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| | number = ML090150378 | | | number = ML090150378 |
| | issue date = 01/15/2009 | | | issue date = 01/15/2009 |
| | title = Millstone, Unit 3, Supplemental Response to the NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems | | | title = Supplemental Response to the NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems |
| | author name = Matthews W R | | | author name = Matthews W R |
| | author affiliation = Dominion, Dominion Nuclear Connecticut, Inc | | | author affiliation = Dominion, Dominion Nuclear Connecticut, Inc |
Latest revision as of 07:57, 19 March 2019
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Category:Letter
MONTHYEARML24317A2562024-11-12012 November 2024 Core Operating Limits Report, Gycle 30 IR 05000245/20240012024-11-12012 November 2024 Safstor Inspection Report 05000245/2024001 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 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) ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) 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) 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) 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 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 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 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 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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Dominion Nuclear Connecticut, Inc.';000 Dominion Boulevard, Glen Allen, Virginia 2.\060 Web Address: www.dom.corn January15,2009 U.S.Nuclear Regulatory Commission Attention:
DocumentControlDesk One WhiteFlintNorth11555RockvilleRockville,MD 20852-2738SerialNo.NLOS/GAWDocketNo.LicenseNo.09-010 RO 50-423 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWERSTATIONUNIT3 SUPPLEMENTAL RESPONSETOTHENRC GENERIC LETTER 2008-01, MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING,DECAYHEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMSThisletter supplementsthenine-monthresponseto GenericLetter(GL)2008-01for MillstonePowerStationUnit3(MPS3)thatwasprovidedinDominion Nuclear Connecticut, Inc.(DNC)letterdated October14,2008(ADAMS Accession ML082890266).Specitically,thisletter completes an alternativecourseofactionforrespondingtotheGl.thatwasapprovedinNuclearRegulatory Commission (NRC)letterdatedJuly23,:2008 (ADAMS Accession ML081980640),whichallowedDNCto acquire confirmatorysysteminformationduringtheMPS3fall2008refuelingoutage (3R12).TheDNC nine-monthresponsetotheGLcontaineda descriptionofa technical evaluationofthe EmergencyCoreCoolingSystem(ECCS),ResidualHeatRemovalsystem(RHS),and ContainmentSpray(CS)system,whichwas performedtoassure DNC's capabilitytomaintaingasvoidinglessthanthe amount that challenges operabilityofthesesystems.Thenine-monthreport summarized the corrective actionstobe completedforthegas accumulation managementplans,assuring compliance withdesign,licensingbasesandquality assurancecriteriainSectionsIII,V,XI,XVI,and XVII of AppendixBto10CFRPart50.During3R12which ended on November 24,2008,DNCcompletedtherequiredGL2008-01system walkdownsatMPS3.Subsequently,plannedgas accumulation management improvementswererefinedandthetechnical evaluationwasupdated accordingly.Theballanceofthisletterprovidesadditionalinformationrelativetothe nine-monthresponseforMPS3.Thecorrectiveactionsandthe associated schedule previously discussedinthe nine-monthresponsetotheGLarenotchanged.DNC confirmsthegas accumulation management plans currentlyinplaceatMPS3, augmentedbyplannedcorrectiveactionsdescribedinthe nine-monthletter,arein compliancewithappllicable quality assurancecriteria,designandlicensingbases.
SerialNo.09-010 DocketNo.50-423Page2of3 Walkdowns previously describedinthe nine-monthresponseand scheduledfor3R12arecomplete, exceptforHighPressureSafetyInjection(HPSI)inside containmentpipingfrom penetration(51)tothereactor coolantsystem(RCS)coldlegs.
Furtherreviewof theseHPSIlines determinedflowratesduring surveillance testing were adequatetofullysweepthepiping.Returning systemstoserviceduring3R12 included numerous confirmatory ultrasonictesting(UT) inspectionstoverifypipingwas adequatelyfilled.The correctiveactionprocessisbeingusedto identify improvementstothe system restorationprocesstoensurethe systemsarefull.A corrective actionplanisinplaceas describedbythe nine-monthresponsetotheGL,whichwill improvethefillandvent processes and proceduresandaddress lessonslearnedfrom system restoration deficiencies encounteredduring3R12.Thisplanwillusethe insights gainedfromGL2008-01 evaluations including walkdowns, slope measurement,andUT information obtainedduring3R12.The walkdowns, identificationoflocalvoid locationsfromplannedUT inspections,andplannedsystem enhancementsresultedinthe following modifications implementedduring3R12aswellas Licensee Event Report 2008-004-00,GasVoid Discoveredinthe EmergencyCoreCoolingSystem SuctionLine,dated December19,2008:*New vent valve 3SIL*V817wasinstalledinthe24-inchsuctionline entering the AuxiliaryBuildingfromtherefueling waterstoragetank.*Newventvalve 3SIL*V816wasinstalledinan8-inchline, upstream of Penetration95and3SIL*MV8840intheRHSpumps dischargetohotlegsloops2and4.*Newventvalve3SIH*V791wasinstalledoutsideof containment at Penetration98intheHPSI discharge piping.*Vent valve 3SIH*V993inHPSIcommonsuctionpipingwasrelocatedtothehighpoint.
Please contact Mr.Geoffrey A.Wertzat(804)273-3572ifyouhaveany questions or require additional information.
SerialNo.09-010 Docket No.50-423Page3of3 Sincerely, e..v£t.-I QJ t..ea.William R.Matthews Senior Vice President-Nuclear Operations COMMONWEALTH OF VIRGINIA-VICKIL.HULLNotary Public Commonwealth of Virginia 140542My Commission Expires May31.2010Notary Publiccc:U.S.NuclearRegulatoryCommissionRegionI Regional Administrator 475 Allendale RoadKingofPrussia,PA 19406-1415 Commitmentsmadeinthisletter:None Attachments:
None My Commission Expires: COUNTY OF HENRICO The foregoing document was acknowledgedbeforeme,inandforthe County and Commonwealth aforesaid, today by William R.Matthews,whois Senior Vice President-Nuclear Operations of Dominion Nuclear Connecticut,Inc.Hehas affirmedbeforemethatheisduly authorized to executeandfilethe foregoing document in behalfofthat company,andthatthe statementsinthe documentaretruetothebestofhis knowledgeandbelief.
- W Acknowledged beforemethis/5;;dayof ,2009.NRC SeniorResidentInspector MillstonePowerStationMs.C.J.Sanders NRC Project ManagerU.S.Nuclear Regulatory Commission One WhiteFlintNorthMailStop 08-8311555RockvillePikeRockville,MD 20852-2738