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Category:Letter
MONTHYEARIR 05000336/20240032024-11-0707 November 2024 Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001 ML24289A0152024-10-21021 October 2024 Review of the Fall 2023 Steam Generator Tube Inspection Report 05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary2024-10-14014 October 2024 Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary IR 05000336/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000336/2024402 and 05000423/2024402 (Cover Letter Only) ML24281A1102024-10-0707 October 2024 Requalification Program Inspection 05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-09-26026 September 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24248A2272024-09-0404 September 2024 Operator Licensing Examination Approval ML24240A1532024-09-0303 September 2024 Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel IR 05000336/20240052024-08-29029 August 2024 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005 IR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 ML24221A2872024-08-0808 August 2024 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Cask Registration for Spent Fuel Storage IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification ML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 ML24180A0932024-06-28028 June 2024 Readiness for Additional Inspection: EA-23-144 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 IR 05000336/20244402024-06-24024 June 2024 Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only) ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (Redacted Version) ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code 05000336/LER-2024-001, Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications2024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications ML24165A1292024-06-0505 June 2024 ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023 ML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML24110A0562024-05-21021 May 2024 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter) ML24141A2432024-05-20020 May 2024 Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15 ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report 05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation 05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24116A0452024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24103A0202024-04-22022 April 2024 Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits ML24106A2032024-04-15015 April 2024 2023 Annual Environmental Operating Report ML24088A3302024-04-0404 April 2024 Regulatory Audit Plan in Support of License Amendment Request to Implement Framatome Gaia Fuel ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification 2024-09-04
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION I
475 ALLENDALE RD, SUITE 102 KING OF PRUSSIA, PA 19406-1415
May 2, 2023
EA-22-106
Daniel Senior Vice President and Chief Nuclear Officer (CNO)
Dominion Energy, Inc.
Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, VA 23060-6711
SUBJECT: MILLSTONE POWER STATION, UNITS 2 AND 3 - FINAL SIGNIFICANCE DETERMINATION OF GREEN FINDING; INSPECTION REPORT 05000336/20234 03 AND 05000423/2023403
Dear Daniel Stoddard:
This letter provides the final significance determination of the preliminary Greater than Green finding and associated apparent violation identified in U. S. Nuclear Regulatory Commission (NRC) Inspection Report 05000336/2022401 and 05000423/2022401 issued on January 26, 2023, ( ML23026A048) 1. The inspection report, and the finding described therein, concern Security-Related Information in accordance with 10 CFR 2.390(d)(1), and disclosure to unauthorized individuals could present a security vulnerability. Consequently, the inspection report enclosed with the January 26, 2023, letter was not publicly available, and details regarding the nature of the finding, were provided in a non-public enclosure.
In a letter dated March 7, 2023, Douglas Lawrence, Vice President - Nuclear Operations and Fleet Performance, provided a response to the NRC staffs preliminary significance determination. On March 28, 2023, NRC staff participated in a telephone call with Dominion Energy, Inc. (Dominion) staff and requested additional information related to some of the points raised by Dominion in the March 7, 2023, letter. Following that discussion, Dominion submitted the additional information with a letter dated March 31, 2023. Subsequently, on April 10, 2023, NRC staff participated in a telephone call with Dominion staff to obtain further clarification about Dominions March 31, 2023, response. Dominion submitted a response to the NRC staffs question with a letter dated April 18, 2023. The responses submitted by Dominion contained safeguards information and, as such, are non -public and are not maintained in ADAMS.
Enclosure transmitted herewith contains Sensitive, Unclassified, Non-Safeguards Information. When separated from the Enclosure, the transmittal document is decontrolled.
1 Designation in parentheses refers to an Agency-wide Documents Access and Management System (ADAMS) accession number. Documents referenced in this letter are publicly-available using the accession number in ADAMS. After considering the information developed during the inspection and the additional information provided with Dominions letters dated March 31, 2023, and April 18, 2023, the NRC has concluded that the finding is appropriately characterized as green. The NRC has also determined that the finding involved a violation of NRC requirements, which is being treated as a non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy. A description of the finding and associated violation and the basis for the NRCs determination is provided in the non-public enclosure.
The following cross-cutting aspect was assigned to a finding using Inspection Manual Chapter 0310, Aspects Within Cross Cutting Areas: [H.1] - Resources.
If you contest the violation or significance of the NCV, you should provide a response within 30 days of the date of this letter, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555- 0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement; and the NRC resident inspector at Millstone Power Station.
If you disagree with the cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; and the NRC resident inspector at Millstone Power Station.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter will be made available electronically for public inspection in the NRC Public Document Room or in the NRCs Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.g ov/reading-rm/adams.html. However, the material enclosed herewith contains Security-Related Information in accordance with 10 CFR 2.390(d)(1)
and its disclosure to unauthorized individuals could present a security vulnerability. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or in ADAMS, accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. If you choose to respond and Security Related Information is necessary to provide an acceptable response, please mark your entire response Security-Related Information in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response. If you have any questions concerning this matter, please contact Daniel Schroeder at 610- 337-5262 or Daniel.Schroeder@nrc.gov.
Sincerely, Daniel Schroeder Security, Emergency Preparedness and Incident Response Branch Division of Radiological Safety and Security
Docket Nos. 05000356 and 05000423 License No. DPR-65 and NPF-49
Enclosure (non-public):
Descriptio n of finding and violation and basis for NRC conclusion
cc w/o encl: Distribution via LISTSERV
cc w/encl:
J. Semancik, Director, Radiation Division, Bureau of Air Management, CT DEEP F. Newton, Manager, Site Security J. Perno, Security Operations Superintendent D.Stoddard 4
SUBJECT: MILLSTONE POWER STATION, UNITS 2 AND 3-FINAL SIGNIFICANCE DETERMINATION OF GREEN FINDING; INSPECTION REPORT 05000336/2023 403 AND 05000423/2023403 : DATED MAY 2, 2023
Distribution w/o encl; w/o OUO-SRI:
MYoung, DORS EBousquet, DORS, RI NWarnek, DORS DHochmuth, DORS, AA JDeBoer, DORS PZurawski, RI OEDO JBresson, DORS RidsNrrPMMillstone Resource JFuller, DORS, SRI RidsNrrDorlLpl1 Resource KMooney, DORS, RI RidsNsirDso Resource
Distribution w/encl; w/OUO -SRI:
ABowers, NSIR MBrooks, NSIR CPantalo, NSIR JWorosilo, DRS, RII DJohnson, NSIR SOrth, DRS, RIII EWharton, NSIR RKellar, DRS, RIV JRey, NSIR MYoung, DORS FSullivan, NSIR JFuller, DORS, SRI
ADAMS ACCESSION NO. ML23121A115 DOCUMENT NAME: https://usnrc.sharepoint.com/teams/RIDRSPSBSEC/Shared Documents/Allegations & Enforcement/Millstone -
Final significance Determination/PUBLIC Millstone final Green EA-22-106_.docx X SUNSI Review/ MMM X Non-Sensitive X Public Availab Sense n -Publiclyvailab
OFFICE /O /DRSS /DRSS RI/D S /DRSS
ML aughli TEck DCaron MY DSoeder TE / / / / 5 /
OFFIALERD COPY