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| {{#Wiki_filter:Domin.on Nuclear Connecticut, Inc.\1 il!-;(, I'L'Power Station'Z\ll'l'!rr)'Road IIlTl.I'd, CT ()(,.3Wi February 25.2008U.S.NuclearRegulatoryCommissionAttention:DocumentControlDeskOneWhiteFlintNorth11555RockvillePikeRockville,MD20852-2378.._, Dominion'SerialNo.:07-0834J NLOS/MAE: R1DocketNo.:50-423LicenseNo.:NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWERSTATIONUNIT3 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING STRETCH POWERUPRATELICENSE AMENDMENT REQUEST SUPPLEMENTAL RESPONSETOQUESTION EMCB-07-0072DominionNuclearConnecticut,Inc.(DNC)submittedastretchpowerupratelicenseamendmentrequest(LAR)forMillstonePowerStationUnit3(MPS3)inlettersdatedJuly13,2007(SerialNos.07-0450and07-0450A),andsupplementedthesubmittalbylettersdatedSeptember12,2007(SerialNo.07-0450B)andDecember13,2007(SerialNo.07-0450C).TheNRC staffforwardedrequestsforadditionalinformation(RAls)inOctober29,2007, November26,2007,December14,2007andDecember20,2007letters.DNCrespondedtotheRAlsinlettersdatedNovember19,2007(SerialNo.07-0751), December 17,2007(SerialNo.07-0799),January10,2008(SerialNos.07-0834,07-0834A,07-0834C,and07-0834F),January11,2008(SerialNos.07-0834B, 07-0834E,07-0834G,and07-0834H),January14,2008(SerialNo. | | {{#Wiki_filter:III~ |
| 07-08340),January18,2008(SerialNos.07-0846,07-0846A,07-0846B,07-0846C, 07-08460),andJanuary 31,2008(SerialNo. | | .. ~, |
| 07-08341).TheresponsetoquestionEMCB-07-0072inDNCletterdatedJanuary14,2008,containedacommitmenttoprovideasummaryoffinalresultsof elastic-plasticanalysisasrequestedintheNRCstaff'squestion.ThesupplementalresponsetoquestionEMCB-07-0072containedintheattachmenttothisletterprovidestherequestedinformation.Theinformationprovidedbythisletterdoesnotaffecttheconclusionsofthe significanthazardsconsiderationdiscussionintheDecember13,2007DNCletter(SerialNo.07-0450C). | | Domin.on Nuclear Connecticut, Inc. |
| SerialNo.07-0834JDocketNo.50-423SPUSupp.RespQues.EMCB-07-0072Page2of3Shouldyouhaveanyquestionsinregardtothissubmittal,pleasecontactMs.MargaretEarleat804-273-2768.
| | \ 1il!-;(,I 'L' Power Station |
| Sincerely, tt;;VicePresident-NuclearEngineering COMMONWEALTHOFVIRGINIACOUNTYOFHENRICOTheforegoingdocumentwasacknowledgedbeforeme,inandfortheCountyandCommonwealthaforesaid,todaybyGeraldT.Bischof,whoisVicePresident-NuclearEngineeringofDominionNuclearConnecticut,Inc.HehasaffirmedbeforemethatheisdulyauthorizedtoexecuteandfiletheforegoingdocumentinbehalfofthatCompany,andthatthestatementsinthe document aretruetothebestofhisknowledgeandbelief.Acknowledgedbeforemethis g5J of liJ.l'S&tt4'u'V, 2008.7 (J My Commission Expires:,'3/,.;)010.r.., Ie 1.2<X.1/LLlK.NotaryPublic Commitmentsmadeinthisletter:None Attachmentcc:U.S.NuclearRegulatoryCommissionRegionI Regional Administrator475AllendaleRoadKingofPrussia,PA19406-1415 Mr.J.G.LambU.S.NuclearRegulatoryCommissionOneWhiteFlintNorth11555RockvillePikeMailStop 0-8B1ARockville,MD20852-2738 VICKI L.HULL Notary PublIc CommotlWeQlth of YIfgInIa 1..a My CommIIIIon | | _, Dominion' |
| .....May 1" 201' SerialNo.07-0834J DocketNo.50-423SPUSupp.RespQues.
| | 'Z\ll'l'! rr)' Road IIlTl. I'd, CT ()(,.3Wi February 25. 2008 U. S. Nuclear Regulatory Commission Serial No.: 07-0834J Attention: Document Control Desk NLOS/MAE: R1 One White Flint North Docket No.: 50-423 11555 Rockville Pike License No.: NPF-49 Rockville, MD 20852-2378 DOMINION NUCLEAR CONNECTICUT, INC. |
| EMCB-07-0072Page3of3Ms.C.J.Sanders Project Manager U.S.Nuclear Regulatory Commission One WhiteFlintNorth11555RockvillePikeMailStop 0-8B3Rockville,MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station DirectorBureauofAir Management MonitoringandRadiationDivision Department of Environmental Protection79Elm StreetHartford,CT 06106-5127 SerialNo.07 | | MILLSTONE POWER STATION UNIT 3 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING STRETCH POWER UPRATE LICENSE AMENDMENT REQUEST SUPPLEMENTAL RESPONSE TO QUESTION EMCB-07-0072 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. |
| -0834J Docket No.50-423 ATTACHMENT LICENSE AMENDMENT REQUEST STRETCH POWER UPRATE LICENSE AMENDMENT REQUEST RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION SUPPLEMENTAL RESPONSE TO QUESTION EMCB-07-0072 MILLSTONEPOWERSTATIONUNIT3 DOMINION NUCLEAR CONNECTICUT, INC. | | 07-0450B) and December 13, 2007 (Serial No. 07-0450C). 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), |
| SerialNo.07-0834JDocketNo.50-423Attachment,Page1of3 Mechanical and Civil Engineering Branch EMCB-07-0072InadditiontoTable2.2.3-3,variouscomponentslistedinTables2.2.2.3-1,2.2.2.5.2.2-1and2.2.2.7.2-2ofLARAttachment5,whichcontainstresssummaries,havefailedtomeettheNB-3222.2primaryplussecondarystressintensityrequirementof3Sm.Attachment5statesthatthesecomponentshavebeenqualifiedbypassingthesimplifiedelastic-plasticanalysisofNB3228.5.a)Provideasummaryoftheevaluationswhichshowsthatthespecialrulesforexceeding3Smasprovidedby(a)through (f)ofsubparagraph3228.5havebeenmet.b)Tables2.2.2.5.2.2-1and2.2.2.7.2-2alsoprovideacceptabilityofcomponents,thatfailedtomeetthe3Smallowable,throughNB-3228.3.DiscussthebasisandshowthatyoumeettherequirementsforusingtheNB-3228.3criteria.Alsoprovideasummaryoftheanalysisresults,whichshowsthattherequirementsofNB-3228.3havebeenmet.
| | 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. 07-0834B, 07-0834E, 07-0834G, and 07-0834H), January 14, 2008 (Serial No. 07-08340), |
| ONCInitialResponse(January14, 2008)Severalsteamgeneratorandpressurizerlocationshavemaximumstressrangesthatexceedthe3SmlimitinNB-3222.2.Mostofthesesectionsmeetthe simplified elastic-plasticanalysiscriteriainNB-3228.3oftheASMEB&PVCode,Section111,1971Editionthroughthesummer1973Addendum(equivalenttoNB-3228.5inlatterCodeEditions).InNB-3228.3therearesixrequirements,(a) through (f),whicharesatisfied.Asummaryshowingthateachoftheserequirementshavebeensatisfiedwillbeprovided.Inaddition,thosesectionsthatexceed3Smandthatwerequalifiedbyfull elastic-plasticanalysiswillalsobesummarizedintheresponseshowingdetailsoftheplasticityanalysis.Documentationofthefinalresultsoftheelastic-plasticanalysisisunderdevelopment.AsummaryoftheresultswillbeprovidedbyFebruary28,2008.
| | January 18, 2008 (Serial Nos. 07-0846, 07-0846A, 07-0846B, 07-0846C, 07-08460), and January 31,2008 (Serial No. 07-08341). |
| ONC Supplemental Response(a&b)Thefollowingsixcriteriawereconsideredinevaluatingthecomponentslistedasnotmeetingthe3S mstresslimit.Eachofthecriteriaislistedfollowedbyabriefdiscussionaboutwhythecriterionwasmetforthosecomponentsinquestion.FatigueanalysisforalloftheaffectedcomponentsproceededaccordingtotheCodewiththeexceptionthattheaffectedstressrangesweremultipliedbytheK efactorcalculatedperNB-3228(b). | | The response to question EMCB-07-0072 in DNC letter dated January 14, 2008, contained a commitment to provide a summary of final results of elastic-plastic analysis as requested in the NRC staff's question. The supplemental response to question EMCB-07-0072 contained in the attachment to this letter provides the requested information. |
| SerialNo.07-0834JDocketNo.50-423Attachment,Page2of3Whilethealternatingstressfailedtomeet38 minitially,itwasshowntomeetthe38 mlimitoncethethermalbendingstresswasremovedandisthereforeacceptable.Inallcases,therequirements(a)through (f),whichrequireasimplifiedplasticanalysis,weremetasdiscussedbelow.
| | 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). |
| NB-3228.3 (a)Therange of primary-plus-secondary membrane plus bendingstressintensity, excluding thermal bending stresses, shall be3S m.Forthecomponentsthatwereevaluatedusingthesimplifiedplasticmethodology,the primary-plus-secondarymembraneplusbendingstressintensityexcludingthermalbendingcomparedtotheallowablelimit(38 m)areshowntobelessthan1.0.Thisrequirementisthereforemetforthecomponentslistedasnotinitiallymeetingthe 38 mlimitwiththermalbendingconsidered. | | |
| NB-3228.3(b)Thevalue of Sausedfor enteringthedesignfatiguecurveis multiplied by the factor K e ,...The K,factorasdefinedforthisrequirementiscalculatedforallstressrangesthatexceedthe3S m limit.SaismultipliedbytheK efactorandthisproductisusedtoenterthedesignfatiguecurve.Thisisdoneforallcomponentswhereasimplifiedelastic-plasticanalysisisperformed. | | Serial No. 07-0834J Docket No. 50-423 SPU Supp. Resp Ques. EMCB-07-0072 Page 2 of 3 Should you have any questions in regard to this submittal, please contact Ms. |
| NB-3228.3(c)Therest ofthefatigue evaluationstaysthesame as required in NB-3222.4, exceptthatthe procedure of NB-3227.6 need notbeused.ThefatigueanalysisforallcomponentsisperformedpertheCode.Where3S misexceeded,thealternatingstress(8 a)usedtoenterthefatiguecurveismultipliedby K,andthefatigueusageforthatcombinationiscalculated.Otherwisetherewasnochangetothemethodologyusedtocalculatethefatigueusagefactorforthe components. | | Margaret Earle at 804-273-2768. |
| NB-3228.3(d)The componentmeetsthethermal ratcheting requirement of NB-3222.5.Thecomponentslistedasapplyingthesimplified elastic-plasticanalysismethodologymeetthisconditioneitherbecausethe componentisnotsubjecttointernalsteadystatepressureloading(blowdownpipe)orbecausethestresshasbeenshowntomeettheCoderequirementsforthermalstressratchet. | | Sincerely, tt;;~c?~-tJ 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. |
| NB-3228.3(e)Thetemperaturedoes not exceed those listedintheabove SerialNo.07-0834JDocketNo.50-423Attachment,Page3of3 table for the various classes ofCodematerials.Sincethemaximumtemperaturesspecifiedinthetableof"m"and"n"parametersforvariousclassesofCodematerials,Item(b)above,is700and800degreesF,andnoneofthesteamgeneratorcomponentsexceed700degreesF,thisrequirementismetforallsteam generator components. | | g5J ~ay of liJ.l'S&tt4'u'V, 2008. |
| NB-3228.3(f)The material shall have a minimum specified yield strength tominimumspecified ultimate strength ratio oflessthan0.80.SteamgeneratormaterialsusedwithintheMillstonesteam generatorshaveaminimumspecifiedyieldstrengthtominimumspecifiedultimatestrengthratiolessthan0.70fortherangeofmaterialsandtemperatures.Thisislessthanthemaximumof0.80requiredbytheCode.Therefore,thisrequirementismetforallofthecomponents considered.}} | | Acknowledged before me this My Commission Expires:,' 7Ia~ 3/, .;)010 . r..X. , |
| | (J Ie 1.2< 1/LLlK. |
| | Notary Public VICKI L. HULL Notary PublIc Commitments made in this letter: None CommotlWeQlth of YIfgInIa 1..a My CommIIIIon . . . . . May 1" 201' Attachment cc: U.S. Nuclear Regulatory Commission Region I 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. 07-0834J Docket No. 50-423 SPU Supp. Resp Ques. EMCB-07-0072 Page 3 of 3 Ms. C. J. Sanders 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. 07-0834J Docket No. 50-423 ATTACHMENT LICENSE AMENDMENT REQUEST STRETCH POWER UPRATE LICENSE AMENDMENT REQUEST RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION SUPPLEMENTAL RESPONSE TO QUESTION EMCB-07-0072 MILLSTONE POWER STATION UNIT 3 DOMINION NUCLEAR CONNECTICUT, INC. |
| | |
| | Serial No. 07-0834J Docket No. 50-423 Attachment, Page 1 of 3 Mechanical and Civil Engineering Branch EMCB-07-0072 In addition to Table 2.2.3-3, various components listed in Tables 2.2.2.3-1, 2.2.2.5.2.2-1 and 2.2.2.7.2-2 of LAR Attachment 5, which contain stress summaries, have failed to meet the NB-3222.2 primary plus secondary stress intensity requirement of 3Sm. Attachment 5 states that these components have been qualified by passing the simplified elastic-plastic analysis of NB 3228.5. |
| | a) Provide a summary of the evaluations which shows that the special rules for exceeding 3Sm as provided by (a) through (f) of subparagraph 3228.5 have been met. |
| | b) Tables 2.2.2.5.2.2-1 and 2.2.2.7.2-2 also provide acceptability of components, that failed to meet the 3Sm allowable, through NB-3228.3. |
| | Discuss the basis and show that you meet the requirements for using the NB-3228.3 criteria. Also provide a summary of the analysis results, which shows that the requirements of NB-3228.3 have been met. |
| | ONC Initial Response (January 14,2008) |
| | Several steam generator and pressurizer locations have maximum stress ranges that exceed the 3Sm limit in NB-3222.2. Most of these sections meet the simplified elastic-plastic analysis criteria in NB-3228.3 of the ASME B&PV Code, Section 111, 1971 Edition through the summer 1973 Addendum (equivalent to NB-3228.5 in latter Code Editions). In NB-3228.3 there are six requirements, (a) through (f), which are satisfied. A summary showing that each of these requirements have been satisfied will be provided. In addition, those sections that exceed 3Sm and that were qualified by full elastic-plastic analysis will also be summarized in the response showing details of the plasticity analysis. |
| | Documentation of the final results of the elastic-plastic analysis is under development. A summary of the results will be provided by February 28, 2008. |
| | ONC Supplemental Response (a & b) The following six criteria were considered in evaluating the components listed as not meeting the 3Sm stress limit. Each of the criteria is listed followed by a brief discussion about why the criterion was met for those components in question. Fatigue analysis for all of the affected components proceeded according to the Code with the exception that the affected stress ranges were multiplied by the Ke factor calculated per NB-3228 (b). |
| | |
| | Serial No. 07-0834J Docket No. 50-423 Attachment, Page 2 of 3 While the alternating stress failed to meet 38 m initially, it was shown to meet the 38 m limit once the thermal bending stress was removed and is therefore acceptable. |
| | In all cases, the requirements (a) through (f), which require a simplified elastic-plastic analysis, were met as discussed below. |
| | NB-3228.3 (a) The range of primary-plus-secondary membrane plus bending stress intensity, excluding thermal bending stresses, shall be ~ 3Sm . |
| | For the components that were evaluated using the simplified elastic-plastic methodology, the primary-plus-secondary membrane plus bending stress intensity excluding thermal bending compared to the allowable limit (38 m) are shown to be less than 1.0. This requirement is therefore met for the components listed as not initially meeting the 38 m limit with thermal bending considered. |
| | NB-3228.3 (b) The value of Sa used for entering the design fatigue curve is multiplied by the factor Ke , ... |
| | The K, factor as defined for this requirement is calculated for all stress ranges that exceed the 3Sm limit. Sa is multiplied by the Ke factor and this product is used to enter the design fatigue curve. This is done for all components where a simplified elastic-plastic analysis is performed. |
| | NB-3228.3 (c) The rest of the fatigue evaluation stays the same as required in NB-3222.4, except that the procedure of NB-3227. 6 need not be used. |
| | The fatigue analysis for all components is performed per the Code. |
| | Where 3Sm is exceeded, the alternating stress (8 a) used to enter the fatigue curve is multiplied by K, and the fatigue usage for that combination is calculated. Otherwise there was no change to the methodology used to calculate the fatigue usage factor for the components. |
| | NB-3228.3 (d) The component meets the thermal ratcheting requirement of NB-3222.5. |
| | The components listed as applying the simplified elastic-plastic analysis methodology meet this condition either because the component is not subject to internal steady state pressure loading (blowdown pipe) or because the stress has been shown to meet the Code requirements for thermal stress ratchet. |
| | NB-3228.3 (e) The temperature does not exceed those listed in the above |
| | |
| | Serial No. 07-0834J Docket No. 50-423 Attachment, Page 3 of 3 table for the various classes of Code materials. |
| | Since the maximum temperatures specified in the table of "m" and "n" parameters for various classes of Code materials, Item (b) above, is 700 and 800 degrees F, and none of the steam generator components exceed 700 degrees F, this requirement is met for all steam generator components. |
| | NB-3228.3 (f) The material shall have a minimum specified yield strength to minimum specified ultimate strength ratio of less than 0.80. |
| | Steam generator materials used within the Millstone steam generators have a minimum specified yield strength to minimum specified ultimate strength ratio less than 0.70 for the range of materials and temperatures. This is less than the maximum of 0.80 required by the Code. Therefore, this requirement is met for all of the components considered.}} |
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Initiation
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- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
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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
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Category:Letter
MONTHYEARML24240A1692024-09-18018 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) 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 ML24162A0882024-06-10010 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 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) 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 ML24141A1502024-05-20020 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 ML24123A2272024-05-0202 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) ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24103A0202024-04-22022 April 2024 Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits ML24106A2032024-04-15015 April 2024 2023 Annual Environmental Operating Report ML24088A3302024-04-0404 April 2024 Regulatory Audit Plan in Support of License Amendment Request to Implement Framatome Gaia Fuel ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification 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 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 2024-09-04
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Domin.on Nuclear Connecticut, Inc.
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'Z\ll'l'! rr)' Road IIlTl. I'd, CT ()(,.3Wi February 25. 2008 U. S. Nuclear Regulatory Commission Serial No.: 07-0834J Attention: Document Control Desk NLOS/MAE: R1 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 SUPPLEMENTAL RESPONSE TO QUESTION EMCB-07-0072 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.
07-0450B) and December 13, 2007 (Serial No. 07-0450C). 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. 07-0834B, 07-0834E, 07-0834G, and 07-0834H), January 14, 2008 (Serial No. 07-08340),
January 18, 2008 (Serial Nos. 07-0846, 07-0846A, 07-0846B, 07-0846C, 07-08460), and January 31,2008 (Serial No. 07-08341).
The response to question EMCB-07-0072 in DNC letter dated January 14, 2008, contained a commitment to provide a summary of final results of elastic-plastic analysis as requested in the NRC staff's question. The supplemental response to question EMCB-07-0072 contained in the attachment to this letter provides the requested information.
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. 07-0834J Docket No. 50-423 SPU Supp. Resp Ques. EMCB-07-0072 Page 2 of 3 Should you have any questions in regard to this submittal, please contact Ms.
Margaret Earle at 804-273-2768.
Sincerely, tt;;~c?~-tJ 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.
g5J ~ay of liJ.l'S&tt4'u'V, 2008.
Acknowledged before me this My Commission Expires:,' 7Ia~ 3/, .;)010 . r..X. ,
(J Ie 1.2< 1/LLlK.
Notary Public VICKI L. HULL Notary PublIc Commitments made in this letter: None CommotlWeQlth of YIfgInIa 1..a My CommIIIIon . . . . . May 1" 201' Attachment cc: U.S. Nuclear Regulatory Commission Region I 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. 07-0834J Docket No. 50-423 SPU Supp. Resp Ques. EMCB-07-0072 Page 3 of 3 Ms. C. J. Sanders 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. 07-0834J Docket No. 50-423 ATTACHMENT LICENSE AMENDMENT REQUEST STRETCH POWER UPRATE LICENSE AMENDMENT REQUEST RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION SUPPLEMENTAL RESPONSE TO QUESTION EMCB-07-0072 MILLSTONE POWER STATION UNIT 3 DOMINION NUCLEAR CONNECTICUT, INC.
Serial No. 07-0834J Docket No. 50-423 Attachment, Page 1 of 3 Mechanical and Civil Engineering Branch EMCB-07-0072 In addition to Table 2.2.3-3, various components listed in Tables 2.2.2.3-1, 2.2.2.5.2.2-1 and 2.2.2.7.2-2 of LAR Attachment 5, which contain stress summaries, have failed to meet the NB-3222.2 primary plus secondary stress intensity requirement of 3Sm. Attachment 5 states that these components have been qualified by passing the simplified elastic-plastic analysis of NB 3228.5.
a) Provide a summary of the evaluations which shows that the special rules for exceeding 3Sm as provided by (a) through (f) of subparagraph 3228.5 have been met.
b) Tables 2.2.2.5.2.2-1 and 2.2.2.7.2-2 also provide acceptability of components, that failed to meet the 3Sm allowable, through NB-3228.3.
Discuss the basis and show that you meet the requirements for using the NB-3228.3 criteria. Also provide a summary of the analysis results, which shows that the requirements of NB-3228.3 have been met.
ONC Initial Response (January 14,2008)
Several steam generator and pressurizer locations have maximum stress ranges that exceed the 3Sm limit in NB-3222.2. Most of these sections meet the simplified elastic-plastic analysis criteria in NB-3228.3 of the ASME B&PV Code, Section 111, 1971 Edition through the summer 1973 Addendum (equivalent to NB-3228.5 in latter Code Editions). In NB-3228.3 there are six requirements, (a) through (f), which are satisfied. A summary showing that each of these requirements have been satisfied will be provided. In addition, those sections that exceed 3Sm and that were qualified by full elastic-plastic analysis will also be summarized in the response showing details of the plasticity analysis.
Documentation of the final results of the elastic-plastic analysis is under development. A summary of the results will be provided by February 28, 2008.
ONC Supplemental Response (a & b) The following six criteria were considered in evaluating the components listed as not meeting the 3Sm stress limit. Each of the criteria is listed followed by a brief discussion about why the criterion was met for those components in question. Fatigue analysis for all of the affected components proceeded according to the Code with the exception that the affected stress ranges were multiplied by the Ke factor calculated per NB-3228 (b).
Serial No. 07-0834J Docket No. 50-423 Attachment, Page 2 of 3 While the alternating stress failed to meet 38 m initially, it was shown to meet the 38 m limit once the thermal bending stress was removed and is therefore acceptable.
In all cases, the requirements (a) through (f), which require a simplified elastic-plastic analysis, were met as discussed below.
NB-3228.3 (a) The range of primary-plus-secondary membrane plus bending stress intensity, excluding thermal bending stresses, shall be ~ 3Sm .
For the components that were evaluated using the simplified elastic-plastic methodology, the primary-plus-secondary membrane plus bending stress intensity excluding thermal bending compared to the allowable limit (38 m) are shown to be less than 1.0. This requirement is therefore met for the components listed as not initially meeting the 38 m limit with thermal bending considered.
NB-3228.3 (b) The value of Sa used for entering the design fatigue curve is multiplied by the factor Ke , ...
The K, factor as defined for this requirement is calculated for all stress ranges that exceed the 3Sm limit. Sa is multiplied by the Ke factor and this product is used to enter the design fatigue curve. This is done for all components where a simplified elastic-plastic analysis is performed.
NB-3228.3 (c) The rest of the fatigue evaluation stays the same as required in NB-3222.4, except that the procedure of NB-3227. 6 need not be used.
The fatigue analysis for all components is performed per the Code.
Where 3Sm is exceeded, the alternating stress (8 a) used to enter the fatigue curve is multiplied by K, and the fatigue usage for that combination is calculated. Otherwise there was no change to the methodology used to calculate the fatigue usage factor for the components.
NB-3228.3 (d) The component meets the thermal ratcheting requirement of NB-3222.5.
The components listed as applying the simplified elastic-plastic analysis methodology meet this condition either because the component is not subject to internal steady state pressure loading (blowdown pipe) or because the stress has been shown to meet the Code requirements for thermal stress ratchet.
NB-3228.3 (e) The temperature does not exceed those listed in the above
Serial No. 07-0834J Docket No. 50-423 Attachment, Page 3 of 3 table for the various classes of Code materials.
Since the maximum temperatures specified in the table of "m" and "n" parameters for various classes of Code materials, Item (b) above, is 700 and 800 degrees F, and none of the steam generator components exceed 700 degrees F, this requirement is met for all steam generator components.
NB-3228.3 (f) The material shall have a minimum specified yield strength to minimum specified ultimate strength ratio of less than 0.80.
Steam generator materials used within the Millstone steam generators have a minimum specified yield strength to minimum specified ultimate strength ratio less than 0.70 for the range of materials and temperatures. This is less than the maximum of 0.80 required by the Code. Therefore, this requirement is met for all of the components considered.