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Category:Letter
MONTHYEARNL-24-0385, Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator2024-10-31031 October 2024 Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator IR 05000424/20240032024-10-30030 October 2024 – Integrated Inspection Report 05000424/2024003 and 05000425/2024003 NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0386, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information2024-10-28028 October 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information NL-24-0366, Core Operating Limits Report, Cycle 26, Version 12024-10-25025 October 2024 Core Operating Limits Report, Cycle 26, Version 1 ML24297A6482024-10-23023 October 2024 5 to the Updated Final Safety Analysis Report, Technical Specification Bases Changes, Technical Requirements Manual Changes, Summary Report and Revised NRC Commitments Report ML24269A2502024-09-26026 September 2024 Acknowledgement of the Withdrawal of the Requested Exemption and License Amendment Request to Remove Tier 1 and Tier 2* Requirements NL-24-0369, Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements2024-09-25025 September 2024 Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements NL-24-0350, Core Operating Limits Report, Cycle 24, Version 22024-09-25025 September 2024 Core Operating Limits Report, Cycle 24, Version 2 ML24243A0072024-09-10010 September 2024 – Correction of Amendment Nos. 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 ML24102A2642024-09-0909 September 2024 – Exemption Request Regarding Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0013) - 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Report 05200025/2024005 and 05200026/2024005 IR 05000424/20244012024-08-15015 August 2024 4 - Security Baseline Inspection Report 05000424-2024401, 05000425-2024401, 05200025-2024402, and 05200026-2024403 - Cover Letter NL-24-0299, Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information2024-08-14014 August 2024 Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information 05000425/LER-2024-001, Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod2024-08-0909 August 2024 Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod ML24218A1842024-08-0707 August 2024 Examination Report and Cover Letter 05200026/LER-2024-001, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal2024-08-0606 August 2024 Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal ML24212A1442024-08-0101 August 2024 Integrated Inspection Report 05200025/2024002 and 05200026/2024002 IR 05000424/20240022024-07-29029 July 2024 Integrated Inspection Report 05000424/2024002 and 05000425/2024002 IR 05000424/20244042024-07-26026 July 2024 Material Control and Accounting Program Inspection Report 05000424/2024404 and 05000425/2024404 (Cover Letter) NL-24-0282, License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements2024-07-25025 July 2024 License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements NL-24-0126, – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.62024-07-25025 July 2024 – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.6 ML24204A0722024-07-23023 July 2024 Issuance of Amendment No. 225, Regarding LAR to Revise TS 3.7.9 for a one-time Change to Support Nuclear Service Cooling Water Transfer Pump Repairs - Emergency Circumstances NL-24-0286, Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair2024-07-20020 July 2024 Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 ML24191A4562024-07-19019 July 2024 Request for Relief and Alternative Requirements for Squib (Explosively Actuated) Valves First Test Interval ML24194A0342024-07-12012 July 2024 Review of the Refueling Outage 1R24 Steam Generator Tube Inspection Report ML24191A3792024-07-10010 July 2024 – Initial Test Program and Operational Programs Inspection Report 05200026/2024011 NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0087, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks2024-06-21021 June 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use ML24163A0632024-06-12012 June 2024 2024 Licensed Operator Re-qualification Inspection Notification Letter Vogtle, Units 3 & 4 ML24155A1772024-06-0505 June 2024 Regulatory Audit in Support of Review of the LAR to Revise Emergency Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1, Surveillance Requirements NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24094A1402024-05-16016 May 2024 Staff Response to Request for Revision to NRC Staff Assessment of Updated Seismic Hazard Information and Latest Understanding of Seismic Hazards at the Vogtle Plant Site Following the NRC Process for the Ongoing Assessment of Natural Hazard ML24130A2412024-05-13013 May 2024 Integrated Inspection Report 05200025/2024001 and 05200026/2024001 ML24120A1812024-05-13013 May 2024 Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage IR24 Steam Generator Tube Inspection Report – Enclosure 2 ML24101A2112024-05-11011 May 2024 Expedited Issuance of Amendment No. 198 Change to Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 ML24127A2372024-05-0909 May 2024 Initial Test Program and Operational Programs Inspection Report 05200026/2024010 NL-24-0194, Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1)2024-05-0707 May 2024 Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1) ML24120A2832024-04-30030 April 2024 Project Manager Reassignment 2024-09-09
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April 8, 2014 Mr. Roy Linthicum PWR Owners Group Risk Management Chairman 4300 Windfield Road Warrenville, IL 60555
Dear Mr. Linthicum,
The purpose of this letter is to formally request the Pressurized Water Reactor Owners Group (PWROG) to perform peer reviews of the U.S. Nuclear Regulatory Commission (NRC) Level 3 Site Probabilistic Risk Assessment for the Vogtle site (the L3PRA project). The Vogtle site contains two Westinghouse 4-loop PWRs. The L3PRA project involves a Level 3 analysis that addresses internal and external hazards, all plant operating modes, and the risk from both reactors, both spent fuel pools, and dry cask storage. The Quality Assurance Plan developed for this project specifies the need for peer reviews in accordance with the ASME/ANS PRA standards.
We have previously discussed these peer reviews with you in public meetings on June 4, 2013 (ADAMS Accession Number ML13241A127), and January 27, 2014 (ADAMS Accession Number ML14043A364), as well as in several phone calls and e-mail exchanges. The following summarizes our preferences and understanding of the process to be followed in performing the peer reviews.
The NRC prefers to have peer reviews performed at various points throughout the study, as opposed to a single peer review at the end of the project. This preference is because (1) it will allow any needed corrections early and, therefore, minimize the amount of any re-work, and (2) a single comprehensive peer review would be difficult considering the different types of expertise needed to cover the entire scope of the project. It is our understanding that the PWROG has budgeted for four peer reviews this calendar year. As discussed in the meeting on January 27, 2014, we are now anticipating that the L3PRA project schedule will only support the following three peer reviews this calendar year:
- Level 1 internal events, and internal flooding (excluding LERF) for the week of July 21, 2014. This will be a focused scope peer review.
- Level 2 peer review the week September 29, 2014. It is anticipated that this will involve a full scope peer review.
- High winds and other hazards peer review the week of either November 3 or November 10, 2014. This will probably require only a couple of days instead of a full week.
R. Linthicum Again, as discussed on January 27, 2014, instead of a fourth peer review, we would like to work with the PWROG to develop review criteria for two of the areas of the L3PRA project for which no PRA standard (either draft or final) currently exists (i.e., dry cask storage and the spent fuel pool). We would like to have these criteria developed by December 2014.
We are looking for the PWROG to lead each peer review, and therefore, provide the facilitator and produce the peer review report. For each peer review, the NRC will identify one or two experienced PRA analysts (e.g., Regional Senior Reactor Analysts) that will supplement the peer review team to be assembled by the PWROG. As part of documenting our request for each peer review, we will include the specific experience and capabilities of the NRC-proposed reviewers. Please see the enclosure (Table 1) for the official request for the first peer review.
We will provide a similar table for the next peer reviews, as discussed above.
We greatly appreciate the PWROGs support in this effort. The peer review is a critical element in ensuring the technical quality and traceability of the work of the L3PRA project. We look forward to working with the PWROG on these peer reviews and, hopefully, others in the future, so that the entire scope of the NRC L3PRA project is fully peer reviewed. If you have any questions, please do not hesitate to contact Mary Drouin of my staff at (301) 251-7574.
Sincerely,
/RA/
Richard P. Correia, Director Division of Risk Analysis Office of Nuclear Regulatory Research
ML14094A344 OFFICE RES/DRA/PRB RES/DRA/PRAB BC: RES/DRA/PRAB D: RES/DRA NAME M. Drouin A. Kuritzky K. Coyne R. Correia DATE 4/4/14 4/7/14 4/7/14 4/8/14