ML17334A975

Forwards Complete & Detailed Description of post-accident Sampling Sys Per Reqirements of NUREG-0737,Section II.B.3. Exemption from Section II.B.3 for Listed Items Requested. Fee Paid

ML17334A975
Person / Time
Site:	Cook
Issue date:	06/27/1986
From:	ALEXICH M P INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	DENTON H R Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM AEP:NRC:0678V, AEP:NRC:678V, NUDOCS 8607010188
Download: ML17334A975 (15)

Text

INDIANA8MICHIGANELECTRICCOMPANYP.O.BOX16631COLUMBUS, OHIO43216June27,1986AEP:NRC:0678V DonaldC.CookNuclearPlantUnitNos.1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74NUREG-0737, SECTIONII.B.3POST-ACCIDENT

SAMPLING, SYSTEMMr.HaroldR.Denton,DirectorOfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission Washington, D.C.20555

DearMr.Denton:

PerItemIofourletterAEP:NRC:0678S, datedFebruary19,1986,attachedisacompleteanddetaileddescription ofthePost-Accident Sampling(PAS)Systemrelativetotherequirements ofNUREG-0737, SectionII.B.3.Asaresultoftheevaluation completed byNUSCorporation, wearerequesting exemptions fromNUREG-0737, SectionII.BE3forthefollowing:

1.Undiluted backupgrabsamplesforin-linemonitoring.

2.Heat-tracing containment airsamplelinetopreventplate-out ofiodine.3.Transporting containment atmosphere sampleforhydrogenanalysis.

OurscheduleforclosingoutNUREG-0737, SectionII.B.3(MPA5F-12)isdependent ontheNRC'sresponsetotheaboverequestsforexemption.

Pursuanttotherequirements of10CFR170.12(c),

wehaveenclosedanapplication feeof$150.00forreviewofthisexemption request.Thisdocumenthasbeenpreparedfollowing Corporate procedures whichincorporate areasonable setofcontrolstoinsureitsaccuracyandcompleteness priortosignature bytheundersigned.

Verytrulyyours,M.P.AlexichVicePresident

'lgSIcmAttachment cc:JohnE.DolanW.G.Smith,Jr.-BridgmanR.C.CallenG.Bruchmann G.CharnoffNRCResidentInspector

-Bridgman8g07010188 860+2PDRADQCK05000318P ie*A1PEJlJ Attachment toAEP:NRC:0678V 0DEC.COOKPLANTPASPROGRAMAsaresultofNUREG-0578, NUSCorporation wascontracted inMay1980todesignandfabricate apost-accident sampling(PAS)systemfortheDonaldC.CookNuclearPlant.InOctober1980,duringfabrica-tionofthePASpanels,NUREG-0737 wasissued.Newrequirements andclarifications forthePASsystemwereincludedinItemII.B.3.whichhadnotbeenoriginally incorporated inthePASpaneldesign.Theserequirements specifically includedchlorideanalysisofreactorcoolantsamples.Duetosizeconstraints andstipulated installation deadlines, in-linechlorideanalysiscouldnotbeincorporated intothePASsamplingequipment.

Fabrication andtestingoftheequipment werecompleted inAugust1981.Theequipment wasshippedinSeptember 1981.Clarifications toNUREG-0737 ItemII.B.3wereissuedinJune1982addingnewrequire-mentstothePASsystem.Tocomplywiththeserequirements, severalmodifications tothePASsystemwereinitiated.

Aftercompletion ofthesemodifications, NUSwascontracted in1985toprovideverification andcompliance testingofthePASsystem.Thistestworkwascompleted inMay1986.TheresultsofthistestworkandreviewofthePASsystemtomeettheintentofNUREG-0737 haveresultedinarequestforthefollowing exemptions fromNUREG-0737:

'1)Exemtionfromundiluted backurabsamlesforin-lineIn-linemonitoring forpHanddissolved oxygenandin-linedegassing foidissolved hydrogenarepreferable toandmoreaccuratethangrabsampleanalyses.

Toinsurethefunctional capability ofthesein-lineapparatus, apreventive mainten-anceprogramisperformed semi-annually.

Also,routineuseofthesesystemsisnecessitated bytheplanttrainingprogram.Iffailureshouldoccurduringlong-term post-accident conditions, thecapability existstoflushallsamplelinesandreplacethefailedcomponents.

2)Exemtionfromheat-tracin containment airsamlelinetorevent.late-outofiodine.ThePAScontainment airsamplesareanalyzedforisotopicnoblegasesandhydrogenonly.Isotopiciodinesandnon-volatile fissionproductsareanalyzedinthereactorcoolantandcontainment sumpforassessment ofcoredamage.Therefore, heat-tracing ofthecontainment airsamplelineisnotnecessary andwouldservenopurpose.3)Exemtionfromtransortincontainment atmosheresamleforhdroenanalsis.ThePASsystemhasthecapability toobtainandanalyzeanundiluted containment atmosphere sampleforhydrogenusinganin-linegaschromatograph.

Otherwise, containment atmosphere samplesaredilutedandtransported tothecountingfacility fornoblegasanalysis.

Analysisofthedilutedsampleforhydrogenwouldnotbewithintherangeofthelaboratory gaschromatograph.

PASSYSTEMDESCRIPTION TheD.C.CookPlantPASsystemconsistsofaliquidandgassamplepanel(LGSP),anUndiluted LiquidSampleStation(ULSS),andrelatedcontrolpanels.Thesamplecollection stationsarelocatedonelevation 587'ftheauxiliary building.

Thesampleanalysisfacilities arelocatedonelevation 609'ftheauxiliary buildingapproximately 220'romthePASsamplingpanellocations.

Grabsamplesfromeithersamplingstationareremovedbylead-shielded syringeandtransported inashieldedcontainer totheanalytical facilities.

Timeandmotionstudieshavebeenconducted toverifythatsamplesofreactorcoolantandcontainment atmosphere canbeobtainedandanalyzedwithinthreehoursfromthetimeadecisionismadetotakeasample.ThePASstationsarepoweredfromanemergency powersupplyorfromthe250V.D.C.stationbatterysystem,andtherefore samplescanbeobtainedduringlossofoffsitepower.Thesamplesrequiring laboratory analysiscanbeanalyzedonlyafteroffsitepowerisrestored.

Basedonthenumberandhighreliability ofCookPlantoffsitepowersources,thesampleanalysiscanbemadewithinthethreehoursfromthetimeadecisionismadetotakeasample.TableIshowsthesamplingandanalytical capabilities ofthePASsystem.Thesystemhasprovisions forsamplingthelocations showninTableIforeitherunitfollowing aLOCA.(3)

LGSPisdesignedforin-lineanalysisofundiluted samplesandfordilutionofgrabsamples.In-lineanalysesareprovidedforpHanddissolved oxygenmeasurements.

Dissolved hydrogenintheireactorcoolantisanalyzedbyanin-linegaschromatograph.

Dilutionofliquidgrabsamplesisperformed byisolating a10mlsampleofreactorcoolantintheLGSPanddilutingwith10litersofdemineralized water.Verification ofthedilutionfactorwasperformed usinglithiumhydroxide andcomparison ofsolubleisotopesI-131,I-133,I-135andNa-24.Acomparison ofallisotopes(suchasCs-134,Te-129andSr-89)wasnotpossiblebecauseofthelowlevelsofradio-activityinthetestdataLGSPdilutedsamples.Themeandilutionfactorwasdetermined tobe846.TheLGSPandULSShaveeightinchesofleadshielding.

TheLGSPhasaventilation systemtoremoveairborneradiation shouldaleakoccurinthepanel.Thisexhaustisfilteredthroughacharcoaladsorberandahigh-efficiency particulate filterintotheauxiliary buildingventilation system.ThesystemisdesignedtoobtainsamplesunderLOCAconditions withoutexposinganyindividual toradiation inexcessof5remtothewholebodyandor75remtotheextremities.

TheULSSisdesignedtocollectanundiluted reactorcoolantsamplefromHotLegs1or3within96hoursoftheaccident.

Thesampleisremovedbyalead-shielded syringein30daystoprovidebackupchlorideanalysis.

ThePASsystemincorporates meansforadequatepurgingofgasandliquidsamplelines.ThepurgeratesforliquidandgassamplesareSdependent onthepressuredropanddrivingforceofeachsamplepoint.(4)

~.Theminimumpurgetimeforthefurthermost point(theUnit2HotLegs1a3)isapproximately 5minutesat4gpm.Tominimizesampleleakage@thesamplelinesuptoandfromtheLGSPandULSSarewelded.Demineralized waterornitrogenisavailable tobeusedtoflushallpost-accident samplelinestominimizeblockage.

TheLGSPliquidsampleinletfiltercanbeback-flushed withdemineralized water.SamplepurgeandflushfluidsareroutedtoaPASwastecollection tank,thenpumpedtothecontainment oftheunitwheretheaccidenthasoccurred.

Thesesamplewastelineshaveremotelyoperatedcontainment isolation valvestoshutoffwasteflowifnecessary.

AllPASvalvesnotaccessible afteranaccidenthavebeenmodifiedtobeenvironmentally qualified forconditions inwhichtheymustoperate.Tooperatethethreeair-operated sampleisolation valvesinsidecontainment, procedures provideforopeningtheinstrument aircontainment isolation valvesafteracontainment isolation signalhasbeeninitiated.

Comparison ofanalytical resultsofsamplesfromthevariouslocations canbeusedtoevaluatesamplerepresentativeness andadequacyofmixing.Inconjunction withthiscomparison, comparison ofphysicalparameters, e.g.,coretemperature andreactorcoolantsystempressure, isavailable tofurtherensurethatrepresentative samplesarebeingtaken.Processauxiliary systemscarryingreactorcoolantorcontainment atmosphere gaseswhichareisolatedpostaccident(i.e.,theletdownsystemorthereactorwatercleanupsystem)arenotrequiredtobeplacedinoperation, butportionsoftheexistingNuclearSamplingSystemmustbeplacedinservicetoobtainpost-accident samples.

APASpreventive maintenance programhasbeendeveloped andwillbeperformed everysixmonthsbyanoutsidecontractor, commencing approximately October1986.ThisprogramincludesserviceofallPAScomponents andcomparison testingtonormalsampledata.ThePAStrainingprogramconsistsofclassroom andon-the-job training.

Qualification forthePASSystemoperation isperformed byclassroom andpaneloperation testing.Chemistry technicians arerequalified everysixmonths.PASANALYTICAL CAPABILITIES TableIIdepictstheanalytical capabilities ofthepost-accident samplingsystem.Matrixtestingforboron,dissolved oxygen,chlorideandpHanalysiswereperformed byNUSCorporation.

Adescription ofeachanalysisfollows.BoronBoronanalysisisperformed usingafluoroborate selective ionelectrode.

Therangeofanalysisis375to2000ppmboronwithanaccuracyof+11.4%.Thisrangeisadequatetoconfirmminimumshutdownmarginduringpost-accident conditions.

Comparison testingshowedthePASanalysistobewithin11.7%oftheanalysisofanormal(undiluted) sample.Dissolved

~sdnoenDissolved hydrogenanalysisisperformed byisolating 10mlofundiluted reactorcoolantintheLGSP.Thesampleisstrippedand(6) degassedusingnitrogen(revisions aretobemadetouseargonforthispurpose)andcollected ina150mlpanel-mounted flask.(Adesignchangecurrently beingprocessed willsubstitute argonasthestripping gas.)Thestrippedgasissweptthroughtheevacuated systemintoaBaselineGasChromatograph (GC).Thehydrogencontentisrecordedonastripchart.TheGCiscalibrated overa0-2000cc/kgrange.TheaccuracyoftheGCwasdetermined tobe+11%for15cc/kgand+5.6%for750cc/kg.Thecomparison testshowedthePASanalysistobewithin+5cc/kgoftheanalysisofanormalsample(40cc/kg).

Dissolved

~OxenDissolved oxygenanalysisisperformed usinganin-lineYellowSpringsInstrument dissolved oxygenprobeandremoteanalyzer-recorder.

Therangeoftheanalyzeris0-20ppmwithanaccuracyof+10%.APASanalysisshowed2.4ppmand0.05ppmcomparedtotheanalysisofanormalsample(2ppmand0ppm,respectively).

pHThepHanalysisisperformed usinganin-lineHorizonanalogpHmeterequippedwithagel-filled combination pHsensingelectrode.

Thesrangeoftheanalyzeris0-14pHwithaaccuracyof+.15pHunits.Comparison testingwithnormalsamplinganalyseswaswithin.01to.05pHunits.ChlorideChlorideanalysiscanbeperformed onadilutedreactorcoolantgrabsamplewithin96hoursoftheinitiation oftheLOCA.Thelower limitofdetectability isapproximately 10ppmusinganIonChromatograph.

Additionally, ULSSisusedtoobtainanundiluted backupgrabsamplefromthereactorcoolantHotLegs1or3forchlorideanalysis.

Thissampleiscollected inanin-line75mlflaskinthesamplestation.(Adesignchangehasbeeninitiated toinstallthein-lineflaskwhichisonsite.Presently, samplesarecollected ina50mlbottleinsidealeadpig).Within30days,asamplecanbeobtainedfromtheflaskusingalead-lined syringeandanalyzedintheIonChromatograph.

Theundiluted sample'slowerlimitofdetectability is10ppbchlorides.

Comparison testingcouldnotbeperformed duetothelowlevelofchlorideinthereactorcoolant.Radionuclides Radionuclide analysisofreactorcoolantisperformed onadilutedgrabsample.Thesampleisremovedusingalead-lined syringeandtakentothecountingroomforgammaanalysisusingtheSeries85MCAwithpdpll/24computerandGe(Li)/HPGe detector.

Thedetectoriscompletely surrounded bya4-inch-thick leadcavewhichactsasashieldfromexternalradiation fields.Thedetectormustbeshielded, sinceatradiation fieldsgreaterthan10mR/hr,thedetectordoesnotfunctionproperly.

Anexternalbackground radiation, fieldof50mR/hr,theexpecteddoseratefromunisolated letdownflowwillbereducedbyafactorof5000toapproximately 0.01mR/hr,whichwillnotaffecttheoperation ofthedetector.

However,intheunlikelyeventofcountingroomventilation failure,theairborneactivityinthecountingfacilitycouldpotentially risetoadoserateofupto981mR/hr.Therefore, samplescouldnotbeanalyzedasthe(8) doserateinsidethecavewouldexceedthe10mR/hroperational limitforthedetectorduetoairbornecontamination.

Inthatcase,radio-nuclideanalysiswouldhavetobedelayeduntilthecondition wascorrected.

Therangeofthecountingequipment forradionuclides willbewithinthe1uCi/gto10Ci/gwithanaccuracyof+10%.DilutionofPASsampleswillreducetheactivitytonormalsamplelevels.Compar-isontodailysurveillance samplesshowedadeviation rangefrom-7.7%to10.5%.hAnalysisofnoblegasfromthelowercontainment atmosphere isperformed onadilutedgrabsample.Containment atmosphere samplesarecapturedintheLGSPineithera0.5ccor5.0ccisolation chamber.Thesampleisthenpurgedintoanevacuated 1literpanel-mounted vesselusingargonfordilution.

Samplesarethenremovedfromthevesselusingalead-shielded syringeandtransported tothecountingroomfornoblegasanalysis.

Thehydrogenanalysisisperformed onanundiluted containment atmosphere sampleusingthein-lineBaselineGasChromatograph.

Gasdilutionsystemtestingwasperformed byNUSCorporation.

Thedilutionfactorsobtainedfromthetestingdemonstrated adilutionof1:225forthe5.0ccsampleand1:1997forthe0.5ccsamplewithanaccuracyof-0.2%to+11.25%.

TABLEIIAMLYSISReaatorCoolantBoronDissolved HydrogenDissolved OxygenpHRANGE0.375-2.0ppm0-2000cc/kgO.l-20ppm0-14ACCURACY+11.4%5.6%>50cc/kg+11%,<50cc/kg+0.15pH>5<9+0.15pH<5>9METHODFluoroborate Selective IonElectrode GasChromatography In-lineprobeIn-lineprobeChlorideRadionuclide ntainment AtmoshereNobleGasHydrogen'>10ppm(diluted)

>10ppb(undiluted) 1pCi/g-10Ci/gFactorof21pCi/g-10Ci/gFactorof20-4%IonChromatography Ge(Li)DetectorGe(Li)DetectorGasChromatograph TABLEISAMPLELOCATIONRADIONUCLIDEB BORONCHLORIDED.O.HotLeglor3D,GD,GDorU,GU,IU,IU,IN/APressurizer SteamSpaceRHREorWLowerContainment SumpLowerContainment Atmosphere D,GD,GD,GD,GD,GD,GD,GD,GD,GD,GU,IU,IU,IN/AN/AN/AN/AU,IU,IU,IN/AN/AN/A~N/AU,IN/ANotApplicable G-GrabSampleI-In-LineAnalysisD-DilutedU-Undiluted D.O.-Dissolved OxygenD.11.-Dissolved Hydrogen

\reJune24,1986DOCKETNO(S).50-315/316 ttr.JohhDohan,ViceePresident IndianaandMichiganElectricCompanyc/oAmericanElectric, PowerServiceCorporation 1Riverside PlazaColumbus, Ohio43216

SUBJECT:

D.C.CookPlant,Units1and2.r/~,~/"/r/er4i/DISTRIION:w/oenclosure

~Docket-F-i.le~

PRCSystemNRCPDRLocalPDRPWR84RdgBJYoungblood Rdgt1DuncanDlligginton OGCACRS(10)JPartlowBGrimesEJordanNThompson Thefollowing documents concerning ourreviewofthesubjectfacilityaretransmitted foryourinformation.

DNoticeofReceiptofApplication, datedDDraft/Final Environmental

Statment, datedDNoticeofAvailability ofDraft/Final Environmental Statement, datedDSafetyEvaluation Report,orSupplement No.,datedDNoticeofHearingonApplication forConstruction Permit,datedDNoticeofConsideration ofIssuanceofFacilityOperating License,datedIIPMonthlyNotice;Applications andAmendments toOperating LicensesInvolving noSignificant HazardsConsiderations, datedJul161986.(Seepage25770)DApplication andSafetyAnalysisReport,VolumeDAmendment No.toApplication/SAR datedDConstruction PermitNo.CPPR-DFacilityOperating LicenseNo.,Amendment No.,Amendment No.dated,datedDOrderExtending Construction'Completion Date,datedDOther(Specify/

Enclosures:

AsstatedOfficeofNuclearReactorRegulation cc:Seenextpage.PjM4/PN.07/4+86.

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