Letter Sequence RAI |
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MONTHYEARCP-201201212, Spent Fuel Pool Criticality Analysis2012-10-0909 October 2012 Spent Fuel Pool Criticality Analysis Project stage: Request CP-201300257, License Amendment Request (LAR) 13-01, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage, 4.3, Fuel Storage, and 5.5 Programs & Manuals.2013-03-28028 March 2013 License Amendment Request (LAR) 13-01, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage, 4.3, Fuel Storage, and 5.5 Programs & Manuals. Project stage: Request CP-201300826, Supplemental Information Supporting LAR 13-01, Spent Pool Criticality Analysis2013-07-16016 July 2013 Supplemental Information Supporting LAR 13-01, Spent Pool Criticality Analysis Project stage: Supplement ML13253A0052013-09-11011 September 2013 Acceptance Review Following Supplement, Amendment Request to Revise TS 3.7.16, Fuel Storage Pool Boron Concentration, TS 3.7.17, Spent Fuel Assembly Storage, and TS 5.5, Programs and Manuals Project stage: Acceptance Review ML13253A0062013-09-26026 September 2013 Request for Withholding Information from Public Disclosure, 3/18/13 Affidavit Executed by J. Gresham, Westinghouse Regarding WCAP-17728-P, Revision 0 Project stage: Withholding Request Acceptance CP-201301215, License Amendment Request (LAR) 13-01 Supplement Spent Fuel Pool Criticality Analysis Removal Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage, 4.3..2013-10-22022 October 2013 License Amendment Request (LAR) 13-01 Supplement Spent Fuel Pool Criticality Analysis Removal Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage, 4.3.. Project stage: Supplement ML13309A0272013-10-31031 October 2013 WCAP-17728-NP, Rev. 1, Comanche Peak Nuclear Power Plant Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis Project stage: Other ML13301A6452013-11-0505 November 2013 Redacted, Request for Additional Information, Amendment Request to Revise TS 3.7.16, Fuel Storage Pool Boron Concentration, TS 3.7.17, Spent Fuel Assembly Storage, and TS 5.5, Programs and Manuals Project stage: RAI ML13317B7032013-11-19019 November 2013 Non-proprietary, Request for Additional Information Round 2, Amendment Request to Revise TS 3.7.16, Fuel Storage Pool Boron Concentration, TS 3.7.17, Spent Fuel Assembly Storage, and TS 5.5, Programs and Manuals Project stage: RAI CP-201301332, License Amendment Request (LAR) 13-01 Supplement Spent Fuel Pool Criticality Analysis Removal Technical Specifications 3.7.17, Spent Fuel Assembly Storage,4.3, Fuel Storage, and 5.5 Programs and Manuals2013-11-26026 November 2013 License Amendment Request (LAR) 13-01 Supplement Spent Fuel Pool Criticality Analysis Removal Technical Specifications 3.7.17, Spent Fuel Assembly Storage,4.3, Fuel Storage, and 5.5 Programs and Manuals Project stage: Supplement ML14016A1242013-12-17017 December 2013 License Amendment Request (LAR) 13-01 Spent Fuel Pool Criticality Analysis, Response to Requests for Additional Information Round 2 Project stage: Response to RAI CP-201301411, Response to Requests for Additional Information Round 2, on License Amendment Request (LAR) 13-01 Spent Fuel Pool Criticality Analysis,2013-12-17017 December 2013 Response to Requests for Additional Information Round 2, on License Amendment Request (LAR) 13-01 Spent Fuel Pool Criticality Analysis, Project stage: Response to RAI ML14027A7052013-12-17017 December 2013 Comanche Peak Responses to LAR 13-01 Request for Additional Information (RAI) - Round 2 Project stage: Request ML14015A5472014-01-15015 January 2014 NRR E-mail Capture - Request for Additional Information - License Amendment Request 13-01 to Revise Technical Specifications 3.7.16, 3.7.17, 4.3 and 5.5 - TACs MF1365 and MF1366 Project stage: RAI CP-201400074, License Amendment Request (LAR) 13-01 Spent Fuel Pool Criticality Analysis, Response to Request for Additional Information2014-01-16016 January 2014 License Amendment Request (LAR) 13-01 Spent Fuel Pool Criticality Analysis, Response to Request for Additional Information Project stage: Response to RAI ML14007A0392014-02-0606 February 2014 Request for Withholding Information from Public Disclosure - 11/22/13 Affidavit Executed by J. Gresham, Westinghouse Responses to 11/5/13 NRC Requests for Additional Information Project stage: RAI ML14058A0892014-02-27027 February 2014 Request for Additional Information Round 3, Amendment Request to Revise TS 3.7.16, Fuel Storage Pool Boron Concentration, TS 3.7.17, Spent Fuel Assembly Storage, and TS 5.5, Programs and Manuals Project stage: RAI ML13318A0292014-03-19019 March 2014 Request for Withholding Information from Public Disclosure, 10/14/13 Affidavit Executed by J. Gresham, Westinghouse Regarding WCAP-17728-P, Revision 1 Project stage: Withholding Request Acceptance ML14022A0462014-03-19019 March 2014 Request for Withholding Proprietary Information from Public Disclosure Project stage: Other ML14097A5132014-04-0707 April 2014 NRR E-mail Capture - Request for Additional Information - License Amendment Request for Spent Fuel Pool Criticality Analysis - TACs MF1365 and MF1366 Project stage: RAI CP-201400503, Response to Requests for Additional Information on License Amendment Request 13-01 Spent Fuel Pool Criticality Analysis2014-04-17017 April 2014 Response to Requests for Additional Information on License Amendment Request 13-01 Spent Fuel Pool Criticality Analysis Project stage: Response to RAI CP-201400619, License Amendment Request (LAR) 13.01, Spent Fuel Pool Criticality Analysis, Supplemental Information to Requests for Additional Information2014-05-0101 May 2014 License Amendment Request (LAR) 13.01, Spent Fuel Pool Criticality Analysis, Supplemental Information to Requests for Additional Information Project stage: Supplement ML14150A1382014-06-30030 June 2014 Request for Withholding Information from Public Disclosure - 7/12/13 Affidavit Executed by B. Maurer, Westinghouse; Supplemental Information Supporting Amendment Request Question 1, 2, and 4 (TAC MF1365-MF1366) Project stage: Withholding Request Acceptance ML14150A1422014-06-30030 June 2014 Request for Withholding Information from Public Disclosure - 4/17/14 Affidavit Executed by J. Gresham, Westinghouse; Responses to Request for Additional Information SFP Configuration Interfaces (TAC MF1365-MF1366) Project stage: RAI ML14160A0352014-07-0101 July 2014 Redacted, Issuance of Amendment No. 162, Revise TS 3.7.16, Fuel Storage Pool Boron Concentration, TS 3.7.17, Spent Fuel Assembly Storage, and TS 5.5, Programs and Manuals Project stage: Approval 2013-09-26
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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:Request for Additional Information (RAI)
MONTHYEARML24019A0742024-01-19019 January 2024 NRR E-mail Capture - Comanche Peak - Draft Request for Additional Information - License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator ML24018A1072024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000445/2024012 and 05000446/2024012) and Request for Information ML23256A1502023-09-11011 September 2023 Request for Additional Information Requests - Comanche Peak - Set 4 ML23256A1492023-09-11011 September 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 4 ML23213A2162023-08-0202 August 2023 Vistra Operations Company, LLC Notification of License Renewal Inspection and Request for Information ML23188A0452023-07-0707 July 2023 Request for Additional Information Requests - Comanche Peak - Set 3 ML23188A0442023-07-0707 July 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 3 ML23181A0212023-06-29029 June 2023 Request for Additional Information Requests - Comanche Peak - Set 2 ML23181A0202023-06-29029 June 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 2 ML23167A0222023-06-14014 June 2023 Email: Request for Additional Information (RAI) Letter for the Review of the Comanche Peak Initial License Renewal Application, Set 1 ML23167A0232023-06-14014 June 2023 Request for Additional Information (RAI) for the Review of the Comanche Peak Initial License Renewal Application (Lra), Set 1 ML23145A2322023-05-25025 May 2023 LRA - Request for Confirmation of Information - Set 2 ML23143A1372023-05-23023 May 2023 LRA - Request for Confirmation of Information - Set 1 ML23132A2542023-05-23023 May 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action LAR to Adopt 10 CFR 50.69,Risk-Informed Categorization & Treatment of Structures,Systems & Components for Nuclear Power Reactors EPID L-2023-LLA-0057 ML23068A0562023-05-0909 May 2023 Request for Additional Information - Comanche Peak License Renewal Application Environmental Review ML23068A0732023-04-13013 April 2023 Requests for Confirmation of Information for the Environmental Review of the Comanche Peak Nuclear Power Plant, Units 1 and 2, Licensed Renewal Application (EPID Number: L-2022-LNE-0004) (Docket Numbers 50-445 and 50-446) ML23103A4682023-04-11011 April 2023 NRR E-mail Capture - Comanche Peak Request for Additional Information - License Amendment Request to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model ML23086B9852023-03-27027 March 2023 NRR E-mail Capture - Comanche Peak Draft Request for Additional Information - Request to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model ML23010A1442023-01-0909 January 2023 Inservice Inspection Request for Information ML22325A2742022-11-21021 November 2022 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Proposed Alternative P-1 Regarding IST of Safeguards Building Sump Pumps ML22318A3102022-11-10010 November 2022 NRR E-mail Capture - Comanche Peak - Draft Request for Additional Information - Proposed Alternative P-1 Regarding IST of Safeguards Building Sump Pumps ML22230B1092022-08-17017 August 2022 NRR E-mail Capture - Comanche Peak Unit 2 - Request for Additional Information - 2RE19 Inspection Summary Report for Steam Generator Tubing ML22220A1942022-08-0808 August 2022 NRR E-mail Capture - Comanche Peak Unit 2 - Draft Request for Additional Information - 2RE19 Inspection Summary Report for Steam Generator Tubing ML22179A3032022-06-28028 June 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000445/2022401; 05000446/2022401 ML22083A0262022-03-23023 March 2022 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Request to Adopt TSTF 505 Revision 2 ML21286A7912021-10-13013 October 2021 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Request to Adopt TSTF-577 Revision 1 ML21253A2242021-09-0909 September 2021 Request for Information Occupational Radiation Safety Inspection (71124.01, 71124.02, and 71151) from 10/18-22/2021 ML21253A2332021-09-0909 September 2021 Request for Information: Comanche Peak Nuclear Power Plant, Units 1 and 2 (05000445 and 05000446); Occupation Radiation Safety (71124.01, 71124.02, 7511) ML21245A3072021-09-0202 September 2021 Request for Information ML21245A307 ML21166A3382021-06-22022 June 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action LAR to Adopt TSTF-505, Rev. 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML21165A1022021-06-13013 June 2021 Pi&R; Request for Information ML21103A3982021-04-13013 April 2021 CP Security Inspection Information Request 2021403 ML20225A0932020-08-12012 August 2020 Notification of Inspection 05000445/2020004 and 05000446/2020004 and Request for Information ML20105A1072020-04-13013 April 2020 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Exigent Amendment Request for One Time Change to Unit 2 Steam Generator Inspection Frequency ML20104A0022020-04-11011 April 2020 NRR E-mail Capture - Comanche Peak Unit 2 - Request for Additional Information - Proposed Alternative to ASME OM Code for Deferral of Snubber Testing (SNB-1) and Visual Examinations (SNB-2) ML20045E3512020-02-13013 February 2020 Information Request February 13, 2020 Notification of Inspection and Request for Information Comanche Peak Unit 2 NRC Inspection Report 05000446/2020002 ML19346B3812019-12-11011 December 2019 NRR E-mail Capture - Comanche Peak RAIs - Quality Assurance Program Reduction in Commitment ML19319A5432019-11-14014 November 2019 NRR E-mail Capture - Draft Comanche Peak RAIs - Quality Assurance Program Reduction in Commitment ML19058A3592019-02-27027 February 2019 NRR E-mail Capture - Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 - Final Request for Additional Information Concerning License Amendment Request to Revise the Emergency Plan IR 05000445/20170072018-02-0808 February 2018 Notification of Nrc Design Bases Assurance Inspection (Programs) (05000445/2017007 and 05000446/2017007) ML17276B8622017-10-0303 October 2017 Notification of NRC Design Bases Assurance Inspection (Programs)(05000445/2017007 and 05000446/2017007) and Initial Request for Information ML17087A2032017-03-28028 March 2017 NRR E-mail Capture - Comanche Peak, Unit 2 - Final Request for Additional Information Regarding Request No. 2B3-1 ML17066A2372017-03-0707 March 2017 Notification of NRC Triennial Fire Protection Baseline Inspection (05000445/2017008 and 05000446/2017008) and Request for Information ML17048A4172017-02-17017 February 2017 Notification of NRC Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/ Staffing/Multi-Unit Dose Assessment... ML16034A1962016-02-0808 February 2016 Independent Spent Fuel Storage Installation - Request for Additional Information, Application for Order Approving Transfer of Facility Operating Licenses and Conforming Amendment 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 ML15345A0112015-12-16016 December 2015 Request for Additional Information, License Amendment Request, Revise Emergency Action Levels Based on Nuclear Energy Institute (NEI) 99-01, Revision 6 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 ML15317A1482015-11-13013 November 2015 Request for Additional Information Email, Relief Request No. B-9 for Reactor Pressure Vessel Outlet Nozzle Safe End to Piping Welds, Second 10-year Inservice Inspection Interval ML15317A1502015-11-13013 November 2015 Request for Additional Information Email, Relief Request No. B-3 for Reactor Coolant System Pipe to Pipe Flange Weld, Second 10-year Inservice Inspection Interval 2024-01-19
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OffiCIAL USI! ONLY PROPRIETARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555.()001 November S, 2013 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
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING REVISION TO TECHNICAL SPECIFICATIONS 3.7.16, "FUEL STORAGE POOL BORON CONCENTRATION," 3.7.17, "SPENT FUEL ASSEMBLY STORAGE," 4.3, "FUEL STORAGE," AND "5.5, "PROGRAMS AND MANUALS" (TAC NOS.
MF1365 AND MF1366)
Dear Mr. Flores:
By letter dated March 28, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML130950023), as supplemented by letter dated July 16, 2013 (ADAMS Accession No. ML13205A056), Luminant Generation Company LLC (the licensee) submitted a license amendment request for revision to the Facility Operating License Nos. NPF-87 and NPF-89 for Comanche Peak Nuclear Power Plant (CPNPP), Units 1 and 2, respectively. The amendment also seeks revision of the CPNPP, Units 1 and 2, Technical Specifications based on an updated criticality analysis methodology for the spent fuel pool.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your application and determined that additional information is required in order to complete its review. A draft copy of the enclosed request for additional information (RAI) was provided to Mr. Jimmy Seawright of your staff via e-mail on October 9, 2013. He informed the NRC on October 22, 2013, that a conference call to discuss the RAis is not needed and agreed to provide the RAI responses within 30 days from the date of this letter. Enclosure 1 to this letter is the proprietary version of the RAis and Enclosure 2 is a non-proprietary version of the RAis.
Please note that the NRC staff is developing an additional set of RAis which will be provided in separate letter. transmitted herewith contains Proprietary information. When separated from , this document is decontrolled.
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION R. Flores If you have any questions, please contact me at 301-415-3016 or balwant.singal@nrc.gov.
Sincerely,
~--t~~~
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosures:
- 1. RAI (proprietary)
- 2. RAI (non-proprietary) cc w/Encl 2: Distribution via Listserv OFFICIAL USE ONLY PROPRIETARY INfORMATION
ENCLOSURE 2 (NON-PROPRIETARY)
REQUEST FOR ADDITIONAL INFORMATION REGARDING REVISION TO TECHNICAL SPECIFICATIONS 3.7.16, "FUEL STORAGE POOL BORON CONCENTRATION." 3.7.17, "SPENT FUEL ASSEMBLY STORAGE," 4.3. "FUEL STORAGE."
AND "5.5. "PROGRAMS AND MANUALS" LUMINANT GENERATION COMPANY LLC COMANCHE PEAK NUCLEAR POWER PLANT. UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446
O~FICIAI.. USE ONlY PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL INFORMATION REGARDING REVISION TO TECHNICAL SPECIFICATION$ 3.7. 16. YFUEL $TO~GE POOL BORON CONCENTAATION." 3.7.17, ~SPENT FUEL ASSEMBLY STORAGE." 4.3. MFUEL STORAGE."
AND "5.5. "PROGRAMS AND MANUALS" LUMINANT GENERATION COMPANY LLC COMANCHE PEAK NUCLEAR POWER PLANT. UNIT$ 1 AND 2 DOCKET NOS. 50-445 AND 50-446 By letter dated March 28, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML130950023), as supplemented by letter dated July 16, 2013 (ADAMS Accession No. Ml13205A056), Luminant Generation Company LLC (the licensee) submitted a Hcense amendment request for revision to the FaciHty Operating License Nos. NPF-87 and NPF-89 for Comanche Peak Nuclear Power Plant (CPNPP), Units 1 and 2, respectively (CPNPP). The amendment also seeks revision of the CPNPP, Units 1 and 2, Technical Specifications based on an updated criticality analysis methodology for the spent fuel pool.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the Information provided in your application and determined that the following additional information is required in order to complete its review.
- 1. In Enclosure 1 to TXX-13045, Section 4, it states that UCPNPP will establish a Boral coupon surveillance program." The NRC staff would like clarifiCation of this statement including:
- a. Please discuss when the program will be established and Implemented.
- b. Please discuss whether there are any other previous surveillance results and, if so, provide a summary of them.
- 2. As part of the criticality analysis, WCAP-17728-P, blisters were evaluated. The WCAP states that at a ([ ]) the racks would maintain their functionality. The NRC staff has also reviewed the Boral coupon surveillance program and the monitoring program for the blisters is not apparent. Please discuss whether the program will monitor blisters and trend any blister formation or increase in blister size.
Also, if they are being monitored, please discuss the acceptance aiteria for the height of the blisters.
- 3. In proposed TS 5.5.22 (in Attachment 2 to TXX-13045 on page 18/18 and Attachment 4 to TXX-13045 on page 17/18), the thickness criteria for the Boral coupons is: "An increase in thickness at any point is greater than 25% of the initial thickness at that point.* The NRC staff would like clarification of this statement including:
OFFICIAl. YSE ONlY PROPRIETARY INFORMATION
OFFICIAl USE OHlY PROPRIETARY INFORMATION
- a. Please discuss whether the initial coupon thicknesses are at least 25 percent less than the thickness listed in the criticality analysis.
- b. Please define what is meant by thickness. Does this Include the thickness/height of the blister?
- c. Please justify why the 25 percent increase in thickness is acceptable.
- 4. In Enclosure 1 to TXX-13045, Section 4, there is discussion about having enough coupons to cover the current operating license and license renewal. The spent fuel pool, however, will be inservice beyond the operating license and be used when the reactor is defueled. In this case, the spent fuel pool, and thereby the Bora!, will still be inservice past the operating and license renewal period. Please discuss whether there will be enough coupons to monitor the Boral until the end of the spent fuel pool life (when the spent fuel pool is permanently defueled).
- 5. Please discuss whether the racks and coupons are vented. If so, discuss whether the coupon wnts are representative of the rack vents.
- 6. In Attachment 3 to TXX-13045 on page 9118, the proposed TS bases, B 3.7.16, Background, states "The neutron absorber material Boral is credited for the storage of spent fuel assemblies within Region 1 racks to maintain K..r less than or equal to 1.0 at 0 ppm [parts per million) soluble boron concentration." The NRC staff needs clarification on this statement including:
- a. Please discuss whether or not the Boral material is credited in the borated case.
This information is not mentioned in the background.
- b. Please clarify why it is necessary to *maintain 1<.1 less than or equal to 1.0" when the regulations state that K..r in the non-borated case should be less than 1.0.
There is no provision for Ken to be equal to 1.0.
- 1. Please confirm that in Attachment 6 to TXX-13045 on page 8/8 in Table 9.1-4 that the second and third column title should be U1 Discharged and U2 Discharged, respectively.
- 8. Please confirm that on [(
n.
- 9. Please confirm that [( ]) is the nominal areal density and that
(( JJ is the minimum certified areal density.
OFF&CIAl USE ONLY PROPRtETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION A. Flores If you have any questions, please contact me at 301-415-3016 or balwant.singal@nrc.gov.
Sincerely, IRA/
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
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PUBLIC RidsNrrPMComanchePeak Resource LPLIV r/f RidsNrrLAJBurkhardt Resource RidsAcrsAcnw_MaiiCTR Resource RidsRgn4MaiiCenter Resource RidsNrrDorllpl4 Resource EWong, NRR/DEIESGB RidsNrrDeEsgb Resource OFFICE ADAMS A ccess1on Nos.: p ropnetary ML13297A162 Non- Propne . tary Ml13301A645 NRR/DORULPL4/PM NRRIDORULPL4/PM NRR/DORULPL4/LA NAME MBartlett BSingal JBurkhardt DATE 10/30/13 10/31/13 10/29/13 OFFICE NRR/DEIESGB/BC NRRIDORULPL4/BC NRRIDORULPL4/PM NAME GKulesa* MMarkley BSingal DATE 10/9/13 11/5/13 11/5/13 OFFICIAL RECORD COPY OFFICIAL USE ONLY PROPRIETARY INFORMATION