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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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REQUEST FOR CONFIRMATION OF INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION COMANCHE PEAK UNITS 1 & 2 LICENSE RENEWAL APPLICATION REVIEW VISTRA OPERATIONS COMPANY LLC COMANCHE PEAK, UNITS 1, 2 DOCKET NO. 05000445, 05000446 Set #1 RCI 4.7.3-1 Based on the review of the applicants TLAA described in LRA Section 4.7.3, Reactor Coolant Pump Flywheel Fatigue Crack Growth Analysis, and the audit review of the associated documents (e.g., technical specifications), the staff needs confirmation that the analysis assumptions supporting the 20-year inspection interval for the flywheels bounds the operating conditions of the actual flywheels.
Confirm that the 6000 start/stop cycles assumed in the technical basis for the flywheel fatigue crack growth analysis bounds the actual start/stop cycles for the flywheels at the Comanche Peak nuclear power plant.
RCI B.2.3.20-1 As amended by letter dated April 24, 2023 (ML23114A377), LRA Section B.2.3.27, Buried and Underground Piping and Tanks, states [w]hen visual inspections of coating reveals evidence of coating damage, selective leaching inspections will also be performed in accordance with the Selective Leaching Program. In addition, a portion [emphasis added by staff] of inspections will be performed on buried piping/components that are susceptible to selective leaching.
Buried components within the scope of the Selective Leaching program include the following:
(a) gray cast iron valve bodies and fire hydrants; and (b) cement-lined ductile iron piping. The use of the term a portion (italicized by the staff in the above paragraph) lacks specificity with respect to the extent of inspections for buried components susceptible to selective leaching.
Confirm that, as discussed in the audit, a portion is consistent with one sample as defined in the GALL Report. Specifically, confirm that at a minimum, the following one-time inspections will be performed within the five (5) year period prior to entering the period of extended operation:
- The external surface of one buried gray cast iron valve body or one buried gray cast iron fire hydrant.
- The external surfaces of a 10-foot section of buried cement-lined ductile iron piping.
RCI B.2.3.31-1
Background:
10 CFR 54.21(a)(3) requires demonstration that the effects of aging will be adequately managed for structures and components within the scope of license renewal. GALL-LR Report, Revision 2, AMP XI.S3, ASME Section XI, Subsection IWF, Operating Experience program element states that [d]egradation of threaded bolting and fasteners has occurred from boric acid corrosion, SCC, and fatigue loading (NRC IE Bulletin 82-02, NRC Generic Letter 91-17).
GALL-LR Revision 2, AMP XI.M10, Boric Acid Corrosion, Corrective Actions, program element states that [b]orated water leakage and areas of resulting boric acid corrosion are evaluated and corrected in accordance with the applicable provisions of NRC GL 88-05 and the corrective action program. Any detected boric acid crystal buildup or deposits should be cleaned.
During the audit, the NRC staff held discussion with the applicant regarding LRA AMP B.2.3.31, ASME Section XI, Subsection IWF, on the existence of boric acid and management of its aging effects on the reactor vessel (RV) support assemblies. During the audit, the applicant informed the NRC staff that:
- Future IWF inspections of the RV supports will, based on the 1RF22 and 2RF19 inspections, assess the condition of the supports and enter the corrective action process and contact the owner of the Boric Acid Corrosion AMP IF additional boric acid accumulation is identified.
Confirm that:
Future IWF inspections of the RV support assemblies (including bolting) will, based on the 1RF22 and 2RF19 inspections, assess the condition of the supports, enter any deficient conditions into the corrective action process, and IF additional boric acid accumulation is identified, ensure the owner of the Boric Acid Corrosion AMP will perform an evaluation, corrective actions, and cleaning consistent with GALL-LR Report, Revision 2, so that an acceptable level of safety is maintained during the period of extended operation.
RCI B.2.3.31-2
Background:
10 CFR 54.21(a)(3) requires demonstration that the effects of aging will be adequately managed for structures and components within the scope of license renewal. Appendix Quality Assurance for Aging Management Programs, to GALL-LR Report, Revision 2, states that [t]he license renewal applicant must demonstrate that the effects of aging on structures and components (SC) subject to an aging management review (AMR) will be managed in a manner that is consistent with the CLB of the facility for the period of extended operation [] subject to the quality assurance (QA) requirements of Appendix B to 10 CFR Part 50.
Exception to LRA AMP B.2.3.31, ASME Section XI, Subsection IWF, Scope of Program program element states that [t]he ISI Program Plan does not include the requirements for the examination of ASME [] Class MC component supports.
It also states that these are inspected for effects of aging by the ASME Section XI, Subsection IWE (LRA AMP B.2.3.29), and other supports and attachments by Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems (LRA AMP B.2.3.13), and Structures Monitoring (LRA AMP B.2.3.34) AMPs as applicable.
Confirm that:
The effects of aging for the supports and attachments excepted from ASME Section XI, Subsection IWF, are managed in a manner consistent with the CLB of the facility
[CPNPPP],the QA requirements of Appendix B and by the ASME Section XI, Subsection IWE (LRA AMP B.2.3.29) and by the Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems (LRA AMP B.2.3.13) and by the Structures Monitoring (LRA AMP B.2.3.34) AMPs for the period of extended operation as applicable.