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

rrREGULATORY ORMATIONDISTRIBUTION SM(RIDS)AOCBSSI'ON NBR8306210160DOC~DATE!83/06/17NOTARIZED~NOFAOIL:5038%St.Lucie Planti.Unilt2<FloridaPowerLLightCo+AUTH~NAMEAUTHORAFFILIATION UHRIGiRiE, FloridaPower3LightCo,RECIP,NAMERECIPIENT AFFILIATION EISENHUTiD

~G.DivisionofLicensing

SUBJECT:

Application toamendLicenseNPF16revisingTechSpecrequirement forprimaryLsecondary coolantsinsteamgenerator tobegreaterthan100Fwhencoolantpressuregreaterthan200psig,SERencl.DISTRIBUTION "CODE!8001SCOPIESRECEIVED:LTR ENCl'SIZE,-TITLE:Licensing "Submittal:

PSAR/FSAR Amdts8RelatedCorrespondence NOTES:DOCKET¹05000389RECIPIENT IDCODE/NAME A/0LICENSNGLICBR¹3LAINTERNAloElD/HDS2IE/DEPER/KPB 36IE/DEQA/QAB 21NRR/DE/CKB 11NRR/DE/EQB 13NRR/DE/MEB 18NRR/DE/SAB 2ANRR/DE/SGEB 30NRR/DHFS/LQB 32NRR/DL/SSPB NRR/DSI/ASBNRR/DSI/CS8 09NRR/DSI/METB 12NRRDAB22IOQI/MIBEXTERNAL:

ACRS01DMB/DSS(AMDTS)LPDR03NSIC05COPIESLTTRENCL1010103j.11122111111110111111111106-6111111RECIPIENT IDCODE/NAME LICBR¹3BCNERSESiV~01IEFILEIE/DEPER/IRB 35NRR/DE/AEAB NRR/DF/EHEB NRR/DE/GB 28NRR/DE/MTEB 17NRR/DE/SGEB 25NRR/DHFS/HFEB40 NRR/DHFS/PSRB NRR/DSI/AEB26NRR/DSI/CPB 10NRR/DSI/ICSB16NRR/DSI/PSB19NRR/DSI/RSB 23RGN2BNL(AMDT'S ONLY)FEMA~REPDIV"39NRCPDR02NTISCOPIESL'TTRENCL101111111011221111111111111111133'TOTALNUMBEROFCOPIESREQUIRED+

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OX14000,JUNOBEACH,FL33408FLORIDAPOWER&LIGHTCOMPANYJunel7,l983L-83-349OfficeofNuclearReactorRegulation

• Attention:

Mr.DarrellG.Eisenhut, DirectorDivisionofLicensing

.U.S.NuclearRegulatory Commission Washington, D.C.20555

DearMr.Eisenhut:

Re:St.LucieUnitNo.2~DocketNo.50-389ProposedLicenseAmendment SteamGenerator Pressure/Temperature Limitation andAdministrative/Editorial chanesInaccordance withIOCFR50.90,FloridaPower&LightCompanysubmitsherewiththreesignedoriginals andfortycopiesofarequesttoamendAppendixAofFacilityOperating LicenseNPF-I6.Thisamendment issubmitted torevisetherequirement forbothprimaryandsecondary

-coolants inthesteamgenerator tobegreaterthanIOOOFwhenthepressureineithercoolantisgreater.than200psig.Thischangeisnecessary toallowheatupoftheprimarycoolantw'ithfheReactorCoolantPumps.Thischangeisarevisiontothelikechangesubmitted aspartofFPLletterL-83-248dated.April20,l983,andtherefore, supercedes thatpartoftheApril20thsubmittal.

Thisamendment isalsosubmitted to.makeseveraladministrative/editorial changes.Thesechangeshavebeenidentified asaresultofcontinuing reviewoftheTechnical Specifications bybothNRCandFPL.Theproposedamendment isdescribed belowandshownontheaccompanying Technical Specificationpages.~P3/3A-1Inthefootnote, delete"and3.I0.6".ThereisnoSpecialTestException 3.I0.6.~33/33-13Changethe"5.6"andthe"5.35"inSpecification 4.7.I.6b.to"4.2".Pae3/47-I2ReviseSpecification.3.7.2 toapplyonlytothesecondary coolantinthesteamgenerator.

Also,changethe"275"inSpecifications 3.7.2,3.7.2a.and4.7.2to"200".Pae3/47-30Changethe"3.7.II.4and3.7.II.5"inSpecification 3.7.II.Ic.to3.7.Il.4"."3.7.11.3 andIlPEOPLE...

SERVINGPEOPLE Page2OfficeofNuclearReactorRegulation Mr.DarrellG.Eisenhut, DirectoriPaeB3/47-4Changethe>>275>>to>>2QQ>>andthe>>3Q>>to>>20>>jnBASES3/472Pacae6-20Deletethewords"firsthalfyear"inthefirstlineofthedouble-asteriskfootnote.

Inaccordance withI0CFR50.9I(b)(l),

acopyofthisproposedlicenseamendment isbeingforwarded totheStateDesigneefortheStateofFlorida.Inaccordance withIOCFR50.9I(a)(I),

wehavedetermined thatthisamendment doesnotinvolveanysignificant hazardsconsiderations pursuanttoIOCFR50.9I(c)inthattheamendment isadministrative innatureandtherefore doesnot:I)'nvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated; or2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated; or3)involveasignificant reduction inamarginorsafety.*el~~ITheproposedamendment hasbeenreviewedbytheSt.LucieFacilityReviewCroupandtheFloridaPower&LightCompariyNuclearReviewBoard.Inthatthisamendment isadministrative innature,ithasbeendetermined tobeaClassIIamendment, inaccordance withIOCFRI70.22.Acheckforpl,200.00 willfollowshortIy.Verytrulyyours,RobertE.UhrigVicePresident AdvancedSystems&Technology REU/RJS/cabAttachments cc:J.P.O'Reilly, RegionIIHaroldF.Reis,EsquireUlrayClark,Administrator Radiological HealthServicesDepartment ofHealthandRehabilitative ServicesI323WinewoodBoulevard Tallahassee, Florida3230I Pae3/44-ISAFETYEVALUATlON, Thischangeisadministrative/editorial, andtherefore ofnosafetyconcern.P~3/47-14Thischangeisadministrative/editorial (theactualvalveclosuretimeis4.2seconds,not5.6secondsor5.35seconds),

andtherefore ofnosafetyconern.Pae3/47-I2andB3/47-4LimitingCondition forOperation 3.7.2forTechnical Specification 3/4.7.2requiresthatthetemperatures ofbothprimaryandsecondary coolantsinthesteamgenerators shallbegreaterthanl00oFwhenthepressureofeithercoolantinthesteamgenerator isgreaterthan275psig.OurNSSSvendorhasindicated thatthe275psiglimitisincorrect andshouldbe200psig.Furthermore, ourstartupprocedures callforinitialheatingoftheprimarycoolanttobeperformed utilizing pumpheatfromthereactorcoolantpumps(RCP).However,thepumpcurvereceivedfromthevendorindicates thatoperation oftheRCPswithintheseprimarycoolantsystempressurelimitswillcausereduction inlifeoftheRCPseals.Sincethetemperature ofthesecondary coolantinthesteamgenerator isatambient,about80to90oF,thisTechnical Specification wouldprecludetheuseofRCPstoheatuptheprimarycoolantwithoutreducingseallife.\44~ThebasesforthisTechnical Specification isthatbyplacinglimitsonthepressureand',temperature ofboth;theprimaryandsecondary

coolants, thepressureinducedstressesinthesteamgenerators donotexceedthemaximumallowable fracturetoughness stresslimits.Thecurrentlimitsarebasedonasteamgenerator RTNDTof20oF.However,Technical Specification 3/4.4.9alsocontainspressureandtemperature limitations forthereactorcoolantsystem(RCS).ThebasesfortheselimitsisthesameasthatforTechnical Specification 3/4.7.2,i.e.,toensurethatthemaximumpressureinducedstressesdonotexceedthemaximumallowable fracturetoughness stresslimitsfortheRCSpressureretaining components.

Bases3/4.4.9statesthatthesecurvesweredeveloped assumingthemaximumRTNDTforallRCSpressure-retaining materials, withtheexception ofthereactorpressurevessel,of50oF.Therefore, thepressure/temperature curvesforTechnical Specification 3/44.9areappropriate forusefortheprimarycoolantinthesteamgenerator aswell,sincetheyarebasedonamoreconservative basis(higherRTNDT)thanthoseinTechnical Specification 3/4.7.2.Thepressuretemperature limitsinTechnical Specification 3/4.7.2areclearlymoreconservative andrestrictive thanrequired.

Duetothepotential problemsoftheRCPsealsbeingoperatedatthelowpressurecurrently

required, theexistinglimitsof3/4.7.2maycausethesystemtobeoperatedinacondition lesssafethandesired.Basedontheabove,itisourdetermination thatremovalofthepressuretemperature limitsfortheprimarycoolantfromTechnical Specification 3/4.7.2doesnotposearisktohealthandsafetyofthepublic.Thisisduetothefactthatthesecondary pressureboundaryremainsprotected bythisTechnical'pecification andthattheprimarypressureboundaryisprotected by'echnical Specification

~3/4.4.9.OurNSSSvendorconcu'rswiththisconclusion.

SAFETYEVALUATION (continued)

Pae3/47-30Thschangeisadministrative/editorial, andtherefore ofnosafetyconcern.Pacee6-20Thischangeisadministrative/editorial, andtherefore ofnosafetyconcern.