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Category:Letter
MONTHYEARML24248A2272024-09-0404 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 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) 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 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 IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 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) 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 IR 05000336/20240112024-04-0101 April 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000336/2024011 and 05000423/2024011 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 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 ML24051A1922024-03-0808 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000336/20230062024-02-28028 February 2024 Annual Assessment Letter for Millstone Power Station, Units 2 and 3, (Reports 05000336/2023006 and 05000423/2023006) ML24053A2632024-02-21021 February 2024 Unit 3, and Independent Spent Fuel Storage Installation, Notification Pursuant to 10 CFR 72.212(b)(1) Prior to First Storage of Spent Fuel Under a General License ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage ML24043A0062024-02-15015 February 2024 Request for Withholding Information from Public Disclosure for License Amendment Request to Support Implementation of Framatome Gaia Fuel IR 05000336/20230042024-02-14014 February 2024 Integrated Inspection Report 05000336/2023004 and 05000423/2023004 IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages 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 . 2024-09-04
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Dominion Nuclear Connecticut, Inc.
Millstone Power Station Dominion-Rope Ferry Road Waterford, CT 06385 JUL12 U.S. Nuclear Regulatory Commission Serial No.06-380 Attention: Document Control Desk MPS Lic/BAI, RO Washington, DC 20555-0001 Docket Nos. 50-336 50-423 License Nos. DPR-65 NPF-49 DOMINION NUCLEAR CONNECTICUT. INC.
MILLSTONE POWER STATION UNITS 2 AND 3 NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT Clarification Associated With a Non-Cited Violation 05000423/2006006-04 Dominion Nuclear Connecticut, INC. (DNC) has reviewed the matters identified as Non-Cited Violations (NCV) in the subject inspection report. DNC does not contest the findings documented in the report, however; following the completion of the inspection, additional information related to NCV 05000423/2006006-04 (Failure To Evaluate and Correct Conditions Adverse to Quality Associated with TDAFW Pump) was received from the equipment vendor. DNC believes this information is relevant to the NRC's consideration of the crosscutting implications of the NCV. This matter is further discussed in Attachment 1.
Should you have any questions regarding this matter, please contact Mr. David W. Dodson at (860) 447-1791, extension 2346.
Very truly yours, J.Ala Price Site ice President - Millstone
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Serial No.06-380 Response to NRC PI&R Inspection Report 05000336/2006006 and 05000423/2006006 Page 2 of 2 Attachments: 1 Commitments made in this letter: None.
cc: U.S. Nuclear Regulatory Commission Region I Regional Administrator 475 Allendale Road King of Prussia, PA 19406-1415 Mr. V. Nerses NRC Senior Project Manager Millstone Units 2 and 3 U.S. Nuclear Regulatory Commission, Mail Stop 8 C2 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 U.S. Nuclear Regulatory Commission Director, Office of Enforcement Washington, D.C. 20555-0001 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station
Serial No.06-380 Attachment I Clarification Associated With a Non-Cited Violation 05000423/2006006-04 Millstone Power Station Units 2 and 3 Dominion Nuclear Connecticut, Inc. (DNC)
Serial No.06-380 Attachment 1 Page 1 of 1 Restatement of NCV: - 05000423/2006006-04, Failure To Evaluate and Correct Conditions Adverse to Quality Associated with TDAFW Pump "The inspectors identified a Green NCV of 10 CFR 50, Appendix B, Criterion XVI, "Corrective Actions," for the failure to take effective corrective action to prevent a repeat failure of the Unit 3 turbine-driven auxiliary feedwater (TDAFW) pump. Specifically, following identification and documentation of excessive internal stuffing box wear, which was identified following an overspeed trip event that occurred in April 2005, the licensee failed to fully evaluate this condition which was later documented as a contributing cause to a recurring failure that occurred on January 9, 2006. The licensee entered this condition into their corrective action program as CR-06-00244. Corrective actions for this issue included repacking of the TDAFW pump governor control valve, repair of a cam plate, and plans to conduct a stuffing box repair within three months of the January 2006 pump failure...."
Clarification Prior to the NRC inspection, DNC had completed its investigation (Root Cause Evaluation M-06-00244) and concluded that a contributing cause to the Unit 3 TDAFW pump trip was TDAFW pump governor control valve stuffing box (3MSS*MCV5) wear.
The initial conclusion, that the stuffing box wear was a contributing cause, resulted from an investigation into what was causing packing wear. Since the available documentation indicated that the packing stuffing box was larger than the value specified in the Vendor Technical Manual, it was decided that the worn stuffing box might be contributing to the packing wear.
However, questions regarding the dimensional tolerances of the stuffing box were unresolved and discussions between representatives of DNC and the Vendor were ongoing during the course of the NRC's inspection. Subsequent to the issuance of the NRC inspection report, the TDAFW pump vendor concluded that the Millstone Unit 3 TDAFW pump governor control valve (3MSS*MCV5) stuffing box should have a bonnet bore ID of 1.047" to 1.077" not to exceed 1.100". The bonnet bore was recently checked using calibrated equipment and found to be 1.0715" to 1.0765". These measured dimensions are within the tolerances specified by the vendor.
Because the TDAFW pump governor control valve (3MSS*MCV5) stuffing box bonnet bore ID remained within tolerances specified by the vendor, the stuffing box is acceptable as is. Consequently, the TDAFW pump governor control valve stuffing box (3MSS*MCV5) wear is no longer considered to have been a contributing cause to the Unit 3 TDAFW pump trip of January 9, 2006. The corrective action plan associated with the root cause evaluation has been updated based on this information. A change to the Vendor Technical Manual has also been approved to delete the misleading stuffing box dimensions.
DNC trusts that this clarification will assist the NRC in any future consideration related to this NCV.