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MONTHYEARML0629101222006-10-17017 October 2006 Alternative Request IR-2-47, Use of Weld Overlays as an Alternative Repair Technique Project stage: Request ML0706006972007-03-0101 March 2007 Revised Actions for the Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds Project stage: Request ML0708103302007-03-27027 March 2007 Confirmatory Action Letter - Millstone Power Station, Unit 3 Project stage: Other ML0709603552007-03-30030 March 2007 Supplemental Information Regarding Request IR-2-47 for Use of Weld Overlays as an Alternative Repair Technique Project stage: Request ML0720600632007-07-13013 July 2007 Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds, Results of Inspections and Response to Request for Additional Information Regarding Completion of the Full Structural Weld Overlays Project stage: Response to RAI ML0721800102007-08-14014 August 2007 Closure of Confirmatory Action Letter NRR-07-020 Project stage: Other 2007-03-27
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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) ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (Redacted Version) ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) 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 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 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) 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) 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 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 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 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 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) 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 2024-09-04
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August 14, 2007 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION UNIT 3 - CLOSURE OF CONFIRMATORY ACTION LETTER NRR-07-020 (TAC NO. MD4162)
Dear Mr. Christian:
On March 27, 2007, the U.S. Nuclear Regulatory Commission (NRC) issued Confirmatory Action Letter (CAL) No. NRR-07-020 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML070810330) regarding dissimilar metal welds in the pressurizer at Millstone Power Station Unit 3 (MPS3). This letter acknowledges receipt of your letter dated July 13, 2007 (ADAMS Accession No. ML072060063), informing the NRC of actions taken in response to this CAL.
In your letter, you stated Dominion Nuclear Connecticut, Inc. has completed the application of full structural weld overlays (WOLs) on the pressurizer surge, spray, safety, and relief nozzle-to-safe end welds containing Alloy 82/182 material at MPS3. The spray nozzle was repaired by WOL in fall 2005 and the remaining nozzles were completed during refueling outage 11 (RFO 3R11). In support of the structural WOL project during RFO 3R11 at MPS3, Performance Demonstration Initiative examinations of five pressurizer nozzle structural WOLs were performed.
Based on your letter, the NRC has found that all the commitments listed in the CAL and supporting commitment letter (ADAMS Accession No. ML070600697) have been met. No further response is required regarding the CAL. We consider the CAL closed. As such, it is no longer necessary to implement enhanced inspection and leakage monitoring requirements for the reactor coolant system. This completes NRC staff action for TAC No. MD4162.
Thank you for informing us of the actions documented in your letter. These actions may be examined during a future NRC inspection of your facility.
Current NRC guidance regarding CALs is contained in the NRC Enforcement Policy and the NRC Enforcement Manual, which are available at the NRC web site at http://www.nrc.gov/about-nrc/regulatory/enforcement.html (click on Enforcement Policy or Enforcement Guidance), or by contacting the Government Printing Office (GPO) toll-free at 1-888-293-6498. The GPO is open from 7:00 a.m. to 9:00 p.m. EST, Monday through Friday (except Federal holidays).
D. Christian In accordance with Title 10 of the Code of Federal Regulations, Part 2, Section 2.390 of the NRC's "Rules of Practice," a copy of this letter will be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system, ADAMS, accessible from the NRC Web site at http://www.nrc.gov/reading-rm.html.
Sincerely,
/ra/
Catherine Haney, Director Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423 cc: See next page
ML072180010 OFFICE DCI/CPNB LPL1-2/PM LPL1-2/LA LPL1-2/BC NAME TLupold JHughey CSola HChernoff DATE 8/14/07 8/7/07 8/7/07 8/16/07 OFFICE DCI/D DRP/D, RGN1 DORL/D NAME MEvans DLew (via e-mail) CHaney DATE 8/16/07 8/14/07 8/14/07 Millstone Power Station, Unit No. 3 cc:
Lillilan M. Cuoco, Esquire Ms. Nancy Burton Senior Counsel 147 Cross Highway Dominion Resources Services, Inc. Redding Ridge, CT 00870 Building 475, 5th Floor Rope Ferry Road Mr. Joseph Roy, Waterford, CT 06385 Director of Operations Massachusetts Municipal Wholesale Edward L. Wilds, Jr., Ph.D. Electric Company Director, Division of Radiation Moody Street Department of Environmental Protection P.O. Box 426 79 Elm Street Ludlow, MA 01056 Hartford, CT 06106-5127 Mr. J. Alan Price Regional Administrator, Region I Site Vice President U.S. Nuclear Regulatory Commission Dominion Nuclear Connecticut, Inc.
475 Allendale Road Building 475, 5th Floor King of Prussia, PA 19406 Rope Ferry Road Waterford, CT 06385 First Selectmen Town of Waterford Mr. Chris Funderburk 15 Rope Ferry Road Director, Nuclear Licensing and Waterford, CT 06385 Operations Support Dominion Resources Services, Inc.
Mr. J. W. "Bill" Sheehan 5000 Dominion Boulevard Co-Chair NEAC Glen Allen, VA 23060-6711 19 Laurel Crest Drive Waterford, CT 06385 Mr. David W. Dodson Licensing Supervisor Mr. Evan W. Woollacott Dominion Nuclear Connecticut, Inc.
Co-Chair Building 475, 5th Floor Nuclear Energy Advisory Council Rope Ferry Road 128 Terry's Plain Road Waterford, CT 06385 Simsbury, CT 06070 Senior Resident Inspector Millstone Power Station c/o U.S. Nuclear Regulatory Commission P. O. Box 513 Niantic, CT 06357