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{{#Wiki_filter:A' | {{#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:== | ||
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:== | ==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. | |||
Dr.T.E.Murley-2-AEP:NRC: | 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}} |
Revision as of 09:18, 29 June 2018
ML17325B139 | |
Person / Time | |
---|---|
Site: | Cook ![]() |
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) | |
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