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MONTHYEARML0603801882006-02-0909 February 2006 RAI Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors (Tac MC4694) Project stage: RAI ML0722905312007-08-30030 August 2007 Report on Results of Staff Audit of Corrective Actions to Address Generic Letter 2004-02 Project stage: Other ML0722905502007-08-30030 August 2007 GSI-191, Generic Letter 2004-02 Corrective Actions Audit Report Project stage: Acceptance Review ML0729706052007-10-24024 October 2007 Exigent License Amendment Request Re Alternative Containment Analysis Methodology Supporting Information - Gothic Model Input Files Project stage: Other ML0731905532007-11-15015 November 2007 North Anna, Units 1 and 2, and Surry, Units 1& 2, Request for Extension of Completion Dates for Corrective Actions Regarding NRC Generic Letter 2004-02 Project stage: Request ML0734505942007-12-13013 December 2007 Approval of Extension of Completion Dates for Corrective Actions of Generic Letter 2004-02 Project stage: Other ML0806503142008-02-29029 February 2008 Kewaunee, NRC Generic Letter 2004-02 Supplemental Response, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0806505622008-02-29029 February 2008 Supplemental Response to NRC GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0806505632008-02-29029 February 2008 Supplemental Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0814306122008-05-22022 May 2008 Units 1 & 2 - NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors Request for Interim. Project stage: Request ML0814905722008-05-29029 May 2008 Request for Extension of Completion Dates for Generic Letter 2004-02 Corrective Actions Project stage: Other ML0818302472008-07-0101 July 2008 Request for Extension of Completion Dates for Generic Letter 2004-02 Corrective Actions Project stage: Other ML0832304692008-12-17017 December 2008 Request for Additional Information, GL 2004-02 Project stage: RAI ML1000700682010-02-0404 February 2010 Request for Additional Information Regarding Generic Letter 2004-02 Project stage: RAI ML1003314992010-03-0101 March 2010 Notice of Conference Call with Dominion Nuclear Connecticut, Inc., to Discuss Millstone Power Station, Unit Nos. 2 and 3 Generic Letter 2004-02 Supplemental Responses Project stage: Other ML1008204222010-03-26026 March 2010 Notice of Conference Call with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit Nos 2 and 3 Generic Letter 2004-02 Supplemental Responses Project stage: Other ML1011705752010-05-0505 May 2010 Summary of Teleconference with DNC to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI ML1012506232010-05-24024 May 2010 Summary of Meeting with Dominion Nuclear Connecticut, Inc. (DNC) to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI ML1013700502010-05-25025 May 2010 Forthcoming Conference Call with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit Nos. 2 and 3 Generic Letter 2004-02 Supplemental Responses Project stage: Other ML1015906482010-06-30030 June 2010 Summary of Meeting with Dominion Nuclear Connecticut, Inc., (DNC) to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI ML1021404372010-08-10010 August 2010 Generic Letter 2004-02 Supplemental Response Project stage: Other 2008-05-29
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Category:Letter
MONTHYEARIR 05000245/20240012024-11-12012 November 2024 Safstor Inspection Report 05000245/2024001 ML24317A2562024-11-12012 November 2024 Core Operating Limits Report, Gycle 30 IR 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 ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification 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) ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 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 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 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 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 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 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 2024-09-04
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August 30, 2007 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 2: REPORT ON RESULTS OF STAFF AUDIT OF CORRECTIVE ACTIONS TO ADDRESS GENERIC LETTER 2004-02 (TAC NO. MC4694)
Dear Mr. Christian:
Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, requested that all pressurized-water reactor (PWR) licensees (1) evaluate the adequacy of the emergency sump recirculation function with respect to potentially adverse effects associated with post-accident debris, and (2) implement any plant modifications determined to be necessary. Dominion Nuclear Connecticut, Inc. (Dominion), the licensee, has conducted an evaluation of recirculation sump performance for Millstone Power Station, Unit No. 2 (Millstone Unit 2). Dominion has installed new sump strainers in Millstone Unit 2.
Consistent with the discussion in the Reasons for Information Request section of GL 2004-02, the Nuclear Regulatory Commission (NRC) staff is using sample audits to help verify that addressees have resolved the concerns identified in the GL. The staff has conducted a detailed audit of the new sump strainer design and associated analyses and testing for Millstone Unit 2.
The NRC previously forwarded the draft report to Dominion, and Dominion, after consultation with its contractors and vendors for GL 2004-02 corrective actions, has confirmed that there is no proprietary information contained in the audit report.
The enclosed audit report provides Dominion feedback on its GL 2004-02 corrective actions and supporting analyses. Also, when made publically available, this audit report will serve as a vehicle to inform other PWR licensees of the NRC staffs technical positions on various aspects of Generic Safety Issue 191, PWR Sump Performance.
The enclosed audit report does not reach a conclusion regarding overall adequacy of Dominions GL 2004-02 corrective actions. The NRC staff expects that Dominions end-of-calendar year (CY) 2007 GL 2004-02 supplemental response will respond to the open items in the enclosed audit report. This expectation has been stated in public meetings with licensees and at the audit exit meeting for the Millstone Unit 2 audit. It is reinforced in a GL 2004-02 supplemental response content guide that the NRC staff released on
D. Christian August 15, 2007 (Agencywide Documents Access and Management System Accession No. ML071060091). In early CY 2008 NRC staff consideration of Dominions end-of-CY 2007 GL 2004-02 supplemental response (including its response to audit open items) will result in a letter to Dominion assessing the overall adequacy of the Millstone Unit 2 GL 2004-02 corrective actions.
The audit team did not evaluate whether the licensee has identified and/or submitted appropriate licensing documents for its GL 2004-02 corrective actions. The audit team did not evaluate the completeness of the licensees implementation of GL 2004-02 corrective actions.
That is within the scope of the Reactor Oversight Program under Test Instruction 2515/166, Pressurized Water Reactor Containment Sump Blockage.
In conclusion, the NRC staff is appreciative of the licensees support during all phases of the audit and the assistance to the NRC staff of the Dominion GSI-191 Audit designated single point-of-contact during the preparation, conduct, and documentation phases of the audit. The staff also thanks Dominion for providing appropriate office space and facilitating the emergency core cooling system pump rooms tour taken by the audit team members.
If you have any questions, please contact John Hughey, Project Manager, at (301) 415-3204.
Sincerely,
/ra/ (RBEnnis for)
Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No: 50-336
Enclosure:
As stated cc w/encls: See next page
D. Christian August 15, 2007 (Agencywide Documents Access and Management System Accession No. ML071060091). In early CY 2008 NRC staff consideration of Dominions end-of-CY 2007 GL 2004-02 supplemental response (including its response to audit open items) will result in a letter to Dominion assessing the overall adequacy of the Millstone Unit 2 GL 2004-02 corrective actions.
The audit team did not evaluate whether the licensee has identified and/or submitted appropriate licensing documents for its GL 2004-02 corrective actions. The audit team did not evaluate the completeness of the licensees implementation of GL 2004-02 corrective actions.
That is within the scope of the Reactor Oversight Program under Test Instruction 2515/166, Pressurized Water Reactor Containment Sump Blockage.
In conclusion, the NRC staff is appreciative of the licensees support during all phases of the audit and the assistance to the NRC staff of the Dominion GSI-191 Audit designated single point-of-contact during the preparation, conduct, and documentation phases of the audit. The staff also thanks Dominion for providing appropriate office space and facilitating the emergency core cooling system pump rooms tour taken by the audit team members.
If you have any questions, please contact John Hughey, Project Manager, at (301) 415-3204.
Sincerely,
/ra/ (RBEnnis for)
Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No: 50-336
Enclosure:
As stated cc w/encls: See next page DISTRIBUTION: JGolla MScott RidsNrrDss RidsNrrPMJHughey RidsNrrPMJLamb RidsNrrLAABaxter KManoly AMendiola AHiser LWhitney WRuland Package.: ML072290454 Memo.: ML072290531 Enclosure.: ML07072290550 OFFICE LPL1-2/PM LPL1-2/LA LPL2-2/LA SSIB/BC LPL1-2/BC NAME JLamb ABaxter RSola MScott HChernoff (RBEnnis for)
DATE 8/17/07 8 /30 /07 8 / 30 /07 8 / 29 /07 8/30/07 OFFICIAL RECORD COPY
Millstone Power Station, Unit No. 2 cc:
Lillian M. Cuoco, Esquire Mr. J. W. "Bill" Sheehan Senior Counsel Co-Chair NEAC Dominion Resources Services, Inc. 19 Laurel Crest Drive Building 475, 5th Floor Waterford, CT 06385 Rope Ferry Road Waterford, CT 06385 Mr. Evan W. Woollacott Co-Chair Edward L. Wilds, Jr., Ph.D. Nuclear Energy Advisory Council Director, Division of Radiation 128 Terry's Plain Road Department of Environmental Protection Simsbury, CT 06070 79 Elm Street Hartford, CT 06106-5127 Ms. Nancy Burton 147 Cross Highway Regional Administrator, Region I Redding Ridge, CT 00870 U.S. Nuclear Regulatory Commission 475 Allendale Road Mr. Chris L. Funderburk King of Prussia, PA 19406 Director, Nuclear Licensing and Operations Support First Selectmen Dominion Resources Services, Inc.
Town of Waterford Innsbrook Technical Center 15 Rope Ferry Road 5000 Dominion Boulevard Waterford, CT 06385 Glen Allen, VA 23060-6711 Charles Brinkman, Director Mr. David W. Dodson Washington Operations Nuclear Services Licensing Supervisor Westinghouse Electric Company Dominion Nuclear Connecticut, Inc.
12300 Twinbrook Pkwy, Suite 330 Building 475, 5th Floor Rockville, MD 20852 Rope Ferry Road Waterford, CT 06385 Senior Resident Inspector Millstone Power Station Mr. Joseph Roy, c/o U.S. Nuclear Regulatory Commission Director of Operations P.O. Box 513 Massachusetts Municipal Wholesale Niantic, CT 06357 Electric Company Moody Street Mr. J. Alan Price P.O. Box 426 Site Vice President Ludlow, MA 01056 Dominion Nuclear Connecticut, Inc.
Building 475, 5th Floor Rope Ferry Road Waterford, CT 06385