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| | number = ML17037C477 | | | number = ML17037C477 |
| | issue date = 11/15/1974 | | | issue date = 11/15/1974 |
| | title = Nine Mile Point, Unit 1 - Letter Enclosing Supplement No. 1 to the Safety Evaluation Report for the Application for a Full-Term Operating License | | | title = Letter Enclosing Supplement No. 1 to the Safety Evaluation Report for the Application for a Full-Term Operating License |
| | author name = Lear G | | | author name = Lear G |
| | author affiliation = US Atomic Energy Commission (AEC) | | | author affiliation = US Atomic Energy Commission (AEC) |
| | addressee name = Raymond P D | | | addressee name = Raymond P |
| | addressee affiliation = Niagara Mohawk Power Corp | | | addressee affiliation = Niagara Mohawk Power Corp |
| | docket = 05000220 | | | docket = 05000220 |
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| {{#Wiki_filter:DocketNo.50-220Gentlemen:full-tennoperatinglicenseforUnit1ofyourNineMilePointpriginalSignedNovember15,1974DISTRIBUTION:AECPDRDMullerLocalPDRKRGollerDocketTJCarterORBi/3RdgOIS(5copies)HJMcAlduffRBrodsky.NiagaraMohawkPowerCorporationSHanauerCStephens(2copies)ATTN:Mr.,PhilipD.RaymondAGiambussoCJDeBevecVicePresident-EngineeringFSchroederSATeets300ErieBoulevardHestRBoyd(4copies)NDubeSyracuse,NewYork13202DKnuth(2copies)'Jones(2cps)RMaccary(2copies)CLongRTedesco(2copies)RVollmerHDenton(2copies)RSchemelTheDirectorateofLicensinghasissuedtheenclosedSupplementVBenaroyaBGrimesNo.1totheSafetyEvaluationReportonyourapplicationforaGLainasSPawlickiTIppolitoJKastnerNuclearStation.SVargaJOsloondSincerely,RO(8)TEnglehardtGeorgeLear,ChiefOperatingReactorsBranch83DirectorateofLicensing | | {{#Wiki_filter:November 15, 1974 DISTRIBUTION: |
| | AEC PDR DMuller Docket No. 50-220 Local PDR KRGoller Docket TJCarter ORBi/3 Rdg OIS (5 copies) |
| | HJMcAlduff RBrodsky |
| | .Niagara Mohawk Power Corporation SHanauer CStephens (2 copies) |
| | ATTN: Mr., Philip D. Raymond AGiambusso CJDeBevec Vice President Engineering FSchroeder SATeets 300 Erie Boulevard Hest RBoyd (4 copies) NDube Syracuse, New York 13202 DKnuth (2 copies) 'Jones (2 cps) |
| | RMaccary (2 copies) CLong Gentlemen: RTedesco (2 copies) RVollmer HDenton (2 copies) RSchemel The Directorate of Licensing has issued the enclosed Supplement VBenaroya BGrimes No. 1 to the Safety Evaluation Report on your application for a GLainas SPawlicki full-tenn operating license for Unit 1 of your Nine Mile Point TIppolito JKastner Nuclear Station. SVarga JOsloond Sincerely, RO (8) |
| | TEnglehardt priginal Signed George Lear, Chief Operating Reactors Branch 83 Directorate of Licensing |
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| ==Enclosure:== | | ==Enclosure:== |
| SupplementNo.1toSafetyEvaluationReportcc:Seenextpage@p~-EEEATTACHEDFOROGCCONCURRENCEOF-11//74ORB./(3..EATR.k4.....1/./+/Z4,....OPPICN~SVRHAMN~DATC~POFmhEC.318(ROT.9.f3)hECM0240LAD./ORa...............c4PH:.....WKRGoller...........wWE>.dy....................oaaz3................................CJDeBayec,........GLear.+....................llL....).5.'......D.4.....11L...)$'......../.2.4..11/................../.74.................................4V,S,OOVNRHMNNTPlllNTINOOPPICNI1S74SRSlSS ILf1cdl4)<<41'If,f Niagara:fohawkPowerCorporation-2-November15,1974cc:w/enclosureHr.ArvinE.Upton,EsquireLe3oeuf,Lamb,Leiby6tfacRae1757NStreet,N.U.Washington,D.C.20036Hr.RobertP.Jones,SupervisorTownofScribaR.D.04Oswego,NewYork13126HissJuanitaIersey,LibrarianOswegoCityLibrary120E.SecondStreetOmmgo,NewYork13126Dr.Vill%amE.SeymourStaffCoordinatorNewYorkStateAtomicEnergyCouncilNewYorkStateDepartmentofCommerce99TfashingtonStreetAlbany,NewYork12210OPRICE5H'VRHAMC~OATR+PormhEC518(ReT.9.55)hXCM02400V2OOVCRHMCHTPRIHTIHOOfRICCIIOTA02IIIel 1,k4hyk')f1IIeQj'I
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| SUPPLEMENTNO.1TOTHESAFETYEVALUATIONREPORTBYTHEDIRECTORATEOFLICENSINGU.S.ATOMICENERGYCO~QHSSIONINTHEMATTEROFNIAGARAMOMtKPOWERCORPORATIONCONVERSIONFROMPROVISIONALOPERATINGLICENSETOFULL-TERMOPERATINGLICENSENINEMILEPOINTUNIT1DOCKETNO.50-220NOVEMBER15''1974
| | Supplement No. 1 to Safety Evaluation Report cc: See next page p~- |
| | EEE ATTACHED FOR OGC CONCURRENCE OF -11/ |
| | /74 OPPICN~ ORB./(3.. ...........wWE>.dy....................oaaz3....................... L AD./ORa...............c4PH:..... W SVRHAMN~ EATR . k4..... .........C JDeBayec,........GLear. + .................... KRGoller DATC ~ 1/./+/Z4,.... llL....).5.'......D.4.....11L...)$ '......../.2.4 .. 11/................../.74................................. |
| | POFm hEC.318 (ROT. 9.f 3) hECM 0240 4 V, S, OOVNRHMNNT PlllNTINO OPPICNI 1S74 SRS lSS |
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| TABLEOFCONTENTSl.0INTRODUCTION2.0REPORTOFADVISORYCOMMITTEEONREACTORSAFEGUARDS(ACRS)2.,1MainSteamLineIsolationValveLeakage2.2ReactorPressureVesselIn-ServiceInspection2.3PossibleAdditionalBackfitImprovements3.0QUALITYASSURANCEPROGRAM4cOCONCLUSIONSAPPENDICES'PPENDIXAReportofACRS
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| ==1.0INTRODUCTION==
| | Niagara:fohawk Power Corporation 2- November 15, 1974 cc: w/enclosure Hr. Arvin E. Upton, Esquire Le3oeuf, Lamb, Leiby 6 tfacRae 1757 N Street, N. U. |
| TheAECRegulatorystaff'sSafetyEvaluationReport(SER),inthematteroftheNiagaraMohawkPowerCorporation(herein'IreferredtoasNMPCorthelicensee)applicationforconversionofProvisionalOperatingLicenseNo.DPR-17toafull-termIoperatinglicenseforNineMilePointUnit1(NMP-1)wasissuedonJuly3,1974.CopiesofthisreportweremadeavailabletotheAdvisoryCommitteeonReactorSafeguards(ACRSorCommittee)toassistitinitsreviewofthisapplication.TheCommittee2.0completeditsreviewofthelicensee'sapplicationinSeptember1974andreporteditsfindingstotheCommissionbyletterdated.September10,1974.REPORTOFTHEADVISORYCOMMITTEEONREACTORSAFEGUARDSAcopyoftheACRSreportto.theCommissionisincluded'sAppendixA.MehaveconsideredthecommentsandrecommendationsmadebytheACRSinthisreportandtheactionswhichwehavetakenorwill'takerelativetothesecommentsandrecommendationsaredescribedinthefollowingparagraphs.TheCommitteeidentifiedthreemattersforfurthersurveillance:thesemattersconsistofmaintainingleaktightnessofmainsteamlineisolationvalves;'possibleimprovementsinaccessibilityforin-serviceinspectionofthereactorpressurevesseltoassurecontinuedvesselintegrity;andconsiderationtothepossibleadvisabilityofadditionalbackfittingwheresignificantandpracticalsafetyimprovementscanbetrade.TheCommitteeconcludedthatthere
| | Washington, D. C. 20036 Hr. Robert P. Jones, Supervisor Town of Scriba R. D. 04 Oswego, New York 13126 Hiss Juanita I ersey, Librarian Oswego City Library 120 E. Second Street Ommgo, New York 13126 Dr. Vill%am E. Seymour Staff Coordinator New York State Atomic Energy Council New York State Department of Commerce 99 Tfashington Street Albany, New York 12210 OPRICE5H'VRHAMC~ |
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| FexistsreasonableassurancethattheNineMilePointNuclearStationUnit1cancontinuetobeoperatedatpowerlevel's.upto18501%itwithoutunduerisktothehealthandsafetyofthe2.1public.Moreover,theCommitteeconcurredinconversion,ofthepresentprovisionaloperatinglicensetoafull-termoperatinglicense.MainSteamLineIsolationValveLeakaeTheCommitteeindicateditsawarenessofthedifficultythathasbeenexperiencedatEP-1inmaintainingtherequiredleaktightnessofthemainsteamlineisolationvalves(MSLIV)andstatedthattheRegulatorystaffshouldcontinuetofollowthismatterclosely.ThelicenseestateditsbeliefthatleakagethroughthesevalveswillbemaintainedatacceptableratesbelowtheTechnicalSpecificationlimitsasaresultofchangesinmaintenanceproceduresinvolvingthevalveseatsandplugs,initiatedduringthe1974refuelingshutdown.Thenextleakageratetestofthell'SLIVs'willbeperformedduringthe1975refuelingshutdown.TheRegulatorystaffwillfollowthismat'tertoconfirm'thattheproblem,iscorrected.l2.2ReactorPressureVesselIn-ServiceInsectionTheCommitteeexpresseditsbeliefthatadditionalmeansforassuringcontinuedvesselintegrity,includingpossibleimprovementinaccessibilityforinspection,shouldcontinuetobeactivelystudiedandimplementedtothedegreepractical.Thelicenseehasstatedits'interesttocontinuetoseekpossibleimprovementsinthematterofvesselacchssibilityandtoimplementsuch
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| improvementstothedegreepractical.Ouron-goingreviewoitheoperatingfacilitywillmonitorprogressinthisarea..2.3Possibl6AdditionalBackfitImrovements'TheCommitteerecommendedthattheRegulatorystaffandthelicensee'ivefurtherconsiderationtoadditionalbackfittingwheresignificantandpracticalsafetyimprovementscanbemade.Thelicenseehasindicatedthatithasacontinuingprogram'ofreviewtodeterminetheconCormanceofRP-1withnewRegulat:oryGuidesastheseareissu'ed.'heRegulatorystaffwillcontinueitson-goingreviewof~~RP-l,includingconsiderationofbackfittingwheresignificant,.3.0and,practicalsafetyimprovementscanbemade.UALITYASSURANCE(A)PROGKQfAsstatedinourSER,wehavereviewedthelicensee'sQAProgramandconcludedthatitisacceptable.Thelicensee'sQAProgramwasdescribedinfourdifferentsubmittals.Thisinformation.wassupersededbythelicensee'ssubmittalofAugust28,'974,entitled,"TenthSupplementtotheFinalSafetyAnalysisReport"which,consolidatesandunifiestheearliersubmittals.WehavereviewedanddeterminedthattheTenthSupplementtotheFSARis4:0thesameastheQAProgramwhichwehadpreviouslyreviewedandfoundacceptable.CCONCLUSIONSOurconclusionsasstatedintheSafetyEvaluationReportremainunchanged..
| | SUPPLEMENT NO. 1 TO THE SAFETY EVALUATION REPORT BY THE DIRECTORATE OF LICENSING U. S. ATOMIC ENERGY CO~QHSSION IN THE MATTER OF NIAGARA MOMtK POWER CORPORATION CONVERSION FROM PROVISIONAL OPERATING LICENSE TO FULL-TERM OPERATING LICENSE NINE MILE POINT UNIT 1 DOCKET NO. 50-220 NOVEMBER 15'' 1974 |
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| CAPPENDIXAnnf7'>flP3D1September10,1974~HonorableDixyLeeRayChairmanU.S.AtomicEnergyCommissionMashington,D.C.20545ADYlSORYCOMMlTTEEONREACTORSAFEGUARDSUNlTEDSTATESATOMlCENERGYCOMMlSSlONVifASHlMkTOH,D.C:.10545apJ0fjIjulCD
| | TABLE OF CONTENTS |
| | : l. 0 INTRODUCTION 2.0 REPORT OF ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS) 2.,1 Main Steam Line Isolation Valve Leakage 2.2 Reactor Pressure Vessel In-Service Inspection 2.3 Possible Additional Backfit Improvements 3.0 QUALITY ASSURANCE PROGRAM 4cO CONCLUSIONS APPENDICES'PPENDIX A Report of ACRS |
| | : 1. 0 INTRODUCTION The AEC Regulatory staff's Safety Evaluation Report (SER), in the matter of the Niagara Mohawk Power Corporation (herein |
| | 'I referred to as NMPC or the licensee) application for conversion of Provisional Operating License No. DPR-17 to a full-term I |
| | operating license for Nine Mile Point Unit 1 (NMP-1) was issued on July 3, 1974. Copies of this report were made available to the Advisory Committee on Reactor Safeguards (ACRS or Committee) to assist it in its review of this application. The Committee completed its review of the licensee's application in September 1974 and reported its findings to the Commission by letter dated. September 10, 1974. |
| | 2.0 REPORT OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS A copy of the ACRS report to. the Commission is included's Appendix A. Me have considered the comments and recommendations made by the ACRS in this report and the actions which we have taken or will'take relative to these comments and recommendations are described in the following paragraphs. The Committee identified three matters for further surveillance: these matters consist of maintaining leak tightness of main steam line isolation valves; 'possible improvements in accessibility for in-service inspection of the reactor pressure vessel to assure continued vessel integrity; and consideration to the possible advisability of additional backfitting where significant and practical safety improvements can be trade. The Committee concluded that there |
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| | F exists reasonable assurance that the Nine Mile Point Nuclear Station Unit 1 can continue to be operated at power level's .up to 1850 1%it without undue risk to the health and safety of the public. Moreover, the Committee concurred in conversion, of the present provisional operating license to a full-term operating license. |
| | 2.1 Main Steam Line Isolation Valve Leaka e The Committee indicated its awareness of the difficulty that has been experienced at EP-1 in maintaining the required leak tightness of the main steam line isolation valves (MSLIV) and stated that the Regulatory staff should continue to follow this matter closely. |
| | The licensee stated its belief that leakage through these valves will be maintained at acceptable rates below the Technical Specification limits as a result of changes in maintenance procedures involving the valve seats and plugs, initiated during the 1974 refueling shutdown. The next leakage rate test of the |
| | 'will be performed during the 1975 refueling shutdown. |
| | ll'SLIVs The Regulatory staff will follow this mat'ter to confirm 'that the problem, is corrected. l 2.2 Reactor Pressure Vessel In-Service Ins ection The Committee expressed its belief that additional means for assuring continued vessel integrity, including possible improvement in accessibility for inspection, should continue to be actively studied and implemented to the degree practical. The licensee has stated its'interest to continue to seek possible improvements in the matter of vessel acchssibility and to implement such |
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| | improvements to the degree practical. Our on-going review oi the operating facility will monitor progress in this area.. |
| | 2.3 Possibl6 Additional Backfit Im rovements The Committee recommended that the Regulatory staff and the licensee'ive further consideration to additional backfitting where significant and practical safety improvements can be made. The licensee has indicated that it has a continuing program 'of review to determine the conCormance of RP-1 with new Regulat:ory Guides as these are issu'ed.'he Regulatory staff will continue its on-going review of |
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| | RP-l, including consideration of backfitting where significant and,practical safety improvements can be made. |
| | ,. 3.0 UALITY ASSURANCE ( A) PROGKQf As stated in our SER, we have reviewed the licensee's QA Program and concluded that it is acceptable. The licensee's QA Program was described in four different submittals. This information .was superseded by the licensee's submittal of August 28,'974, entitled, "Tenth Supplement to the Final Safety Analysis Report" which |
| | ,consolidates and unifies the earlier submittals. We have reviewed and determined that the Tenth Supplement to the FSAR is the same as the QA Program which we had previously reviewed and found acceptable. |
| | C 4:0 CONCLUSIONS Our conclusions as stated in the Safety Evaluation Report remain unchanged.. |
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| | C APPENDIX A ADYlSORY COMMlTTEE ON REACTOR SAFEGUARDS UNlTED STATES ATOMlC ENERGY COMMlSSlON VifASHlMkTOH, D.C:. 10545 nn September 10, 1974 ~ |
| | f7'> a fl pJ 0fj I Honorable Dixy Lee Ray Chairman jul U. S. Atomic Energy Commission P3 CD D1 Mashington, D. C. 20545 |
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| ==Subject:== | | ==Subject:== |
| REPORTONNINEMILE.POINTNUCLEARSTATIONUN'
| | REPORT ON NINE MILE. POINT NUCLEAR STATION UN' |
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| ==DearDr.Ray:== | | ==Dear Dr. Ray:== |
| Atits173rdmeeting,September5-7,1.974,theAdvisoryCommittee'onReactorSafeguazdscompletearevewodiftheapplicationbytheNiagaraMohawkPowerCorporationforconversionosfitsNineMilePointNuclearStationVnit1~1~provisionaopera1ngc1tinlicensetoafull-teanooeratingl.icense.Theapp1-cationalsowasconsideredataSubcommitteemeetinginasngon,July29,1974.Duringltdreview,theCommitteehadthebenefitofdiscus-sionswithrepresentatvesoiftheNiagaraMohawkPowerCorporation,GeneraldtheElectricCompany,antedheAECRegulatoryStaff.TheCommitteealsohatebenefitoEthedocumentsl.isted.TheCommitteepreviousyiscusseprojectinanoperatinglicensereportofp*fAri1171969andinsubsequentxeportsdatedJune16,1970andFebruazy6,1971.Initszev1ewpteommhCitteeevaluatedtheoperationandperformanceofh'tith'rticularemphasisontheresponseoftheapp1canopastrecommendationsforimprovementsinsafetyrelatesysems.Untsanon-eUi1ion-jetpumpboilingwater.reactorof1850~M(t)ratedpowerleve.ommexc1a1C1poweroperationof-theplantwasbegun1nHoweverTheoperatingisoryoh'oftheunithasbeengenerallysatisfactory.ountezedooeratinroblemsordesigndeficiencieshavebeenencounanumberofoperatngproduringtheapproximatelyfiveyearpexiodo=poweroperaion.rackinofacoxespraynozzlesafeend;developmentocracstheseare:crac1ngoacluishness.'failureof:thsteamdryerassembly;contxol.rodscramsugg1si.xnesntzolrodstoremainfullyinsertedaEterscram,increasedcontrol.someconzortoassurerotectionforapos-xod'operatingrestrictionsfoundnecessarytoassurep1dddroaccident.feedwatexcontxoldeficiency,withresultantbxeliefvalvesteamfloodinofsteamlines;torusbaffledislocationyxeoo1ngosfailureofareliefvalvetoreclose,Alldischargeintothetorus;and,faiureorilcorrected.Reactorofthesedeficienciesappeartohavebeensatisfactorilycoxrecte.aavailabilityhasaveragedapproximately667..
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| ~eHonorableDixyLeeRay.Cr'0September10,1974Difficultyalsohasbeenexperiencedinrespecttorepeatedoccurrencesofexcessive'leakageratesofthemainsteamisolationvalvesunder'testcon-ditions.Theapplicantnowproposestoremachinethevalveseatsandplugstoanimprovedconfigurationandbelievesthatthis,togetherwiththeprobablelowlevelsofresidualstressesnowexistinginthesevalves,wi'llenablemaintenanceofacceptableleakagerates"inthefuture'.-ThismattershouldbefollowedcloselybytheRegulatoryStaff.aAnumberofdesignimprovementshavebeenaccomplishedorcomnittedtosinceoperationbegan.Amongthemostsignificantofthesefromthepointofviewofsafetyarethefollowing.Thefeedwoter"systemhasbeenmodifiedalsotoserveasanadditionalemergencycorecoolingsystemforsmallbreaks;emergencypowerforthissystemissuppliedbyanoffsitesourceofhydro-electricpower.'fuelcaskdropprotectionsystemhasbeendesignedandapproved,andinstallationwillbecompletedbeforeshipmentofspentfuelisundertaken.Acontainmentatmospheredilution(CAD)systemforcombustiblegascontrolwillbeinstalledandavailableforoperationin1976.Anad-ditionalprimarypressureboundaryleakdetectionsystemhasbeenadded,andposition'indicationinthecontrolroomforthecontaitunentvacuumbreakervalveshasbeenprovided.Approximatelyone-fifthofthereactor7x7fuelbundleshavebeenreplacedwith8x8fuel;throughadditionalreloads,thecoreeventuallyistoconsistentirelyof,8x8fuel.Becauseoftherelativelylimitedaccessibilityforin-serviceinspectionofthereactorpressurevessel,theCommitteewishestoemphasizeagainitsbeliefthatadditionalmeansforassuringcontinuedvesselintegrity,in-cludingpossibleimprovementinaccessibility,shouldcontinue,tobeactivelystudied'andimplementedtothedegreepractical.TheCommitteerecotrrnendsthattheRegulatoryStaffandtheapplicantgiveturtherconsiderationtothepossibleadvisabilityofadditionalbackfittingofUnit1wheres'ignificantandpracticalsafetyimprovementscanbcmade.TheCommitteebelievesthat,inviewofthegenerallysatisfactoryoperatingexperiencetodateandthe'improvements'madeintheplant'asnotedherein,andsubjecttotheabovecommentsand-thoseinpreviousACRSreportsonthisplant,thereexistsreasonableassurancethattheNineMilePoint"'-NuclearStationUnit1,cancontinuetobeoperatedatpowerlevelsupto1850MM('t)withoutunduerisktothehealthandsafetyof'hepublic.TheCommitteeconcursinconversionofthepresentprovisionaloperatinglicensetoafull-termoperatinglicense.Sincerelyyours,M.R.StrattonChoirman | | At its 173rd meeting, September 5-7, 1.974, the Advisory Committee'on Reactor i |
| | Safeguazds complete d a rev ew o f the application by the Niagara Mohawk Power Corporation for conversion o f itss Nine Mile Point Nuclear Station Vnit 1 provisiona 1 opera tin 1ng license c to a full-tean ooerating l.icense. The app 1 1- ~ ~ |
| | cation also was considered at a Subcommittee meeting in as ng on, July 29, 1974. During ltd review, the Committee had the benefit of discus-i sions with representat ves o f the Niagara Mohawk Power Corporation, General Electric Company, an d t hee AEC Regulatory Staff. The Committee also ha d tthee benefit oE the documents l.isted. The Committee previous y iscusse project in an operating license report off Ap ri* 1 17 1969 and in subsequent xeports dated June 16, 1970 and Februazy 6, 1971. |
| | In its zev1ewp t h e C omm ittee evaluated the operation and performance of h' t ith'rticular emphasis on the response of the app 1can o past recommendations for improvements in safety relate sys ems. |
| | Un U it 1 is anon- e pump boiling water. reactor of 1850 ~M(t) rated power on-jet leve 1 . C ommexc1a 1 power operation of- the plant was begun 1n The operating h'is ory of o the unit has been generally satisfactory. However eratinng pro a number oof ooperat roblems or design deficiencies have been encoun ountezed during the approximately five year pexiod o =power opera ion. |
| | these are: crac 1ng oof a ccoxe spray nozzle safe end; development o crac s rackin |
| | .xn th e ssteam dryer assembly; contxol. rod scram s luugg1s ishness.'failure i of: |
| | some conntzolzo r rods to remain fully inserted aEter scram, increased control. |
| | xod'operating restrictions found necessary to assure p rotection for a pos-1 d d dro accident. feedwatex contxol deficiency, with resultant oo 1ngoof ssteam lines; torus baffle dislocation b y xe floodin xelief valve steam discharge into the torus; and, fai ure oof a relief valve to reclose, All failure of these deficiencies appear to have been satisfactorily coxrecte ril corrected. . Reactora availability has averaged approximately 667.. |
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| | '0 Honorable Dixy Lee Ray . |
| | September 10, 1974 Difficulty also has been experienced in respect to repeated occurrences of excessive'leakage rates of the main steam isolation valves under 'test con-ditions. The applicant now proposes to remachine the valve seats and plugs to an improved configuration and believes that this, together with the probable low levels of residual stressesnow existing in these valves, wi'll enable maintenance of acceptable leakage rates "in the future'. - This matter should be followed closely by the Regulatory Staff. a A number of design improvements have been accomplished or comnitted to since operation began. Among the most significant of these from the point of view of safety are the following. The feedwoter" system has been modified also to serve as an additional emergency core cooling system for small breaks; emergency power for this system is supplied by an offsite source of hydro-electric power.' fuel cask drop protection system has been designed and approved, and installation will be completed before shipment of spent fuel is undertaken. A containment atmosphere dilution (CAD) system for combustible gas control will be installed and available for operation in 1976. An ad-ditional primary pressure boundary leak detection system has been added, and position'indication in the control room for the contaitunent vacuum breaker valves has been provided. |
| | Approximately one-fifth of the reactor 7x7 fuel bundles have been replaced with 8x8 fuel; through additional reloads, the core eventually is to consist entirely of,8x8 fuel. |
| | Because of the relatively limited accessibility for in-service inspection of the reactor pressure vessel, the Committee wishes to emphasize again its belief that additional means for assuring continued vessel integrity, in-cluding possible improvement in accessibility, should continue,to be actively studied 'and implemented to the degree practical. |
| | The Committee recotrrnends that the Regulatory Staff and the applicant give turther consideration to the possible advisability of additional backfitting of Unit 1 where s'ignificant and practical safety improvements can bc made. |
| | The Committee believes that, in view of the generally satisfactory operating experience to date and the 'improvements'made in the plant'as noted herein, and subject to the above comments and -those in previous ACRS reports on this plant, there exists reasonable assurance that the Nine Mile Point" Nuclear Station Unit 1, can continue to be operated at power levels up to 1850 MM('t) without undue risk to the health and safety of'he public. The Committee concurs in conversion of the present provisional operating license to a full-term operating license. |
| | Sincerely yours, M. R. Stratton Choirman |
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| ==References:== | | ==References:== |
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| | 0 September 10. '974 Honorable Dixy Lee Ray References! |
| | : 1. Niagara Mohawk Power Company Technical Supplement to Petition for Conversion from Provisional Operating, License to Full-Term Operating License dated July 1972. |
| | : 2. Applicant'nvironmental Report, Operating License Stage, Conversion to Full-Term Operating License, June 1972. |
| | : 3. Amendments 1 through 3 to Application for Full-Term Operating License. |
| | : 4. Directorate'f Licensing Safety Evaluation Report dated July .3, 1974. |
| | 5~ Directorate of'icensing letter dated July 3, 1974 concerning list of outstanding items in connection with their review of application for Full-Term Operating License. |
| | : 6. Niagara Mohawk Power Corporation letter dated November 20, 1972 con-cerning Fuel Densification and its Effect on Reactor Operation Including Transients and Postulated Loss-of-Coolant Accident. |
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| ~+)'~~HonorableDixyLeeRaye&3%0September10.'974References!1.NiagaraMohawkPowerCompanyTechnicalSupplementtoPetitionforConversionfromProvisionalOperating,LicensetoFull-TermOperatingLicensedatedJuly1972.2.Applicant'nvironmentalReport,OperatingLicenseStage,ConversiontoFull-TermOperatingLicense,June1972.3.Amendments1through3toApplicationforFull-TermOperatingLicense.4.Directorate'fLicensingSafetyEvaluationReportdatedJuly.3,1974.5~Directorateof'icensingletterdatedJuly3,1974concerninglistofoutstandingitemsinconnectionwiththeirreviewofapplicationforFull-TermOperatingLicense.6.NiagaraMohawkPowerCorporationletterdatedNovember20,1972con-cerningFuelDensificationanditsEffectonReactorOperationIncludingTransientsandPostulatedLoss-of-CoolantAccident.
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Category:ACRS Summary Report
MONTHYEARML17037C4771974-11-15015 November 1974 Letter Enclosing Supplement No. 1 to the Safety Evaluation Report for the Application for a Full-Term Operating License ML17037C2071974-09-25025 September 1974 Letter Responding to a September 17, 1974 Letter Requesting a Response to Two ACRS Identified Items Concerning Main Steam Isolation Valve Leakage and Inservice Inspection of the Reactor Pressure Vessel and Advising That Inform. ML17037C4801974-09-13013 September 1974 Letter Transmitting ACRS Report Dated September 10, 1974, on the Application for Conversion of the Provisional Operating License to a Full-Term Operating License for the Nine Mile Point Nuclear Station Unit ML17037C4901974-02-20020 February 1974 Letter Submitting Copy of Report of the Advisory Committee on Reactor Safeguards Dated February 12, 1974 on Expected Performance of General Electric 8x8 Fuel Design for Reload Use ML17037C3691971-03-12012 March 1971 Letter Responding to a February 11, 1971 Forwarding an ACRS Report Pertaining to the Request for an Increase from 1538 to 1850 Thermal Megawatts in the Licensed Power Level ML17037C3501970-06-19019 June 1970 Letter Authorizing the Return to Operation of Unit 1 in Accordance with Your Documented Program and Subject to Conditions Defined and Enclosing an ACRS Report Dated June 16, 1970 1974-09-25
[Table view] Category:Letter
MONTHYEARNMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds NMP2L2880, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) 2024-09-04
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARNMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NMP1L3484, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-15015 December 2022 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-12-15015 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22298A0112022-10-25025 October 2022 License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration NMP1L3477, License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise.2022-08-12012 August 2022 License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise. NMP1L3467, License Amendment Request - Revision to Alternative Source Term Calculation for Main Steam Isolation Valve (MSIV) Leakage and Non-MSIV Leakage2022-06-29029 June 2022 License Amendment Request - Revision to Alternative Source Term Calculation for Main Steam Isolation Valve (MSIV) Leakage and Non-MSIV Leakage NMP2L2799, License Amendment Request - Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators2022-05-24024 May 2022 License Amendment Request - Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-30030 September 2021 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position NMP2L2762, License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2021-05-26026 May 2021 License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments NMP1L3369, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-12-18018 December 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RS-20-031, License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process2020-04-30030 April 2020 License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process NMP2L2716, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-12-26026 December 2019 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors NMP2L2706, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.2019-10-31031 October 2019 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability NMP1L3278, License Amendment Request - Administrative Changes to the Technical Specifications2019-06-26026 June 2019 License Amendment Request - Administrative Changes to the Technical Specifications RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program NMP2L2699, License Amendment Request to Revise Technical Specifications Main Steam Isolation Valve Leak Rate2019-05-31031 May 2019 License Amendment Request to Revise Technical Specifications Main Steam Isolation Valve Leak Rate RS-19-003, Application to Adopt TSTF-564, Safety Limit Mcpr.2019-02-0101 February 2019 Application to Adopt TSTF-564, Safety Limit Mcpr. NMP2L2694, Emergency License Amendment Request: One Time Extension to the High Pressure Core Spray Completion Time and Associated Surveillances2018-12-0606 December 2018 Emergency License Amendment Request: One Time Extension to the High Pressure Core Spray Completion Time and Associated Surveillances NMP1L3192, License Amendment Request - Revise Technical Specification 3.3.1 for Primary Containment Oxygen Concentration2018-06-26026 June 2018 License Amendment Request - Revise Technical Specification 3.3.1 for Primary Containment Oxygen Concentration RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) NMP1L3188, License Amendment Request - Proposed Change to Remove Boraflex Credit from Spent Fuel Racks2018-02-0909 February 2018 License Amendment Request - Proposed Change to Remove Boraflex Credit from Spent Fuel Racks NMP1L3142, License Amendment Request - Revise Technical Specifications to Apply TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-15015 December 2017 License Amendment Request - Revise Technical Specifications to Apply TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 RS-17-137, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2017-11-0808 November 2017 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NMP2L2660, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change2017-11-0303 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note2017-08-22022 August 2017 License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note ML17164A1542017-05-31031 May 2017 Enclosure 4C - EAL Basis Document for Nine Mile Point Nuclear Station, Unit 1 ML17164A1552017-05-31031 May 2017 Enclosure 4D - EAL Front Matter for Nine Mile Point Nuclear Station, Unit 1 ML17164A1532017-05-31031 May 2017 Enclosure 4B - EAL Red-Line Basis Document for Nine Mile Point Nuclear Station, Unit 1 NMP2L2641, License Amendment Request - Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Revision 02017-05-31031 May 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Revision 0 NMP1L3158, Enclosure 4E - Procedure Matrix for Nine Mile Point Nuclear Station, Unit 12017-05-31031 May 2017 Enclosure 4E - Procedure Matrix for Nine Mile Point Nuclear Station, Unit 1 JAFP-17-0050, Exigent License Amendment Request to Revise Emergency Action Level HU1.52017-05-19019 May 2017 Exigent License Amendment Request to Revise Emergency Action Level HU1.5 ML17037C4192017-05-11011 May 2017 Amendment to Operating License/Change to Appendix a of Technical Specification Concerning Certain Repairs at Facility and Concomitantly to Allow a Continuation of a Slightly Lower Water Level in the Reactor... NMP2L2643, License Amendment Request-Adoption of TSTF-283-A, Revision 3, Modify Section 3.8 Mode Restriction Notes2017-04-0505 April 2017 License Amendment Request-Adoption of TSTF-283-A, Revision 3, Modify Section 3.8 Mode Restriction Notes RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process NMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-02-28028 February 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 NMP2L2639, Supplement to License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy- Nuclear 10 CFR Part 21 Safety Communication SC05-032017-02-17017 February 2017 Supplement to License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy- Nuclear 10 CFR Part 21 Safety Communication SC05-03 NMP1L3122, License Amendment Request - Proposed Changes Regarding Partial Length Fuel Rod (PLR) Burnup2017-01-0303 January 2017 License Amendment Request - Proposed Changes Regarding Partial Length Fuel Rod (PLR) Burnup 2024-06-13
[Table view] Category:Safety Evaluation Report
MONTHYEARML0628901292006-09-30030 September 2006 NUREG-1900, Vol 1 Safety Evaluation Report Related to the License Renewal of Nine Mile Point Nuclear Station Units 1 & 2 ML0614603132006-06-0101 June 2006 Safety Evaluation Report Related to the License Renewal of the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC Nos. MC3272 and MC3273) ML0610201662006-04-0303 April 2006 Safety Evaluation Report with Open Items Related to the License Renewal of Nine Mile Point, Dated March 2006 - NMPNS Comments (TAC Nos. MC3272 and MC3273) ML0605807582006-03-0303 March 2006 Safety Evaluation Report for the Nine Mile Point Nuclear Station, Units 1 and 2, License Renewal Application ML17037B5881978-05-26026 May 1978 Letter Regarding a Request for Evaluation of the Effect on Unit 1 Containment of Multiple Subsequent Actuations of Safety/Relief Valves Following a Postulated Isolation Event ML17037B9231977-08-22022 August 1977 Letter Regarding a Report Describing the Unit 2 Reactor Building Polar Crane and a Review of the Information Provided in a July 20, 1977 Letter ML17037B6251977-06-0202 June 1977 Letter Regarding a Review of Licensee Responses to Previous Generic Request for Information Relative to the Electrical Power Distribution Systems and an Enclosed Safety Evaluation and Statement of Staff Positions ML17037B9601976-03-0505 March 1976 Letter Regarding a Review of the Design and Analysis Methods for the Revetment-Ditch System and Requesting a First Review and Approval of Section 4, Physical Model Study. ML17037C4771974-11-15015 November 1974 Letter Enclosing Supplement No. 1 to the Safety Evaluation Report for the Application for a Full-Term Operating License ML17037C0291973-06-15015 June 1973 Letter Regarding the Safety Evaluation of Niagara Mohawk Power Corporation Application for a Permit to Construct the Nine Mile Point Nuclear Station Unit 2 2006-09-30
[Table view] |
Text
November 15, 1974 DISTRIBUTION:
AEC PDR DMuller Docket No. 50-220 Local PDR KRGoller Docket TJCarter ORBi/3 Rdg OIS (5 copies)
HJMcAlduff RBrodsky
.Niagara Mohawk Power Corporation SHanauer CStephens (2 copies)
ATTN: Mr., Philip D. Raymond AGiambusso CJDeBevec Vice President Engineering FSchroeder SATeets 300 Erie Boulevard Hest RBoyd (4 copies) NDube Syracuse, New York 13202 DKnuth (2 copies) 'Jones (2 cps)
RMaccary (2 copies) CLong Gentlemen: RTedesco (2 copies) RVollmer HDenton (2 copies) RSchemel The Directorate of Licensing has issued the enclosed Supplement VBenaroya BGrimes No. 1 to the Safety Evaluation Report on your application for a GLainas SPawlicki full-tenn operating license for Unit 1 of your Nine Mile Point TIppolito JKastner Nuclear Station. SVarga JOsloond Sincerely, RO (8)
TEnglehardt priginal Signed George Lear, Chief Operating Reactors Branch 83 Directorate of Licensing
Enclosure:
Supplement No. 1 to Safety Evaluation Report cc: See next page p~-
EEE ATTACHED FOR OGC CONCURRENCE OF -11/
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Niagara:fohawk Power Corporation 2- November 15, 1974 cc: w/enclosure Hr. Arvin E. Upton, Esquire Le3oeuf, Lamb, Leiby 6 tfacRae 1757 N Street, N. U.
Washington, D. C. 20036 Hr. Robert P. Jones, Supervisor Town of Scriba R. D. 04 Oswego, New York 13126 Hiss Juanita I ersey, Librarian Oswego City Library 120 E. Second Street Ommgo, New York 13126 Dr. Vill%am E. Seymour Staff Coordinator New York State Atomic Energy Council New York State Department of Commerce 99 Tfashington Street Albany, New York 12210 OPRICE5H'VRHAMC~
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SUPPLEMENT NO. 1 TO THE SAFETY EVALUATION REPORT BY THE DIRECTORATE OF LICENSING U. S. ATOMIC ENERGY CO~QHSSION IN THE MATTER OF NIAGARA MOMtK POWER CORPORATION CONVERSION FROM PROVISIONAL OPERATING LICENSE TO FULL-TERM OPERATING LICENSE NINE MILE POINT UNIT 1 DOCKET NO. 50-220 NOVEMBER 15 1974
TABLE OF CONTENTS
- l. 0 INTRODUCTION 2.0 REPORT OF ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS) 2.,1 Main Steam Line Isolation Valve Leakage 2.2 Reactor Pressure Vessel In-Service Inspection 2.3 Possible Additional Backfit Improvements 3.0 QUALITY ASSURANCE PROGRAM 4cO CONCLUSIONS APPENDICES'PPENDIX A Report of ACRS
- 1. 0 INTRODUCTION The AEC Regulatory staff's Safety Evaluation Report (SER), in the matter of the Niagara Mohawk Power Corporation (herein
'I referred to as NMPC or the licensee) application for conversion of Provisional Operating License No. DPR-17 to a full-term I
operating license for Nine Mile Point Unit 1 (NMP-1) was issued on July 3, 1974. Copies of this report were made available to the Advisory Committee on Reactor Safeguards (ACRS or Committee) to assist it in its review of this application. The Committee completed its review of the licensee's application in September 1974 and reported its findings to the Commission by letter dated. September 10, 1974.
2.0 REPORT OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS A copy of the ACRS report to. the Commission is included's Appendix A. Me have considered the comments and recommendations made by the ACRS in this report and the actions which we have taken or will'take relative to these comments and recommendations are described in the following paragraphs. The Committee identified three matters for further surveillance: these matters consist of maintaining leak tightness of main steam line isolation valves; 'possible improvements in accessibility for in-service inspection of the reactor pressure vessel to assure continued vessel integrity; and consideration to the possible advisability of additional backfitting where significant and practical safety improvements can be trade. The Committee concluded that there
F exists reasonable assurance that the Nine Mile Point Nuclear Station Unit 1 can continue to be operated at power level's .up to 1850 1%it without undue risk to the health and safety of the public. Moreover, the Committee concurred in conversion, of the present provisional operating license to a full-term operating license.
2.1 Main Steam Line Isolation Valve Leaka e The Committee indicated its awareness of the difficulty that has been experienced at EP-1 in maintaining the required leak tightness of the main steam line isolation valves (MSLIV) and stated that the Regulatory staff should continue to follow this matter closely.
The licensee stated its belief that leakage through these valves will be maintained at acceptable rates below the Technical Specification limits as a result of changes in maintenance procedures involving the valve seats and plugs, initiated during the 1974 refueling shutdown. The next leakage rate test of the
'will be performed during the 1975 refueling shutdown.
ll'SLIVs The Regulatory staff will follow this mat'ter to confirm 'that the problem, is corrected. l 2.2 Reactor Pressure Vessel In-Service Ins ection The Committee expressed its belief that additional means for assuring continued vessel integrity, including possible improvement in accessibility for inspection, should continue to be actively studied and implemented to the degree practical. The licensee has stated its'interest to continue to seek possible improvements in the matter of vessel acchssibility and to implement such
improvements to the degree practical. Our on-going review oi the operating facility will monitor progress in this area..
2.3 Possibl6 Additional Backfit Im rovements The Committee recommended that the Regulatory staff and the licensee'ive further consideration to additional backfitting where significant and practical safety improvements can be made. The licensee has indicated that it has a continuing program 'of review to determine the conCormance of RP-1 with new Regulat:ory Guides as these are issu'ed.'he Regulatory staff will continue its on-going review of
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RP-l, including consideration of backfitting where significant and,practical safety improvements can be made.
,. 3.0 UALITY ASSURANCE ( A) PROGKQf As stated in our SER, we have reviewed the licensee's QA Program and concluded that it is acceptable. The licensee's QA Program was described in four different submittals. This information .was superseded by the licensee's submittal of August 28,'974, entitled, "Tenth Supplement to the Final Safety Analysis Report" which
,consolidates and unifies the earlier submittals. We have reviewed and determined that the Tenth Supplement to the FSAR is the same as the QA Program which we had previously reviewed and found acceptable.
C 4:0 CONCLUSIONS Our conclusions as stated in the Safety Evaluation Report remain unchanged..
C APPENDIX A ADYlSORY COMMlTTEE ON REACTOR SAFEGUARDS UNlTED STATES ATOMlC ENERGY COMMlSSlON VifASHlMkTOH, D.C:. 10545 nn September 10, 1974 ~
f7'> a fl pJ 0fj I Honorable Dixy Lee Ray Chairman jul U. S. Atomic Energy Commission P3 CD D1 Mashington, D. C. 20545
Subject:
REPORT ON NINE MILE. POINT NUCLEAR STATION UN'
Dear Dr. Ray:
At its 173rd meeting, September 5-7, 1.974, the Advisory Committee'on Reactor i
Safeguazds complete d a rev ew o f the application by the Niagara Mohawk Power Corporation for conversion o f itss Nine Mile Point Nuclear Station Vnit 1 provisiona 1 opera tin 1ng license c to a full-tean ooerating l.icense. The app 1 1- ~ ~
cation also was considered at a Subcommittee meeting in as ng on, July 29, 1974. During ltd review, the Committee had the benefit of discus-i sions with representat ves o f the Niagara Mohawk Power Corporation, General Electric Company, an d t hee AEC Regulatory Staff. The Committee also ha d tthee benefit oE the documents l.isted. The Committee previous y iscusse project in an operating license report off Ap ri* 1 17 1969 and in subsequent xeports dated June 16, 1970 and Februazy 6, 1971.
In its zev1ewp t h e C omm ittee evaluated the operation and performance of h' t ith'rticular emphasis on the response of the app 1can o past recommendations for improvements in safety relate sys ems.
Un U it 1 is anon- e pump boiling water. reactor of 1850 ~M(t) rated power on-jet leve 1 . C ommexc1a 1 power operation of- the plant was begun 1n The operating h'is ory of o the unit has been generally satisfactory. However eratinng pro a number oof ooperat roblems or design deficiencies have been encoun ountezed during the approximately five year pexiod o =power opera ion.
these are: crac 1ng oof a ccoxe spray nozzle safe end; development o crac s rackin
.xn th e ssteam dryer assembly; contxol. rod scram s luugg1s ishness.'failure i of:
some conntzolzo r rods to remain fully inserted aEter scram, increased control.
xod'operating restrictions found necessary to assure p rotection for a pos-1 d d dro accident. feedwatex contxol deficiency, with resultant oo 1ngoof ssteam lines; torus baffle dislocation b y xe floodin xelief valve steam discharge into the torus; and, fai ure oof a relief valve to reclose, All failure of these deficiencies appear to have been satisfactorily coxrecte ril corrected. . Reactora availability has averaged approximately 667..
~e C r
'0 Honorable Dixy Lee Ray .
September 10, 1974 Difficulty also has been experienced in respect to repeated occurrences of excessive'leakage rates of the main steam isolation valves under 'test con-ditions. The applicant now proposes to remachine the valve seats and plugs to an improved configuration and believes that this, together with the probable low levels of residual stressesnow existing in these valves, wi'll enable maintenance of acceptable leakage rates "in the future'. - This matter should be followed closely by the Regulatory Staff. a A number of design improvements have been accomplished or comnitted to since operation began. Among the most significant of these from the point of view of safety are the following. The feedwoter" system has been modified also to serve as an additional emergency core cooling system for small breaks; emergency power for this system is supplied by an offsite source of hydro-electric power.' fuel cask drop protection system has been designed and approved, and installation will be completed before shipment of spent fuel is undertaken. A containment atmosphere dilution (CAD) system for combustible gas control will be installed and available for operation in 1976. An ad-ditional primary pressure boundary leak detection system has been added, and position'indication in the control room for the contaitunent vacuum breaker valves has been provided.
Approximately one-fifth of the reactor 7x7 fuel bundles have been replaced with 8x8 fuel; through additional reloads, the core eventually is to consist entirely of,8x8 fuel.
Because of the relatively limited accessibility for in-service inspection of the reactor pressure vessel, the Committee wishes to emphasize again its belief that additional means for assuring continued vessel integrity, in-cluding possible improvement in accessibility, should continue,to be actively studied 'and implemented to the degree practical.
The Committee recotrrnends that the Regulatory Staff and the applicant give turther consideration to the possible advisability of additional backfitting of Unit 1 where s'ignificant and practical safety improvements can bc made.
The Committee believes that, in view of the generally satisfactory operating experience to date and the 'improvements'made in the plant'as noted herein, and subject to the above comments and -those in previous ACRS reports on this plant, there exists reasonable assurance that the Nine Mile Point" Nuclear Station Unit 1, can continue to be operated at power levels up to 1850 MM('t) without undue risk to the health and safety of'he public. The Committee concurs in conversion of the present provisional operating license to a full-term operating license.
Sincerely yours, M. R. Stratton Choirman
References:
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0 September 10. '974 Honorable Dixy Lee Ray References!
- 1. Niagara Mohawk Power Company Technical Supplement to Petition for Conversion from Provisional Operating, License to Full-Term Operating License dated July 1972.
- 2. Applicant'nvironmental Report, Operating License Stage, Conversion to Full-Term Operating License, June 1972.
- 3. Amendments 1 through 3 to Application for Full-Term Operating License.
- 4. Directorate'f Licensing Safety Evaluation Report dated July .3, 1974.
5~ Directorate of'icensing letter dated July 3, 1974 concerning list of outstanding items in connection with their review of application for Full-Term Operating License.
- 6. Niagara Mohawk Power Corporation letter dated November 20, 1972 con-cerning Fuel Densification and its Effect on Reactor Operation Including Transients and Postulated Loss-of-Coolant Accident.
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