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| {{#Wiki_filter:rrREGULATORYORMATIONDISTRIBUTIONSM(RIDS)AOCBSSI'ONNBR8306210160DOC~DATE!83/06/17NOTARIZED~NOFAOIL:5038%St.''LuciePlanti.Unilt2<FloridaPowerLLightCo+AUTH~NAMEAUTHORAFFILIATIONUHRIGiRiE,FloridaPower3LightCo,RECIP,NAMERECIPIENTAFFILIATIONEISENHUTiD~G.DivisionofLicensing | | {{#Wiki_filter: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 |
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| ==SUBJECT:== | | ==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
| | Application toamendLicenseNPF16revisingTechSpecrequirement forprimaryLsecondary coolantsinsteamgenerator tobegreaterthan100Fwhencoolantpressuregreaterthan200psig,SERencl.DISTRIBUTION "CODE!8001SCOPIESRECEIVED:LTR ENCl'SIZE,-TITLE:Licensing "Submittal: |
| >>nhrM<<MM'I,,y.I)J'erf')))h14~Ir<<l>lllI'>>f)M''fI"I')!'l)tf,<<)4rrh]fIfI$..M,,pl-ME,IIIMfr>>>g>)M>fIgg<<Mn>>fe1fhhepilh'n~X'Mi!I,Ir~hi'lli,~Ill)>>1~1>~f>>>>nii>)nrl>>1wm>>a:i3n)fMPILHMQrrfr''Q'>'1>L~Mhli'li~iiI>>')I'Mn'MenI4'Ml))Mi}i7'If'MM'1'1.'Ij(~I)<11<I,.l."<<Ir,4''LO"1)I'IfhI>}'I'e"It>>if4')"IM)III>>>'II'e)>i4')'II>fJIM)fIEg4hh>>1Ieil>>>4ni,'9>>'",llhlli<<InMifflfMI)lf,iillrf>ChefIn,I;''x1Iir,hfIIilIIriI'li<<>>ifknbI),II,M-IIrIIIfrf'hN~IflftA>>',,r'hhfI>4f><<'f,'nlk4IhhIiiI,,lf>>'ili'MM,fii))MMhn>Iflfif>,r"ltgg1Ihf<<Ii>>'IIMIII~i<<IIIl.f"h,lM.e', | | PSAR/FSAR Amdts8RelatedCorrespondence NOTES:DOCKET¹05000389RECIPIENT IDCODE/NAME A/0LICENSNGLICBR¹3LAINTERNAloElD/HDS2IE/DEPER/KPB 36IE/DEQA/QAB 21NRR/DE/CKB 11NRR/DE/EQB 13NRR/DE/MEB 18NRR/DE/SAB 2ANRR/DE/SGEB 30NRR/DHFS/LQB 32NRR/DL/SSPB NRR/DSI/ASBNRR/DSI/CS8 09NRR/DSI/METB 12NRRDAB22IOQI/MIBEXTERNAL: |
| OX14000,JUNOBEACH,FL33408FLORIDAPOWER&LIGHTCOMPANYJunel7,l983L-83-349OfficeofNuclearReactorRegulation*Attention:Mr.DarrellG.Eisenhut,DirectorDivisionofLicensing.U.S.NuclearRegulatoryCommissionWashington,D.C.20555 | | ACRS01DMB/DSS(AMDTS)LPDR03NSIC05COPIESLTTRENCL1010103j.11122111111110111111111106-6111111RECIPIENT IDCODE/NAME LICBR¹3BCNERSESiV~01IEFILEIE/DEPER/IRB 35NRR/DE/AEAB NRR/DF/EHEB NRR/DE/GB 28NRR/DE/MTEB 17NRR/DE/SGEB 25NRR/DHFS/HFEB40 NRR/DHFS/PSRB NRR/DSI/AEB26NRR/DSI/CPB 10NRR/DSI/ICSB16NRR/DSI/PSB19NRR/DSI/RSB 23RGN2BNL(AMDT'S ONLY)FEMA~REPDIV"39NRCPDR02NTISCOPIESL'TTRENCL101111111011221111111111111111133'TOTALNUMBEROFCOPIESREQUIRED+ |
| | LTTR54ENCl07 |
| | >>nhrM<<MM'I,,y.I)J'erf')))h14~Ir<<l>lllI'>>f)M''fI"I')!'l)tf,<<)4rrh]fIfI$..M,,pl-ME,I IIMfr>>>g>)M>fIgg<<Mn>>fe1fhhepilh'n~X'Mi!I,Ir~hi'lli,~Ill)>>1~1>~f>>>>nii>)nrl>>1wm>>a:i3n)fMPILHMQrrfr''Q'>'1>L~Mhli'li~iiI>>')I'Mn'MenI4'Ml))Mi}i7'If'MM'1'1.'Ij(~I)<11<I,.l."<<Ir,4''LO"1)I'IfhI>}'I'e"It>>if4')"IM)III>>>'II'e)>i4')'II>fJIM)fIEg4hh>>1Ieil>>>4ni,'9>>'",llhlli<<InMifflfMI)lf,iillrf>ChefIn,I;''x1Iir,hfIIilIIriI'li<<>>ifknbI),II,M-IIrIIIfrf'hN~IflftA>>',,r'hhfI>4f><<'f,'nlk4IhhIiiI,,lf>>'ili'MM,fii))MMhn>Iflfif>,r"ltgg1Ihf<<Ii>>'IIMIII~i<<IIIl.f"h,lM.e', |
| | OX14000,JUNOBEACH,FL33408FLORIDAPOWER&LIGHTCOMPANYJunel7,l983L-83-349OfficeofNuclearReactorRegulation |
| | *Attention: |
| | Mr.DarrellG.Eisenhut, DirectorDivisionofLicensing |
| | .U.S.NuclearRegulatory Commission Washington, D.C.20555 |
|
| |
|
| ==DearMr.Eisenhut:== | | ==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.}} | | 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.}} |
|
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17241A4441999-08-18018 August 1999
Application for Amend to License NPF-16,to Change Required Surveillance Frequency for Cycling Steam Valves in Turbine Overspeed Protection Sys from Once Per Month to Once Per Quarter (92 Days).Proprietary Encls Withheld
ML17241A3521999-06-0101 June 1999
Application for Amends to Licenses DPR-67 & NPF-16,revising TS 3.5.2 to Allow Up to 7 Days to Restore Inoperable LPSI Train to Operable Status
ML17241A3431999-05-24024 May 1999
Application for Amend to License NPF-16,revising Unit 2 TS 3/4.5.1, Safety Injection Tanks, by Clarifying Nonconservative Wording of Surveillance 4.5.1.1.d.1 to Align Surveillance with Intent & Design Bases Requirements
ML17229B0181999-02-23023 February 1999
Application for Amend to License NPF-16,removing Redundant Concentration Monitoring Requirements Specified for Modes 3 Through 6 by Deleting TS 3/4.1.2.9, Reactivity Control Sys- Boron Dilution.
ML17229A9541998-12-16016 December 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising Administrative Controls TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position
ML17229A9221998-11-22022 November 1998
Application for Amend to License DPR-67,revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1
ML17229A9111998-11-19019 November 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising Administrative Controls TS 6.3, Unit Staff Qualifications & Incorporate Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position
ML17229A8421998-08-24024 August 1998
Application for Amends to Licenses DPR-67 & NPF-16,removing Obsolete License Conditions & Incorporating Attached TS Revs
ML17229A7581998-06-0303 June 1998
Application for Amends to Licenses DPR-67 & NPF-16 to Incorporate Attached TS Revs.Proposed Amends Are Administrative in Nature & Will Modify Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1
ML17229A7461998-05-27027 May 1998
Application for Amend to License NPF-16,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions
ML17229A7491998-05-27027 May 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising TS 6.2.2.f to Allow Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews
ML17229A7421998-05-27027 May 1998
Supplemental Application to 961031 Proposed Amend to Licenses DPR-67 & NPF-16,providing for More Efficient Use of on-site Mgt Personnel in Review & Approval Process for Plant Procedures
ML17229A6481998-03-0303 March 1998
Application for Amend to License NPF-16,revising Applicability of TS 3.4.7 Re RCS Chemistry,Consistent W/ Corresponding Specification for Unit 1
ML17309A9161997-12-31031 December 1997
Application for Amend to License NPF-16 by Incorporating Attached TS Rev.Amend Will Modify TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity
ML17309A9111997-12-29029 December 1997
Application for Amend to License NPF-16,modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values
ML17229A5471997-12-0101 December 1997
Application for Amends to Licenses DPR-67 & NPF-16,revising EPP Section 4, Environ Conditions & Section 5, Administrative Procedures, to Incorporate Proposed Terms & Conditions of Incidental Take Statement
ML17229A4601997-08-22022 August 1997
Application for Amends to Licenses DPR-67 & NPF-16,revising Specification 4.0.5,Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Controls Section
ML17229A4321997-08-0101 August 1997
Application for Amend to License NPF-16,extending semi- Annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996
ML17229A4211997-07-22022 July 1997
Application for Amend to License DPR-67,incorporating Recent Evaluation of Postulated Inadvertent Opening of MSSV Into Current Licensing Basis
ML17229A3581997-05-29029 May 1997
Application for Amends to Licenses DPR-67 & NPF-16, Incorporating Administrative Changes That Will Improve Consistency Throughout TSs & Related Bases
ML17229A1811996-12-20020 December 1996
Application for Amend to License DPR-67,requesting Deletion of Footnote Re TS 2.1.1, Reactor Core Safety Limits.
ML17229A1591996-12-0909 December 1996
Application for Amend to License DPR-67,requesting Mod for Selected cycle-specific Reactor Physics Parameters to Refer to COLR for Limiting Values
ML17229A1171996-10-31031 October 1996
Application for Amends to Licenses DPR-67 & NPF-16, Requesting Revisions to 6.5.1 Re Facility Review Group & 6.8 Re Procedures & Programs
ML17339A0431996-10-30030 October 1996
Application for Amends to Licenses DPR-67 & NPF-16, Requesting to Revise TS 3/4.9.9 Re Refueling Requirements & TS 3/4.9.10 Re Refueling Operations,Water level-reactor Vessel
ML17229A1071996-10-28028 October 1996
Application for Amend to License NPF-16,modifying TS to Implement 10CFR50,App J,Option B,To Revise TS to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
ML17229A1041996-10-28028 October 1996
Application for Amend to License DPR-67,requesting to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
ML17228B5621996-07-15015 July 1996
Application for Amends to Licenses DPR-67 & NPF-16 Revising Core Alteration Definition
ML17228B5021996-06-0101 June 1996
Application for Exigent Amend to License DPR-67,revising TS Re Thermal Margin & RCS Flow Limits.Siemens Power Corp Rept EMF-96-135, St Lucie Unit 1 Chapter 15 Event Review & Analysis for 30% SG Tube Plugging Encl
ML17228B3741996-01-0404 January 1996
Application for Amends to Licenses DPR-67 & NPF-16 Revising TS 3.5.3 to Rectify Discrepancy for Each St Lucie Unit & to Provide Assurance That Admin Controls for Hpsip Remain Effective in Lower Operational Modes
ML17228B3341995-11-22022 November 1995
Application for Amends to Licenses DPR-67 & NPF-16,amending TS 3/4.4.6.1 for RCS Leakage Detection Instrumentation by Adapting STS for C-E Plants (NUREG-1432),Spec 3.4.15 for Facilities
ML17228B2861995-10-0505 October 1995
Application for Amends to Licenses DPR-67 & NPF-16,removing SR Re Dune & Mangrove Surveys from TS
ML17228B2401995-08-16016 August 1995
Application for Amends to Licenses DPR-67 & NPF-16, Relocating Selected TS Requirements Re Instrumentation,Per Final Policy Statement on TS Improvements & Relocating TS Re Emergency & Security Plan Review Process Per GL 93-07
ML17228B2431995-08-16016 August 1995
Application for Amend to License NPF-16,modifying Spec 3.6.6.1, Sbvs to More Effectively Address Design Functions Performed by Sbvs for Shield Bldg & Fuel Handling Bldg,Per NUREG-1432
ML17228B1871995-06-21021 June 1995
Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Revise Action Statements & Certain Surveillances of TS 3/4.5.1 Re Safety Injection Tanks
ML17228B1771995-06-21021 June 1995
Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Extend Allowed Outage Time for Inoperable EDGs
ML17309A7921995-06-21021 June 1995
Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Allow Up to Seven Days to Restore an Inoperable LPSI Train to Operable Status
ML17228B1451995-05-17017 May 1995
Application for Amend to License DPR-67,extending Applicability of Current RCS Pressure/Temp Limits & Maximum Allowed RCS Heatup & Cooldown Rates to 23.6 Effective Full Power Yrs of Operation
ML17228B1421995-05-17017 May 1995
Application for Amends to Licenses DPR-67 & NPF-16 Re Administrative & Conforming Update
ML17228B0881995-04-0303 April 1995
Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Incorporate line-item TS Improvements to TSs 3/4.8.1 & 4.8.1.2.2
ML17228B0571995-02-27027 February 1995
Application for Amend to License NPF-16,modifying Surveillance Requirement 4.9.8.1 & 4.9.8.2 to Allow Reduction in Required Min Shutdown Cooling Flow Rate Under Certain Conditions During Operational Mode 6
ML17228B0501995-02-27027 February 1995
Application for Amend to License NPF-16,revising TS Tables 3.3-3 & 3.3-4 to Accommodate Improved Coincidence Logic & Relay Replacement for 4.16 Kv Loss of Voltage Relay
ML17228B0311995-02-22022 February 1995
Application for Amends to Licenses DPR-67 & NPF-16,deleting Refs to Automatic Tester for Containment Personnel Air Lock from TS 4.6.1.3
ML17228A9901995-01-20020 January 1995
Application for Amends to Licenses DPR-67 & NPF-16, Relocating Operability Requirements for Incore Detectors (TS 3/4.3.3.2) to Updated FSAR & Revising Lhr Surveillance 4.2.1.4 & Special Test Exceptions Surveillances
ML17352B0001995-01-17017 January 1995
Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.9.1.7, COLR, Re Implementation of FPL Nuclear Physics Methodology for Calculations of COLR Parameters.Fpl Topical Rept NF-TR-95-01, Nuclear Physics Methodology... Encl
ML17228A9011994-11-0202 November 1994
Application for Amends to Licenses DPR-67 & NPF-16,upgrading TS 3/4.6.2.1 & 3/4.6.2.3 by Adapting Combined Spec for Containment Spray & Cooling Sys Contained in Std TS for C-E Plants
ML17309A7511994-10-27027 October 1994
Application for Amends to Licenses DPR-67 & NPF-16, Incorporating Encl Administrative Changes
ML17228A6501994-07-28028 July 1994
Application for Amends to Licenses DPR-67,revising TS 3/4.4.13 to Incorporate LTOP Requirements Similar to LTOP Requirements Recommended by NRC Via GL 90-06,in Accordance W/Resolution of Generic Issue 94
ML17228A6571994-07-25025 July 1994
Application for Amends to Licenses DPR-67 & NPF-16,revising Ts,Implementing Enhancements Recommended by GL 93-05 Re line-item TS Improvements to Reduce SR for Testing During Power Operation.
ML17228A6541994-07-25025 July 1994
Application for Amend to License NPF-16,proposing TS Upgrading TS 3/4.7.1.6 for Main Feedwater Line Isolation Valves to Be Consistent w/NUREG-1432,standard TS for C-E Plants
ML17228A5751994-05-23023 May 1994
Application for Amend to License DPR-67,revising TS 3.5.2 for ECCS by Removing Option That Allows HPSI Pump 1C to Be Used as Alternative to Preferred Pump for Subsystem Operability
1999-08-18
[Table view]
Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17241A4441999-08-18018 August 1999
Application for Amend to License NPF-16,to Change Required Surveillance Frequency for Cycling Steam Valves in Turbine Overspeed Protection Sys from Once Per Month to Once Per Quarter (92 Days).Proprietary Encls Withheld
ML17241A3521999-06-0101 June 1999
Application for Amends to Licenses DPR-67 & NPF-16,revising TS 3.5.2 to Allow Up to 7 Days to Restore Inoperable LPSI Train to Operable Status
ML17241A3431999-05-24024 May 1999
Application for Amend to License NPF-16,revising Unit 2 TS 3/4.5.1, Safety Injection Tanks, by Clarifying Nonconservative Wording of Surveillance 4.5.1.1.d.1 to Align Surveillance with Intent & Design Bases Requirements
ML17229B0181999-02-23023 February 1999
Application for Amend to License NPF-16,removing Redundant Concentration Monitoring Requirements Specified for Modes 3 Through 6 by Deleting TS 3/4.1.2.9, Reactivity Control Sys- Boron Dilution.
ML17229A9541998-12-16016 December 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising Administrative Controls TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position
ML17229A9221998-11-22022 November 1998
Application for Amend to License DPR-67,revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1
ML17229A9111998-11-19019 November 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising Administrative Controls TS 6.3, Unit Staff Qualifications & Incorporate Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position
ML17229A8421998-08-24024 August 1998
Application for Amends to Licenses DPR-67 & NPF-16,removing Obsolete License Conditions & Incorporating Attached TS Revs
ML17229A7581998-06-0303 June 1998
Application for Amends to Licenses DPR-67 & NPF-16 to Incorporate Attached TS Revs.Proposed Amends Are Administrative in Nature & Will Modify Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1
ML17229A7461998-05-27027 May 1998
Application for Amend to License NPF-16,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions
ML17229A7491998-05-27027 May 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising TS 6.2.2.f to Allow Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews
ML17229A7421998-05-27027 May 1998
Supplemental Application to 961031 Proposed Amend to Licenses DPR-67 & NPF-16,providing for More Efficient Use of on-site Mgt Personnel in Review & Approval Process for Plant Procedures
ML17229A6481998-03-0303 March 1998
Application for Amend to License NPF-16,revising Applicability of TS 3.4.7 Re RCS Chemistry,Consistent W/ Corresponding Specification for Unit 1
ML17309A9161997-12-31031 December 1997
Application for Amend to License NPF-16 by Incorporating Attached TS Rev.Amend Will Modify TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity
ML17309A9111997-12-29029 December 1997
Application for Amend to License NPF-16,modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values
ML17229A5471997-12-0101 December 1997
Application for Amends to Licenses DPR-67 & NPF-16,revising EPP Section 4, Environ Conditions & Section 5, Administrative Procedures, to Incorporate Proposed Terms & Conditions of Incidental Take Statement
ML17229A4601997-08-22022 August 1997
Application for Amends to Licenses DPR-67 & NPF-16,revising Specification 4.0.5,Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Controls Section
ML17229A4321997-08-0101 August 1997
Application for Amend to License NPF-16,extending semi- Annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996
ML17229A4211997-07-22022 July 1997
Application for Amend to License DPR-67,incorporating Recent Evaluation of Postulated Inadvertent Opening of MSSV Into Current Licensing Basis
ML17229A3581997-05-29029 May 1997
Application for Amends to Licenses DPR-67 & NPF-16, Incorporating Administrative Changes That Will Improve Consistency Throughout TSs & Related Bases
ML17229A1811996-12-20020 December 1996
Application for Amend to License DPR-67,requesting Deletion of Footnote Re TS 2.1.1, Reactor Core Safety Limits.
ML17229A1591996-12-0909 December 1996
Application for Amend to License DPR-67,requesting Mod for Selected cycle-specific Reactor Physics Parameters to Refer to COLR for Limiting Values
ML17229A1171996-10-31031 October 1996
Application for Amends to Licenses DPR-67 & NPF-16, Requesting Revisions to 6.5.1 Re Facility Review Group & 6.8 Re Procedures & Programs
ML17339A0431996-10-30030 October 1996
Application for Amends to Licenses DPR-67 & NPF-16, Requesting to Revise TS 3/4.9.9 Re Refueling Requirements & TS 3/4.9.10 Re Refueling Operations,Water level-reactor Vessel
ML17229A1071996-10-28028 October 1996
Application for Amend to License NPF-16,modifying TS to Implement 10CFR50,App J,Option B,To Revise TS to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
ML17229A1041996-10-28028 October 1996
Application for Amend to License DPR-67,requesting to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
ML17228B5621996-07-15015 July 1996
Application for Amends to Licenses DPR-67 & NPF-16 Revising Core Alteration Definition
ML17228B5021996-06-0101 June 1996
Application for Exigent Amend to License DPR-67,revising TS Re Thermal Margin & RCS Flow Limits.Siemens Power Corp Rept EMF-96-135, St Lucie Unit 1 Chapter 15 Event Review & Analysis for 30% SG Tube Plugging Encl
ML17228B3741996-01-0404 January 1996
Application for Amends to Licenses DPR-67 & NPF-16 Revising TS 3.5.3 to Rectify Discrepancy for Each St Lucie Unit & to Provide Assurance That Admin Controls for Hpsip Remain Effective in Lower Operational Modes
ML17228B3341995-11-22022 November 1995
Application for Amends to Licenses DPR-67 & NPF-16,amending TS 3/4.4.6.1 for RCS Leakage Detection Instrumentation by Adapting STS for C-E Plants (NUREG-1432),Spec 3.4.15 for Facilities
ML17228B2861995-10-0505 October 1995
Application for Amends to Licenses DPR-67 & NPF-16,removing SR Re Dune & Mangrove Surveys from TS
ML17228B2401995-08-16016 August 1995
Application for Amends to Licenses DPR-67 & NPF-16, Relocating Selected TS Requirements Re Instrumentation,Per Final Policy Statement on TS Improvements & Relocating TS Re Emergency & Security Plan Review Process Per GL 93-07
ML17228B2431995-08-16016 August 1995
Application for Amend to License NPF-16,modifying Spec 3.6.6.1, Sbvs to More Effectively Address Design Functions Performed by Sbvs for Shield Bldg & Fuel Handling Bldg,Per NUREG-1432
ML17228B1871995-06-21021 June 1995
Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Revise Action Statements & Certain Surveillances of TS 3/4.5.1 Re Safety Injection Tanks
ML17228B1771995-06-21021 June 1995
Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Extend Allowed Outage Time for Inoperable EDGs
ML17309A7921995-06-21021 June 1995
Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Allow Up to Seven Days to Restore an Inoperable LPSI Train to Operable Status
ML17228B1451995-05-17017 May 1995
Application for Amend to License DPR-67,extending Applicability of Current RCS Pressure/Temp Limits & Maximum Allowed RCS Heatup & Cooldown Rates to 23.6 Effective Full Power Yrs of Operation
ML17228B1421995-05-17017 May 1995
Application for Amends to Licenses DPR-67 & NPF-16 Re Administrative & Conforming Update
ML17228B0881995-04-0303 April 1995
Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Incorporate line-item TS Improvements to TSs 3/4.8.1 & 4.8.1.2.2
ML17228B0571995-02-27027 February 1995
Application for Amend to License NPF-16,modifying Surveillance Requirement 4.9.8.1 & 4.9.8.2 to Allow Reduction in Required Min Shutdown Cooling Flow Rate Under Certain Conditions During Operational Mode 6
ML17228B0501995-02-27027 February 1995
Application for Amend to License NPF-16,revising TS Tables 3.3-3 & 3.3-4 to Accommodate Improved Coincidence Logic & Relay Replacement for 4.16 Kv Loss of Voltage Relay
ML17228B0311995-02-22022 February 1995
Application for Amends to Licenses DPR-67 & NPF-16,deleting Refs to Automatic Tester for Containment Personnel Air Lock from TS 4.6.1.3
ML17228A9901995-01-20020 January 1995
Application for Amends to Licenses DPR-67 & NPF-16, Relocating Operability Requirements for Incore Detectors (TS 3/4.3.3.2) to Updated FSAR & Revising Lhr Surveillance 4.2.1.4 & Special Test Exceptions Surveillances
ML17352B0001995-01-17017 January 1995
Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.9.1.7, COLR, Re Implementation of FPL Nuclear Physics Methodology for Calculations of COLR Parameters.Fpl Topical Rept NF-TR-95-01, Nuclear Physics Methodology... Encl
ML17228A9011994-11-0202 November 1994
Application for Amends to Licenses DPR-67 & NPF-16,upgrading TS 3/4.6.2.1 & 3/4.6.2.3 by Adapting Combined Spec for Containment Spray & Cooling Sys Contained in Std TS for C-E Plants
ML17309A7511994-10-27027 October 1994
Application for Amends to Licenses DPR-67 & NPF-16, Incorporating Encl Administrative Changes
ML17228A6501994-07-28028 July 1994
Application for Amends to Licenses DPR-67,revising TS 3/4.4.13 to Incorporate LTOP Requirements Similar to LTOP Requirements Recommended by NRC Via GL 90-06,in Accordance W/Resolution of Generic Issue 94
ML17228A6571994-07-25025 July 1994
Application for Amends to Licenses DPR-67 & NPF-16,revising Ts,Implementing Enhancements Recommended by GL 93-05 Re line-item TS Improvements to Reduce SR for Testing During Power Operation.
ML17228A6541994-07-25025 July 1994
Application for Amend to License NPF-16,proposing TS Upgrading TS 3/4.7.1.6 for Main Feedwater Line Isolation Valves to Be Consistent w/NUREG-1432,standard TS for C-E Plants
ML17228A5751994-05-23023 May 1994
Application for Amend to License DPR-67,revising TS 3.5.2 for ECCS by Removing Option That Allows HPSI Pump 1C to Be Used as Alternative to Preferred Pump for Subsystem Operability
1999-08-18
[Table view] |
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+
LTTR54ENCl07
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OX14000,JUNOBEACH,FL33408FLORIDAPOWER&LIGHTCOMPANYJunel7,l983L-83-349OfficeofNuclearReactorRegulation
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.
