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| | number = ML072290531 | | | number = ML072290531 |
| | issue date = 08/30/2007 | | | issue date = 08/30/2007 |
| | title = Millstone, Unit 2: Report on Results of Staff Audit of Corrective Actions to Address Generic Letter 2004-02 (TAC No. MC4694) | | | title = Report on Results of Staff Audit of Corrective Actions to Address Generic Letter 2004-02 |
| | author name = Chernoff H K | | | author name = Chernoff H |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLI-2 | | | author affiliation = NRC/NRR/ADRO/DORL/LPLI-2 |
| | addressee name = Christian D A | | | addressee name = Christian D |
| | addressee affiliation = Dominion Nuclear Connecticut, Inc | | | addressee affiliation = Dominion Nuclear Connecticut, Inc |
| | docket = 05000336 | | | docket = 05000336 |
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| =Text= | | =Text= |
| {{#Wiki_filter:August 30, 2007Mr. David A. ChristianSr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc. | | {{#Wiki_filter: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 | | Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| MILLSTONE POWER STATION, UNIT NO. 2: REPORT ON RESULTS OFSTAFF AUDIT OF CORRECTIVE ACTIONS TO ADDRESS GENERIC LETTER 2004-02 (TAC NO. MC4694) | | MILLSTONE POWER STATION, UNIT NO. 2: REPORT ON RESULTS OF STAFF AUDIT OF CORRECTIVE ACTIONS TO ADDRESS GENERIC LETTER 2004-02 (TAC NO. MC4694) |
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| ==Dear Mr. Christian:== | | ==Dear Mr. Christian:== |
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| Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency RecirculationDuring 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 consultationwith 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 actionsand supporting analyses. Also, when made publically available, this audit report will serve as a vehicle to inform other PWR licensees of the NRC staff's technical positions on various aspectsof Generic Safety Issue 191, PWR Sump Performance.The enclosed audit report does not reach a conclusion regarding overall adequacy ofDominion's GL 2004-02 corrective actions. The NRC staff expects that Dominion's 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- 2 -August 15, 2007 (Agencywide Documents Access and Management System AccessionNo. ML071060091). In early CY 2008 NRC staff consideration of Dominion's 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 submittedappropriate licensing documents for its GL 2004-02 corrective actions. The audit team did not evaluate the completeness of the licensee's implementation of GL 2004-02 corrective actions. | | 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. |
| 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 licensee's support during all phases of theaudit 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, ChiefPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No:50-336 | | 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 |
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| | 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 |
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| ==Enclosure:== | | ==Enclosure:== |
| As stated cc w/encls:See next page D. Christian- 2 -August 15, 2007 (Agencywide Documents Access and Management System AccessionNo. ML071060091). In early CY 2008 NRC staff consideration of Dominion's 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 submittedappropriate licensing documents for its GL 2004-02 corrective actions. The audit team did not evaluate the completeness of the licensee's 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 licensee's support during all phases of theaudit 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, ChiefPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No:50-336 | | As stated cc w/encls: See next page |
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| | 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 |
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| ==Enclosure:== | | ==Enclosure:== |
| As stated cc w/encls:See next pageDISTRIBUTION:JGollaMScottRidsNrrDssRidsNrrPMJHugheyRidsNrrPMJLambRidsNrrLAABaxterKManoly AMendiolaAHiserLWhitneyWRulandPackage.: ML072290454 Memo.: ML072290531 Enclosure.: ML07072290550 OFFICELPL1-2/PMLPL1-2/LALPL2-2/LASSIB/BCLPL1-2/BCNAMEJLambABaxterRSolaMScottHChernoff(RBEnnis for)DATE8/17/07 8 /30 /07 8 / 30 /07 8 / 29 /078/30/07OFFICIAL RECORD COPY Millstone Power Station, Unit No. 2 cc: | | 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) |
| Lillian M. Cuoco, EsquireSenior Counsel Dominion Resources Services, Inc.
| | DATE 8/17/07 8 /30 /07 8 / 30 /07 8 / 29 /07 8/30/07 OFFICIAL RECORD COPY |
| Building 475, 5 th FloorRope Ferry Road Waterford, CT 06385Edward L. Wilds, Jr., Ph.D.Director, Division of Radiation Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127Regional Administrator, Region IU.S. Nuclear Regulatory Commission
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| 475 Allendale Road King of Prussia, PA 19406First SelectmenTown of Waterford 15 Rope Ferry Road Waterford, CT 06385Charles Brinkman, DirectorWashington Operations Nuclear Services Westinghouse Electric Company 12300 Twinbrook Pkwy, Suite 330 Rockville, MD 20852Senior Resident InspectorMillstone Power Station c/o U.S. Nuclear Regulatory Commission P.O. Box 513 Niantic, CT 06357Mr. J. Alan PriceSite Vice President Dominion Nuclear Connecticut, Inc.
| | Millstone Power Station, Unit No. 2 cc: |
| Building 475, 5 th FloorRope Ferry Road Waterford, CT 06385Mr. J. W. "Bill" Sheehan Co-Chair NEAC 19 Laurel Crest Drive Waterford, CT 06385Mr. Evan W. WoollacottCo-Chair Nuclear Energy Advisory Council 128 Terry's Plain Road Simsbury, CT 06070Ms. Nancy Burton147 Cross Highway Redding Ridge, CT 00870Mr. Chris L. FunderburkDirector, Nuclear Licensing and Operations Support Dominion Resources Services, Inc.
| | 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. |
| Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711Mr. David W. DodsonLicensing Supervisor Dominion Nuclear Connecticut, 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. |
| Building 475, 5 th FloorRope Ferry Road Waterford, CT 06385Mr. Joseph Roy, Director of Operations Massachusetts Municipal Wholesale Electric Company Moody Street P.O. Box 426 Ludlow, MA 01056}} | | 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}} |
Letter Sequence Other |
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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
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
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
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
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
ML1009804152010-04-0808 April 2010
Draft Millstone GL2004-02 Supplemental Responses to Support Public Teleconference on 4/08
Project stage: Request
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
ML1015305562010-06-0202 June 2010
Mps GL-04-002 Draft RAI Responses/Public Telecon Handouts
Project stage: Request
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
ML1018005132010-07-0101 July 2010
Notice of Forthcoming Public Meeting with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit No. 3 Generic Letter 2004-02 Supplemental Response
Project stage: Meeting
ML1019505052010-07-13013 July 2010
MPS3 RAI 6
Project stage: Request
ML1019502842010-07-14014 July 2010
Notice of Forthcoming Public Teleconference with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit No. 3 Generic Letter 2004-02 Supplemental Response
Project stage: Meeting
ML1020102612010-07-29029 July 2010
Summary of July 13, 2010, Meeting with 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
ML1022201102010-09-14014 September 2010
July 28, 2010, Summary of Teleconference with DNC to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information
Project stage: RAI
ML1026402102010-09-16016 September 2010
Response to Request for Additional Information Regarding Generic Letter 2004-02
Project stage: Request
ML1031202422010-11-0808 November 2010
Notice of Teleconference with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit No. 3 Generic Letter 2004-02 Supplemental Response
Project stage: Meeting
ML1034706502010-12-13013 December 2010
Millstone 3 Draft Response to GL2004-02 RAI No. 6
Project stage: Request
ML1034807622011-01-12012 January 2011
November 8, 2010 Summary of Teleconference W/ DNC to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information
Project stage: RAI
2010-03-26
[Table View] |
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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)
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
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
IR 05000336/20240112024-04-0101 April 2024
Comprehensive Engineering Team Inspection - Inspection Report 05000336/2024011 and 05000423/2024011
ML24092A0752024-03-28028 March 2024
3R22 Refueling Outage Inservice Inspection (ISI) Owners Activity Report Extension
ML24088A2352024-03-26026 March 2024
Decommissioning Funding Status Report
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
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
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
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
2024-08-06
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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
