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MONTHYEARCP-201401035, Relief Requests Nos. B-7, B-12 and B-13 for the Second 10-Year ISI Interval (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End Date: August 2, 2014)2014-08-27027 August 2014 Relief Requests Nos. B-7, B-12 and B-13 for the Second 10-Year ISI Interval (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End Date: August 2, 2014) Project stage: Request ML14266A2052014-09-23023 September 2014 NRR E-mail Capture - Acceptance Review - Request Requests B-7, B-12, and B-13, Comanche Peak Nuclear Power Plant, Unit 2 Project stage: Acceptance Review ML14350B3702014-12-16016 December 2014 NRR E-mail Capture - Request for Additional Information - Relief Requests (Rrs) B-7, B-12, and B-13 Project stage: RAI CP-201500032, Response to Request for Additional Information for Relief Requests B-7, B-12, and B-132015-01-0808 January 2015 Response to Request for Additional Information for Relief Requests B-7, B-12, and B-13 Project stage: Response to RAI 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 Project stage: Other 2014-09-23
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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-202400294, (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule ML24177A2692024-08-0707 August 2024 Issuance of Amendment Nos. 188 and 188, Respectively, Revision to Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program CP-202400315, (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-0505 August 2024 (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality IR 05000445/20240022024-07-31031 July 2024 Units 1 and 2 - Integrated Inspection Report 05000445/2024002 and 05000446/2024002,and Independent Spent Fuel Storage Installation Inspection Report 07200074/2024001 IR 05000445/20244032024-07-16016 July 2024 Security Baseline Inspection Report 05000445/2024403 and 05000446/2024403 (Full Report) ML24187A0372024-07-15015 July 2024 Withdrawal of Requested Licensing Action Exemption from Select Requirements of 10 CFR Part 55, Operators Licenses ML24192A1862024-07-10010 July 2024 Notification of Inspection (NRC Inspection Report 05000445/2024003 and 05000446/2024003) and Request for Information ML24185A1382024-07-0202 July 2024 Inservice Inspection Request for Information IR 05000445/20244012024-06-26026 June 2024 MC&A Program Inspection Report 05000445-2024401 and 05000446-2024401 Public-Final CP-202400253, (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 52024-06-26026 June 2024 (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 5 CP-202400235, (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 02024-06-18018 June 2024 (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 0 IR 05000445/20240122024-06-17017 June 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000445/2024012 and 05000446/2024012 ML24120A3632024-06-10010 June 2024 Issuance of Amendment Nos. 187 and 187, Respectively Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants CP-202400205, (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval2024-05-30030 May 2024 (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval CP-202400175, (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-05-16016 May 2024 (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator ML24120A2912024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cooper, D, Apache Tribe of Oklahoma ML24120A2972024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martin, R, Tonkawa Tribe of Oklahoma ML24120A3072024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yargee, W, Alabama-Quassarte Tribal Town ML24120A2962024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Kaskaske, D, Kickapoo Tribe of Oklahoma ML24120A3022024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Pierite, M, Tunica-Biloxi Tribe of Louisiana ML24120A2932024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Garza, Jr, Juan, Kickapoo Traditional Tribe of Texas ML24120A3052024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Woommavovah, M, Comanche Nation ML24107B1012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cernek, J, Coushatta Tribe of Louisiana ML24120A3042024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Sylestine, R, Alabama-Coushatta Tribe of Texas ML24120A2942024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Gonzalez, B, Caddo Nation ML24120A2922024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Dotson, Delaware Nation ML24120A2982024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martinez, E, Mescalero Apache Tribe ML24120A2952024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Johnson, L.J., Seminole Nation of Oklahoma CP-202400153, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2024-04-29029 April 2024 (Cpnpp), Registration of Dry Spent Fuel Storage Canisters ML24120A2902024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Bunch, J, United Keetoowah Band of Cherokee Indians ML24120A3002024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Morrow, R K, Thlopthlocco Tribal Town ML24120A3062024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yahola, s, Kialegee Tribal Town ML24120A3012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Parton, T, Wichita and Affiliated Tribes ML24120A3032024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-SpottedBird, L, Kiowa Indian Tribe ML24107B0292024-04-26026 April 2024 Lr Feis Section 106 Consultation Letters Shpo ML24080A1802024-04-26026 April 2024 Ltr to Ken J. Peters, Sr VP and Chief Nuclear Officer, CPNPP re-NOA Final Plant Specific Supplement 60 IR 05000445/20240012024-04-26026 April 2024 Integrated Inspection Report 05000445/2024001 and 05000446/2024001 ML24108A1542024-04-26026 April 2024 Lr Feis Section 106 Consultation Letters Achp CP-202400107, (CPNPP) - 2023 Annual Radiological Environmental Operating Report2024-04-18018 April 2024 (CPNPP) - 2023 Annual Radiological Environmental Operating Report IR 05000445/20244022024-04-17017 April 2024 Security Baseline Inspection Report 05000445/2024402 and 05000446/2024402 (Full Report) ML24085A2252024-04-11011 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0037 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) CP-202400099, (CPNPP) - Registration of Dry Spent Fuel Storage Canisters2024-04-0909 April 2024 (CPNPP) - Registration of Dry Spent Fuel Storage Canisters CP-202400092, (CPNPP) - Supplement to Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-04-0101 April 2024 (CPNPP) - Supplement to Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program CP-202400089, Property Damage Insurance2024-03-25025 March 2024 Property Damage Insurance CP-202400087, (CPNPP) - Notification of Deviation from Electric Power Research Institute (EPRI) MRP 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-Isolatable2024-03-21021 March 2024 (CPNPP) - Notification of Deviation from Electric Power Research Institute (EPRI) MRP 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-Isolatable ML24068A0762024-03-18018 March 2024 Final Transmittal Letter for Comanche Peak SE for LRA Review CP-202400085, (CPNPP) - Revised Requested Compliance Date - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-0707 March 2024 (CPNPP) - Revised Requested Compliance Date - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CP-202400073, (CPNPP) - Response to RAI for License Amendment Request to Extend Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-03-0404 March 2024 (CPNPP) - Response to RAI for License Amendment Request to Extend Allowed Outage Time for an Inoperable Emergency Diesel Generator CP-202400072, (Cpnpp), Unit 1, Special Report 1-SR-24-001-00, Inoperable Post Accident Monitoring Instrumentation2024-02-29029 February 2024 (Cpnpp), Unit 1, Special Report 1-SR-24-001-00, Inoperable Post Accident Monitoring Instrumentation IR 05000445/20230062024-02-28028 February 2024 Annual Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 Reports 05000445/2023006 and 05000446/2023006 2024-08-07
[Table view] Category:Safety Evaluation
MONTHYEARML24177A2692024-08-0707 August 2024 Issuance of Amendment Nos. 188 and 188, Respectively, Revision to Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program ML24120A3632024-06-10010 June 2024 Issuance of Amendment Nos. 187 and 187, Respectively Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24023A2962024-02-0909 February 2024 Issuance of Amendment Nos. 186 and 186 Regarding General Design Criterion 5 of Appendix a to 10 CFR Part 50 and Regulatory Guide 1.81 ML23319A3872023-12-20020 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 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) ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments 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)) 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)) ML20346A0192021-02-0101 February 2021 Issuance of Amendment Nos. 177 and 177 Regarding Revision to Technical Specifications 3.8.1, AC Sources - Operating 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 ML16096A2642016-05-0606 May 2016 Draft Conforming Amendments, Application for Order Approving Direct and Indirect Transfer of Licenses and Conforming License Amendments 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 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 2024-08-07
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Rafael Flores Senior Vice President and Chief Nuclear Officer Attention:
Regulatory Affairs Luminant Generation Company LLC P.O. Box 1002 Glen Rose, TX 76043 April 3, 2015
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT, UNIT 2 -RELIEF REQUESTS B-7, B-12, AND B-13 FOR STEAM GENERATOR HEAD-TO-TUBESHEET WELDS FOR RELIEF FROM CERTAIN ASME CODE INSPECTION REQUIREMENTS FOR THE SECOND 10-YEAR INSERVICE INSPECTION INTERVAL (TAC NO. MF4752)
Dear Mr. Flores:
By letter dated August 27, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14253A211), as supplemented by letter dated January 8, 2015 (ADAMS Accession No. ML 15022A015), Luminant Generation Company LLC (the licensee) submitted Relief Requests (RRs) B-7, B-12, and B-13 to the U.S. Nuclear Regulatory Commission (NRC) for Comanche Peak Nuclear Power Plant, Unit 2, for the second 10-year inservice inspection interval.
In its submittal, the licensee requested relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI for Steam Generator Head-to-Tubesheet welds. Pursuant to Title 10 of the Code of Federal Regulations (10 CFR), paragraph 50.55a(g)(5)(iii), the licensee requested to use alternatives on the basis that complying with the specified requirement is impractical.
The NRC staff has reviewed the request and concludes, as set forth in the enclosed safety evaluation, that the examinations performed to the extent practical provide reasonable assurance of structural integrity of the subject components and that complying with the specified ASME Code,Section XI, requirements, is impractical.
Therefore, pursuant to 1 O CFR 50.55a(g)(6)(i), the NRC staff grants relief for the subject examinations of components described in RRs B-7, B-12, and B-13 for the second 10-year inservice inspection interval, which began on August 3, 2004, and ended on August 2, 2014. All other ASME Code,Section XI, requirements for which relief has not been specifically requested, remain applicable, including a third-party review by the Authorized Nuclear lnservice Inspector.
R. Flores If you have any questions, please contact Balwant K. Singal at 301-415-3016 or via e-mail at Balwant.Singal@nrc.gov.
Docket No. 50-446
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv Sincerely, Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUESTS B-7, B-12, AND B-13 FOR THE SECOND 10-YEAR INSERVICE INSPECTION INTERVAL LUMINANT GENERATION COMPANY LLC COMANCHE PEAK NUCLEAR POWER PLANT. UNIT 2 DOCKET NO. 50-446
1.0 INTRODUCTION
By letter dated August 27, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14253A211), as supplemented by letter dated January 8, 2015 (ADAMS Accession No. ML 15022A015), Luminant Generation Company LLC (the licensee) submitted Relief Requests (RRs) B-7, B-12, and B-13 to the U.S. Nuclear Regulatory Commission (NRC) for Comanche Peak Nuclear Power Plant (CPNPP), Unit 2, for the second 10-year inservice inspection interval.
In its submittal, the licensee requested relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI for Steam Generator (SG) Head-to-Tubesheet welds. Pursuant to Title 10 of the Code of Federal Regulations (10 CFR), paragraph 50.55a(g)(5)(iii), the licensee requested to use alternatives on the basis that complying with the specified requirement is impractical.
2.0 REGULATORY EVALUATION Pursuant to 10 CFR) 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI to the extent practical within the limitations of design, geometry, and materials of construction of the components.
The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code, which was incorporated by reference in 10 CFR 50.55a(b) (retitled paragraph 50.55a(a)(1
)(i) by Federal Register notice dated November 5, 2014 (79 FR 65776), 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The regulations in 10 CFR 50.55a(g)(5)(iii) state, in part, that licensees may determine that conformance with certain code requirements is impractical and that the licensee shall notify the Commission and submit information in support of the determination.
Determination of Enclosure impracticality in accordance with this section must be based on the demonstrated limitations experienced when attempting to comply with the code requirements during the inservice inspection interval for which the request is being submitted.
Requests for relief made in accordance with this section must be submitted to the NRC no later than 12 months after the expiration of the initial 120-month inspection interval or subsequent 120-month inspection interval for which relief is sought. The regulations in 10 CFR 50.55a(g)(6)(i) state that the Commission will evaluate determinations under paragraph (g)(5) of this section that code requirements are impractical.
The Commission may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
The licensee has requested relief from ASME Code requirements pursuant to 10 CFR 50.55a(g)(5)(iii).
The ASME Code of record for second 10-year interval inservice inspection program is the 1998 Edition through the 2000 Addenda. 3.0 TECHNICAL EVALUATION In its letter dated January 8, 2015, the licensee confirmed that no Nickel Alloy weld metals (182 and 82) were used in the ASME Code,Section XI, Category 8-8, Item 82.40 SG Head-to-Tubesheet Welds listed in RRs 8-7, 8-12, and 8-13. The duration of the proposed relief request for CPNPP, Unit 2, is the second 10-year inservice inspection interval which began on August 3, 2004, and ended on August 2, 2014. 3.1 ASME Code Requirement For RRs 8-7. 812. and 8-13 The ASME Code Section XI, Code Class 1, Table IW8-2500-1, Examination Category 8-8, Item 82.40, Figure IW8-2500-6 (Design 8) requires a volumetric examination of essentially 100 percent of the required weld volume extending 1 /2t (where t is the thickness of the base metal) into the base metal on both the head side and tubesheet side of the head-to-tubesheet weld. ASME Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 1," as an alternative approved for use by the NRC in Regulatory Guide (RG) 1.147, Revision 17, "lnservice Inspection Code Case Acceptability,Section XI, Division 1," August 2014 (ADAMS Accession No. ML 13339A689), states that a reduction in examination coverage due to part geometry or interference for any Class 1 and 2 weld is acceptable provided that the reduction is less than 10 percent (i.e., greater than 90 percent examination coverage is obtained).
3.2 Relief Request 8-7 In accordance with 10 CFR 50.55a(g)(5)(iii), the licensee requested relief from the ASME Code-required volumetric examination of SG 2-02 Head-to-Tubesheet Weld TCX-1-3100-2-1 (Component No. TCX-RCPCSG-02). 3.2.1 Licensee's Basis for Relief Request (as stated, in part) The examination of the subject component weld is limited by the presence of four 24" x 24" Steam Generator support pads and seventeen 2.5" x 2.5" welded pads [see weld profile sketch, pages 3 and 4 of Attachment 1 to the letter dated August 27, 2014]. The examinations were conducted in accordance with procedure TX-ISl-210, "Ultrasonic Examination Procedure for Welds in Ferritic Steel Vessels." Straight beam (0°) and angle beam (45° shear and 60° longitudinal) scans were used to achieve the weld volume obtained.
The licensee further stated: The design configuration restrictions of the subject component makes the Code required examination coverage requirements for the weld volume impractical.
Plant modifications or replacements of components designed to allow for complete coverage would be needed to meet the Code requirements.
This would cause considerable burden to CPNPP. 3.2.2 Licensee's Proposed Alternative Examination (as stated) The following alternatives are proposed in lieu of the required examination coverage of essentially 100 percent: 1. Ultrasonic testing (UT) of the subject component weld was performed to the maximum extent practical during the second ten-year interval.
- 2. Pressure test VT-2 visual examinations were performed, as required by Code Category 8-P, during the second ten-year interval.
No evidence of leakage was identified for this component.
3.2.3 NRC Staff Evaluation The ASME Code,Section XI, Table IWB-2500-1, Examination Category B-B, Item 82.40, Figure IWB-2500-6 (Design B) requires a volumetric examination of essentially 100 percent of the required weld volume extending 1 /2t into the base metal on both the head side and tubesheet side of the Head-to-Tubesheet Weld TCX-1-3100-2-1.
The required volumetric examinations are limited due to the design configuration of the subject welds and by four 24" x 24" SG support pads and 17 2.5" x 2.5" welded pads. In order for the licensee to perform the ASME Code-required examinations, the subject components would have to be redesigned and replaced.
The licensee noted that the examinations were conducted in accordance with the licensee's procedure TX-ISl-21 O, "Ultrasonic Examination Procedure for Welds in Ferritic Steel Vessels." The examinations were performed with a straight beam (0 degree (0)) and angle beam (45° shear and 60° longitudinal) scans to achieve the weld examination volume of 69 percent. The data sheets (Attachment 1 to the letter dated August 27, 2014) provided by the licensee shows that the 0° and 45° examination angles were both limited to 22 percent not examined, and the 60° examination angle was limited to 31 percent not examined.
The licensee examined the subject weld to the extent practical and obtained an average coverage of 69 percent of the ASME Code-required examination volume of the SG 2-02 Head-to-Tubesheet Weld TCX-1-3100-2-1.
The licensee has shown that it is impractical to meet the ASME Code-required 100 percent volumetric examination coverage of the SG 2-02 Head-to-Tubesheet Weld TCX-1-3100-2-1 due to the design configuration of the subject welds and by four 24" x 24" SG support pads and 17 2.5" x 2.5" welded pads near the subject weld. Based on the volumetric coverage obtained of 69 percent for the subject welds, and considering the licensee's performance of UT techniques employed to maximize this coverage, it is reasonable to conclude that if significant service-induced degradation had occurred, evidence of it would have been detected by the examinations that were performed.
In addition, by letter dated January 8, 2015, the licensee confirmed that no Nickel alloy weld metals 182 and 82 were used in the welds that are listed in this relief request. Since low alloy steel welds have better resistance to stress corrosion-cracking (SCC) than Nickel alloy welds, there is no active aging degradation in the welds. Therefore, the proposed request for relief submitted by the licensee for these welds is acceptable.
The licensee is also performing system leakage testing that is performed each refueling outage in accordance with ASME Code,Section XI, Table IWB-2500-1, Examination Category B-P, which requires a VT-2 visual examination to detect evidence of leakage. This test and VT-2 examination provides additional assurance of pressure boundary integrity.
Therefore, the NRC staff concludes that the results of the ASME Code examinations and the pressure test VT-2 visual examinations provide reasonable assurance of structural integrity of the subject component.
3.3 Relief Request B-12 In accordance with 10 CFR 50.55a(g)(5)(iii), the licensee requested relief from the ASME Code-required volumetric examination of the SG 2-01 Head-to-Tubesheet Weld TCX-1-3100-1-1 (Component No. TCX-RCPCSG-01).
3.3.1 Licensee's Basis for Relief Request (as stated) The examination of the subject component weld is limited by the presence of four 24" x 24" Steam Generator support pads and seventeen 2.5" x 2.5" welded pads [see weld profile sketch, page 4 of Attachment 2 to the licensee's letter dated August 27, 2014]. The examinations were conducted in accordance with procedure TX-ISl-210, "Ultrasonic Examination Procedure for Welds in Ferritic Steel Vessels." Straight beam (0°) and angle beam (45° shear and 60° longitudinal) scans were used to achieve the weld volume obtained.
As shown on the [examination data sheets, pages 6 through 14 of Attachment 2 to the licensee's letter dated August 27, 2014) the 0° and 45° exam[ination]
angles achieved 78% examination coverage, and the 60° exam[ination]
angle achieved 69% examination coverage.
Taking the worst case limitation this corresponds to coverage of 69% of the required examination volume. 3.3.2 Licensee's Proposed Alternative Examination (as stated) The following alternatives are proposed in lieu of the required examination coverage of essentially 100 percent: [1.] Ultrasonic Testing (UT) of the subject component weld was performed to the maximum extent practical during the second ten-year interval.
[2.] Pressure test VT-2 visual examinations were performed, as required by Code Category 8-P, during the second ten-year interval.
No evidence of leakage was identified for this component.
3.3.3 NRC Staff Evaluation The ASME Code,Section XI, Table IWB-2500-1, Examination Category 8-8, Item 82.40, Figure IWB-2500-6 (Design B) requires a volumetric examination of essentially 100 percent of the required weld volume extending 1 /2t into the base metal on both the head side and tubesheet side of the SG 2-01 Head-to-Tubesheet Weld TCX-1-3100-1-1.
The required volumetric examinations are limited due to the design configuration of the subject welds and by four 24" x 24" SG support pads and 17 2.5" x 2.5" welded pads. In order for the licensee to perform the ASME Code-required examinations, the subject components would have to redesigned and replaced.
The licensee noted that the examinations were conducted in accordance with the licensee's procedure TX-ISl-210, "Ultrasonic Examination Procedure for Welds in Ferritic Steel Vessels." The examinations were performed with a straight beam (0°) and angle beam (45° shear and 60° longitudinal) scans to achieve the weld examination volume of 69 percent. The data sheets (Attachment 2 to the letter dated August 27, 2014) provided by the licensee shows that the 0° and 45° examination angles were both limited to 22 percent not examined, and the 60° examination angle was limited to 31 percent not examined.
The licensee examined the subject weld to the extent practical and obtained an average coverage of 69 percent of the ASME Code-required examination volume of the SG 2-01 Head-to-Tubesheet Weld TCX-1-3100-1-1.
The licensee has shown that it is impractical to meet the ASME Code-required 100 percent volumetric examination coverage of the SG 2-01 Head-to-Tubesheet Weld TCX-1-3100-1-1 due to the design configuration of the subject welds and by four 24" x 24" SG support pads and 17 2.5" x 2.5" welded pads near the subject weld. Based on the volumetric coverage obtained of 69 percent for the subject welds, and considering the licensee's performance of UT techniques employed to maximize this coverage, it is reasonable to conclude that if significant service-induced degradation had occurred, evidence of it would have been detected by the examinations that were performed.
In addition, by letter dated January 8, 2015, the licensee confirmed that no Nickel alloy weld metals 182 and 82 were used in the welds that are listed in this relief request. Since low alloy steel welds have better resistance to sec than Nickel alloy welds, there is no active aging degradation in the welds. Therefore, the proposed request for relief submitted by the licensee for these welds is acceptable.
The licensee is also performing system leakage testing that is performed each refueling outage in accordance with ASME Code,Section XI, Table IWB-2500-1, Examination Category 8-P, which requires a VT-2 visual examination to detect evidence of leakage. This test and VT-2 examination provides additional assurance of pressure boundary integrity.
Therefore, the NRC staff concludes that the results of the ASME Code examinations and pressure test VT-2 visual examination provide reasonable assurance of structural integrity of the subject component.
3.4 Relief Request No. 8-13 In accordance with 10 CFR 50.55a(g)(5)(iii), the licensee requested relief from the ASME Code-required volumetric examination of the SG 2-04 Head-to-Tubesheet Weld TCX-1-3100-4-1 (Component No. TCX-RCPCSG-04).
3.4.1 Licensee's Basis for Relief Request (as stated) The examination of the subject component weld is limited by the presence of four 24" x 24" Steam Generator support pads and nineteen 2.5" x 2.5" welded pads [see weld profile sketch, pages 4 and 5 of Attachment 3 to the licensee's letter dated August 27, 2014]. The examinations were conducted in accordance with procedure TX-ISl-210, "Ultrasonic Examination Procedure for Welds in Ferritic Steel Vessels." Straight beam (0°) and angle beam (45° shear and 60° longitudinal) scans were used to achieve the weld volume obtained.
As shown on the [examination data sheets, pages 6 through 14 of Attachment 3 to the licensee's letter dated August 27, 2014] the 0°, 45°, and 60° exam[ination]
angles all achieved 77.5% examined.
Therefore, this corresponds to a cumulative exam[ination]
coverage of 77.5% of the required examination volume. 3.4.2 Licensee's Proposed Alternative Examination (as stated) The following alternatives are proposed in lieu of the required examination coverage of essentially 100 percent: 1. Ultrasonic Testing (UT) of the subject component weld was performed to the maximum extent practical during the second ten-year interval.
- 2. Pressure test VT-2 visual examinations were performed, as required by Code Category 8-P, during the second ten-year interval.
No evidence of leakage was identified for this component.
3.4.3 NRC Staff Evaluation The ASME Code,Section XI, Table IWB-2500-1, Examination Category 8-8, Item 82.40, Figure IWB-2500-6 (Design B) requires a volumetric examination of essentially 100 percent of the required weld volume extending 1 /2t into the base metal on both the head side and tubesheet side of the SG 2-04 Head-to-Tubesheet Weld TCX-1-3100-4-1.
The required volumetric examinations are limited due to the design configuration of the subject welds and by four 24" x 24" SG support pads and 19 2.5" x 2.5" welded pads. In order for the licensee to perform the ASME Code-required examinations, the subject components would have to redesigned and replaced. The licensee noted that the examinations were conducted in accordance with the licensee's procedure TX-ISl-210, "Ultrasonic Examination Procedure for Welds in Ferritic Steel Vessels." The examinations were performed with a straight beam (0°) and angle beam (45° shear and 60° longitudinal) scans to achieve the weld examination volume of 69 percent. The data sheets (Attachment 3 to the letter dated August 27, 2014) provided by the licensee shows that the 0°, 45°, and 60° examination angles all achieved 77.5 percent examined.
The licensee examined the subject weld to the extent practical and obtained an average coverage of 77.5 percent of the ASME Code-required examination volume of the SG 2-04 Head-to-Tubesheet Weld TCX-1-3100-4-1.
The licensee has shown that it is impractical to meet the ASME Code-required 100 percent volumetric examination coverage of the SG 2-04 Head-to-Tubesheet Weld TCX-1-3100-4-1 due to the design configuration of the subject welds and by four 24" x 24" SG support pads and 19 2.5" x 2.5" welded pads near the subject weld. Based on the volumetric coverage obtained of 77.5 percent for the subject welds, and considering the licensee's performance of UT techniques employed to maximize this coverage, it is reasonable to conclude that if significant service-induced degradation had occurred, evidence of it would have been detected by the examinations that were performed.
In addition, by letter dated January 8, 2015, the licensee confirmed that no Nickel alloy weld metals 182 and 82 were used in the welds that are listed in this relief request. Since low alloy steel welds have better resistance to sec than Nickel alloy welds, there is no active aging degradation in the welds. Therefore, the proposed request for relief submitted by the licensee for these welds is acceptable.
The licensee is also performing system leakage testing during each refueling outage in accordance with ASME Code,Section XI, Table IWB-2500-1, Examination Category 8-P, which requires a VT-2 visual examination to detect evidence of leakage. This test and VT-2 examination provides additional assurance of pressure boundary integrity.
Therefore, the NRC staff concludes that the results of the ASME Code examinations and the pressure test VT-2 visual examinations provide reasonable assurance of structural integrity of the subject component.
4.0 CONCLUSION
As set forth above, the NRC staff has determined that granting relief pursuant to 1 O CFR 50.55a(g)(6)(i) is authorized by law and will not endanger life or property, or the common defense and security, and is otherwise in the public interest, given the burden that could be faced by the licensee if the requirements were imposed on the facility.
Furthermore, the staff concluded that the examinations performed to the extent practical provide reasonable assurance of structural integrity of the subject components.
In addition, the licensee confirmed that no Nickel alloy weld metals182 and 82 were used in the welds that are listed in the relief request. Since low alloy steel welds have better resistance to sec than Nickel alloy welds, there is no active aging degradation in the welds. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(6)(i).
Therefore, the NRC staff grants relief for the subject examinations of the components contained in RRs 8-7, 8-12, and B-13 for CPNPP, Unit 2, second 10-year inservice inspection Interval, which began on August 3, 2004, and ended on August 2, 2014. All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in the subject requests for relief remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor:
Thomas Mclellan, NRR/DE/EVIB Date: April 3, 2015 R. Flores If you have any questions, please contact Balwant K. Singal at 301-415-3016 or via e-mail at Balwant. Singal@nrc.gov.
Docket No. 50-446
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL4-1 Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDeEvibResource RidsNrrDorlDpr Resource ADAMS Accession No. ML 15090A104 OFFICE NRR/DORULPL4-1/PM NRR/DORL/LPL4-1
/PM NAME SGoetz BSingal DATE 3/31/15 4/2/15 Sincerely, IRA/ Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDorllpl4-1 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMComanchePeak Resource RidsRgn4MailCenter Resource TMclellan, NRR/DE/EVIB
- Memo dated March 11, 2015 NRR/DORL/LPL4-1/LA NRR/DE/EVIB/BC NRR/DORL/LPL4-1/BC JBurkhardt SRosenberg*
MMarkley (Clyon for) 3/31/15 3/11/15 4/3/15 OFFICIAL AGENCY RECORD