEAK RATE TEST Date 11106/2012 Past Performance History Report Time: 13:35:32 Unit/Pene. No 810-ELEC-PEN SystemlService: ELEC. PENS.
Procedure OPT-858A / RT 504950 Current Interval : 3660
-h,1jU,*I Test Type As ,.., =.5 . .40 :*"Pene.
7r3 Status :
Passed j*s: * .* . . Next Test Due .10/292015 Valve/Boundary : 810-ELEC-TC Inside /Oustide : Outside Concurrently Tested Valve(s)/Boundary(s) Admin. Limit : 100 No Related Tag(s)
Test Leak Work Order As Left Test Date Rate Number Entered? Status AS FOUND 10/21/2005 31.00 5-05-504950-AA Passed AS LEFT 10/21/2005 31.00 5-05-504950-AA Yes Passed AS FOUND 03/01/2005 4.00 5-99-504950-AA Passed AS LEFT 03/01/2005 4.00 5-99-504950-AA Yes Passed AS FOUND 03/04/1995 20.00 5-94-500217-AA Passed AS LEFT 03/04/1995 20.00 5-94-500217-AA Yes Passed AS FOUND 04/15/1993 20.00 5-92-500217-AA Passed AS LEFT 04/15/1993 20.00 5-92-500217-AA Yes Passed AS FOUND 09/12/1991 49.00 S-91-000082-3 Passed AF Comments:SEE TE 91-2683 AS LEFT 09/12/1991 49.00 S-91-000082-3 Yes Passed
- END OF HISTORY REPORT FOR : 810-BLEC-PEN
NMMLR07 TU ELECTRIC Page: 1 of 1 CPSES LOCAL LEAK RATE TEST Date : 11/06/2012 Past Performance History Report Time: 13:20:53 Unit/ Pene. No : 2-852-ELEC-PEN SystemlService : ELEC PEN Procedure OPT-860B / RT 504708 CurrentInterval : 1830 Test Type . C ArSA5,ý7'i Mi i ,P :* As Eound'*:**:F ) Pene. Status P a ss e d a';*;*!* ;*7 00"
(*i Next Test Due : 09/25/2017 Valve/Boundary 2-852-ELEC-TC Inside /Oustide
- Outside Concurrently Tested Valve(s)/Boundary(s) Admin. Limit : 100 No Related Tag(s)
Test Leak Work Order As Left Test Date Rate Number Entered? Status AS FOUND 09/21/2012 71.00 -- 444939-1 Passed AS LEFT 09/21/2012 71.00 -- 444939-1 Yes Passed AS FOUND 07/30/2009 20.00 -- 350413-7 Passed AS LEFT 07/30/2009 20.00 -- 350413-7 Yes Passed AS FOUND 04/21/2005 78.00 5-05-504708-AA Passed AS LEFT 04/21/2005 78.00 5-05-504708-AA Yes Passed AS FOUND 04/02/2002 20.00 5-02-504708-AA Passed AS LEFT 04/02/2002 20.00 5-02-504708-AA Yes Passed AS FOUND 01/02/2001 20.30 5-99-504708-AA Passed AS LEFT 01/02/2001 20.30 5-99-504708-AA Yes Passed AS FOUND 02/25/1996 11.76 5-95-501368-AA Passed AS LEFT 02/25/1996 11.76 5-95-501368-AA Yes Passed AS FOUND 10/09/1994 7.80 5-94-501368-AA Passed AS LEFT 10/09/1994 7.80 5-94-501368-AA Yes Passed
- END OF HISTORY REPORT FOR : 2-852-BLEC-PEN
NMMLF.07 TU ELECTRIC Page: 1 of 1 CPSES LOCAL LEAK RATE TEST Date 11/06/2012 Past Performance History Report Time: 13:25:06 Unit/Pene.No : 2-832-ELEC-PEN System/Service : ELEC PEN Procedure : OPT-859B CurrentInterval : 1830
-hf Rath,, 7 aMixiffi t Test Type :C
" 3. 0 Pene. Status : Passed
-i l*e*f' 'AI~. '*$*Next Test Due : 09/25/2 017 Valve/Boundary : 2-832-ELEC-TC Inside /Oustide
- Outside Concurrently Tested Valve(s)/Boundary(s) Admin. Limit 100 No Related Tag(s)
Test Leak Work Order As Left Test Date Rate Number Entered? Status AS FOUND 09/21/2012 53.00 -- 442849-1 Passed AS LEFT 09/21/2012 53.00 -- 442849-1 Yes Passed AS FOUND 06/27/2009 96.00 -- 350324-2 Passed AS LEFT 06/27/2009 96.00 -- 350324-2 Yes Passed AS FOUND 04/20/2005 84.00 5-03-504698-AA Passed AS LEFT 04/20/2005 84.00 5-03-504698-AA Yes Passed AS FOUND 12/01/2000 50.00 5-99-504698-AA Passed AS LEFT 12/01/2000 50.00 5-99-504698-AA Yes Passed AS FOUND 02/24/1996 19.40 5-95-502014-AA Passed AS LEFT 02/24/1996 19.40 5-95-502014-AA Yes Passed AS FOUND 10/08/1994 14.00 5-94-502014-AA Passed AS LEFT 10/08/1994 14.00 5-94-502014-AA Yes Passed
- END OF HISTORY REPORT FOR : 2-832-BLEC-PEN
NMMLR07 TU ELECTRIC Page: I of 1 CPSES LOCAL LEAK RATE TEST Date 11106/2012 Past Performance History Report Time: 13"27:01 Unit/ Pene. No : 2-810-ELEC-PEN System/Service : ELEC PEN OPT-858B/ RT 504697 Procedure Current Interval : 1830
- C Test Type Pene. Status : Passed Next Test Due :09/30/2017 Valve/Boundary : 2-810-ELEC-TC Inside / Oustide
- Outside Concurrently Tested Valve(s)/Boundary(s) Admin. Limit : 100 No Related Tag(s)
Test Leak Work Order As Left Test Date Rate Number Entered? Status AS FOUND 09/26/2012 55.50 -- 443028-4 Passed AS LEFT 09/26/2012 55.50 -- 443028-4 Yes Passed AS FOUND 06/30/2009 74.50 -- 350321-4 Passed AS LEFT 06/30/2009 74.50 -- 350321-4 Yes Passed AS FOUND 04/20/2005 77.40 5-03-504697-AA Passed AS LEFT 04/20/2005 77.40 5-03-504697-AA Yes Passed AS FOUND 12/16/2000 85.00 5-99-504697-AA Passed AS LEFT 12/16/2000 85.00 5-99-504697-AA Yes Passed AS FOUND 02/25/1996 15.62 5-95-500059-AA Passed AS LEFT 02/25/1996 15.62 5-95-500059-AA Yes Passed AS FOUND 10/09/1994 23.40 5-94-500059-AA Passed AS LEFT 10/09/1994 23.40 5-94-500059-AA Yes Passed
- END OF HISTORY REPORT FOR : 2-810-ELEC-PEN