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Category:Letter
MONTHYEARIR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 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 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code 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) ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report 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 IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation 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) IR 05000336/20244402024-04-25025 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) ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release 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 ML24093A2162024-04-0101 April 2024 Response to Request for Additional Information Regarding License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits IR 05000336/20240112024-04-0101 April 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000336/2024011 and 05000423/2024011 ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification ML24092A0752024-03-28028 March 2024 3R22 Refueling Outage Inservice Inspection (ISI) Owners Activity Report Extension ML24088A2352024-03-26026 March 2024 Decommissioning Funding Status Report ML24086A4802024-03-22022 March 2024 Alternative Request IR-4-14, Proposed Alternative Request to Defer ASME Code Section XI Inservice Inspection Examination for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles ML24086A4762024-03-22022 March 2024 Application for Technical Specification Change to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line-Item Improvement Process ML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) ML24004A1052024-01-0404 January 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010 ML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal ML23352A0202023-12-18018 December 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23334A2242023-11-30030 November 2023 Request for Exemption from Enhanced Weapons Firearms Background Checks, and Security Event Notifications Implementation ML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23317A2702023-11-13013 November 2023 Core Operating Limits Report, Cycle 23 2024-08-06
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 475 ALLENDALE ROAD KING OF PRUSSIA, PENNSYLVANIA 19406-1415 May 9, 2012 Mr. David Sr. Vice President and Chief Nuclear Officer Dominion Resources 500 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT: ASSESSMENT FOLLOW-UP LETTER FOR MILLSTONE POWER STATION UNIT 2 (05000336/2012009)
Dear Mr. Heacock:
On May 1, 2012, the U. S. Nuclear Regulatory Commission (NRC) staff completed its quarterly review of plant performance for Millstone Power Station Unit 2. The NRC reviewed the most recent quarterly performance indicators (PIs) and inspection results. This letter informs you of the NRC's assessment of your facility and its plans for future inspections at your facility. This letter supplements, but does not supersede, the annual assessment letter issued on March 5, 2012 (ADAMS Accession No. ML12061A240). The NRC determined the performance at Millstone Power Station Unit 2 during the most recent quarter was within the Regulatory Response Column of the NRC's Reactor Oversight Process (ROP) Action Matrix, based on one finding originating in the second quarter of 2011 having low to moderate safety significance (White) in the Initiating Events Cornerstone. This finding involved the failure of Millstone Unit 2 personnel to carry out their assigned roles and responsibilities and inadequate reactivity management during main turbine control valve testing, which contributed to an unintended eight percent reactor power transient (88 percent to 96 percent) on February 12, 2011. The details of this finding were documented in NRC Special Inspection Team (SIT) report 05000336/2011008 (ADAMS Accession No. ML111470484).
The SIT concluded that the plant operated within acceptable power limits and no equipment malfunctioned during the power transient. Additionally, prior to leaving the site, the team verified the immediate corrective actions taken by Dominion, which included the removal of the Millstone Unit 2 control room crew involved in the transient from operational duties pending remediation, issuance of a standing order, and temporarily establishing a continuous management presence in the Millstone Unit 2 control room while long term corrective actions were developed.
As a result of our quarterly review of Millstone Power Station Unit 2 performance, we plan to conduct a supplemental inspection using NRC Inspection Procedure 95001, "Inspection for One or Two White Inputs in a Strategic Performance Area," when your staff has notified us of your readiness for this inspection. This inspection procedure is conducted to provide assurance that the root cause and contributing causes of risk significant performance issues are understood, the extent of condition is identified, and the corrective actions are sufficient to prevent recurrence. During a telephone conversation on May 4, 2012, Mr. Stephen Scace, Millstone Site Vice President, informed me that Millstone is completing corrective actions to address the White finding. Since the supplemental inspection has not been completed within the finding's first four calendar year quarters, the finding will remain open and will continue to be an input into the NRC's ROP Action Matrix. As a result, Millstone Power Station Unit 2 will remain in the Regulatory Response Column until a successful supplemental inspection is completed. The NRC's process for held-open findings is described in NRC Inspection Manual Chapter 0305,
"Operating Reactor Assessment Program."
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Please contact Ronald R. Bellamy at (610) 337-5200 with any questions you have regarding this letter.
Sincerely,/RA/
Darrell J. Roberts, Director Division of Reactor Projects Docket No. 50-336 License No. DPR-65
cc w/encl: Distribution via ListServ During a telephone conversation on May 4, 2012, Mr. Stephen Scace, Millstone Site Vice President, informed me that Millstone is completing corrective actions to address the White finding. Since the supplemental inspection has not been completed within the finding's first four calendar year quarters, the finding will remain open and will continue to be an input into the NRC's ROP Action Matrix. As a result, Millstone Power Station Unit 2 will remain in the Regulatory Response Column until a successful supplemental inspection is completed. The NRC's process for held-open findings is described in NRC Inspection Manual Chapter 0305,
"Operating Reactor Assessment Program."
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Please contact Ronald R. Bellamy at (610) 337-5200 with any questions you have regarding this letter.
Sincerely,/RA/ Darrell J. Roberts, Director Division of Reactor Projects Docket No. 50-336 License No. DPR-65 cc w/encl: Distribution via ListServ Distribution: (via email) W. Dean, RA D. Lew, DRA D. Roberts, DRP J. Clifford, DRP C. Miller, DRS P. Wilson, DRS R. Bellamy, DRP T. Setzer, DRP E. Keighley, DRP J. DeBoer, DRP S. Shaffer, DRP, SRI B. Haagensen, RI J. Krafty, DRP, RI C. Kowalyshyn, OA DRS Branch Chiefs (6) N. McNamara, SLO D. Tifft, SLO D. Screnci, PAO, N. Sheehan, PAO ROPassessment Resource RidsNrrDirslpabResource RidsNRRPM Millstone Resource RidsNRRDorlLpl1-2 Resource ROPreportsResource DOCUMENT NAME: G:\DRP\BRANCH5\3-MS\MS 2012 1Q Follow-up Assessment Letter.docx ADAMS ACCESSION NUMBER: ML12130A172 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP RI/DRP NAME TSetzer RPowell RBellamy DRoberts DATE 05/07/12 05/07/12 05/07/12 05/09/12 OFFICIAL RECORD COPY