ML17301A044

Application to Amend License NPF-16 Revising Tech Spec Requirement for Primary & Secondary Coolants in Steam Generator to Be Greater than 100 F When Coolant Pressure Greater than 200 Psig.Ser Encl

ML17301A044
Person / Time
Site:	Saint Lucie
Issue date:	06/17/1983
From:	UHRIG R E FLORIDA POWER & LIGHT CO.
To:	EISENHUT D G Office of Nuclear Reactor Regulation
Shared Package
ML17214A236	List: ML17214A234 ML17301A044
References
L-83-349, NUDOCS 8306210160
Download: ML17301A044 (6)

Text

rrREGULATORYORMATIONDISTRIBUTIONSM(RIDS)AOCBSSI'ONNBR8306210160DOC~DATE!83/06/17NOTARIZED~NOFAOIL:5038%St.LuciePlanti.Unilt2<FloridaPowerLLightCo+AUTH~NAMEAUTHORAFFILIATIONUHRIGiRiE,FloridaPower3LightCo,RECIP,NAMERECIPIENTAFFILIATIONEISENHUTiD~G.DivisionofLicensing

SUBJECT:

ApplicationtoamendLicenseNPF16revisingTechSpecrequirementforprimaryLsecondarycoolantsinsteamgeneratortobegreaterthan100Fwhencoolantpressuregreaterthan200psig,SERencl.DISTRIBUTION"CODE!8001SCOPIESRECEIVED:LTRENCl'SIZE,-TITLE:Licensing"Submittal:PSAR/FSARAmdts8RelatedCorrespondenceNOTES:DOCKET¹05000389RECIPIENTIDCODE/NAMEA/0LICENSNGLICBR¹3LAINTERNAloElD/HDS2IE/DEPER/KPB36IE/DEQA/QAB21NRR/DE/CKB11NRR/DE/EQB13NRR/DE/MEB18NRR/DE/SAB2ANRR/DE/SGEB30NRR/DHFS/LQB32NRR/DL/SSPBNRR/DSI/ASBNRR/DSI/CS809NRR/DSI/METB12NRRDAB22IOQI/MIBEXTERNAL:ACRS01DMB/DSS(AMDTS)LPDR03NSIC05COPIESLTTRENCL1010103j.11122111111110111111111106-6111111RECIPIENTIDCODE/NAMELICBR¹3BCNERSESiV~01IEFILEIE/DEPER/IRB35NRR/DE/AEABNRR/DF/EHEBNRR/DE/GB28NRR/DE/MTEB17NRR/DE/SGEB25NRR/DHFS/HFEB40NRR/DHFS/PSRBNRR/DSI/AEB26NRR/DSI/CPB10NRR/DSI/ICSB16NRR/DSI/PSB19NRR/DSI/RSB23RGN2BNL(AMDT'SONLY)FEMA~REPDIV"39NRCPDR02NTISCOPIESL'TTRENCL101111111011221111111111111111133'TOTALNUMBEROFCOPIESREQUIRED+LTTR54ENCl07

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OX14000,JUNOBEACH,FL33408FLORIDAPOWER&LIGHTCOMPANYJunel7,l983L-83-349OfficeofNuclearReactorRegulation*Attention:Mr.DarrellG.Eisenhut,DirectorDivisionofLicensing.U.S.NuclearRegulatoryCommissionWashington,D.C.20555

DearMr.Eisenhut:

Re:St.LucieUnitNo.2~DocketNo.50-389ProposedLicenseAmendmentSteamGeneratorPressure/TemperatureLimitationandAdministrative/EditorialchanesInaccordancewithIOCFR50.90,FloridaPower&LightCompanysubmitsherewiththreesignedoriginalsandfortycopiesofarequesttoamendAppendixAofFacilityOperatingLicenseNPF-I6.Thisamendmentissubmittedtorevisetherequirementforbothprimaryandsecondary-coolantsinthesteamgeneratortobegreaterthanIOOOFwhenthepressureineithercoolantisgreater.than200psig.Thischangeisnecessarytoallowheatupoftheprimarycoolantw'ithfheReactorCoolantPumps.ThischangeisarevisiontothelikechangesubmittedaspartofFPLletterL-83-248dated.April20,l983,andtherefore,supercedesthatpartoftheApril20thsubmittal.Thisamendmentisalsosubmittedto.makeseveraladministrative/editorialchanges.ThesechangeshavebeenidentifiedasaresultofcontinuingreviewoftheTechnicalSpecificationsbybothNRCandFPL.TheproposedamendmentisdescribedbelowandshownontheaccompanyingTechnicalSpecificationpages.~P3/3A-1Inthefootnote,delete"and3.I0.6".ThereisnoSpecialTestException3.I0.6.~33/33-13Changethe"5.6"andthe"5.35"inSpecification4.7.I.6b.to"4.2".Pae3/47-I2ReviseSpecification.3.7.2toapplyonlytothesecondarycoolantinthesteamgenerator.Also,changethe"275"inSpecifications3.7.2,3.7.2a.and4.7.2to"200".Pae3/47-30Changethe"3.7.II.4and3.7.II.5"inSpecification3.7.II.Ic.to3.7.Il.4"."3.7.11.3andIlPEOPLE...SERVINGPEOPLE Page2OfficeofNuclearReactorRegulationMr.DarrellG.Eisenhut,DirectoriPaeB3/47-4Changethe>>275>>to>>2QQ>>andthe>>3Q>>to>>20>>jnBASES3/472Pacae6-20Deletethewords"firsthalfyear"inthefirstlineofthedouble-asteriskfootnote.InaccordancewithI0CFR50.9I(b)(l),acopyofthisproposedlicenseamendmentisbeingforwardedtotheStateDesigneefortheStateofFlorida.InaccordancewithIOCFR50.9I(a)(I),wehavedeterminedthatthisamendmentdoesnotinvolveanysignificanthazardsconsiderationspursuanttoIOCFR50.9I(c)inthattheamendmentisadministrativeinnatureandthereforedoesnot:I)'nvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated;or2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated;or3)involveasignificantreductioninamarginorsafety.*el~~ITheproposedamendmenthasbeenreviewedbytheSt.LucieFacilityReviewCroupandtheFloridaPower&LightCompariyNuclearReviewBoard.Inthatthisamendmentisadministrativeinnature,ithasbeendeterminedtobeaClassIIamendment,inaccordancewithIOCFRI70.22.Acheckforpl,200.00willfollowshortIy.Verytrulyyours,RobertE.UhrigVicePresidentAdvancedSystems&TechnologyREU/RJS/cabAttachmentscc:J.P.O'Reilly,RegionIIHaroldF.Reis,EsquireUlrayClark,AdministratorRadiologicalHealthServicesDepartmentofHealthandRehabilitativeServicesI323WinewoodBoulevardTallahassee,Florida3230I Pae3/44-ISAFETYEVALUATlON,Thischangeisadministrative/editorial,andthereforeofnosafetyconcern.P~3/47-14Thischangeisadministrative/editorial(theactualvalveclosuretimeis4.2seconds,not5.6secondsor5.35seconds),andthereforeofnosafetyconern.Pae3/47-I2andB3/47-4LimitingConditionforOperation3.7.2forTechnicalSpecification3/4.7.2requiresthatthetemperaturesofbothprimaryandsecondarycoolantsinthesteamgeneratorsshallbegreaterthanl00oFwhenthepressureofeithercoolantinthesteamgeneratorisgreaterthan275psig.OurNSSSvendorhasindicatedthatthe275psiglimitisincorrectandshouldbe200psig.Furthermore,ourstartupprocedurescallforinitialheatingoftheprimarycoolanttobeperformedutilizingpumpheatfromthereactorcoolantpumps(RCP).However,thepumpcurvereceivedfromthevendorindicatesthatoperationoftheRCPswithintheseprimarycoolantsystempressurelimitswillcausereductioninlifeoftheRCPseals.Sincethetemperatureofthesecondarycoolantinthesteamgeneratorisatambient,about80to90oF,thisTechnicalSpecificationwouldprecludetheuseofRCPstoheatuptheprimarycoolantwithoutreducingseallife.\44~ThebasesforthisTechnicalSpecificationisthatbyplacinglimitsonthepressureand',temperatureofboth;theprimaryandsecondarycoolants,thepressureinducedstressesinthesteamgeneratorsdonotexceedthemaximumallowablefracturetoughnessstresslimits.ThecurrentlimitsarebasedonasteamgeneratorRTNDTof20oF.However,TechnicalSpecification3/4.4.9alsocontainspressureandtemperaturelimitationsforthereactorcoolantsystem(RCS).ThebasesfortheselimitsisthesameasthatforTechnicalSpecification3/4.7.2,i.e.,toensurethatthemaximumpressureinducedstressesdonotexceedthemaximumallowablefracturetoughnessstresslimitsfortheRCSpressureretainingcomponents.Bases3/4.4.9statesthatthesecurvesweredevelopedassumingthemaximumRTNDTforallRCSpressure-retainingmaterials,withtheexceptionofthereactorpressurevessel,of50oF.Therefore,thepressure/temperaturecurvesforTechnicalSpecification3/44.9areappropriateforusefortheprimarycoolantinthesteamgeneratoraswell,sincetheyarebasedonamoreconservativebasis(higherRTNDT)thanthoseinTechnicalSpecification3/4.7.2.ThepressuretemperaturelimitsinTechnicalSpecification3/4.7.2areclearlymoreconservativeandrestrictivethanrequired.DuetothepotentialproblemsoftheRCPsealsbeingoperatedatthelowpressurecurrentlyrequired,theexistinglimitsof3/4.7.2maycausethesystemtobeoperatedinaconditionlesssafethandesired.Basedontheabove,itisourdeterminationthatremovalofthepressuretemperaturelimitsfortheprimarycoolantfromTechnicalSpecification3/4.7.2doesnotposearisktohealthandsafetyofthepublic.ThisisduetothefactthatthesecondarypressureboundaryremainsprotectedbythisTechnical'pecificationandthattheprimarypressureboundaryisprotectedby'echnicalSpecification~3/4.4.9.OurNSSSvendorconcu'rswiththisconclusion.

SAFETYEVALUATION(continued)Pae3/47-30Thschangeisadministrative/editorial,andthereforeofnosafetyconcern.Pacee6-20Thischangeisadministrative/editorial,andthereforeofnosafetyconcern.