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MONTHYEARCP-201500402, Relief Request 1B3-3 Inservice Inspection for Application of an Alternative to ASME Boiler & Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Cold Leg Weld Inspection Frequency2015-04-20020 April 2015 Relief Request 1B3-3 Inservice Inspection for Application of an Alternative to ASME Boiler & Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Cold Leg Weld Inspection Frequency Project stage: Request CP-201500999, Revision to Relief Request 1B3-3 Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Cold Leg Weld Inspection..2015-10-15015 October 2015 Revision to Relief Request 1B3-3 Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Cold Leg Weld Inspection.. Project stage: Request ML16015A0032016-01-14014 January 2016 NRR E-mail Capture - Request for Additional Information - Relief Request 1B3-3 for Comanche Peak Nuclear Power Plant, Unit 1 Project stage: RAI 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 Project stage: Other ML16057A3092016-02-15015 February 2016 Response to Request for Additional Information Re Relief Request 1B3-3 Project stage: Response to RAI CP-201600097, Westinghouse LTR-PAFM-16-2-NP, Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds.2016-02-29029 February 2016 Westinghouse LTR-PAFM-16-2-NP, Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds. Project stage: Other ML16053A4462016-03-10010 March 2016 Request for Withholding Information from Public Disclosure, 2/10/16 Affidavit Executed by J. Gresham, Westinghouse Electric Company LLC LTR-PAFM-16-8 and LTR-PAFM-16-2-P, Revision 0, Relief Request 1B3-3 Project stage: Withholding Request Acceptance 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 Project stage: Other 2016-02-12
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Category:Letter
MONTHYEARCP-202400030, License Renewal Application Revision 0 - Supplement 3, Revision 12024-01-31031 January 2024 License Renewal Application Revision 0 - Supplement 3, Revision 1 IR 05000445/20230042024-01-29029 January 2024 Integrated Inspection Report 05000445/2023004 and 05000446/2023004 CP-202400034, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1)2024-01-29029 January 2024 (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1) ML24024A2102024-01-29029 January 2024 Summary of Regulatory Audit Regarding a License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24025A0052024-01-25025 January 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report ML24023A0242024-01-24024 January 2024 Correction to Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident Methodology ML24018A1072024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000445/2024012 and 05000446/2024012) and Request for Information ML23159A2082023-12-20020 December 2023 Request for Withholding Information from Public Disclosure ML23319A3872023-12-20020 December 2023 Issuance of Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology ML23348A2392023-12-19019 December 2023 Nonacceptance of License Amendment Request to Relocate Technical Specification 3.9.3, Nuclear Instrumentation, to the Technical Requirements Manual CP-202300575, (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 22023-12-13013 December 2023 (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 2 ML23333A0872023-12-13013 December 2023 Transmittal of Dam Safety Inspection Report - Public CP-202300566, (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation2023-12-12012 December 2023 (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation CP-202300494, License Renewal Application Revision 0, Supplement 32023-12-0606 December 2023 License Renewal Application Revision 0, Supplement 3 ML23313A0732023-12-0606 December 2023 Issuance of Amendment Nos. 184 and 184 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Rev. 1, Improved Roac and CAOC Fq Surveillance Technical Specifications ML23291A4382023-11-30030 November 2023 Notice of Availability of the Draft Plant-Specific Supplement 60, to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Comanche Peak Nuclear Power Plant, Unit Numbers 1 and 2, License Renewal Applica ML23325A0182023-11-30030 November 2023 Schedule Revision for the License Renewal Application Review IR 05000445/20234022023-11-30030 November 2023 NRC Security Inspection Report 05000445/2023402 and 05000446/2023402 CP-202300349, License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation2023-11-20020 November 2023 License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation ML23308A0032023-11-17017 November 2023 Letter to R. Nelson, Executive Director; Achp; Re., Comanche Peak Draft Environmental Impact Statement ML23308A0022023-11-17017 November 2023 Letter to M. Wolfe, Executive Director; Shpo; Re., Comanche Peak Draft Environmental Impact Statement ML23317A3002023-11-13013 November 2023 Letter to R. Sylestine, Chairman, Alabama-Coushatta Tribe of Texas Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2972023-11-13013 November 2023 Letter to R. Martin, President, Tonkawa Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2872023-11-13013 November 2023 Letter to J. Garza, Chairman, Kickapoo Traditional Tribe of Texas Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2832023-11-13013 November 2023 Letter to D. Dotson, President, Delaware Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2852023-11-13013 November 2023 Letter to E. Martinez, President, Mescalero Apache Tribe Regarding Comanche Peak Draft Environmental Impact Statement ML23306A0302023-11-13013 November 2023 Letter to J. Cernek, Chairman; Coushatta Tribe of Louisiana Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2902023-11-13013 November 2023 Letter to M. Pierite, Chairman, Tunica Biloxi Tribe of Louisiana Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2982023-11-13013 November 2023 Letter to R. Morrow, Town King, Thlopthlocco Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2842023-11-13013 November 2023 Letter to D. Kaskaske, Chairman, Kickapoo Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2822023-11-13013 November 2023 Letter to D. Cooper, Chairman, Apache Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2962023-11-13013 November 2023 Letter to M. Woommavovah, Chairman, Comanche Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2812023-11-13013 November 2023 Letter to C. Hoskin, Principal Chief, Cherokee Nation; Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2862023-11-13013 November 2023 Letter to J. Bunch, Chief, United Keetoowah Band of Cherokee Indians Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3032023-11-13013 November 2023 Letter to W. Yargee, Chief, Alabama-Quassarte Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2882023-11-13013 November 2023 Letter to L. Johnson, Chief, Seminole Nation of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3012023-11-13013 November 2023 Letter to S. Yahola, Mekko, Kialegee Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2792023-11-13013 November 2023 Letter to B. Gonzalez, Chairman, Caddo Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3022023-11-13013 November 2023 Letter to T. Parton, President, Wichita and Affiliated Tribes Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2892023-11-13013 November 2023 Letter to L. Spottedbird, Chairman, Kiowa Indian Tribe Regarding Comanche Peak Draft Environmental Impact Statement ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23360A6312023-10-26026 October 2023 FEMA, Submittal of Radiological Emergency Preparedness Final Report for the Comanche Peak Nuclear Power Plant Medical Services Drill Evaluated on August 23, 2023 CP-202300416, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-10-12012 October 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202300432, Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 42023-10-0404 October 2023 Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 4 ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23263A0242023-09-21021 September 2023 Revision of Schedule for the Environmental Review of the Comanche Peak Nuclear Power Plant Units 1 and 2 License Renewal Application 2024-01-31
[Table view] Category: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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Kenneth J. Peters Senior Vice President& Chief Nuclear Officer (Acting)Kenneth.Peters@iuminant.com Luminant Power P0O Box 1002 6322 North FM 56 Glen Rose, TX 76043 Luminant ,2548976565 F 254 897 6652 CP-201600097 TXX-16020 Ref. # 10CFR50.55a(z)(1)
February 15, 2016 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NOS. 50-445 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST 1B3-3 FOR COMANCHE PEAK NUCLEAR POWER PLANT, UNIT 1 (CAC NO. MF6125)1. Letter logged TXX-15056 dated April 20, 2015 from Rafael Flores tO the NRC submitting Relief Request 1B3-3 for Unit 1 Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Cold Leg Weld Inspection Frequency 2. NRC Email dated January 14, 2016 from Balwant Singal of the NRC to Timothy Hope of Luminant Power requesting additional information regarding Relief Request 1B3-3 for Comanche Peak Nuclear Power Plant, Unit 1 (CAC No. MF6125)
Dear Sir or Madam:
Per Reference 1, Luminant Generation Company, LLC (Luminant Power) submitted Unit 1 Relief Request 1B3-3 for application of an alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Cold Leg Weld Inspection Frequency.
Per Reference 2, the NRC provided a request for additional information regarding the subject relief request.The Lumninant Power response to the request for additional information is contained in Enclosure 1.Attachment A to Enclosure 1 contains proprietary information.
Attachment B to Enclosure 1 contains the non-proprietary version of the response.
Enclosure 2 contains the proprietary version of the technical justification supporting Enclosure
- 1. Enclosure 3 contains the non-proprietary version of the technical justification supporting Enclosure
- 1. Enclosure 4 contains the affidavit for withholding proprietary information.
Enclosure 4 contains the Westinghouse authorization letter CAW-16-4376 with accompanying affidavit, Proprietary Information Notice, and Copyright Notice. As Attachment A to Enclosure 1 and Enclosure 2 contain information proprietary to Westinghouse Electric Company LLC, it is supported by an affidavit signed by Westinghouse, the owner of the information.
The affidavit sets forth the basis for which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.390 of the Commission's regulations.
Accordingly, it is respectfully requested that information which is proprietary to Westinghouse be .
U. S. Nuclear Regulatory Commission TXX-1 6020 Page 2 of 2 02/15/2016 withheld from public disclosure in accordance 10 CFR Section 2.390 of the Commission's regulations.
Correspondence with respect to the proprietary aspects of the items listed above or the supporting Westinghouse affidavit should reference CAW-16-4376 and should be addressed to James A. Gresham, Manager, Regulatory Compliance, Westinghouse Electric Company, 1000 Westinghouse Drive, Building 3 Suite 310, Cranberry Township, Pennsylvania 16066.This communication contains no new licensing basis commitments regarding Comanche Peak Unit 1.Should you have any questions, please contact Mr. Jack Hicks at (254) 897-6725.Sincerely, Luminant Generation Company LLC Kenneth J. Pter B:Thorr~s/.
McC/z -Iool Site Vice President (Acting)Enclosure 1 -Westinghouse Letter LTR-PAFM-16-8, Revision 0, Responses to the NRC RAIs Regarding Comanche Peak Unit 1 Extension of Required Inspection Frequency for Reactor Vessel Inlet Nozzle Dissimilar Metal Welds from 7 to 9 Calendar Years, February 12, 2016 Enclosure 2 -Westinghouse Letter LTR-PAFM-16-2-P, Revision 0, Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds, February 2016 Enclosure 3 -Westinghouse Letter LTR-PAFM-16-2-NP, Revision 0, Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds, February 2016 Enclosure 4 -. Westinghouse Letter LTR-CAW-16-4376, Application for Withholding Proprietary Information from Public Disclosure, dated February 10, 2016 c -Marc L. Dapas, Region IV Balwant K. Singal, NIRR Resident Inspectors, Comanche Peak Robert Free, TDLR TXX-1 6020 ENCLOSURE 4
W e in houseWestinghouse Electric Company' 1000 Westinghouse Drive Cranberry Township, Pennsylvania 16066 USA U.S. Nuclear Regulatory Commission Direct tel: (412) 374-4643 Document Control Desk Direct fax: (724) 940-8560 11555 Rockville Pike e-mail: greshaja@westinghouse.com Rockville, MD 20852 CAW-16-4376 February 10, 2016 APPLICATION FOR WrITHHIOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Subject:
- 1) LTR-PAFM-16-2-P, Revision 0, "Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet.Nozzle to Safe End Dissimilar Metal Welds." (Proprietary)
- 2) LTR-PAFM-16-8, Revision 0, Attachment A, "Responses to the NRC RAIs Regarding Comanche Peak Unit 1 Extension of Required Inspection Frequency for Reactor Vessel Inlet Nozzle Dissimilar Metal Welds from 7 to 9 Calendar Years" (Proprietary)
The Application for Withholding Proprietary Information from Public Disclosure is submitted by Westinghouse Electric Company LLC (Westinghouse), pursuant to the provisions of paragraph (b)(1) of Section 2.390 of the Commission's regulations.
It contains commercial strategic information proprietary to Westinghouse and .customarily held in confidence.
The proprietary information for which withholding is being requested in the above-referenced reports is further identified in Affidavit CAW-16-4376 signed by the owner of the proprietary information, Westinghouse Electric Company LLC. The Affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR Section 2.390 of the Commission's regulations.
Accordingly, this letter authorizes the utilization of the accompanying Affidavit by Luminant Generation ComPanY LCC.Corresponden~ce with respect to the proprietary aspects of the Appli~cation for Withholding or the Westinghouse Affidavit should reference CAW-16-4376, and should be addressed to James A. Gresham, Manager, Regulatory Compliance, Westinghouse Electric Company, 1000 Westinghouse Drive, Building 3 Suite 310, Cranberry Township, Pennsylvania 16066.Jamse.r Regulatory Compliance CAW- 16-4376 February 10, 2016 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
SS COUNhTY OF BUTLER:" I, James A. Gresham, am authorized to execute this Affidavit on behalf of Westinghouse Electric Company LLC (Westinghouse), and that the averments of fact set forth in this Affidavit are true and correct to the best of my knowledge, information, and belief.Jaes A. Gresham, Manager Regulatory Compliance 2 2 CAW-16-4376 (1) I am Manager, Regulatory Compliance, Westinghouse Electric Company LLC (Westinghouse), and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rule making proceedings, and am authorized to apply for its withholding on behalf of Westinghouse.
(2) I am~making this Affidavit in conformance With the provisions of 10 CFR Section 2.390 of the Commission's regulations and in conjunction with the Westinghouse Application for Withholding Proprietary Information from Public Disclosure accompanying this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse in designating information as a trade secret, privileged or as confidential commercial or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.390 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.(i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.(ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence.
The application of that system and the substance of that system constitute Westinghouse policy and provide the rational basis required.Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows: (a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of 3 3 ~CAW-1 6-4376 Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.(d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.(f) It contains patentable ideas, for which patent protection may be desirable.(iii) There are sound policy reasons behind the Westinghouse system which include the following: (a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors.
It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.(b) It is information that is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
4 ~CAW-1 6-43 76 (d) Each component of proprietary information pertinent to a particular competitive
- advantage is potentially as valuable as the total competitive advantage.
If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.(e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.(iv) The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.3 90, it is to be receiv~ed in confidence by the Commission.(v) The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.(vi) The proprietary information sought to be *withheld in this submittal is that which is appropriately marked in: 1) LTR-PAFM-1 6-2-P, Revision 0, 'Trechnical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds." (Proprietary)
- 2) LTR-PAFM-16-8, Revision 0, Attachment A, "Responses to the NRC RAIs Regarding Comanche Peak Unit 1 Extension of Required Inspection Frequency for Reactor Vessel Inlet Nozzle Dissimilar Metal Welds from 7 to 9 Calendar Years" (Proprietary) for submittal to the Commission, being transmitted by Luminant Generation Company LCC letter and Application for Withholding Proprietary Information from Public*Disclosure, to the Document Control Desk. The proprietary information as submitted by Westinghouse is that associated with technical justification to support extended 5 5 ~CAW-1 6-43 76 volumetric examination interval for Comanche Peak Unit 1 reactor vessel inlet nozzle to safe end dissimilar metal welds, and may be used only for that purpose.(a) This information is part of that which will enable Westinghouse to provide technical justification to support extended volumetric examination interval for Comanche Peak Unit 1 reactor vessel inlet nozzle to safe end dissimilar metal welds.(b) Further this information has substantial commercial value as follows: (i) Westinghouse plans to sell the use of similar information to its customers for the purpose of providing technical justification to support extended volumetric examination interval for reactor vessel nozzle to safe end dissimilar metal welds.(ii) Westinghouse can sell support and defense of industry guidelines and acceptance criteria for plant-specific applications.(iii) The information requested to be withheld reveals the distinguishing aspects of a methodology which was developed by Westinghouse.
Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar technical evaluation justifications and licensing defense services for. commercial power reactors without commensurate expenses.
Also, public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
The development of the technology described in part by the information is the result of applying the results .of many years of experience in an intensive Westinghouse effort and the expenditure of a considerable sum of money.
6 CAW-1 6-4376 In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended.Further the deponent sayeth not.
PROPRIETARY INFORMATION NOTICE Transmitted herewith are proprietary and non-proprietary versions of documents furnished to the NRC associated with fracture mechanics technical justification to support extended volumetric examination interval for Comanche Peak Unit 1 reactor vessel inlet nozzle to safe end dissimilar metal welds.In order to conform to the requirements of 10 CFR 2.390 of the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets, and where the proprietary information has been deleted in the non-proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted).
The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f)located as a superscript immediately following the brackets enclosing each item Of information being identified as proprietary or in the margin opposite such information.
These lower case letters refer to the types of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through (4)(ii)(f) of the Affidavit accompanying this transmittal pursuant to 10 CFR 2.390(b)(1).
COPYRIGHT NOTICE The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.390 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding.
With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose. Copies made by the NxRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.
Luminant Generation Company Letter for Transmittal to the NRC The following paragraphs should be included in your letter to the NRC Document Control Desk: Enclosed are: 1. LTR-PAFM-1 6-2-P, Revision 0, 'Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds" (Proprietary)
- 2. LTR-PAFM-1 6-2-NP, Revision 0, "Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds" (Non-Proprietary)
- 3. LTR-PAFM-1 6-8, Revision 0, Attachment A, "Responses to the NRC RAIs Regarding Comanche Peak Unit 1 Extension of Required Inspection Frequency for Reactor Vessel Inlet Nozzle Dissimilar Metal Welds from 7 to 9 Calendar Years" (Proprietary)
- 4. LTR-PAFM-1 6-8, Revision 0, Attachment B, "Responses to the NRC RAIs Regarding Comanche Peak Unit 1 Extension of Required Inspection Frequency for Reactor Vessel Inlet Nozzle Dissimilar Metal Welds from 7 to 9 Calendar Years" (Non-Proprietary)
Also enclosed is the Westinghouse Application for Withholding Proprietary Information from Public Disclosure CAW- 16-4376, accompanying Affidavit, Proprietary Information Notice, and Copyright Notice.As Items 1 and 3 contain information proprietary to Westinghouse Electric Company LLC, it is supported by an Affidavit signed by Westinghouse, the owner of the information.
The Affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.390 of the Commission's regulations.
Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.390 of the Commission's regulations.
Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse Affidavit should reference CAW- 16-4376 and should be addressed to James A. Gresham, Manager, Regulatory Compliance, Westinghouse Electric Company, 1000 Westinghouse Drive, Building 3 Suite 310, Cranberry Township, Pennsylvania 16066.