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{{#Wiki_filter:A'CCKLFRATEDSISTRIBUTlONDEMO.iSTRATIONSYSTEMREGULAT(ZNFORMATZONDZSTRZBUTZONZSTEM(RZDS)ACCESSIONNBR;8902080288DOC.DATE:89/02/03NOTARIZED:NODOCKETIFACIL:50-316DonaldC.CookNuclearPowerPlant,Unit2,Indiana&05000316AUTH.NAMEAUTHORAFFILIATIONALEXICH,M.P.IndianaMichiganPowerCo.(formerlyIndiana&MichiganEleRECIP.NAMERECIPIENTAFFILIATIONMURDEY,T.E.OfficeofNuclearReactorRegulation,Director(Post870411
{{#Wiki_filter:A'CCKLFRATED SISTRIBUTlON DEMO.iSTRATIONSYSTEMREGULAT(ZNFORMATZON DZSTRZBUTZONZSTEM (RZDS)ACCESSION NBR;8902080288 DOC.DATE:
89/02/03NOTARIZED:
NODOCKETIFACIL:50-316 DonaldC.CookNuclearPowerPlant,Unit2,Indiana&05000316AUTH.NAMEAUTHORAFFILIATION ALEXICH,M.P.
IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION MURDEY,T.E.
OfficeofNuclearReactorRegulation, Director(Post870411


==SUBJECT:==
==SUBJECT:==
ApplicationtoamendDPR-74,tomodifyT/STable3.2-1(DNBParameters).DISTRIBUTION'CODE:A001DCOPIESRECEIVED:LTRIENCLJSIZE:(P+~TITLE:ORSubmittal:GeneralDistributionNOTES:RECIPIENTIDCODE/NAMEPD3-1LASTANGFJCOPIESLTTRENCL1011RECIPIENTIDCODE/NAMEPD3-1PDCOPIESLTTRENCL22INTERNAL:ARM/DAF/LFMBNRR/DEST/CEB8HNRR/DEST/MTB9HNRR/DEST/SICBNUDOCS-BSTRACTE01EXTERNAL:LPDRNSIC101111111111-1111NRR/DEST/ADS7ENRR/DEST/ESB8DNRR/DEST/RSB8ENRR/DOEA/TSB11OGC/HDS1RES/DSIR/EIBNRCPDR11111111101111RINOrE'roALLRIDS~XXPIENXS.PLEASEHELPUSTOREDUCEHASTE.'GWZACr'%HEDOCXMÃZ'CONrROLDESK,BOCKPl-37(EXT.20079)KOELGHZHtGRYOURMMEFBOHDISTRIHlTIQNLISTSPORDOCUMENXSVXJDGNFT5EEDtTOTALNUMBEROFCOPIESREQUIRED:LTTR19ENCL16 I
Application toamendDPR-74,to modifyT/STable3.2-1(DNBParameters).
IndianaWlichiganPowerCompanyP.O.Box16631.Columbus,OH432168AEP:NRC:1070A10CFR50.90DonaldC.CookNuclearPlantUnit2DocketNo.50-316LicenseNo.DPR-74TECHNICALSPECIFICATIONCHANGE:MINIMUMREACTORCOOLANTFLOWREQUIREMENTU.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Attn:T.E.MurleyFebruary3,1989
DISTRIBUTION'CODE:
A001DCOPIESRECEIVED:LTR IENCLJSIZE:(P+~TITLE:ORSubmittal:
GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD3-1LASTANGFJCOPIESLTTRENCL1011RECIPIENT IDCODE/NAME PD3-1PDCOPIESLTTRENCL22INTERNAL:
ARM/DAF/LFMB NRR/DEST/CEB 8HNRR/DEST/MTB 9HNRR/DEST/SICB NUDOCS-BSTRACTE01EXTERNAL:
LPDRNSIC101111111111-1111NRR/DEST/ADS 7ENRR/DEST/ESB 8DNRR/DEST/RSB 8ENRR/DOEA/TSB 11OGC/HDS1RES/DSIR/EIB NRCPDR11111111101111RINOrE'roALLRIDS~XXPIENXS.
PLEASEHELPUSTOREDUCEHASTE.'GWZACr
'%HEDOCXMÃZ'CONrROL DESK,BOCKPl-37(EXT.20079)KOELGHZHtGR YOURMMEFBOHDISTRIHlTIQN LISTSPORDOCUMENXS VXJDGNFT5EEDtTOTALNUMBEROFCOPIESREQUIRED:
LTTR19ENCL16 I
IndianaWlichigan PowerCompanyP.O.Box16631.Columbus, OH432168AEP:NRC:1070A 10CFR50.90DonaldC.CookNuclearPlantUnit2DocketNo.50-316LicenseNo.DPR-74TECHNICAL SPECIFICATION CHANGE:MINIMUMREACTORCOOLANTFLOWREQUIREMENT U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Attn:T.E.MurleyFebruary3,1989


==DearDr.Murley:==
==DearDr.Murley:==
ThisletteranditsattachmentsconstituteanapplicationforamendmenttotheTechnicalSpecifications(T/Ss)fortheDonaldC.CookNuclearPlantUnit2.Specifically,weproposetomodifyT/STable3.2-1(DNBParameters)suchthatthereactorcoolantsystemflowrateisexpressedonavolumetricratherthanamassbasis.TheproposedchangeisintendedtoensuretherequirementsofthesafetyanalysesareappropriatelyreflectedintheT/Ss.ThechangeissimilartoachangeproposedforUnit1oftheCookNuclearPlantinletterNo.AEP:NRC:1067,datedOctober14,1988.Attachment1tothislettersummarizesthebasisfortheproposedchangeandincludesoursignificanthazardsevaluation.Attachment2containstheproposedrevisedT/Spage.Attachment3containsaletterfromANF(theCookNuclearPlantUnit2fuelvendor)documentingtheirconcurrencewiththechange.Webelievethattheproposedchangeswillnotresultin(1)asignificantchangeinthetypesofeffluentsorasignificantincreaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificantincreaseinindividualorcumulativeoccupationalradiationexposure.TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommitteeandwillbereviewedbytheNuclearSafetyandDesignReviewCommitteeattheirnextregularlyscheduledmeeting.8+020802888V0203PDRADOCK05000~1+F'NUot/l(
Thisletteranditsattachments constitute anapplication foramendment totheTechnical Specifications (T/Ss)fortheDonaldC.CookNuclearPlantUnit2.Specifically, weproposetomodifyT/STable3.2-1(DNBParameters) suchthatthereactorcoolantsystemflowrateisexpressed onavolumetric ratherthanamassbasis.Theproposedchangeisintendedtoensuretherequirements ofthesafetyanalysesareappropriately reflected intheT/Ss.ThechangeissimilartoachangeproposedforUnit1oftheCookNuclearPlantinletterNo.AEP:NRC:1067, datedOctober14,1988.Attachment 1tothislettersummarizes thebasisfortheproposedchangeandincludesoursignificant hazardsevaluation.
Dr.T.E.Murley-2-AEP:NRC:1070AIncompliancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtoMr.R.C.CallenoftheMichiganPublicServiceCommissionandMr.GeorgeBruchmannoftheMichiganDepartmentofPublicHealth.ThisdocumenthasbeenpreparedfollowingCorporateproceduresthatincorporateareasonablesetofcontrolstoensureitsaccuracyandcompletenesspriortosignaturebytheundersigned.Sincerely,M..AlxichVicePresidentldpAttachmentscc:D.H.Williams,Jr.W.G.Smith,Jr.-BridgmanG~BruchmannR.C.CallenG.CharnoffA.B.Davis-RegionIIINRCResidentInspector-Bridgman ATTACHMENT1TOAEP:NRC:1070ADESCRIPTIONAND10CFR50.92SIGNIFICANTHAZARDSEVALUATIONFORCHANGESTOTHETECHNICALSPECIFICATIONSFORTHEDONALDC.COOKNUCLEARPLANTUNIT2 Attachment1toAEP:NRC:1070APage1WeareproposingtochangetheminimumrequiredreactorcoolantsystemflogratespecifiedinTable3.2-1(DNBParameters)from138.6x10lbs/hrtothecorrespondingflowrateof364,960gpm.Thischangeisadministrativeinnature,intendedtoensureconsistencybetweenthesafetyanalysisassumptionsandtheT/S.ThechangefrommassflowtovolumetricflowinT/STable3.2-1resultsfromourreviewoftherelationshipbetweentheanalysisassumptionandthesurveillancetestthatensuresthesafetyanalysisassumptionissatisfied.ThesafetyanalysesperformedbyAdvancedNuclearFuels(ANF),theUnit2fuelvendor,makeanassumptionregardingtheprimaryvolumetricflowatthecoreentrance.Thesurveillancetest,whichisacalorimetrictest,obtainsthemassflowrequiredtoremovetheheatgeneratedinthecoreatthemeasuredtemperaturedifferencebetweenthehotandcoldlegs.Thevolumetricflowisapproximatelyindependentofcoolanttemperature.However,themassflowdependsdirectlyoncoolantdensity,whichdoesvarywithtemperature.,Inordertoensureacorrectcomparisonbetweenthesafetyanalysisassumedflowandthemeasuredflow,weproposetospecifythevolumetricflowintheT/Ss.Thesurveillanceprocedurewillthenconvertthemeasuredmassflowtovolumetricflowusingtemperaturesfromthetestdata.Theproposedminimumflowvalueof364,960gpm)sthevolumetricflowcorrespondingtoamassflowof138.6x10lbs/hrandaninlettemperatureof542.3F.The364,960gpmvalueisexactly0fourtimesthesingleloopdesignflowvalueof91,240gpmspecifiedinT/STable2.2-1.Theinlettemperatureof542.3FisconsistentwiththeUnit2fullpowerTvalueof574.1F.ANF'sconcurrencewiththechangeisprovi8e5inAttachment3tothisletter.AsimilarchangewasproposedforUnit1oftheCookNuclearPlantinourletterAEP:NRC:1067,datedOctober14,1988.ThatletterprovidedtheanalysesandT/SchangeswhichsupportourreducedtemperatureandpressureprogramforUnit1.10CFR50.92EvaluationPer10CFR50.92,aproposedamendmentwillnotinvolvesignificanthazardsconsiderationiftheproposedamendmentdoesnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident,(2)createthepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluated,or(3)involveasignificantreductioninamarginofsafety.  
Attachment 2containstheproposedrevisedT/Spage.Attachment 3containsaletterfromANF(theCookNuclearPlantUnit2fuelvendor)documenting theirconcurrence withthechange.Webelievethattheproposedchangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee attheirnextregularly scheduled meeting.8+02080288 8V0203PDRADOCK05000~1+F'NUot/l(
Dr.T.E.Murley-2-AEP:NRC:1070A Incompliance withtherequirements of10CFR50.91(b)(1),
copiesofthisletteranditsattachments havebeentransmitted toMr.R.C.CallenoftheMichiganPublicServiceCommission andMr.GeorgeBruchmann oftheMichiganDepartment ofPublicHealth.Thisdocumenthasbeenpreparedfollowing Corporate procedures thatincorporate areasonable setofcontrolstoensureitsaccuracyandcompleteness priortosignature bytheundersigned.
Sincerely, M..AlxichVicePresident ldpAttachments cc:D.H.Williams, Jr.W.G.Smith,Jr.-BridgmanG~Bruchmann R.C.CallenG.CharnoffA.B.Davis-RegionIIINRCResidentInspector
-Bridgman ATTACHMENT 1TOAEP:NRC:1070A DESCRIPTION AND10CFR50.92SIGNIFICANT HAZARDSEVALUATION FORCHANGESTOTHETECHNICAL SPECIFICATIONS FORTHEDONALDC.COOKNUCLEARPLANTUNIT2 Attachment 1toAEP:NRC:1070A Page1Weareproposing tochangetheminimumrequiredreactorcoolantsystemflogratespecified inTable3.2-1(DNBParameters) from138.6x10lbs/hrtothecorresponding flowrateof364,960gpm.Thischangeisadministrative innature,intendedtoensureconsistency betweenthesafetyanalysisassumptions andtheT/S.Thechangefrommassflowtovolumetric flowinT/STable3.2-1resultsfromourreviewoftherelationship betweentheanalysisassumption andthesurveillance testthatensuresthesafetyanalysisassumption issatisfied.
Thesafetyanalysesperformed byAdvancedNuclearFuels(ANF),theUnit2fuelvendor,makeanassumption regarding theprimaryvolumetric flowatthecoreentrance.
Thesurveillance test,whichisacalorimetric test,obtainsthemassflowrequiredtoremovetheheatgenerated inthecoreatthemeasuredtemperature difference betweenthehotandcoldlegs.Thevolumetric flowisapproximately independent ofcoolanttemperature.
However,themassflowdependsdirectlyoncoolantdensity,whichdoesvarywithtemperature.,
Inordertoensureacorrectcomparison betweenthesafetyanalysisassumedflowandthemeasuredflow,weproposetospecifythevolumetric flowintheT/Ss.Thesurveillance procedure willthenconvertthemeasuredmassflowtovolumetric flowusingtemperatures fromthetestdata.Theproposedminimumflowvalueof364,960gpm)sthevolumetric flowcorresponding toamassflowof138.6x10lbs/hrandaninlettemperature of542.3F.The364,960gpmvalueisexactly0fourtimesthesingleloopdesignflowvalueof91,240gpmspecified inT/STable2.2-1.Theinlettemperature of542.3Fisconsistent withtheUnit2fullpowerTvalueof574.1F.ANF'sconcurrence withthechangeisprovi8e5inAttachment 3tothisletter.AsimilarchangewasproposedforUnit1oftheCookNuclearPlantinourletterAEP:NRC:1067, datedOctober14,1988.ThatletterprovidedtheanalysesandT/Schangeswhichsupportourreducedtemperature andpressureprogramforUnit1.10CFR50.92Evaluation Per10CFR50.92,aproposedamendment willnotinvolvesignificant hazardsconsideration iftheproposedamendment doesnot:(1)involveasignificant increaseintheprobability orconsequences ofapreviously evaluated
: accident, (2)createthepossibility ofanewordifferent kindofaccidentfromanypreviously evaluated, or(3)involveasignificant reduction inamarginofsafety.  


Attachment1toAEP:NRC:1070APage2Criterion1Thechangeisadministrativeinnature,consistingonlyofchangingamassflowratetoavolumetricflowrateattheappropriatetemperature.Thechangedoesnotlessenanypreviousrequirements.Thus,thechangeisnotexpectedtoincreasetheprobabilityorconsequencesofapreviouslyevaluatedaccident,norshoulditreducethemarginofsafety.Criterion2Thechangeisadministrativeinnature,intendedtoensureconsistencybetweentheT/Ssandthesafetyanalysisassumptions.Therefore,thechangeisnotexpectedtocreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluated.Criterion3SeeCriterion1above.WenotethattheCommissionhasprovidedguidanceconcerningthedeterminationofsignificanthazardsbyprovidingcertainexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thefirstoftheseexamplesreferstochangesthatarepurelyadministrativeinnature:forexample,changestoachieveconsistencythroughouttheT/Ss,correctionofanerror,orachangeinnomenclature.TheproposedchangesareintendedonlytoensurethatcurrentlyexistinganalysesarereflectedintheT/Ss.Webelievethatthechangesareadministrativeinnaturesincetheydonotreflectnewanalysesorpermitany'elaxationinrequirementsbutrather'larifytherelationshipbetweenanalysesandT/Ss.WethereforebelievethattheFederalRegisterexamplecitedisapplicableandthatthechangesinvolvenosignificanthazardsconsideration.Additionally,wehavemadeaneditorialchangetoTable3.2-1.Mathematicalsymbolshavebeenwrittenoutinwords.Sincethesechangesarepurelyeditorialinnature,theywillnotincreasetheprobabilityorconsequencesofapreviouslyevaluatedaccident,willnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluated,anddonotinvolvesignificanthazardsconsideration.
Attachment 1toAEP:NRC:1070A Page2Criterion 1Thechangeisadministrative innature,consisting onlyofchangingamassflowratetoavolumetric flowrateattheappropriate temperature.
ATTACHMENT2TOAEP:NRC:1070APROPOSEDTECHNICALSPECIFICATIONPAGE}}
Thechangedoesnotlessenanypreviousrequirements.
Thus,thechangeisnotexpectedtoincreasetheprobability orconsequences ofapreviously evaluated
: accident, norshoulditreducethemarginofsafety.Criterion 2Thechangeisadministrative innature,intendedtoensureconsistency betweentheT/Ssandthesafetyanalysisassumptions.
Therefore, thechangeisnotexpectedtocreatethepossibility ofanewordifferent kindofaccidentfromanypreviously evaluated.
Criterion 3SeeCriterion 1above.WenotethattheCommission hasprovidedguidanceconcerning thedetermination ofsignificant hazardsbyproviding certainexamples(48FR14870)ofamendments considered notlikelytoinvolvesignificant hazardsconsideration.
Thefirstoftheseexamplesreferstochangesthatarepurelyadministrative innature:forexample,changestoachieveconsistency throughout theT/Ss,correction ofanerror,orachangeinnomenclature.
Theproposedchangesareintendedonlytoensurethatcurrently existinganalysesarereflected intheT/Ss.Webelievethatthechangesareadministrative innaturesincetheydonotreflectnewanalysesorpermitany'elaxation inrequirements butrather'larifytherelationship betweenanalysesandT/Ss.Wetherefore believethattheFederalRegisterexamplecitedisapplicable andthatthechangesinvolvenosignificant hazardsconsideration.
Additionally, wehavemadeaneditorial changetoTable3.2-1.Mathematical symbolshavebeenwrittenoutinwords.Sincethesechangesarepurelyeditorial innature,theywillnotincreasetheprobability orconsequences ofapreviously evaluated
: accident, willnotcreatethepossibility ofanewordifferent kindofaccidentfromanypreviously evaluated, anddonotinvolvesignificant hazardsconsideration.
ATTACHMENT 2TOAEP:NRC:1070A PROPOSEDTECHNICAL SPECIFICATION PAGE}}

Revision as of 09:18, 29 June 2018

Application for Amend to License DPR-74,modifying Tech Spec Table 3.2-1, DNB Parameters to Express RCS Flow Rate on Volumetric Rather than Mass Basis.Util No Significant Hazards Evaluation Encl
ML17325B139
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 02/03/1989
From: ALEXICH M P
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To: MURLEY T E
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML17325B140 List:
References
AEP:NRC:1070A, NUDOCS 8902080288
Download: ML17325B139 (9)
v • d • e


Text

A'CCKLFRATED SISTRIBUTlON DEMO.iSTRATIONSYSTEMREGULAT(ZNFORMATZON DZSTRZBUTZONZSTEM (RZDS)ACCESSION NBR;8902080288 DOC.DATE:

89/02/03NOTARIZED:

NODOCKETIFACIL:50-316 DonaldC.CookNuclearPowerPlant,Unit2,Indiana&05000316AUTH.NAMEAUTHORAFFILIATION ALEXICH,M.P.

IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION MURDEY,T.E.

OfficeofNuclearReactorRegulation, Director(Post870411

SUBJECT:

Application toamendDPR-74,to modifyT/STable3.2-1(DNBParameters).

DISTRIBUTION'CODE:

A001DCOPIESRECEIVED:LTR IENCLJSIZE:(P+~TITLE:ORSubmittal:

GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD3-1LASTANGFJCOPIESLTTRENCL1011RECIPIENT IDCODE/NAME PD3-1PDCOPIESLTTRENCL22INTERNAL:

ARM/DAF/LFMB NRR/DEST/CEB 8HNRR/DEST/MTB 9HNRR/DEST/SICB NUDOCS-BSTRACTE01EXTERNAL:

LPDRNSIC101111111111-1111NRR/DEST/ADS 7ENRR/DEST/ESB 8DNRR/DEST/RSB 8ENRR/DOEA/TSB 11OGC/HDS1RES/DSIR/EIB NRCPDR11111111101111RINOrE'roALLRIDS~XXPIENXS.

PLEASEHELPUSTOREDUCEHASTE.'GWZACr

'%HEDOCXMÃZ'CONrROL DESK,BOCKPl-37(EXT.20079)KOELGHZHtGR YOURMMEFBOHDISTRIHlTIQN LISTSPORDOCUMENXS VXJDGNFT5EEDtTOTALNUMBEROFCOPIESREQUIRED:

LTTR19ENCL16 I

IndianaWlichigan PowerCompanyP.O.Box16631.Columbus, OH432168AEP:NRC:1070A 10CFR50.90DonaldC.CookNuclearPlantUnit2DocketNo.50-316LicenseNo.DPR-74TECHNICAL SPECIFICATION CHANGE:MINIMUMREACTORCOOLANTFLOWREQUIREMENT U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Attn:T.E.MurleyFebruary3,1989

DearDr.Murley:

Thisletteranditsattachments constitute anapplication foramendment totheTechnical Specifications (T/Ss)fortheDonaldC.CookNuclearPlantUnit2.Specifically, weproposetomodifyT/STable3.2-1(DNBParameters) suchthatthereactorcoolantsystemflowrateisexpressed onavolumetric ratherthanamassbasis.Theproposedchangeisintendedtoensuretherequirements ofthesafetyanalysesareappropriately reflected intheT/Ss.ThechangeissimilartoachangeproposedforUnit1oftheCookNuclearPlantinletterNo.AEP:NRC:1067, datedOctober14,1988.Attachment 1tothislettersummarizes thebasisfortheproposedchangeandincludesoursignificant hazardsevaluation.

Attachment 2containstheproposedrevisedT/Spage.Attachment 3containsaletterfromANF(theCookNuclearPlantUnit2fuelvendor)documenting theirconcurrence withthechange.Webelievethattheproposedchangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.

TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee attheirnextregularly scheduled meeting.8+02080288 8V0203PDRADOCK05000~1+F'NUot/l(

Dr.T.E.Murley-2-AEP:NRC:1070A Incompliance withtherequirements of10CFR50.91(b)(1),

copiesofthisletteranditsattachments havebeentransmitted toMr.R.C.CallenoftheMichiganPublicServiceCommission andMr.GeorgeBruchmann oftheMichiganDepartment ofPublicHealth.Thisdocumenthasbeenpreparedfollowing Corporate procedures thatincorporate areasonable setofcontrolstoensureitsaccuracyandcompleteness priortosignature bytheundersigned.

Sincerely, M..AlxichVicePresident ldpAttachments cc:D.H.Williams, Jr.W.G.Smith,Jr.-BridgmanG~Bruchmann R.C.CallenG.CharnoffA.B.Davis-RegionIIINRCResidentInspector

-Bridgman ATTACHMENT 1TOAEP:NRC:1070A DESCRIPTION AND10CFR50.92SIGNIFICANT HAZARDSEVALUATION FORCHANGESTOTHETECHNICAL SPECIFICATIONS FORTHEDONALDC.COOKNUCLEARPLANTUNIT2 Attachment 1toAEP:NRC:1070A Page1Weareproposing tochangetheminimumrequiredreactorcoolantsystemflogratespecified inTable3.2-1(DNBParameters) from138.6x10lbs/hrtothecorresponding flowrateof364,960gpm.Thischangeisadministrative innature,intendedtoensureconsistency betweenthesafetyanalysisassumptions andtheT/S.Thechangefrommassflowtovolumetric flowinT/STable3.2-1resultsfromourreviewoftherelationship betweentheanalysisassumption andthesurveillance testthatensuresthesafetyanalysisassumption issatisfied.

Thesafetyanalysesperformed byAdvancedNuclearFuels(ANF),theUnit2fuelvendor,makeanassumption regarding theprimaryvolumetric flowatthecoreentrance.

Thesurveillance test,whichisacalorimetric test,obtainsthemassflowrequiredtoremovetheheatgenerated inthecoreatthemeasuredtemperature difference betweenthehotandcoldlegs.Thevolumetric flowisapproximately independent ofcoolanttemperature.

However,themassflowdependsdirectlyoncoolantdensity,whichdoesvarywithtemperature.,

Inordertoensureacorrectcomparison betweenthesafetyanalysisassumedflowandthemeasuredflow,weproposetospecifythevolumetric flowintheT/Ss.Thesurveillance procedure willthenconvertthemeasuredmassflowtovolumetric flowusingtemperatures fromthetestdata.Theproposedminimumflowvalueof364,960gpm)sthevolumetric flowcorresponding toamassflowof138.6x10lbs/hrandaninlettemperature of542.3F.The364,960gpmvalueisexactly0fourtimesthesingleloopdesignflowvalueof91,240gpmspecified inT/STable2.2-1.Theinlettemperature of542.3Fisconsistent withtheUnit2fullpowerTvalueof574.1F.ANF'sconcurrence withthechangeisprovi8e5inAttachment 3tothisletter.AsimilarchangewasproposedforUnit1oftheCookNuclearPlantinourletterAEP:NRC:1067, datedOctober14,1988.ThatletterprovidedtheanalysesandT/Schangeswhichsupportourreducedtemperature andpressureprogramforUnit1.10CFR50.92Evaluation Per10CFR50.92,aproposedamendment willnotinvolvesignificant hazardsconsideration iftheproposedamendment doesnot:(1)involveasignificant increaseintheprobability orconsequences ofapreviously evaluated

accident, (2)createthepossibility ofanewordifferent kindofaccidentfromanypreviously evaluated, or(3)involveasignificant reduction inamarginofsafety.

Attachment 1toAEP:NRC:1070A Page2Criterion 1Thechangeisadministrative innature,consisting onlyofchangingamassflowratetoavolumetric flowrateattheappropriate temperature.

Thechangedoesnotlessenanypreviousrequirements.

Thus,thechangeisnotexpectedtoincreasetheprobability orconsequences ofapreviously evaluated

accident, norshoulditreducethemarginofsafety.Criterion 2Thechangeisadministrative innature,intendedtoensureconsistency betweentheT/Ssandthesafetyanalysisassumptions.

Therefore, thechangeisnotexpectedtocreatethepossibility ofanewordifferent kindofaccidentfromanypreviously evaluated.

Criterion 3SeeCriterion 1above.WenotethattheCommission hasprovidedguidanceconcerning thedetermination ofsignificant hazardsbyproviding certainexamples(48FR14870)ofamendments considered notlikelytoinvolvesignificant hazardsconsideration.

Thefirstoftheseexamplesreferstochangesthatarepurelyadministrative innature:forexample,changestoachieveconsistency throughout theT/Ss,correction ofanerror,orachangeinnomenclature.

Theproposedchangesareintendedonlytoensurethatcurrently existinganalysesarereflected intheT/Ss.Webelievethatthechangesareadministrative innaturesincetheydonotreflectnewanalysesorpermitany'elaxation inrequirements butrather'larifytherelationship betweenanalysesandT/Ss.Wetherefore believethattheFederalRegisterexamplecitedisapplicable andthatthechangesinvolvenosignificant hazardsconsideration.

Additionally, wehavemadeaneditorial changetoTable3.2-1.Mathematical symbolshavebeenwrittenoutinwords.Sincethesechangesarepurelyeditorial innature,theywillnotincreasetheprobability orconsequences ofapreviously evaluated

accident, willnotcreatethepossibility ofanewordifferent kindofaccidentfromanypreviously evaluated, anddonotinvolvesignificant hazardsconsideration.

ATTACHMENT 2TOAEP:NRC:1070A PROPOSEDTECHNICAL SPECIFICATION PAGE

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