ML17335A365

Proposed Tech Specs 3/4.7.7, Sealed Source Contamination & Associated Bases Addressing Revised Testing Requirements for Fission Detectors

ML17335A365
Person / Time
Site:	Cook
Issue date:	12/03/1998
From:	INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17335A364	List: ML17335A363 ML17335A365
References
NUDOCS 9812080066
Download: ML17335A365 (23)

Text

ATTACHMENT 2TOAEP:NRC:1315 TECHNICAL SPECIFICATIONS PAGESMARKEDTOSHOWPROPOSEDCHANGESREVISEDPAGESUNIT13/47-263/47-27B3/47-5B3/47-5a9812080066 981208PDRADOCK05000815PPDR' Ig~~I's~II(~~~~~~~~~~~~,~~~~t~~~~~~~~~~~~I~s~~~~~~~~~~0~I~o~~~~~I~~~~~~~~~I.~.~I~~~~I~~~~~~~~~~~~~~I~~~~~~~~~~~~

,7PLANTSYSTEMSSURVEILLANCE REUIREMENTS Contiued1.Withahalf-life greaterthan30days(excluding Hydrogen3)iand2.Inanyformotherthangas.Jf;sso~4a4cb.Storedsourcesnotinuse-Eachsealedsourceshallbetestedpriortouseortransfertoanctherlicenseeunlesstestedwithintheprevioussixmonths.Sealedsourcesransferred withoutacertificate

'indicating theastdateshallettedpriortobeingplacedintouse.o~gf;ss'on,4g ggfJQg;s$)y~c.sStartusources-Eachsealedstartupsourceshallbetestedwithin31dayspriortobeingsub)ected tocorefluxandfollowing repairormaintenance tothesource.gc4c444.7.7.1.3

~Reorts-ASpecialReportshallbepreparedaodsubmitted totheCommission onanannualbasisifsealedsourceorfissionder~onleakagetestsrevealthepresenceof20.005microcuries ofremovable contamination.

COOKNUCLEARPLANT-UNIT13/47-27AMENDMENT NO.69 era1i-I~lipI'~I~(IfrpIIl

~5~f3/4BASES3/4.7PLANTSYSTEMS3/4.7.5CONTROLROOMEMERGENCY VENTILATION SYSTEMTheOPERABILITY ofthecontrolroomemergency ventilation systemensuresthatthecontrolroomwillremainhabitable foroperations personnel duringandfollowing allcredibleaccidentconditions.

TheOPERABILITY ofthissysteminconjunction withcontrolroomdesignprovisions isbasedonlimitingtheradiation exposuretopersonnel occupying, thecontrolroomto5remorlesswholebody,oritsequivalent.

Thislimitation isconsistent withtherequirements ofGeneralDesignCriteria19ofAppendix"A",10CFR50.TheUnitIcontrolroomemergency ventilation systemoperatesautomatically onaSafetyInjection SignalfromeitherUnitIorUnit2.Theautomatic startfromUnit2isonlyavailable whentheUnit2ESFactuation systemisactiveinmodesIthrough4inUnit2.Thecontrolroomventilation systemnormallymaintains thecontrolroomattemperatures atwhichcontrolroomequipment isqualified forthelifeoftheplant.Continued operation attheTechnical Specification limitispermitted sincetheportionoftimethetemperature islikelytobeelevatedissmallincomparison tothequalified lifeoftheequipment atthelimit.3/4.7.6ESFVENTILATION SYSTEMTheOPERABILITY oftheESFventilation systemensuresthatadequatecoolingisprovidedforECCSequipment andthatradioactive materials leakingfromtheECCSequipment withinthepumproomfollowing aLOCAarefilteredpriortoreachingtheenvironment.

Theoperation ofthissystemandtheresultant effectonoffsitedosagecalculations wereassumedintheaccidentanalyses.

The1980versionofANSIN510isusedasatestingguide.Thisstandard, however,isintendedtoberigorously appliedonlytosystemswhich,unliketheESFventilation system,aredesignedtoANSIN509standards.

Forthespecificcaseoftheair-aerosol mixinguniformity testrequiredbyANSIN510asaprerequisite toin-placeleaktestingofcharcoalandHEPAfilters,theair-aerosol uniformmixingtestacceptance criteriawerenotrigorously met.Forthisreason,astatistical correction factorwillbeappliedtoapplicable surveillance testresultswhererequired.

3/4.7.7SEALEDSOURCECONTAMINATION TIMimitatio~~al~ure~emovabl~ntanmmtio~is~~otaWxxl~rindividu6@rgaairradiation material.

Thelimitations onremovable contamination forsourcesrequiring leaktesting,including alphaemitters, arebasedon10CFR70.39(c)limitsforplutonium.

Quantitiere&interest-t~~peeiAeation-vtthieh-are+xempt

[fitsrt4nafle~agc."rLyp~4V~V, s<<<+e,<<d>P~"~~yk<virtues.COOKNUCLEARPLANT-UNIT IPageB.3/47-5AMENDMENT 444,444,4',218 plIIW3 3/4BASES3/4.7PLANTSYSTEMS3t4..SEALEDSOURCCONTAMINATION ontinuedand70.19.Leakagefromsourceexcludedfromthereirementsofthissp'cattonisnotliketorepresemmorethanonimumpermissibl odyburdenfortotyirradiation ifsourcematerialis'ledoringested.

3/4.7.8HYDRAULIC SNUBBERSAllsnubbersarerequiredOPERABLEtoensurethatthestructural integrity ofthereactorcoolantsystemandallothersafetyrelatedsystemsismaintained duringandfollowing aseismicorothereventinitiating dynamicloads.Snubbersexcludedfromthisinspection programarethoseinstalled onnonsafety-related systemsandthenonlyiftheirfailureorfailureofthesystemonwhichtheyareinstalled, wouldhavenoadverseeffectonanysafety-related system.COOKNUCLEARPLANT-UNIT 1PageB3/47-5aAMENDMENT 159

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ATTACHMENT 3TOAEP:NRC:1315 PROPOSEDTECHNICAL SPECIFICATIONS PAGESREVISEDPAGESUNIT13/47-263/47-27B3/47-5B3/47-Sa 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCEREQUIREMENTS 3/4.7PLANTSYSTEMS3/4.7.7SEALEDSOURCECONTAMINATION LIMITINGCONDITION FOROPERATION 3.7.7.1Eachsealedsourcecontaining radioactive materialeitherinexcessof100microcuries ofbetaand/orgammaemittingmaterialor5microcuries ofalphaemittingmaterial, shallbefreeof20.005microcuries ofremovable contamination.

APPLICABILITY:

Atalltimes.ACTIONEachsealedsourcewithremovable contamination inexcessoftheabovelimitsshallbeimmediately withdrawn fromuseand:1.Eitherdecontaminatedand

repaired, or2.Disposedofinaccordance withCommission Regulations.

b.Theprovisions ofSpecification3.0.3 and3.0.4arenotapplicable.

SURVEILLANCE REUIREMENTS 4.7.7.1.1 TestReuirements

-Eachsealedsourceshallbetestedforleakageand/orcontaminationby:

a.Thelicensee, orb.Otherpersonsspecifically authorized bytheCommission oranAgreement State.Thetestmethodshallhaveadetectionsensitivityof atleast0.005microcuriesper testsample.4.7.7.1.2 Sourcesinuseexcludinstartusourcesandfissiondetectors reviouslsub'ected tocore~flux-Atleastoncepersixmonthsforallsealedsourcescontaining radioactive materials COOKNUCLEARPLANT-UNIT 1Page3/47-26AMENDMENT

~~~~3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCEREQUIREMENTS 3/4.7PLANTSYSTEMSSURVEILLANCERE UIREMENTS Continued 1.Withahalf-life greaterthan30days(excluding Hydrogen3),and2.Inanyformotherthangas.Storedsourcesnotinuse-Eachsealedsourceandfissiondetectorshallbetestedpriortouseortransfertoanotherlicenseeunlesstestedwithintheprevioussixmonths.Sealedsourcesandfissiondetectors transferred withoutacertificate indicating thelasttestdateshallbetestedpriortobeingplacedintouse.dayspriortobeingsubjected tocorefluxandfollowing repairormaintenance tothesource.4.7.7.1.3

~Rerts-ASpeeiaiReportshallbepreparedandsubmiuedto theCommission onanannualbasistfsealedsourceorfissiondetectorleakagetestsrevealthepresenceof20.005microcuries ofremovable contamination.

COOKNUCLEARPLANT-UNIT 1Page3/47-27AMENDMENT@9 Ip4E~IE.>

3/4BASES3/4.7PLANTSYSTEMS3/4.7.5CONTROLROOMEMERGENCY VENTILATION SYSTEMTheOPERABILITY ofthecontrolroomemergency ventilation systemensuresthatthecontrolroomwillremainhabitable foroperations personnel duringandfollowing allcredibleaccidentconditions.

TheOPERABILITY ofthissysteminconjunction withcontrolroomdesignprovisions isbasedonlimitingtheradiation exposuretopersonnel occupying thecontrolroomto5remorlesswholebody,oritsequivalent.

Thislimitation isconsistent withtherequirements ofGeneralDesignCriteria19ofAppendix"A",10CFR50.TheUnit1controlroomemergency ventilation systemoperatesautomatically onaSafetyInjection SignalfromeitherUnit1orUnit2.Theautomatic startfromUnit2isonlyavailable whentheUnit2ESFactuation systemisactiveinmodes1through4inUnit2.Thecontrolroomventilation systemnormallymaintains thecontrolroomattemperatures atwhichcontrolroomequipment isqualified forthelifeoftheplant.Continued operation attheTechnical Specification limitispermitted sincetheportionoftimethetemperature islikelytobeelevatedissmallincomparison tothequalified lifeoftheequipment atthelimit.3/4.7.6ESFVENTILATION SYSTEMTheOPERABILITY oftheESFventilation systemensuresthatadequatecoolingisprovidedforECCSequipment andthatradioactive materials leakingfromtheECCSequipment withinthepumproomfollowing aLOCAarefilteredpriortoreachingtheenvironment.

Theoperation ofthissystemandtheresultant effectonoffsitedosagecalculations wereassumedintheaccidentanalyses.

The1980versionofANSIN510isusedasatestingguide.Thisstandard, however,isintendedtoberigorously appliedonlytosystemswhich,unliketheESFventilation system,aredesignedtoANSIN509standards.

Forthespecificcaseoftheair-aerosol mixinguniformity testrequiredbyANSIN510asaprerequisite toin-placeleaktestingofcharcoalandHEPAfilters,theair-aerosol uniformmixingtestacceptance criteriawerenotrigorously met.Forthisreason,astatistical correction factorwillbeappliedtoapplicable surveillance testresultswhererequired.

3/4.7.7SEALEDSOURCECONTAMINATION Thelimitations onremovable contamination forsourcesrequiring leaktesting,including alphaemitters, arebasedon10CFR70.39(c)limitsforplutonium.

Thislimitation willensurethatleakagefrombyproduct, source,andspecialnuclearmaterialsourceswillnotexceedallowable intakevalues.COOKNUCLEARPLANT-UNIT 1PageB3/47-5AMENDMENT446, 424,4$9,Q4S g4Cr'er 3/4BASES3/4.7PLANTSYSTEMS3/4.7.8HYDRAULIC SNUBBERSAllsnubbersarerequiredOPERABLEtoensurethatthestructural integrity ofthereactorcoolantsystemandallothersafetyrelatedsystemsismaintained duringandfollowing aseismicorothereventinitiating dynamicloads.Snubbersexcludedfromthisinspection programarethoseinstalled onnonsafety-relatedsystems andthenonlyiftheirfailureorfailureofthesystemonwhichtheyareinstalled, wouldhavenoadverseeffectonanysafety-related system.COOKNUCLEARPLANT-UNIT 1PageB3/47-5aAMENDMENT 4$9

~ti~CATTACHMENT 4TOAEP:NRC:1315 EVALUATION OFSIGNIFICANT HAZARDSCONSIDERATION i'4 Attachment 4TOAEP:NRC:1315 Page1Evaluation ofSinificantHazardsConsideration Thelicenseehasevaluated thisproposedamendment anddetermined thatitinvolvesnosignificant hazardsconsideration.

According to10CFR50.92(c),

aproposedamendment toanoperating licenseinvolvesnosignificant hazardsconsideration ifoperation ofthefacilityinaccordance withtheproposedamendment wouldnot:1.involveasignificant increaseintheprobability ofoccurrence orconsequences ofanaccidentpreviously evaluated; 2.createthepossibility ofanewordifferent kindofaccidentfromanypreviously analyzed; or3.involveasignificant reduction inamarginofsafety.Thelicenseeproposes,to revisetechnical specification (T/S)3/4.7,7,"SealedSourceContamination,"

anditsassociated basestoaddresstestingrequirements forfissiondetectors.

Theproposedchangeswouldprovideconsistency withtheunit2T/Srequirements andNUREG-0452, "Standard Technical Specifications."

Thedetermination thatthecriteriasetforthin10CFR50.92aremetforthisamendment requestisindicated'elow.

1.Doesthechangeinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated?

Theproposedchangesclarifytestingrequirements forfissiondetectors.

Whenthefissiondetectors aretestedforsurfacecontamination, theydonotinterface withplantequipment andtheydonotaffectplantoperation.

Thedetectors arenotassumedtoinitiateanaccident; therefore, theprobability ofanaccidentpreviously evaluated isnotchanged.Conducting testspriortousinganewfissiondetectorprovidesassurance thatintakelimitswillnotbeexceeded.

Thereisnochangetothenuclearmaterialcontained inthedetector.

Thefissiondetectors arenotusedtomitigatetheconsequences ofpostulated accidents.

Therefore, theconsequences ofanaccidentremainthesameaspreviously evaluated.

Therefore, itisconcluded thattheproposedchangesdonotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

I2.Doesthechangecreatethepossibility ofanewordifferent typeofaccidentfromanyaccidentpreviously evaluated?

Theproposedchangesdonotaffectthedesignoroperation ofsystems,structures, orcomponents intheplant.Therearenochangestoparameters governing plantoperation, andnonewor Attachment 4TOAEP:NRC:1315 Page2different typeofequipment willbeinstalled.

Therefore, itisconcluded that.theproposedchangesdonotcreatethepossibility ofanewordifferent kindofaccidentfromanypreviously evaluated.

3~Doesthechangeinvolveasignificant reduction inamarginofsafety?Theproposedchangesdonotintroduce newequipment, equipment modifications, ornewordifferent modesofplantoperation.

Thesechangesdonotaffecttheoperational characteristics ofanyequipment orsystems.Therefore, itisconcluded thatthesechangesdonotinvolveasignificant reduction inthemarginofsafety.Insummary,basedupontheaboveevaluation, theLicenseehasconcluded thatthesechangesinvolvenosignificant hazardsconsideration.

ATTACHMENT 5TOAEP:NRC:1315 ENVIRONMENTAL ASSESSMENT

~~0fy' Attachment 5toAEP:NRC:1315 Page1Environmental Assessment TheLicenseehasevaluated thislicenseamendment requestagainstthecriteriaforidentification of'icensing andregulatory actionsrequiring environmental assessment inaccordance with10CFR51.21.TheLicenseehasdetermined thatthislicenseamendment requestmeetsthecriteriaforacategorical exclusion setforthin10CFR51.22(c)(9).Thisdetermination isbasedonthefactthatthischangeisbeingproposedasanamendment toalicenseissuedpursuantto10CFR50thatchangesarequirement withrespecttoinstallation oruseofafacilitycomponent locatedwithintherestricted area,asdefinedin10CFR20,orthatchangesaninspection orasurveillance requirement, andtheamendment meetsthefollowing specificcriteria:

(i)Theamendment involvesnosignificant hazardsconsideration.

Asdemonstrated inattachment 4,thisproposedamendment doesnotinvolveanysignificant hazardsconsideration.

(ii)Thereisnosignificant changeinthetypesorsignificant increaseintheamountsofanyeffluentthatmaybereleasedoffsite.Asdocumented inattachment 1,therewillbenochangeinthe,typesorsignificant increaseintheamountsofanyeffluents releasedoffsite.(iii)Thereisnosignificant increaseinindividual orcumulative occupational radiation exposure.

Theproposedchangeswillnotresultinsignificant changesintheoperation orconfiguration ofthefacility.

Therewillbenochangeinthelevelofcontrolsormethodology usedforprocessing ofradioactive effluents orhandlingofsolidradioactive waste,norwilltheproposalresultinanychangeinthenormalradiation levelswithintheplant.Therefore, therewillbenoincreaseinindividual orcumulative occupational radiation exposureresulting fromthischange.

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