ML17222A314
| ML17222A314 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/23/1988 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17222A313 | List: |
| References | |
| NUDOCS 8807010660 | |
| Download: ML17222A314 (17) | |
Text
ATTACHMENT 1Marked-up Technical Specification Pages:Unit13/46-2B3/46-1Unit23/46-2B3/46-188007010660 880623PDRADOCK05000335PDCDEJWCILR.PLA CONTAINMENT SYSTEMSCONTAINMENT LEAKAGELIMITINGCONDITION FOROPERATION 3.6.1.2Containment leakageratesshallbelimitedto:a.Anoverallintegrated leakagerateof:2.<La,0.50percentbyweightofthecontainment airper24hoursatP,(39.6psig),or<Lt,0.32percentbyweightofthecontainment airper24hoursatareducedpressureofPt,(19.8psig).b.Acombinedleakagerateof<0.60Laforallpenetrations andvalvessubjecttoType8andCtestsasidentified inTable3.6-1whenpressurized toPa.c.Acombinedleakagerateof<0.27Laforallpenetrations identified inTable3.6-1assecondary containment bypassleakagepathswhenpressurized toPa.APPLICABILITY:
NODES1,2,3and4.ACTION:Witheither(a)themeasuredoverallintegrated containment leakagerateexceeding 0.75Laor0.75Lt,asapplicable, or(b)withthemeasuredcombinedleakagerateforallpenetrations andvalvessubjecttoTypes8andCtestsexceeding 0.60La,or(c)withthecombinedbypassleakagerateexceeding 0.27La,restoretheleakagerate(s)towithinthellimit(s)priortoincreasing theReactorCoolantSystemtemperature above200'F.SURVEILLANCE REUIREMENTS 4.6.1.2Thecontainment leakageratesshallbedemonstrated atthefollowing tdstscheduleandshallbedetermined inconformance withthecriteriaspecified inAppendixJof10CFR50',v.~s-P+l.+V~a.ThreeTypeAtests(OverallIntegrated Containment LeakageRate)shallbeconducted at40+10monthintervals duringshutdownateitherPa(39.6psig)oratPt(19.8psig)duringeach.l0-year ST.LUCIE-UNIT13/46-2Amendment No.38 34;6CONTAINMENT SYSTEMSBASES34.6.1CONTAINMENT VESSEL34.6.1.1CONTAINMENT VESSELINTEGRITY CONTAINMENT VESSELINTEGRITY ensuresthatthereleaseofradioactive materials fromthecontainment atmosphere willberestricted tothoseleakagepathsandassociated leakratesassumedintheaccidentanalyses.
Thisrestriction, inconjunction withtheleakageratelimitation, willlimitthesiteboundaryradiation dosestowithinthelimitsof10CFRPart100duringaccidentconditions.
34.6.1.2CONTAINMENT LEAKAGEThelimitations oncontainment leakageratesensurethatthetotalcontainment leakagevolumewillnotexceedthevalueassumedintheaccidentanalysesatthepeakaccidentpressure, Pa(39.6psig).Asanaddedconservatism, themeasuredoverallintegrated leakagerateisfurtherlimitedto<0.75Laor<0.75Lt(asapplicable) duringperformance oftheperiodicteststoaccountforpossibledegradation ofthecontainment leakagearriersbetweenleakagetests.Thesurveillance testingformeasuring leakagerrotentwitht'di""10CFRPart50~,'4g~oppfusi'mp<nyAl<c-appltou<~
mc.food~p~~i'g~g/gtc.~nQQ,ng&l~/q44/4crAu/'C!TAINMThelimitations onclosureandleakrateforthecontainment airlocksarerequiredtomeettherestrictions onCONTAINMENT INTEGRITY andcontain-mentleakrate.Surveillance testingoftheairlocksealsprovidesassurance thattheoverallairlockleakagewillnotbecomeexcessive duetosealdamageduringtheintervals betweenairlockleakagetests.ST.LUCIE-UNIT1B3/46-1Amendment No.85
CONTAINMENT SYSTEMSCONTAINMENT LEAKAGELIMITINGCONOITION FOROPERATION 3.6.1.2Containment leakageratesshallbelimitedto:a.Anoverallintegrated leakagerateof:1.LessthanorequaltoL,0.50percentbyweightoftheacontainment airper24hoursatP,43.4psig,orb.co2.LessthanorequaltoLt,0.35percentbyweightofthecontainment airper24hoursatareducedpressureofPt,21.7psig.Acombinedleakagerateoflessthanorequalto0.60Lforallapenetrations andvalvessubjecttoType8andCtests,whenpressurized toP.Acombinedbypassleakagerateoflessofthanorequal0.12Lforaallpenetrations identified inTable3.6-1assecondary containment bypassleakagepathswhenpressurized toP.a'PPLICABILITY:
MOOES1,2,3,and4.ACTION:Witheither(a)themeasuredoverallintegrated containment leakagerateexceeding 0.75Lor0.75Lt,asapplicable, or(b)withthemeasuredcombinedleakagerateforallpenetrations andvalvessubjecttoTypesBandCtestsexceeding 0.60L,or(c)withthecombinedbypassleakagerateexceeding 0.12L,restoretheoverallintegrated leakageratetolessthanorequalto0.75Lorlessthanorequalto0.75L,asapplicable, andthecombinedleakagerateforallpenetrations andvalvessubjecttoTypeBandCteststolessthanorequalto0.60L,andthebypassleakageratetolessthanorequalto0.12Lpriortoincreasing theReactorCoolantSystemtemperature above2004F.SURVEILLANCE REUIREMENTS 4.6.1.2Thecontainment leakageratesshallbedemonstrated atthefollowing testscheduleandshallbedetermined inconformance withthecriteriaspecified inAppendixJof10CFR50'g*iga.ThreeTypeAtests(OverallIntegrated Containment LeakageRate)shallbeconducted at40+10monthintervals duringST.LUCIE-UNIT23/46-2 3/4.6CONTAINMENT SYSTEMSBASES3/4.6.1PRIMARYCONTAINMENT 3/4.6.1.1CONTAINMENT INTEGRITY PrimaryCONTAINMENT INTEGRITY ensuresthatthereleaseofradioactive materials fromthecontainment atmosphere willberestricted tothoseleakagepathsandassociated leakratesassumedinthesafetyanalyses.
Thisrestriction, inconjunction withtheleakageratelimitation, willlimitthesiteboundaryradiation dosestowithinthelimitsof10CFR100duringaccidentconditions.
3/4.6.1.2CONTAINMENT LEAKAGEThelimitations oncontainment leakageratesensurethatthetotalcontainment leakagevolumewillnotexceedthevalueassumedintheaccidentanalysesatthepeakaccidentpressure, P.Asanaddedconservatism, themeasuredoverallintegrated leakageratefsfurtherlimitedtolessthanorequalto0.75Lorlessthanorequalto0.75Lt,asapplicable duringperformance of$heperiodicteststoaccountforpossibledegradation ofthecontainment leakagebarriersbetweenleakagetests.Thesurveillance testingformeasuring leakageratesareconsistent withtherequirements ofAppendixJof10CFR50.3/4.6.1.3CONTAINMENT AIRLOCKSThelimitations onclosureandleakrateforthecontainment airlocksarerequiredtomeettherestrictions onCONTAINMENT INTEGRITY andcontainment leakrate.Surveillance testingoftheairlocksealsprovidesassurance thattheoverallairlockleakagewi11notbecomeexcessive duetosealdamageduringtheintervals betweenairlockleakagetests.3/4.6.1.4 INTERNALPRESSUREThelimitations oncontainment internalpressureensurethat(1)thecontainment structure isprevented fromexceeding i.tsdesignnegativepressuredifferential withrespecttotheannulusatmosphere of0.7psiand(2)thecontainment peakpressuredoesnotexceedthedesignpressureof44psigduringsteamlinebreakconditions.
Themaximumpeakpressureexpectedtobeobtainedfromasteamlinebreakeventis43.4psig.Thelimitof0,4psigforinitialpositivecontainment pressurewilllimitthetotalpressureto43.99psigwhichislessthanthedesignpressureandisconsistent withthesafetyanalyses.
ST.LUGIE-UNIT283/46-1 ATTACHMENT 2SAFETYEVALUATION INTRODUCTION Theproposedamendments totheSt.LucieUnits1and2Technical Specifications reflectanewermethodforevaluating testdatacalledtheMassPointmethod.Theproposedamendments deletereference toANSIN45.4-1972 fromSection3/4..6.1.2 oftheSt.LucieUnits1and2Technical Specifications.
SincetheissuanceofANSIN45.4-1972, amoreaccuratemethodofdetermining thecontainment leakagerates,theMassPointmethod,wasdeveloped asdescribed inANSI/ANS56.8-1981, "Containment SystemLeakageTestingRequirements."
AchangeisalsoproposedtoBasesSection3/4.6.1.2 toincludetheprovision foruseoftheMassPointorotherNRC-approved methodsforperforming leakageratecalculations.
DISCUSSION TheSt.LucieUnit1andUnit2Technical Specifications eachrequirethatcontainment ileakagerates,bedemonstrated atspecified intervals andthattheybedetermined tobeinconformance withthecriteriaspecified inAppendixJof10CFR50usingthemethodsandprovisions
.ofANSIN45.4-1972, "LeakageRateTestingofContainment Structures forNuclearReactors."
ANSIN45.4-1972 specifies thepractices andtestrequirements forthequantitative determination ofleakageratesforcontainment structures.
Thestandardprovidesforoneoftwoacceptable methodsforleakage-rate testing:theTotalTimemethodandthePoint-to-Point method.IntheTotalTimemethod,aseriesofleakageratesarecalculated onthebasisofcontainment airmassdifferences betweenaninitialdatapointandeachindividual datapointthereafter.
InthePoint-to-Point methodtheleakageratesarebasedontheairmassdifferences betweeneachpairofconsecutive datapoints.Advancesinleakageratetestingsubsequent totheissuanceofANSIN45.4-1972 haveprovidedimprovedtestmethods,including anewermethodofevaluating testdatacalledtheMassPointmethod.TheMassPointmethodinvolvescalculation oftheairmassataseriesofpointsintimeandtheplottingofmassagainsttime.Alinearregression lineplottedthroughthemass-time pointsusingaleastsquaresfitisusedtoobtainthecalculated leakagerate.EJWCILR.PLA
'(14 ThisMassPointmethodwasincorporated inanewerANSIstandard, ANSI/ANS56.8-1981, "Containment SystemLeakageTestingRequirements" (revised1987)andhasbeenacceptedbytheNRCstaffasanimprovedalternative methodofcalculating containment leakagerates.However,ithasbeenrecognized bytheNRCstaffthatastrictinterpretation ofthespecificwordingofAppendixJ,III.A.3,byreferencing onlytheolderANSIstandard, wouldprecludeuseofthenewerimprovedmethod.WhiletheNRCcontemplates amending'10CFRPart50AppendixJbyarulechangewhichwouldendorsetheuseoftheMassPointmethod,FPLproposesanexemption to10CFRPart50AppendixJinaccordance with10CFR50.12.Thisproposedexemption isattachedasAttachment 4tothisapplication.
FPLproposesintheexemption, andintheproposedlicenseamendment, thedeletionofthereference toANSIN45.4-1972 ineachUnits'echnical Specifications inordertoallowanyNRC-approved leakageratetestingmethodtobeusedatSt.LuciePlant.NRCapprovalofthisproposedlicenseamendment, coupledwiththeapprovalofFPL'sproposedexemption from10CFRPart50AppendixJ,III.A.3,wouldpermitneartermapplication ofthenewerMassPointmethodology.
EJWCILR.PLA I
~~ATTACHMENT 3DETERM1NATION OFNOSIGNIFICANT HAZARDSCONSIDERATION Thestandards usedtoarriveatadetermination thatarequestforamendment involvesnosignificant hazardsconsideration areincludedin,theCommission sregulations, 10CFR50.92,whichstatesthatnosignificant hazardsconsiderations areinvolvediftheoperation ofthefacilityinaccordance withtheproposedamendment'ould not(1)involveasignificant increase'intheprobability orconsequences ofanaccidentpreviously-evaluated; or(2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated or(3)involveasignificant reduction inamarginofsafety.Eachstandardisdiscussed asfollows:(1)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
Removingthereference toANSIStandardN45.4-1972 willallowmorecurrentmethodstobeusedindetermining themannerinwhichtheleakageratetestdataareanalyzedandevaluated.
Sincetheacceptability ofthecontainment leakageratedatawillcontinuetobeanalyzedbytheuseofacceptedmethodologies, andsincenochangeinacceptance criteriaisproposed, theprobability orconsequences ofanaccidentpreviously evaluated willnotincrease.
(2)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccident, previously evaluated.
Nochangestoplantoperation orsurveillance acceptance criteriaarerequested inthisproposedlicenseamendment.
Theacceptability ofleakageratetestdataresultswillremainunchanged.
NRC-approved methodsofleakageratetestingaresatisfactory methodsandtheMassPointmethodisrecognized asanimprovedalternate methodofcalculating containment leakagerates.Therearenonewfailuremodesassociated withthischangeandtherefore, thepossibility ofanewordifferent kindofaccidentwillnotbecreated.EJWCILR.PLA 1EIIII (3)Useofthemodifiedspecification wouldnotinvolveasignificant reduction inamarginofsafety.Thisproposedamendment includesSurveillance Requirement methodology changesandthereisnoimpactonthereactorcontainment orleakagerateacceptability limits.Theimprovedanalytical methodology providesanadditional methodforverifying thatcontainment integrity andcontainment.
designleakagerateswouldbemaintained underaccidentconditions.
Therefore, thereisnoreduction inamarginofsafetyasaresultofthisproposedlicenseamendment.
Basedontheabove,wehavedetermined thattheamendment requestdoesnot(1)involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, (2)createtheprobability ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated, or(3)involveasignificant reduction inamarginofsafety;andtherefore doesnotinvolveasignificant hazardsconsideration.
EJWCILR.PLA ATTACHMENT 4ST.LUCIEUNITS1AND2REQUESTFORPARTIALEXEMPTION FROMTHEREQUIREMENTS OF10CFR50'PPENDIX JDISCUSSION TheCommission sregulations, specifically 10CFR50.12(a),
providethatexemptions maybegrantedfromtheregulations in10CFR50providedthattheyare"authorized bylaw,willnotpresentanunduerisktothepublichealthandsafety,andareconsistent withthecommondefenseandsecurity."
Basedontheinformation providedbelow,FloridaPowerLightCompany(FPL)concludes thatanexemption fromtherequirements of10CFR50,AppendixJisjustified pursuantto10CFR50.12(a)(1) and10CFR50.12(a)(2)(ii).
Thatis,theexemption:
000Isauthorized bylaw;Willnotpresentunduerisktopublichealthandsafety;andIsconsistent withthecommondefense,and security.
Specialcircumstances arepresentinthiscaseinthatapplication oftheregulation isnotnecessary toachievetheunderlying purposeoftherule.Theproposed'exemption toallowapplication ofanyNRC-approved acceptedleakageratetestingmethodology, including theMassPointmethod,forleakageratetestingwillsatisfytheaccuracyrequirements of10CFR50,AppendixJ,Paragraph III.A.3forTypeAtests.EXEMPTION REVESTEDSectionIII.A.3(a) of10CFR50,'Appendix Jrequiresthat:"AllTypeAtestsshallbeconducted inaccordance withtheprovisions oftheAmericanNationalStandardN45.4-1972, LeakageRateTestingofContainment Structures forNuclearReactors, March16,1972.Themethodchosenfortheinitialtestshallnormallybeusedfortheperiodictests."(footnote omitted)FPLherebyrequestsanexemption tothisprovision inordertousetheMassPointmethod,asdescribed inANSI/ANS56.8-1981,theTotalTimeorPoint-to-Point methodologies asdescribed inANSIN45.4-1972, oranyotherNRC-approved methodforcalculating containment leakagerates.EJWCILR.PLA EVALUATION TheTotalTimemethodcalculates aseriesoftime-weighted leakagerates,basedupondifferences betweenaninitialdatapointandpointsoccurring laterintime.Theadequacyofthismethodissensitive totheinitialdatapoint.ThePoint-to-Point methodcalculates leakageratesbasedontheairmassdifferences betweeneachpairofconsecutive datapoints.Perturbations, suchasfluctuations incontainment airtemperature, ingassing oroutgassing, orinstrument error,canaffectthevalidityofdatapointsanddownstream leakagecalculations foreitherofthesemethods.Ontheotherhand,theMassPointmethodcalculates leakageratesbaseduponcontained airmass.Thistechnique accurately calculates themassofairinsidecontainment andplotsitasafunctionoftime.Theslopeofthelinearleastsquaresfitofthedataisusedtocalculate theleakagerate.Theuseofthismethodiswell-known andendorsedbyANS,EPRIandtheNRCStaff.WhiletheMassPointmethodisconsidered moreaccurate, FPLdesirestheoptionofusinganyoneofthethreeacceptable methodsforperforming containment integrated leakageratetesting.Thisflexibility inchoosingleakageratetestingmethodology willallowFPLtotailoroutageleakageratetestingtominimizeoutagecriticalpaths.JUSTIFICATION FOREXEMPTION 1FPL'sexemption requestfromtherequirements of10CFR50,AppendixJ(SectionIII.A.3(a))
willnotresultinunduerisktothehealthorsafetyofthepublic:NI(a)Theproposed'xemption doesnotchange,'~
modify,orrestrictexistingplantsafetylimits,safetysettings, systems,oroperations.
Thechangedoesnotimpactthedesignbasesofcontainment ormodifyitsresponseduringaDBA.(b)Therearenoadversesafetyeffectsassociated withthisexemption.
(c)TheuseoftheMassPoint,TotalTimeandPoint-to-Point methodsrepresent thebestavailable andprovencontainment leakageratecalculational andmeasurement technology.
EJWCILR.PLA CONCLUSION Basedontheaboveinformation, FPLconcludes thattherequested exemption iswarranted andthattheunderlying purposeoftheregulation wouldstillbemet.EZWCILR.PLA C'