Letter Sequence Response to RAI |
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MONTHYEARCP-201500781, Relief Request C-4, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August..2015-08-0303 August 2015 Relief Request C-4, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August.. Project stage: Request CP-201500780, Relief Request C-2, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August..2015-08-0303 August 2015 Relief Request C-2, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August.. Project stage: Request CP-201500779, Relief Request B-15, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August..2015-08-0303 August 2015 Relief Request B-15, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August.. Project stage: Request ML15317A1582015-11-13013 November 2015 Request for Additional Information Email, Relief Request 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 Project stage: RAI CP-201501104, Response to Request for Additional Information for Relief Requests B-15, C-2, and C-4 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition Of.2015-12-14014 December 2015 Response to Request for Additional Information for Relief Requests B-15, C-2, and C-4 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition Of. Project stage: Response to RAI 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 Project stage: Other 2015-12-14
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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
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARCP-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-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-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 ML23164A2232023-06-13013 June 2023 Response to Request for Confirmation of Information Regarding Review of the License Renewal Application - Set 1 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-202300270, (CPNPP) - Response to Request for Supplemental Information for License Amendment Request to Adopt 10 CFR 50.59, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-06-0808 June 2023 (CPNPP) - Response to Request for Supplemental Information for License Amendment Request to Adopt 10 CFR 50.59, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors 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 TXX-2304, (Cpnpp), Response to Request for Information for Application to Revise Technical Specifications to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model LAR 22-0022023-06-0101 June 2023 (Cpnpp), Response to Request for Information for Application to Revise Technical Specifications to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model LAR 22-002 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-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-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 ML22228A0942022-08-17017 August 2022 Notification of Inspection (NRC Inspection Report 05000445/2022004 and 05000446/2022004) and Request for Information CP-202200123, (CPNPP) - 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.2022-03-29029 March 2022 (CPNPP) - 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. CP-202100694, (CPNPP) - NRC Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections2021-10-25025 October 2021 (CPNPP) - NRC Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections CP-202000428, (CPNPP) - Response to Request for Additional Information Regarding Proposed Alternative SNB-1 for a One-Time Extension of Snubber Testing2020-08-0505 August 2020 (CPNPP) - Response to Request for Additional Information Regarding Proposed Alternative SNB-1 for a One-Time Extension of Snubber Testing TXX-2003, Response to Request for Additional Information Regarding Exigent License Amendment 20-003 Revision to Technical Specification 5.5.9, Unit 1 Model D76 and Unit 2 Model D5 Steam Generator (SG) Program2020-04-14014 April 2020 Response to Request for Additional Information Regarding Exigent License Amendment 20-003 Revision to Technical Specification 5.5.9, Unit 1 Model D76 and Unit 2 Model D5 Steam Generator (SG) Program CP-202000273, Response to Request for Additional Information Regarding Snubber Testing (SNB-1) and Snubber Visual Examination (SNB-2) Relief Requests2020-04-13013 April 2020 Response to Request for Additional Information Regarding Snubber Testing (SNB-1) and Snubber Visual Examination (SNB-2) Relief Requests CP-202000024, Response to NRC Request for Additional Information on Biennial Review of Procedures and Station Operations Review Committee Meetings2020-01-14014 January 2020 Response to NRC Request for Additional Information on Biennial Review of Procedures and Station Operations Review Committee Meetings CP-201800659, (Cpnpp), Unit 1 - Response to Request for Additional Information Regarding Exigent License Amendment Request (LAR) 18-001, Revision to Technical Specification 3.8.4, 11DC Sources - Operating, Condition B2018-09-20020 September 2018 (Cpnpp), Unit 1 - Response to Request for Additional Information Regarding Exigent License Amendment Request (LAR) 18-001, Revision to Technical Specification 3.8.4, 11DC Sources - Operating, Condition B CP-201700904, Response to Request for Additional Information Regarding Relief Request 1/2B3-2 for the Units 1 and 2 Third Ten Year Inservice Inspection Interval2017-11-0101 November 2017 Response to Request for Additional Information Regarding Relief Request 1/2B3-2 for the Units 1 and 2 Third Ten Year Inservice Inspection Interval CP-201600934, Information Regarding NRC Order Approving Transfer of Licenses and Conforming License Amendments (CPNPP Unit 1 Operating License (NPF-87) and CPNPP Unit 2 Operating License (NPF-89))2016-09-29029 September 2016 Information Regarding NRC Order Approving Transfer of Licenses and Conforming License Amendments (CPNPP Unit 1 Operating License (NPF-87) and CPNPP Unit 2 Operating License (NPF-89)) CP-201600328, Additional Information Regarding Application for Order Approving Transfer of Licenses and Conforming License Amendments (CPNPP Unit 1 Operating License (NPF-87) and CPNPP Unit 2 Operating License (NPF-89))2016-03-29029 March 2016 Additional Information Regarding Application for Order Approving Transfer of Licenses and Conforming License Amendments (CPNPP Unit 1 Operating License (NPF-87) and CPNPP Unit 2 Operating License (NPF-89)) CP-201600136, and Independent Spent Fuel Storage Installation (Isfsi), Additional Information Regarding Application for Order Approving Transfer of Licenses and Conforming License Amendments2016-03-14014 March 2016 and Independent Spent Fuel Storage Installation (Isfsi), Additional Information Regarding Application for Order Approving Transfer of Licenses and Conforming License Amendments CP-201600177, Supplemental to Response to Request for Additional Information Regarding License Amendment Request 15-003 for Revision to Emergency Action Levels2016-03-0303 March 2016 Supplemental to Response to Request for Additional Information Regarding License Amendment Request 15-003 for Revision to Emergency Action Levels CP-201600148, Requesting Additional Information for Relief Request b-9 for Unit 2 Second Ten Year Inservice Inspection Interval2016-03-0202 March 2016 Requesting Additional Information for Relief Request b-9 for Unit 2 Second Ten Year Inservice Inspection Interval CP-201600147, Revision Response to Request for Additional Information Regarding for Relief Request B-3 for Second Ten Year Interval Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code Section XI, 2000 Addenda.2016-03-0202 March 2016 Revision Response to Request for Additional Information Regarding for Relief Request B-3 for Second Ten Year Interval Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code Section XI, 2000 Addenda. ML16057A3092016-02-15015 February 2016 Response to Request for Additional Information Re Relief Request 1B3-3 ML16057A3102016-02-12012 February 2016 Westinghouse LTR-PAFM-16-8 Attachment B - Responses to the NRC RAIs Re Comanche Peak Unit 1 Extension of Required Inspection Frequency for Reactor Vessel Inlet Nozzle Dissimilar Metal Welds from 7 to 9 Calendar Years CP-201600048, Response to Request for Additional Information Regarding License Amendment Request 15-003 for Revision to Emergency Action Levels2016-01-27027 January 2016 Response to Request for Additional Information Regarding License Amendment Request 15-003 for Revision to Emergency Action Levels CP-201501102, Response to Request for Additional Information for Relief Request B-10 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME, Section...)2015-12-14014 December 2015 Response to Request for Additional Information for Relief Request B-10 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME, Section...) CP-201501101, Response to Request for Additional Information for Relief Request B-9 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code....)2015-12-14014 December 2015 Response to Request for Additional Information for Relief Request B-9 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code....) CP-201501104, Response to Request for Additional Information for Relief Requests B-15, C-2, and C-4 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition Of.2015-12-14014 December 2015 Response to Request for Additional Information for Relief Requests B-15, C-2, and C-4 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition Of. CP-201501103, Response to Request for Additional Information for Relief Request B-11 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code....)2015-12-14014 December 2015 Response to Request for Additional Information for Relief Request B-11 for the Second Ten-Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code....) CP-201501100, Response to Request for Additional Information for Relief Request B-3 for the Second Ten-Year Inservice Inspection Interval Fram 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code....)2015-12-14014 December 2015 Response to Request for Additional Information for Relief Request B-3 for the Second Ten-Year Inservice Inspection Interval Fram 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code....) CP-201501130, ISFSI - Transmittal of Additional Information Regarding Application for Order Approving Transfer of Licenses and Conforming License Amendments2015-12-0909 December 2015 ISFSI - Transmittal of Additional Information Regarding Application for Order Approving Transfer of Licenses and Conforming License Amendments CP-201500740, Submittal of Request for Additional Information Regarding Fukushima Lessons Learned - Flooding Hazard Reanalysis Report2015-09-22022 September 2015 Submittal of Request for Additional Information Regarding Fukushima Lessons Learned - Flooding Hazard Reanalysis Report CP-201500810, Compliance with NRC Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, Response to Request for Additional Information (Order Number EA-12-051)2015-08-13013 August 2015 Compliance with NRC Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, Response to Request for Additional Information (Order Number EA-12-051) CP-201500749, Response to Request for Additional Information for License Amendment Request 14-002, Extension of Containment Leakage Test Frequency2015-07-29029 July 2015 Response to Request for Additional Information for License Amendment Request 14-002, Extension of Containment Leakage Test Frequency CP-201500685, Response to Request for Additional Information for Relief Request 2A3-1, Unit 2, Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Class 1 & 2.2015-07-22022 July 2015 Response to Request for Additional Information for Relief Request 2A3-1, Unit 2, Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Class 1 & 2. 2023-07-27
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Senior Vice President P0O Box 1002 SRafael
____& Flores Chief Nuclear Officer Luminant Power 6322 North FM 56 Rafael.Flores@Luminant.com Glen Rose, TX 76043 Lum inant ,254 897 5590 F254 897 6652 CP-201501104 Ref. # 10CFR50.55a(z)(1)
TXX-15158 December 14, 2015 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NO. 50-446 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUESTS B-i5, C-2, AND C-4 FOR UNIT 2 SECOND TEN YEAR JINSERVICE INSPECTION INTERVAL FROM 10CFR50.55a INSPECTION REQUIREMENTS DUE TO PHYSICAL INTERERENCES (1998 EDITION OF ASME CODE, SECTION XI, 2000ADDENDA THIRD INTERVAL START DATE: AUGUST 3, 2004 THIRD INTERVAL END DATE:
AUGUST 2, 2014) CAC NOS. MF6557, MF6558, MF6559
REFERENCES:
- 1. Letter logged TXX-15119 dated August 3, 2015 from Rafael Flores to the NRC submitting Relief Request B-15 for Unit 2 Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements due to Physical Interferences
- 2. Letter logged TXX-15120 dated August 3, 2015 from Rafael Flores to the NRC submitting Relief Request C-2 for Unit 2 Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements due to Physical Interferences
- 3. Letter logged TXX-15121 dated August 3, 2015 from Rafael Flores to the NRC submitting Relief Request C-4 for Unit 2 Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements due to Physical Interferences
- 4. Email dated November 13, 2015 from Baiwant Singal of the NRC to Timothy Hope of Luminant Power requesting additional information regarding Relief Requests B-15, C-2 and C-4 (CAC Nos. MF6557, MF6558, MF6559)
Dear Sir or Madam:
Per References 1, 2 and 3, Luminant Generation Company, LLC (Luminant Power) submitted Relief Requests B-i5, C-2, and C-4 for Comanche Peak Unit 2 for the second ten year inservice inspection interval. Per Reference 2, the NRC provided a request for additional information regarding the subject relief request.
Attached is the Luminant Power response to the request for additional information.
This communication contains no new licensing basis commitments regarding Comanche Peak Unit 2.
tf^
U. S. Nuclear Regulatory Commission TXX-15 158 Page 2 of 2 12/14/2015 Should you have any questions, please contact Mr. Jack Hicks at (254) 897-6725.
Sincerely, Luminant Generation Company LLC Rafael Flores By: Th~~cool Vice President, Engineering and Support Attachment - Response to Request for Information Regarding Unit 2 Relief Requests B-15, C-2 and C-4 Second Ten Year Interval Inspection Requirements due to Physical Interferences c - Marc L. Dapas, Region IV Balwant K. Singal, NRR Resident Inspectors, Comanche Peak Robert Free, TDLR Jack Ballard, ANII, Comanche Peak
Attachment to TXX-15158 Page 1 of 6 COMANCHE PEAK NUCLEAR POWER PLANT UNIT 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST B-15, C-2, AND C-4 FOR SECOND TEN YEAR INTERVAL INSPECTION REQUIREMENTS DUE TO PHYSICAL INTERFERENCES (SECOND 10-YEAR ISI INTERVAL END DATE: August 2, 2014)
CAC NOS. MF65571MF6558/MF6559 NRC REQUEST 1:
In relief request B-15, the staff notes that weld TCX-1-1300-2 is in Examination Category B-A, Item No.
B1.21 of Table IWB-2500-1, "Examination Categories," of the ASME Code,Section XI. As indicated in Table IWB-2500-1, the examination requirement for Item No. B1.21 welds is essentially 100% of the accessible weld length. The ASME Code Committees recognize the limitations of examining these welds and specifically stated in this particular ASME Code requirement to examine the "accessible length" of the welds. Please clarify whether or not that essentially 100% of the accessible weld length was achieved for weld TCX-1-1300-2.
LUMINANT POWER RESPONSE TO REQUEST 1:
As stated in RAI 1 above, TCX-1-1300-2 does not require a relief request for coverage. As allowed ASME Section XI Examination Category B-A, Item No. B1.21 of Table IWB-2500-1, only the accessible areas of the weld length are required to be examined. Essentially 100% of the accessible weld length was inspected both parallel and transverse to the weld. Due to the component configuration only single direction coverage was obtained in the transverse direction. This single direction coverage has been qualified prEPRI Generic prcdr PDI*T-TTNTpoeue XII36 n teeaie a been qualified to the single sided technique. No further discussion of weld TCX-1-1300-2 is required.
NRC REQUEST 2:
Please provide the following additional information regarding the examination diagrams of the subject RRs:
a) Depending on the licensee's response to RAI 1 regarding R.R B-15, with respect to weld TCX-1-1300-2, provide the following information: (1) the ASME Code,Section XI required examination volume (cross sectional area multiplied by weld length), (2) the scan angles used for the examination, and (3) the achieved scanned volumes (cross sectional area multiplied by weld length) for both the axial and circumferential scan directions. Please refer to the presentation slides for, "Industry/NRC NDE [Non Destructive Examination] Technical Information Exchange Public Meeting, January 13 -
15, 2015," (ADAMS Accession Number ML15013A266) for a discussion of the staff's expectations for the content of an examination/inspection diagram (see slide 12 for an example). The sketch/diagram should show relevant dimensions, such as wall thickness and weld dimensions.
b) Regarding RiR C-2, with respect to weld TCX-2-1180-1-2, provide the following information: (1) the ASME Code,Section XI required examination volume (cross sectional area multiplied by weld length), (2) the scan angles used for the examination, (3) the achieved scanned volumes for both the axial and circumferential scan directions (cross sectional area multiplied by weld length), and (4) the material of construction of weld TCX-2-1180-1-2 and the base metal immediately adjacent to the weld. Please refer to the presentation slides for, "Industry/NRC NDE Technical Information Exchange Public Meeting, January 13 -15, 2015," for a discussion of the staff's expectations for the content of an examination/inspection diagram (see slide 12 for an example). The sketch/diagram should show relevant dimensions, such as wall thickness and weld dimensions.
c) Regarding RR{ C-4, with respect to the subject welds, provide the following information: (1) the
Attachment to TXX-1 5158 Page 2 of 6 COMANCHE PEAK NUCLEAR POWER PLANT UNIT 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST B-15, 0-2, AND C-4 FOR SECOND TEN YEAR INTERVAL INSPECTION REQUIREMENTS DUE TO PHYSICAL INTERFERENCES (SECOND 10-YEAR ISI INTERVAL END DATE: August 2, 2014)
CAC NOS. MF6557/MF6558/MF6559 ASME Code,Section XI required examination volume (cross sectional area multiplied by weld length), (2) the scan angles used for the examination, (3) the achieved scanned volumes for both the axial and circumferential scan directions (cross sectional area multiplied by weld length), and (4) the material of construction of the subject welds and the base metal immediately adjacent to the welds. Please refer to the presentation slides for, "Industry/NRC NDE Technical Information Exchange Public Meeting, January 13 -15, 2015," for a discussion of the staff's expectations for the content of an examination/inspection diagram (see slide 12 for an example). The sketch/diagram should show relevant dimensions, such as wall thickness and weld dimensions.
LUMINANT POWER RESPONSE TO REOUEST 2:
- a. As stated in the response to RAI 1 no further discussion of weld TCX-1-1300-2 is required.
- b. Component ID- TCX-2-1180-1-2 CT Heat Exchanger Shell-to-Flange Weld Code Category - C-A Code Item Number - C1.10 IWC Examination Figure - IWC-2500-1 Code Required Volume - Full volu~me and d" to each side of the weld Scan Angle Used for Examination - 45 degree shear Achieved Coverage Showing Calculations - 86% coverage reported.
(See Relief Request C-2 for examination data sheets and sketches)
Were RL's used to achieve additional coverage on a best effort basis - No Material of Construction - Shell: SA-240 Type 304 Stainless Steel, Flange: SA-182F Type 304 Radiography (RT) would be impractical to perform due to the physical and access limitations present. i.e. placement of source and film.
Phased array ultrasonic examination would not gain any additional coverage due to the inherently large search unit size of the phased array search units and would likely result in less coverage than the manual technique applied.
- c. Component ID- TCX-2-1120-1-1 RHR Heat Exchanger Head-to-Shell Weld Code Category - C-A Code Item Number - C1.20 IWC Examination Figure - IWC-2500-1 Code Required Volume - Full volume and 11/2" to each side of the weld Scan Angle Used for Examination - 45 degree shear Achieved Coverage Showing Calculations - 75% coverage was achieved due to an integrally welded support to the vessel.
36" limitation of total weld length of 142.08" 36/142.08= .253 or 25% reduced examination volume (See Relief Request C-4 for examination data sheets and sketches)
Were RL's used to achieve additional coverage on a best effort basis - No Material of Construction - Shell/Head: SA-240 Type 304 Stainless Steel, Weld Material: ER-308 or ER-309
Attachment to TXX-15158 Page 3 of 6 COMANCHE PEAK NUCLEAR POWER PLANT UNIT 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST B-15, C-2, AND C-4 FOR SECOND TEN YEAR INTERVAL INSPECTION REQUIREMENTS DUE TO PHYSICAL INTERFERENCES (SECOND 10-YEAR ISI INTERVAL END DATE: August 2, 2014)
CAC NOS. MF6557/MF6558/MF6559 Radiography (RT) would be impractical to perform due to the physical and access limitations present. i.e. placement of source and film.
Phased array ultrasonic examination would not gain any additional coverage due to the inherently large search unit size of the phased array search units and would likely result in less coverage than the manual technique applied.
Component ID- TCX-2-1120-1-2 RHR Heat Exchanger Shell-to-Flange Weld Code Category - C-A Code Item Number - C1.10 IWC Examination Figure - IWC-2500-1 Code Required Volume - Full volume and 1/2" to each side of the weld Scan Angle Used for Examination - 45 degree shear & 60 degree shear Achieved Coverage Showing Calculations - 63% coverage was achieved due to an integrally welded support to the vessel.
52" limitation of total weld length of 142.08" 52/142.08-- .366 or 37% reduced examination volume (See Relief Request C-4 for exmnto ,*f* h 0 0o* ~an .. -
Were RL's used to achieve additional coverage on a best effort basis - No Material of Construction - Shell/Flange: SA-240 Type 304 Stainless Steel, Weld Material: ER-308 or ER-309 Radiography (RT) would be impractical to perform due to the physical and access limitations present. i.e. placement of source and film.
Phased array ultrasonic examination would not gain any additional coverage due to the inherently large search unit size of the phased array search units and would likely result in less coverage than the manual technique applied.
Component ID- TCX-2-1120-1-3 RHR Heat Exchanger Inlet Nozzle-to-Shell Weld Code Category - C-B Code Item Number - C2.21 IWC Examination Figure - IWC-2500-4 Code Required Volume - Bottom 1/3t volume and 1/2,"to each side of the weld Scan Angle Used for Examination - 45 degree shear, 60 degree shear, 60 degree RL Achieved Coverage Showing Calculations - 75% coverage was achieved due to one sided vessel access.
450 Axial Scan 100%
450 Circ Scan 50%
450 Circ Scan 37.68/2 = 18.8 18.84/37.68 = .500 (50%)
Total 450 Coverage = 75%
Attachment to TXX-1 51 58 Page 4 of 6 COMANCHE PEAK NUCLEAR POWER PLANT UNIT 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST B-15, C-2, AND C-4 FOR SECOND TEN YEAR INTERVAL INSPECTION REQUIREMENTS DUE TO PHYSICAL INTERFERENCES (SECOND 10-YEAR ISI INTERVAL END DATE: August 2, 2014)
CAC NOS. MF6557/MF6558/MF6559 Supplemental Coverage 600 Shear Axial Scan 100%
60° RL Axial Scan 100%
(See Relief Request C-4 for examination data sheets and sketches)
Were RL's used to achieve additional coverage on a best effort basis - Yes, 60 degree RL used for supplemental best effort examination Material of Construction - Shell/Nozzle: SA-240 Type 304 Stainless Steel, Weld Material: ER-308 or ER-309 Radiography (RT) would be impractical to perform due to the physical and access limitations present. i.e. placement of source and film.
Phased array ultrasonic examination would not gain any additional coverage due to the inherently large search unit size of the phased array search units and would likely result in less coverage than the manual technique applied.
Component ID- TCX-2-1120-1-4 RHR Heat Exchanger Outlet Nozzle-to-Shell Weld Code Category - C-B Code Item Number - C2.21 IWC Examination Figure - IWC-2500-4 Code Required Volume - Bottom 1/3t volume and 1/2,"to each side of the weld Scan Angle Used for Examination - 45 degree shear, 60 degree shear, 60 degree RL Achieved Coverage Showing Calculations - 75% coverage was achieved due to one sided vessel access.
450 Axial Scan 100%
450 Circ Scan 50%
450 Circ Scan 37.68/2 = 18.8 18.84/37.68 = .500 (50%)
Total 450 Coverage = 75%
Supplemental Coverage 60° Shear Axial Scan 100%
60° RL Axial Scan 100%
(See Relief Request C-4 for examination data sheets and sketches)
Were RL's used to achieve additional coverage on a best effort basis - Yes, 60 degree RL used for supplemental best effort examination Material of Construction - Shell/Nozzle: SA-240 Type 304 Stainless Steel, Weld Material: ER-308 or ER-309
Attachment to TXX-15158 Page 5 of 6 COMANCHE PEAK NUCLEAR POWER PLANT UNIT 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST B-15, C-.2, AND C-4 FOR SECOND TEN YEAR INTERVAL INSPECTION REQUIREMENTS DUE TO PHYSICAL INTERFERENCES (SECOND 10-YEAR 151 INTERVAL END DATE: August 2, 2014)
CAC NOS. MF6557/MF6558/MF6559 Radiography (RT) would be impractical to perform due to the physical and access limitations present. i.e. placement of source and film.
Phased array ultrasonic examination would not gain any additional coverage due to the inherently large search unit size of the phased array search units and would likely result in less coverage than the manual technique applied.
NRC REQUEST 3:
For the examinations performed in RRs B-15, C-2, and C-4, please discuss the adequacy of one-sided exams, if applicable. Please discuss, for example, whether 50% or 100% credit is given to the achieved one-sided examination volume. If 100% credit is given, please provide the justification.
LUMINANT POWER RESPONSE TO REQUEST 3:
As stated in the response to RAII1 no further discussion of weld TCX-1-1300-2 is required.
For C-2 approximately 86% coverage was achieved based on limitation calculations and examination volume achieved. Liniltation drawing shows limitations associated with this component. No further examination volume could be achieved utilizing phased array, due to transducer size limitations.
For C-4 approximately 75% coverage was achieved for the one-sided exams based on limitation calculations and examination volume achieved. Limitation drawing shows limitations associated with this component. No further examination volume could be achieved utilizing phased array, due to transducer size limitations.
NRC REQUEST 4:
Please provide the following information regarding the ultrasonic examination procedures used in the subject RRs:
a) Depending on the licensee's response to RAI 1 regarding RR B-15, please discuss the ASME Code Section XI, Appendix I requirement from which procedure TXI-ISI-306 is based. If supplements apply, please discuss which supplements were used.
b) With respect to RRs C-2 and C-4, please discuss the ASME Code Section XI, Appendix I requirement from which procedure TXI-ISI-214 is based. If supplements apply, please discuss which supplements were used.
Attachment to TXX-1 5158 Page 6 of 6 COMANCHE PEAK NUCLEAR POWER PLANT UNIT 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST B-15, C-2, AND C-4 FOR SECOND TEN YEAR INTERVAL INSPECTION REQUIREMENTS DUE TO PHYSICAL INTERFERENCES (SECOND 10-YEAR ISI INTERVAL END DATE: August 2, 2014)
CAC NOS. MF65571MF6558/MF6559 LUMINANT POWER RESPONSE TO REQUEST 4:
- a. As stated in the response to RAI 1 no further discussion of weld TCX-I-1300-2 is required.
- b. Per ASME Section XI, Appendix I, the subject weld examinations were conducted in accordance with Appendix III, as supplemented by Table 1-2000-1. In addition to the requirements of Appendix III, the applicable supplements for vessels <2 inches in thickness from Table 1-2000-1 used in preparation of the examination procedure TX-ISI-214 and for these particular examinations were:
- 3 -- Calibration Blocks for Curved Surfaces
- 4-- Alternative Calibration Block Design
- 6 -- Pulse Repetition Rate
- 11 -- Geometric Reflectors
- 12-- Flaw Sizing NRC REQUEST 5:
For the examinations performed in RRs B-15 (if applicable), C-2, and C-4, please discuss other means attempted, if any, to achieve the ASME Code-required volume.
LUMINANT POWER RESPONSE TO REQUEST 5:
As stated in the response to RAII1 no further discussion of weld TCX-1-1300-2 (B-i5) is required. As for TCX-2-1180-1-2 (C-2) the component weld is limited by the configuration of the flange design and the proximity of two welded support plates on the shell side of the heat exchanger. No other means were attempted beyond the "Best Effort" Ultrasonic examination of weld TCX-2-1180-1-2. As for welds TCX-2-1120-1-1, TCX-2-1120-1-1WS-WA, TCX-2-1120-1-2, TCX-2-1120-1-2WS-WA, TCX-2-1120-1-3 and TCX-2-1120-1-4 (C-4) the "Best Effort" Ultrasonic Examination combining both 45 degree and 60 degree angles as well as surface Liquid Penetrant examinations were performed for each of the welds as required. No other means were attempted beyond these "Best Effort" examinations due to configuration limitations.
NRC REQUEST 6:
Please discuss any plant-specific operating experience regarding potential degradation in the subject welds in RRs C-2 and C-4, such as stress corrosion cracking or general corrosion.
LUMINANT POWER RESPONSE TO REQUEST 6:
No plant-specific operating experience regarding potential degradation in the subject welds in R~s C-2 and C-4 is identified.