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| | issue date = 03/10/2008 | | | issue date = 03/10/2008 |
| | title = Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question SCVB-07-0091 | | | title = Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question SCVB-07-0091 |
| | author name = Bischof G T | | | author name = Bischof G |
| | author affiliation = Dominion Nuclear Connecticut, Inc | | | author affiliation = Dominion Nuclear Connecticut, Inc |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:Dominion Nuclear Connecticut, Inc.\lii!SI'lIlC Power Station R(ITI"!"v Road\\"rclfore!, C:1'065R'iMarch10,2008 07-0846F RO 50-423 NPF-49SerialNo.: | | {{#Wiki_filter:Dominion Nuclear Connecticut, Inc. |
| NLOS/MAE:DocketNo.:LicenseNo.:U.S.NuclearRegulatoryCommissionAttention:DocumentControlDeskOneWhiteFlintNorth11555RockvillePikeRockville,MD20852-2378 DOMINION NUCLEAR CONNECTICUT. | | \lii!SI'lIlC Power Station R()Pl~ ITI"!"v Road |
| INC.MILLSTONE POWERSTATIONUNIT3 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING STRETCH POWERUPRATELICENSE AMENDMENT REQUEST RESPONSE TO QUESTIONSCVB-07-0091DominionNuclearConnecticut,Inc.(DNC)submittedastretchpowerupratelicense amendmentrequest(LAR)forMillstonePowerStationUnit3(MPS3)inlettersdatedJuly13,2007(SerialNos.07-0450and07-0450A),andsupplementedthesubmittalbylettersdatedSeptember12,2007(SerialNo.07-04508),December13,2007(SerialNo.07-0450C)andMarch5,2008(SerialNo.07-0450D).TheNRCstaffforwardedrequestsforadditionalinformation(RAls)inOctober29,2007,November26,2007,December14,2007andDecember20,2007letters.DNCrespondedtotheRAlsinlettersdatedNovember19,2007(SerialNo.07-0751),December17,2007(SerialNo.07-0799),January10,2008(SerialNos.07-0834,07-0834A,07-0834C,and07-0834F),January11,2008(SerialNos.07-08348,07-0834E,07-0834G,and07-0834H),January14,2008(SerialNo.07-0834D),January18,2008(SerialNos.07-0846, 07-0846A, 07-08468,07-0846C,and07-0846D),January31,2008(SerialNo. | | \\ "rclfore!, C:1' 065R'i March 10, 2008 U. S. Nuclear Regulatory Commission Serial No.: 07-0846F Attention: Document Control Desk NLOS/MAE: RO One White Flint North Docket No.: 50-423 11555 Rockville Pike License No.: NPF-49 Rockville, MD 20852-2378 DOMINION NUCLEAR CONNECTICUT. INC. |
| 08341)andFebruary 25,2008(SerialNos.07-0799A,and07-0834J).Ina letter dated January18,2008(SerialNo. | | MILLSTONE POWER STATION UNIT 3 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING STRETCH POWER UPRATE LICENSE AMENDMENT REQUEST RESPONSE TO QUESTION SCVB-07 -0091 Dominion Nuclear Connecticut, Inc. (DNC) submitted a stretch power uprate license amendment request (LAR) for Millstone Power Station Unit 3 (MPS3) in letters dated July 13, 2007 (Serial Nos. 07-0450 and 07-0450A), and supplemented the submittal by letters dated September 12, 2007 (Serial No. 07-04508), December 13, 2007 (Serial No. 07-0450C) and March 5, 2008 (Serial No. 07-0450D). The NRC staff forwarded requests for additional information (RAls) in October 29, 2007, November 26, 2007, December 14, 2007 and December 20, 2007 letters. DNC responded to the RAls in letters dated November 19, 2007 (Serial No. 07-0751), December 17, 2007 (Serial No. |
| 07-0846C), DNC provided a responsetoNRC question SCVB-07-0091.Subsequently,ina conferencecallwiththeNRC staff on February26,2008,DNC informedtheNRC staffofthe intent to supersede the response to question SCVB-07-0091.The superseded response additionally providestheinitial conditionsusedfor stretch power uprateinthe pressurizer compartment analysis.Therevised responsetoRAI Question SCVB-07-0091is providedinthe attachmenttothis letter and supersedes the previous responseinits entirety.TheinformationprovidedbythisletterdoesnotaffecttheconclusionsofthesignificanthazardsconsiderationdiscussionintheDecember13,2007DNCletter(SerialNo. | | 07-0799), January 10, 2008 (Serial Nos. 07-0834, 07-0834A, 07-0834C, and 07-0834F), |
| 0450C). | | January 11, 2008 (Serial Nos. 07-08348, 07-0834E, 07-0834G, and 07-0834H), |
| SerialNo.07
| | January 14, 2008 (Serial No. 07-0834D), January 18, 2008 (Serial Nos. 07-0846, 07-0846A, 07-08468, 07-0846C, and 07-0846D), January 31, 2008 (Serial No. 07-08341) and February 25,2008 (Serial Nos. 07-0799A, and 07-0834J). |
| -0846F Docket No.50-423RAIQues.SCVB-07-0091, SPU Page2of3 Shouldyouhaveany questionsinregardtothis submittal, please contact Ms.MargaretEarleat 804-273-2768. | | In a letter dated January 18, 2008 (Serial No. 07-0846C), DNC provided a response to NRC question SCVB-07-0091. Subsequently, in a conference call with the NRC staff on February 26, 2008, DNC informed the NRC staff of the intent to supersede the response to question SCVB-07-0091. The superseded response additionally provides the initial conditions used for stretch power uprate in the pressurizer compartment analysis. The revised response to RAI Question SCVB-07-0091 is provided in the attachment to this letter and supersedes the previous response in its entirety. |
| Sincerely, Vice President-Nuclear Engineering COMMONWEALTHOFVIRGINIACOUNTYOFHENRICOTheforegoingdocumentwasacknowledgedbeforeme,inandfortheCountyand Commonwealthaforesaid,todaybyGerald T.Bischof,whoisVicePresident-NuclearEngineeringofDominionNuclearConnecticut,Inc.HehasaffirmedbeforemethatheisdulyauthorizedtoexecuteandfiletheforegoingdocumentinbehalfofthatCompany,andthatthestatementsinthedocumentaretruetothebestofhisknowledgeandbelief.Acknowledgedbeforemethis It) of AllrcA , 2008.My Commission EXPires:ffiuzdJ(;.//J.s-.s:NotaryPublic Attachment Commitments madeinthisletter:Nonecc:U.S.Nuclear Regulatory Commission Region I Regional Administrator 475 Allendale RoadKingof Prussia, PA 19406-1415Mr.J.G.Lamb U.S.Nuclear Regulatory Commission One WhiteFlintNorth 11555 Rockville PikeMailStop 0-8B1A Rockville, MD 20852-2738VICKIL.HULL 4 Notary PubUccommonweGlth of V1fglnla 1....1 IMY CommtAIOn Ix""" May al.1010*-- | | The information provided by this letter does not affect the conclusions of the significant hazards consideration discussion in the December 13, 2007 DNC letter (Serial No. 07-0450C). |
| Mr.J.D.Hughey Project Manager U.S.Nuclear Regulatory Commission One WhiteFlintNorth 11555 Rockville PikeMailStop 0-8B3Rockville,MD 20852-2738 NRC Senior Resident Inspector MillstonePowerStation DirectorBureauofAir Management MonitoringandRadiationDivision Department of Environmental Protection79Elm StreetHartford,CT 06106-5127SerialNo.07-0846F DocketNo.50-423RAIQues.SCVB-07-0091, SPUPage3of3 SerialNo.07 | | |
| -0846F Docket No.50-423 ATTACHMENT LICENSE AMENDMENT REQUEST STRETCH POWER UPRATE LICENSE AMENDMENT REQUEST RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RESPONSE TO QUESTION SCVB-07-0091 MILLSTONE POWER STATION UNIT 3 DOMINION NUCLEAR CONNECTICUT, INC. | | Serial No. 07-0846F Docket No. 50-423 RAI Ques. SCVB-07-0091, SPU Page 2 of 3 Should you have any questions in regard to this submittal, please contact Ms. Margaret Earle at 804-273-2768. |
| SerialNo.07-0846FDocketNo.50-423Attachment,Page1of1 Containment and Ventilation Branch NRC Question SCVB-07-0091 Millstone Power Station Unit3(MPS3)FSAR lists the following initial containment conditions selected for the subcompartment analyses: Pressurizer Subcompartment:
| | Sincerely, Vice President - Nuclear Engineering COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Gerald T. Bischof, who is Vice President - Nuclear Engineering of Dominion Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief. |
| Temperature 100 0 F;Air partial pressure 8.9 pounds per square inch absolute (psia);relative humidity 10 percent.Steam Generator and Upper Reactor Cavity Subcompartments: | | Acknowledged before me this It) ~day of AllrcA ,2008. |
| Temperature 120 0 F;air partial pressure 9.0 psia;relative humidity 50 percent.Section 2.6.2 of Attachment 5 of the licensing amendment request (LAR)does not list the initial conditions used for subcompartment analysis.Please provide the initial conditions used for SPU subcompartment analysis.In case any of these conditions deviate from the current licensing bases, provide appropriate justification for the deviation. | | 3~ zdJ(;. // |
| DNC Response Since the Stretch Power Uprate(SPU)Massand Energy releases for the steam generator and reactor cavity subcompartments are boundedbytheMassand Energy releases assumedinthe current analyses,nonew subcompartment analyses were performedforthe steam generator and reactor cavity subcompartments. | | My Commission EXPires:ffiu J .s-.s:~-=:.....L...I<LLtt==-=-- |
| The assumptiononinitial conditions (stated in MPS3 FSAR Section 6.2.1.2.1) remains unchanged.Forthepressurizercompartment,theSPUMassandEnergyreleasesarenotboundedbythecurrentanalyses.Thus,thepressurizer compartment analyseswerere-performed.Sensitivitystudieswereperformedtodeterminethelimitingconditions.Fourcaseswereanalyzed:*80°Fand9.0psia(totalpressure)*100°Fand9.0psia(totalpressure)*100°Fand10.4psia(totalpressure)*100°Fand14.2psia(totalpressure)Allcasesassumedrelativehumidityof10percent.Thesensitivitystudiesboundthecurrentassumedconditions.BasedonthesensitivitystudiesandtheTechnicalSpecificationlowerlimiton containmentpressure,theinitialconditionsassumedforthelimitingcaseare100 OFand10.4psia(totalpressure).}} | | Notary Public Attachment VICKI L. HULL 4 Notary PubUc ~ |
| | Commitments made in this letter: None commonweGlth of V1fglnla 1....1 IMY CommtAIOn Ix""" al. 1010 |
| | * cc: U.S. Nuclear Regulatory Commission Region I |
| | -- May Regional Administrator 475 Allendale Road King of Prussia, PA 19406-1415 Mr. J. G. Lamb U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8B1A Rockville, MD 20852-2738 |
| | |
| | Serial No. 07-0846F Docket No. 50-423 RAI Ques. SCVB-07-0091, SPU Page 3 of 3 Mr. J. D. Hughey Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8B3 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director Bureau of Air Management Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127 |
| | |
| | Serial No. 07-0846F Docket No. 50-423 ATTACHMENT LICENSE AMENDMENT REQUEST STRETCH POWER UPRATE LICENSE AMENDMENT REQUEST RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RESPONSE TO QUESTION SCVB-07-0091 MILLSTONE POWER STATION UNIT 3 DOMINION NUCLEAR CONNECTICUT, INC. |
| | |
| | Serial No. 07-0846F Docket No. 50-423 Attachment, Page 1 of 1 Containment and Ventilation Branch NRC Question SCVB-07-0091 Millstone Power Station Unit 3 (MPS3) FSAR lists the following initial containment conditions selected for the subcompartment analyses: |
| | Pressurizer Subcompartment: Temperature 1000 F; Air partial pressure 8.9 pounds per square inch absolute (psia); relative humidity 10 percent. |
| | Steam Generator and Upper Reactor Cavity Subcompartments: |
| | Temperature 120 0 F; air partial pressure 9.0 psia; relative humidity 50 percent. |
| | Section 2.6.2 of Attachment 5 of the licensing amendment request (LAR) does not list the initial conditions used for subcompartment analysis. |
| | Please provide the initial conditions used for SPU subcompartment analysis. In case any of these conditions deviate from the current licensing bases, provide appropriate justification for the deviation. |
| | DNC Response Since the Stretch Power Uprate (SPU) Mass and Energy releases for the steam generator and reactor cavity subcompartments are bounded by the Mass and Energy releases assumed in the current analyses, no new subcompartment analyses were performed for the steam generator and reactor cavity subcompartments. The assumption on initial conditions (stated in MPS3 FSAR Section 6.2.1.2.1) remains unchanged. |
| | For the pressurizer compartment, the SPU Mass and Energy releases are not bounded by the current analyses. Thus, the pressurizer compartment analyses were re-performed. Sensitivity studies were performed to determine the limiting conditions. Four cases were analyzed: |
| | * 80°F and 9.0 psia (total pressure) |
| | * 100°F and 9.0 psia (total pressure) |
| | * 100°F and 10.4 psia (total pressure) |
| | * 100°F and 14.2 psia (total pressure) |
| | All cases assumed relative humidity of 10 percent. |
| | The sensitivity studies bound the current assumed conditions. Based on the sensitivity studies and the Technical Specification lower limit on containment pressure, the initial conditions assumed for the limiting case are 100 OF and 10.4 psia (total pressure).}} |
Letter Sequence Response to RAI |
|---|
|
Initiation
- Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
|
MONTHYEARML0720002812007-07-13013 July 2007
License Amendment Request - Stretch Power Uprate - Supplemental Information
Project stage: Supplement
ML0720003862007-07-13013 July 2007
License Amendment Request, Stretch Power Uprate
Project stage: Request
ML0726702162007-10-15015 October 2007
Stretch Power Uprate Acceptance Review
Project stage: Acceptance Review
ML0727005452007-10-18018 October 2007
Westinghouse Electric Company LLC Request for Withholding Information from Public Disclosure Regarding Letter (CAW-07-2296), Subject: NEU-07-128 P-Attachment, Millstone Nuclear Power Station Unit 2 Stretch Power Uprate Program Supplemental
Project stage: Withholding Request Acceptance
ML0729601792007-10-29029 October 2007
Request for Additional Information, Stretch Power Uprate Amendment Request
Project stage: RAI
ML0732309762007-11-19019 November 2007
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request
Project stage: Response to RAI
ML0731706652007-11-26026 November 2007
Request for Additional Information on Instrumentation and Controls and Fire Protection Regarding Stretch Power Uprate Amendment Request
Project stage: RAI
ML0734802402007-12-13013 December 2007
Supplemental Information for License Amendment Request Stretch Power Uprate
Project stage: Supplement
ML0733703842007-12-14014 December 2007
Request for Additional Information on the Stretch Power Uprate Amendment Request
Project stage: RAI
ML0732500812007-12-14014 December 2007
Westinghouse Electric Company LLC Request for Withholding Information from Public Disclosure Regarding Letter (CAW-07-2252), Subject: WCAP-16271-P, Millstone Unit 3 Spent Fuel Pool Criticality Safety Analysis, March 2007 (Proprietary), Date
Project stage: Withholding Request Acceptance
ML0735200512007-12-17017 December 2007
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request
Project stage: Response to RAI
ML0801006002008-01-10010 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Questions EEEB-07-0049 Through EEEB-07-0057
Project stage: Response to RAI
ML0801006112008-01-10010 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question CPNB-07-0048
Project stage: Response to RAI
ML0801006042008-01-10010 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question AADB-07-0012
Project stage: Response to RAI
ML0801006062008-01-10010 January 2008
Response to Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Questions SCVB-07-0058 and SCVB-07-0059
Project stage: Response to RAI
ML0805804762008-01-11011 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Questions SRXB-07-0013 Through SRXB-07-0047
Project stage: Response to RAI
ML0801704952008-01-11011 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question EMCB-07-0070
Project stage: Response to RAI
ML0801400772008-01-11011 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request, Response to Questions SBPB-07-0082 Through SBPB-07-0087
Project stage: Response to RAI
ML0801106952008-01-11011 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request, Response to Questions CSGB-07-0010 and CSGB-07-0011
Project stage: Response to RAI
ML0801405702008-01-14014 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Questions EMCB-07-0060 Through EMCB-07-0069 and EMCB-07-0071 Through EMCB-07-0081
Project stage: Response to RAI
ML0802205062008-01-18018 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question EICB-07-0106
Project stage: Response to RAI
ML0802205272008-01-18018 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question SBPB-07-0105
Project stage: Response to RAI
ML0802205302008-01-18018 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Questions SCVB-07-0091 Through SCVB-07-0104
Project stage: Response to RAI
ML0802205412008-01-18018 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Questions SRXB-07-0088 Through SRXB-07-0090
Project stage: Response to RAI
ML0802803752008-01-18018 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request, Response to Question AADB-07-0107
Project stage: Response to RAI
ML0803203082008-01-31031 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question EMCB-07-0070
Project stage: Response to RAI
ML0805603922008-02-25025 February 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request, Supplemental Response to Question EMCB-07-0072
Project stage: Supplement
ML0805606152008-02-25025 February 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Revised and Supplemental Responses to Questions AFPB-07-0007 & AFPB-07-0008
Project stage: Supplement
ML0807103912008-03-10010 March 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question SCVB-07-0091
Project stage: Response to RAI
ML0807103772008-03-10010 March 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question AADB-07-0107
Project stage: Response to RAI
ML0803501322008-03-13013 March 2008
Request for Withholding Information from Public Disclosure Regarding Millstone Power Station, Unit 3
Project stage: Withholding Request Acceptance
ML0808405272008-03-17017 March 2008
Nancy Burton Petition to Intervene and Request for Hearing
Project stage: Request
ML0808508942008-03-25025 March 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Supplemental Response to Question EEEB-07-0052
Project stage: Supplement
ML0808802682008-03-27027 March 2008
Supplemental Information Regarding Stretch Power Uprate License Amendment Request
Project stage: Supplement
ML0804606202008-03-28028 March 2008
Potential Schedule Change for Proposed Stretch Power Uprate License Amendment Request
Project stage: Other
ML0814300142008-04-0404 April 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Supplemental Response to Question EMCB-07-0072
Project stage: Supplement
ML0810800242008-04-23023 April 2008
Request for Additional Information, Stretch Power Uprate Amendment Request
Project stage: RAI
ML0811506792008-04-24024 April 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Supplemental Information, Rod Withdrawal at Power Event
Project stage: Supplement
ML0812006432008-04-29029 April 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Revised Response to Questions EEEB-07-0052, EEEB-07-0054 and EEEB-07-0055
Project stage: Response to RAI
ML0813606252008-05-15015 May 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Revised Response to Follow-ups EEEB-08-0108 Through EEEB08-0113 to Question EEEB-07-0052
Project stage: Response to RAI
ML0814204432008-05-20020 May 2008
Supplemental Information Regarding Stretch Power Uprate License Amendment Request Miscellaneous Updates to the License Amendment Request
Project stage: Supplement
ML0814208242008-05-21021 May 2008
Stretch Power Uprate License Amendment Request Additional Information in Connection with the NRC Audit Held on May 13, 2008 in Rockville, Maryland
Project stage: Request
ML0808704572008-05-29029 May 2008
Draft Environmental Assessment and Finding of No Significant Impact for Proposed Stretch Power Uprate
Project stage: Draft Other
ML0817502222008-06-16016 June 2008
Notice of Appeal
Project stage: Request
ML0819302742008-07-10010 July 2008
Stretch Power Uprate License Amendment Request DNC Comments on Draft Safety Evaluation - Stretch Power Uprate
Project stage: Draft Request
ML0819307572008-07-11011 July 2008
Follow-up to Dominion Nuclear Connecticut, Inc. Letter, Dated July 10, 2008, Regarding the Draft Safety Evaluation - Stretch Power Uprate
Project stage: Draft Approval
ML0819901122008-07-16016 July 2008
Stretch Power Uprate License Amendment Request - Supplement to DNC Comments on Draft Safety Evaluation - Stretch Power Uprate
ML0819300702008-07-30030 July 2008
Final Environmental Assessment and Finding of No Significant Impact for Proposed Stretch Power Uprate
Project stage: Other
ML0816105852008-08-12012 August 2008
License Amendment, Stretch Power Uprate
Project stage: Other
ML0822504182008-08-12012 August 2008
Stretch Power Uprate, Tec Specs to Amd 242
Project stage: Acceptance Review
2008-03-17
[Table View] |
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Category:Letter
MONTHYEARML24030A7522024-01-30030 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
ML23334A2242023-11-30030 November 2023
Request for Exemption from Enhanced Weapons Firearms Background Checks, and Security Event Notifications Implementation
ML23324A4222023-11-20020 November 2023
Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13
ML23324A4302023-11-20020 November 2023
Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15
ML23317A2702023-11-13013 November 2023
Core Operating Limits Report, Cycle 23
IR 05000336/20230032023-11-0606 November 2023
Integrated Inspection Report 05000336/2023003 and 05000423/2023003
ML23298A1652023-10-26026 October 2023
Requalification Program Inspection
IR 05000336/20234202023-10-0404 October 2023
Security Inspection Report 05000336/2023420 and 05000423/2023420
ML23230A0502023-10-0202 October 2023
5 of the Quality Assurance Topical Report - Review of Program Changes
ML23226A0052023-09-26026 September 2023
Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis
IR 05000245/20230012023-09-19019 September 2023
Safstor Inspection Report 05000245/2023001
IR 05000336/20230102023-09-0808 September 2023
Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010
IR 05000336/20230052023-08-31031 August 2023
Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005)
ML23248A2132023-08-30030 August 2023
Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature.
ML23242A0142023-08-30030 August 2023
Operator Licensing Examination Approval
ML23223A0552023-08-18018 August 2023
Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel
ML23223A0482023-08-18018 August 2023
Request for Withholding Information from Public Disclosure for License Amendment Request to Use Framatome Small Break and Realistic Large Break LOCA Evaluation Methodologies for Establishing COLR Limits
IR 05000336/20230022023-08-0909 August 2023
Integrated Inspection Report 05000336/2023002 and 05000423/2023002
ML23188A0432023-07-31031 July 2023
Authorization and Safety Evaluation for Alternative Request No. IR-04-11
ML23208A0922023-07-26026 July 2023
Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response
ML23188A0202023-07-26026 July 2023
Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ML23207A1102023-07-26026 July 2023
NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations
IR 05000336/20234012023-07-17017 July 2023
Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only)
ML23175A0052023-07-12012 July 2023
Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps
ML23193A8562023-06-28028 June 2023
Submittal of Updates to the Final Safety Analysis Reports
ML23178A1682023-06-26026 June 2023
2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46
ML23153A1732023-06-16016 June 2023
Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement
ML23151A0742023-06-12012 June 2023
Review of the Spring 2022 Steam Generator Tube Inspection Report
ML23159A2202023-06-0808 June 2023
Associated Independent Spent Fuel Storage Installation Revision to Emergence Plan - Report of Changes
IR 07200047/20234012023-06-0808 June 2023
NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401
2024-01-04
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Dominion Nuclear Connecticut, Inc.
\lii!SI'lIlC Power Station R()Pl~ ITI"!"v Road
\\ "rclfore!, C:1' 065R'i March 10, 2008 U. S. Nuclear Regulatory Commission Serial No.: 07-0846F Attention: Document Control Desk NLOS/MAE: RO One White Flint North Docket No.: 50-423 11555 Rockville Pike License No.: NPF-49 Rockville, MD 20852-2378 DOMINION NUCLEAR CONNECTICUT. INC.
MILLSTONE POWER STATION UNIT 3 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING STRETCH POWER UPRATE LICENSE AMENDMENT REQUEST RESPONSE TO QUESTION SCVB-07 -0091 Dominion Nuclear Connecticut, Inc. (DNC) submitted a stretch power uprate license amendment request (LAR) for Millstone Power Station Unit 3 (MPS3) in letters dated July 13, 2007 (Serial Nos. 07-0450 and 07-0450A), and supplemented the submittal by letters dated September 12, 2007 (Serial No. 07-04508), December 13, 2007 (Serial No. 07-0450C) and March 5, 2008 (Serial No. 07-0450D). The NRC staff forwarded requests for additional information (RAls) in October 29, 2007, November 26, 2007, December 14, 2007 and December 20, 2007 letters. DNC responded to the RAls in letters dated November 19, 2007 (Serial No. 07-0751), December 17, 2007 (Serial No.
07-0799), January 10, 2008 (Serial Nos. 07-0834, 07-0834A, 07-0834C, and 07-0834F),
January 11, 2008 (Serial Nos. 07-08348, 07-0834E, 07-0834G, and 07-0834H),
January 14, 2008 (Serial No. 07-0834D), January 18, 2008 (Serial Nos. 07-0846, 07-0846A, 07-08468, 07-0846C, and 07-0846D), January 31, 2008 (Serial No. 07-08341) and February 25,2008 (Serial Nos. 07-0799A, and 07-0834J).
In a letter dated January 18, 2008 (Serial No. 07-0846C), DNC provided a response to NRC question SCVB-07-0091. Subsequently, in a conference call with the NRC staff on February 26, 2008, DNC informed the NRC staff of the intent to supersede the response to question SCVB-07-0091. The superseded response additionally provides the initial conditions used for stretch power uprate in the pressurizer compartment analysis. The revised response to RAI Question SCVB-07-0091 is provided in the attachment to this letter and supersedes the previous response in its entirety.
The information provided by this letter does not affect the conclusions of the significant hazards consideration discussion in the December 13, 2007 DNC letter (Serial No. 07-0450C).
Serial No. 07-0846F Docket No. 50-423 RAI Ques. SCVB-07-0091, SPU Page 2 of 3 Should you have any questions in regard to this submittal, please contact Ms. Margaret Earle at 804-273-2768.
Sincerely, Vice President - Nuclear Engineering COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Gerald T. Bischof, who is Vice President - Nuclear Engineering of Dominion Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this It) ~day of AllrcA ,2008.
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My Commission EXPires:ffiu J .s-.s:~-=:.....L...I<LLtt==-=--
Notary Public Attachment VICKI L. HULL 4 Notary PubUc ~
Commitments made in this letter: None commonweGlth of V1fglnla 1....1 IMY CommtAIOn Ix""" al. 1010
- cc: U.S. Nuclear Regulatory Commission Region I
-- May Regional Administrator 475 Allendale Road King of Prussia, PA 19406-1415 Mr. J. G. Lamb U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8B1A Rockville, MD 20852-2738
Serial No. 07-0846F Docket No. 50-423 RAI Ques. SCVB-07-0091, SPU Page 3 of 3 Mr. J. D. Hughey Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8B3 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director Bureau of Air Management Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127
Serial No. 07-0846F Docket No. 50-423 ATTACHMENT LICENSE AMENDMENT REQUEST STRETCH POWER UPRATE LICENSE AMENDMENT REQUEST RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RESPONSE TO QUESTION SCVB-07-0091 MILLSTONE POWER STATION UNIT 3 DOMINION NUCLEAR CONNECTICUT, INC.
Serial No. 07-0846F Docket No. 50-423 Attachment, Page 1 of 1 Containment and Ventilation Branch NRC Question SCVB-07-0091 Millstone Power Station Unit 3 (MPS3) FSAR lists the following initial containment conditions selected for the subcompartment analyses:
Pressurizer Subcompartment: Temperature 1000 F; Air partial pressure 8.9 pounds per square inch absolute (psia); relative humidity 10 percent.
Steam Generator and Upper Reactor Cavity Subcompartments:
Temperature 120 0 F; air partial pressure 9.0 psia; relative humidity 50 percent.
Section 2.6.2 of Attachment 5 of the licensing amendment request (LAR) does not list the initial conditions used for subcompartment analysis.
Please provide the initial conditions used for SPU subcompartment analysis. In case any of these conditions deviate from the current licensing bases, provide appropriate justification for the deviation.
DNC Response Since the Stretch Power Uprate (SPU) Mass and Energy releases for the steam generator and reactor cavity subcompartments are bounded by the Mass and Energy releases assumed in the current analyses, no new subcompartment analyses were performed for the steam generator and reactor cavity subcompartments. The assumption on initial conditions (stated in MPS3 FSAR Section 6.2.1.2.1) remains unchanged.
For the pressurizer compartment, the SPU Mass and Energy releases are not bounded by the current analyses. Thus, the pressurizer compartment analyses were re-performed. Sensitivity studies were performed to determine the limiting conditions. Four cases were analyzed:
- 80°F and 9.0 psia (total pressure)
- 100°F and 9.0 psia (total pressure)
- 100°F and 10.4 psia (total pressure)
- 100°F and 14.2 psia (total pressure)
All cases assumed relative humidity of 10 percent.
The sensitivity studies bound the current assumed conditions. Based on the sensitivity studies and the Technical Specification lower limit on containment pressure, the initial conditions assumed for the limiting case are 100 OF and 10.4 psia (total pressure).
