ML17324B134

Application for Amends to Licenses DPR-58 & DPR-74,changing Tech Spec 3/4.4.5, Steam Generators, to Clarify Requirements for Steam Generator Tube Integrity.Fee Paid

ML17324B134
Person / Time
Site:	Cook
Issue date:	11/13/1986
From:	ALEXICH M P INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	DENTON H R Office of Nuclear Reactor Regulation
Shared Package
ML17324B135	List: ML17324B134 ML17324B136
References
AEP:NRC:0936D, AEP:NRC:936D, NUDOCS 8611180250
Download: ML17324B134 (9)

Text

REGULATORY

-ORl1ATIONDISTRIBUTION SYS(RIDS)ACCESSION NBR-'611180250 DOC.DATE:86/11/13NOTARIZED:

NODOCKETFACIL:50-315DonaldC.CookNuclearPowerPlantiUnit1>Indiana50500031550-316DonaldC.CoolNuclearPowerPlantiUnit2.Indiana005000316AUTH.NANEAUTHORAFFILIATION ALEXICH,N.P.Indiana8rNichiganElectricCo.RECIP.NANERECIPIENT AFFILIATION DENTONpH.R.OfficeoFNuclearReactorRegulationi Director(post851125

SUBJECT:

Application foramendtoLicensesDPR-588cDPR-74>changingTechSpec3/4.4.Si"SteamGenerators" toclarifgrequirements forsteamgenerator tubeintegritg.

DISTRIBUTION CODE:A058DCOPIESRECEIVED:

LTRENCLSIZE:TITLE:OR/Licensing/Generic Submittal:

SteamGenerator ubeIntegritg (WaterNOTES:RECIPIENT IDCODE/NANE PWR-AADTSPWR-AEICSBPWR-APD4LAWIQQINQTON DPWR-ARSBINTERNALIEDIRNRRPWR-AADTSNRR/DSRO/EIB COPIESLTTRENCL1221111111RECIPIENT IDCODE/NANE PWR-AEBPWR-AFOBPWR-APD4PDPWR-APSBNRRBWR*DTS-B*DTSREGFIL01COPIESLTTRENCL1111111111EXTERNAL:

LPDRNSIC221NRCPDR11TOTALNUNBEROFCOPIESREQUIRED:

LTTR20ENCL20 t~rI~%tl,I~tN,,N4 INDIANA8MICHIGANELECTRICCOMPANYP.O.BOX16631COLUMBUS, OHIO43216November13,1986AEP:NRC:0936D DonaldC.CookNuclearPlantUnitNos.1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74STEAMGENERATOR TUBEINTEGRITY TECHNICAL SPECIFICATIONS CHANGEREQUESTMr.HaroldR.Denton,DirectorOfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission Washington, D.C.20555

DearMr.Denton:

Thisletteranditsattachments constitute anapplication foramendment totheTechnical Specifications (T/Ss)fortheDonaldC.CookNuclearPlantUnitNos.1and2.Specifically weareproposing achangetoT/Ss3/4.4.5,SteamGenerators, toclarifythattherequirements areforsteamgenerator tubeintegrity.

Thereasonsfortheproposedchangeandouranalysisconcerning significant hazardsconsiderations arecontained inAttachment 1tothisletter.TheproposedrevisedTechnical Specification pagesarecontained inAttachment 2.Webelievethattheproposedchangewillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.

TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee (PNSRC)andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee (NSDRC)attheirnextregularly scheduled meeting.Incompliance withtherequirements of10CFR50.91(b)(1),

copiesofthisletteranditsattachments havebeentransmitted toMr.R.C.CallenoftheMichiganPublicServiceCommission andMr.G.Bruchmann oftheMichiganDepartment ofPublicHealth.Pursuantto10CFR170.12(c),

wehaveenclosedanapplication feeof$150.00fortheproposedamendments.

if.3eoR~Oagii18ocg0500oasoe~~iosisP--'iM@g~&.00 p)Mr.HaroldR.Denton-2-AEP:NRC:0936D Thisdocumenthasbeenpreparedfollowing Corporate procedures whichincorporate areasonable setofcontrolstoinsureitsaccuracyandcompleteness pri.ortosignature bytheundersigned.

Verytrulyyours,fM.Q.Aleichg,Ciceesxen0)gcmAttachments cc'.JohnE.DolanW.G.Smith,Jr.-BridgmanG.Bruchmann R.C.CallenG.CharnoffNRCResidentInspector

-Bridgman ATTACHMENT 1TOAEP:NRC:0936D REASONSAND10CFR50.92ANALYSISFORCHANGETOTHEDONALDC.COOKNUCLEARPLANTUNITNOS.1AND2TECHNICAL SPECIFICATIONS aII Attachment toAEP:NRC:0936D Page1Inrecentdiscussions withNRCstaff,adiscrepancy wasbroughttoourattention concerning T/Srequirements forsteamgenerators, specifically T/S3/4.4.5.TheBasessectiontothisT/SclearlystatesthatthepurposeoftheT/Sandassociated surveillance requirements istomaintainthestructural integrity ofthesteamgenerator tubes.ThecurrentT/S,however,addresses onlytheoperability ofthesteamgenerator.

Webelievethescopeofthesteamgenerator operability includessteamgenerator tubeintegrity, butweagreewiththeNRCstaffthatthisshouldbestatedexplicitly.

Weproposethefollowing changes1.Retitlethesectionbeginning onpage3/44-7"SteamGenerator TubeIntegrity."

Thecorresponding Basessectionisalsoretitled.

2.ChangetheLimitingCondition forOperation 3.4.5to"Thetubeintegrity ofeachsteamgenerator shallbemaintained."

Changethe"Action"onpage3/44-7toread:"Withthetubeintegrity ofoneormoresteamgenerators notmaintained, restorethetubeintegrity oftheaffectedsteamgenerator(s) priortoincreasing Tabove200F."avgInT/Ss4.4.5.0,4.4.5.1and4.4.5.4.b, deletetheword"OPERABLE" andinsertthephrase"Thetubeintegrity of."5.InTable4.4-1,Notation2,page3/44-12,changethewords"Eachoftheothertwo"to"thethirdandfourth"andaddtheword"respectively" forclarity.Asstatedabove,webelievethescopeofthecurrentT/Sincludessteamgenerator tubeintegrity.

Steamgenerator operability, whichisdeletedfromthisT/S,isaddressed inT/S3/4.4.1(ReactorCoolantLoopsandCoolantCirculation).

Thesechangesdonotaffecttherequirements ofT/S3/4.4.1.Therefore webelievethesechangesareadministrative andmerelyclarifythe'intent ofT/S3/4.4.5.Per10CFR50.92,aproposedamendment willnotinvolveasignificant hazardsconsideration iftheproposedamendment doesnot:(1)involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, (2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously analyzedorevaluated, or(3)involveasignificant reduction inamarginofsafety.Criterion.

1ThechangesproposedinthisletterwillclarifytheintentoftheT/Sbutwillnotimpactplantcomponents orsystems.Therefore webelievethesechangeswillnotinvolveasignificant increaseintheprobability orconsequences ofapreviously evaluated accident.

Attachment toAEP:NRC:0936D Page2Criterion 2Thesechangesarepurelyadministrative innature.Theplantsystems,components andoperation willnotbealteredbythesechanges.Therefore webelievethischangewillnotcreatethepossibility ofanewordifferent kindofaccidentthanhaspreviously beenanalyzedorevaluated.

Criterion 3Sincethesechangesareadministrative innature,theywillnotimpacttheabilityofplantsystemsandcomponents toperformtheirsafetyfunction.

Therefore webelievethesechangeswillnotinvolveasignificant reduction inamarginofsafety.TheCommission hasprovidedguidanceconcerning thedetermination ofsignificant hazardsbyproviding certainexamples(48FR14780)ofamendments considered notlikelytoinvolveasignificant hazardsconsideration.

Thefirstexampleisthatofapurelyadministrative changetotheT/Ss:forexample,achangetoachieveconsistency throughout theT/Ss,correction ofanerror,orachangeinnomenclature.

Webelievethatthechangesrequested inthisletterareofthetypespecified intheexample.Sincethesechangesareadministrative innature,theydonotreduceamarginofsafety,donotincreasetheprobability orconsequences ofapreviously analyzedaccident, anddo'otintroduce thepossibility ofanewaccident.

Therefore, webelievethesechangesdonotinvolveasignificant hazardsconsideration asdefinedby10CFR50.92.WerequestthatthetitleoftheBasesSection3/4.4.5bechangedtocorrespond tothechangeintitleofT/S3/4.4.5.Inaddition, wewouldliketoaddthefollowing statement toT/SBases3/4.4.5:"InMODES1,2,3and4thetubeintegrity ofthesteamgenerators shallbeconsidered maintained iftheprimary-to-secondary leakagerateiswithinthelimitsofSpecification 3.4.6.2."

Thisstatement clarifies theintentofthechangeinnomenclature andbetterdefinestheterm"tubeintegrity."

ATTACHMENT 2TOAEP:NRC:0936D REVISEDPAGESFORTHEDONALDC.COOKNUCLEARPLANTUNITNOS.IAND2TECHNICAL SPECIFICATIONS