ML17254A294: Difference between revisions
StriderTol (talk | contribs) Created page by program invented by StriderTol |
StriderTol (talk | contribs) Created page by program invented by StriderTol |
||
| Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:REGULATORY FORMATION DISTRIBUTION SM(RIDS) | ||
==SUBJECT:== | ==SUBJECT:== | ||
RespondstoNRCr'equestforreviewofcertainconcernsreExxonnuclearCor' | RespondstoNRCr'equestforreviewofcertainconcernsreExxonnuclearCor'pECCSevaluation modelsBasedonlistedrevieww/Exxon8'riestinghouse<stated concernsinapplicable tofacility, SIZE:DISTRIBUTION CODE+A001DCOPIESRECEIVED:LTR ENCLTITLE:ORSubmittal: | ||
t///////////////////////////II/El)7/IIII//////8'vis// | GeneralDistribution ACCESSION NBR;8504030076 DOC~DATE:85/03/26NOTARIZED; NODOCKETFACIL:50244RobertEmmetGinnaNuclearPlantgUnitiiRochester G05000244AUTHINANE'UTHOR AFFILIATION KOBERgR,HE Rochester Gas8ElectricCorp.RECIP~NAME>>RECIPIENT AFFILIATION ZNOLINSKI'i J.AOperatingReactorsBranch5NOTES;NRR/DL/SEP 1cy,OL:09/19/6905000244RECIPIENT IDCODE/NAME'RR ORB5BC01INTERNAL: | ||
ACRS'9ELD/HDS4NRR/DLDIRNRR/DL/TSRG | |||
.NRR/DSI/RAB RGN1COPIESLTTRENCL7611111RECIPIENT IDCODE/NAME ADM/LFMBNRR/DE/MTEB NRR/Dl/ORABETBREFILE04COPIESLTTRENCLEXTERNAL: | |||
EGSGBRUSKE,SNRCPDR02NOTES:LPDRNSIC0305TOTALNUMBEROFCOPIESREQUIRED: | |||
LTTR28ENCL H(IIIII~~'Ilg''llI'Pt~ | |||
t////////////// | |||
///////////// | |||
II/El)7/IIII | |||
//////8'vis//ROCHESTER GASANDIstAtCELECTRICCORPORATION o69EASTAVENUE,ROCHESTER, N.Y.14649-0001 ROGERtN.KOBERVICePRESIDSNT ELECTRIC6STEAMPttODVCTION March26>1985TSI.CPHONC ARCACODETld546-2700DirectorofNuclearReactorRegulation Attention: | |||
Mr.JohnA.Zwolinski> | |||
ChiefOperating ReactorsBranchNo.5U.S.NuclearRegulatory Commission Washington< | |||
D.C.20555 | |||
==Subject:== | ==Subject:== | ||
| Line 26: | Line 37: | ||
==DearMr.Zwolinski:== | ==DearMr.Zwolinski:== | ||
ThisletterisinresponsetoarequestfrommembersoftheNRCstafftoaddresscertainconcernsregarding ExxonNuclearCorporation's (ENC)emergency corecoolingsystemevaluation model.WehavereviewedtheseconcernswithExxonNuclearandwithourcurrentfuelvendorandcoredesignerWestinghouse ElectricCorporation and>asdescribed below<havereachedtheconclusion thatthestatedconcernsarenotapplicable toGinnaFrom1978through1983>GinnareloadfuelwassuppliedbyENC.ThemostrecentENClossofcoolantaccidentanalysisforGinnawasperformed inSpring1982andwassubmitted totheNRCwithourletterdatedAugust9<1982.Thatanalysisresultedinacalculated peakcladtemperature (PCT)of1928F.ENChasconfirmed tousthatthespecificmodelsusedfortheGinnaanalysisdidnotcontainanyofthethreeerrorswhichtheNRCStaffhasidentified tousregarding heattransfercorrelations andaugmentation factorsandmixingassumptions. | |||
Regarding thefourthconcernraisedbytheNRCStaff>thefollowing background information andconclusions areprovided. | |||
In1984<RG6Ebeganatransition toWestinghouse fuel.Intheanalysisperformed byWestinghouse forthattransition< | |||
theyevaluated theplantresponsetoalltransients whichmaybeaffectedbyfueltype>including thelossofcoolantaccident. | |||
Westinghouse wasprovidedwithdetailedfuelparameters suchasdimensions> | |||
densities andenrichments. | |||
Westinghouse performed detailedpressuredropmeasurements onWestinghouse optimized fuelassembly(OFA)designfuelandENCfuelassemblies. | |||
Westinghouse concluded thatanalyzing acompletecoreofOFAunderLOCAconditions wasconservative withrespecttoanypotential combination andconfiguration ofWestinghouse andENCassemblytypes.Theassumption ofmodelingafullcoreofOFAwasdetermined tobeconservative fortransition cyclesfortwomajorreasons:8504OSOO7S 850S2SlPDRADOCK05000244PPDRADO),)O ROCHESTER GASANDELECTRICCORP.DATEMarch26>1985TOMr.JohnA.Zwolinski SHEETNO.2Theincreaseincoreflowareaassociated withOFAduetothesmallerroddiameterhasanimportant impactonfloodingratesduringreflood.AfullOFAcoreconfiguration decreases corefloodingrateswhichreducesheattransfercoefficients andresultsinearliersteamcooling.2.TheOFAhasahighervolumetric heatgeneration ratethantheENCfuel.Theanalysisassumestha'tanOFAassemblyhasthehottestrodandmaximumFHwhichmaximizes thecalculated PCT.Westinghouse alsoevaluated theimpactofanyhydraulic resistance difference. | |||
TheonlyportionoftheLOCAevaluation modelimpactedbythesmallhydraulic resistance difference whichexistsbetweentheENCandOFAfuelisthecorerefloodtransient. | |||
Sincethehydraulic mismatchissosmall>onlycrossflows duetosmallerrodsizeandgriddesignsneedtobeevaluated. | |||
Themaximumrefloodaxialflowreduction fortheOFAatanypossiblepeakcladtemperature locationinthecore<resulting fromcrossflows toadjacentENCassemblies< | |||
hasbeenconservatively calculated tobeonepercent.Analyseswereperformed whichdemonstrated thatthemaximumPCTpenaltypossibleofOFAfuelduringthetransition periodis4F.Afterthistransition> | |||
the0Westinghouse ECCSanalysiswillapplytoafull-core OFAwithoutthecrossflowpenalty.Inadditiontothefactorsidentified above<theburnuplevelsand/orpowerlevelsoftheENCfuelfurtherassurethatthelimitingfuelistheOFAfuel.ThelastregionofENCfuelwasloadedin1983.Fourofthesefuelassemblies haveburnupsofatleast11,000MWD/MTU<whiletheotherassemblies inthisregionhaveburnuplevelsinexcessof20>000MWD/MTU.EightfreshENCfuelassemblies wereloadedduringtheSpring1984refueling out-ageandcurrently haveburnupsinexcessofll>000MWD/MTU.Maxi-mumburnupswillremainbelowthedesignlimitsestablished byENC.TheENCassemblies arenotlocatedinpeakpowerlocations forCycle15buthaveFvaluesatleast5%belowthatinthelimitingOFAlocations. | |||
TheminimummargintotheFlimitpre-0dietedforanENCassemblyoccursatanelevation wheretheFlimitis2.29andthepredicted Fis2.125.Itshouldben8tedthatthisvalueispredicted b2sedonloadfollowoperation< | |||
whileGinnatypically operatesbaseloaded.Asdescribed inourletterdatedApril10<1984<wehaveloadedfourENCannularfuelpelletdemonstration assemblies duringthecurrentCycle14-15refueling outage.Inadditiontothefueltemperature andstoredenergybenefitswhichderivefromtheuseofanannularfuelpellet,theseassemblies areloadedinthecoreperiphery andhaveassemblypowerlevelslessthan0.8timescoreaveragepower.Theseassemblies havebeenexplicitly modeledinthemostrecentWestinghouse reloadanalysis. | |||
Thus>theseassemblies alsoareboundedbytheOFAfuelanalysis. | |||
ROCHESTER GASANPELECTRICCORP.pATENarch26,l985ToNr.JohnA.zwolinski SHEETNO.Forthereasonsstatedaboveiwehaveconcluded thattheanalysesperformed byWestinghouse withtheapprovedWestinghouse evaluation modelsboundallfuelcurrently loadedintheGinnareactor.Thisevaluation demonstrates thatthelimitingfueltypeistheWestinghouse OFAfuel.Thus<norelianceiscurrently madebytheENCLOCAmodelsandpotential concernsregarding thosecodesdonotapplytoGinna.ytrulyyoursiRogerW.Kober}} | |||
Revision as of 13:06, 29 June 2018
| ML17254A294 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 03/26/1985 |
| From: | KOBER R W ROCHESTER GAS & ELECTRIC CORP. |
| To: | ZWOLINSKI J A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8504030076 | |
| Download: ML17254A294 (5) | |
Text
REGULATORY FORMATION DISTRIBUTION SM(RIDS)
SUBJECT:
RespondstoNRCr'equestforreviewofcertainconcernsreExxonnuclearCor'pECCSevaluation modelsBasedonlistedrevieww/Exxon8'riestinghouse<stated concernsinapplicable tofacility, SIZE:DISTRIBUTION CODE+A001DCOPIESRECEIVED:LTR ENCLTITLE:ORSubmittal:
GeneralDistribution ACCESSION NBR;8504030076 DOC~DATE:85/03/26NOTARIZED; NODOCKETFACIL:50244RobertEmmetGinnaNuclearPlantgUnitiiRochester G05000244AUTHINANE'UTHOR AFFILIATION KOBERgR,HE Rochester Gas8ElectricCorp.RECIP~NAME>>RECIPIENT AFFILIATION ZNOLINSKI'i J.AOperatingReactorsBranch5NOTES;NRR/DL/SEP 1cy,OL:09/19/6905000244RECIPIENT IDCODE/NAME'RR ORB5BC01INTERNAL:
ACRS'9ELD/HDS4NRR/DLDIRNRR/DL/TSRG
.NRR/DSI/RAB RGN1COPIESLTTRENCL7611111RECIPIENT IDCODE/NAME ADM/LFMBNRR/DE/MTEB NRR/Dl/ORABETBREFILE04COPIESLTTRENCLEXTERNAL:
EGSGBRUSKE,SNRCPDR02NOTES:LPDRNSIC0305TOTALNUMBEROFCOPIESREQUIRED:
LTTR28ENCL H(IIIII~~'IlgllI'Pt~
t//////////////
/////////////
II/El)7/IIII
//////8'vis//ROCHESTER GASANDIstAtCELECTRICCORPORATION o69EASTAVENUE,ROCHESTER, N.Y.14649-0001 ROGERtN.KOBERVICePRESIDSNT ELECTRIC6STEAMPttODVCTION March26>1985TSI.CPHONC ARCACODETld546-2700DirectorofNuclearReactorRegulation Attention:
Mr.JohnA.Zwolinski>
ChiefOperating ReactorsBranchNo.5U.S.NuclearRegulatory Commission Washington<
D.C.20555
Subject:
LossofCoolantAccidentAnalysisR.E.GinnaNuclearPowerPlantDocketNo.50-244
DearMr.Zwolinski:
ThisletterisinresponsetoarequestfrommembersoftheNRCstafftoaddresscertainconcernsregarding ExxonNuclearCorporation's (ENC)emergency corecoolingsystemevaluation model.WehavereviewedtheseconcernswithExxonNuclearandwithourcurrentfuelvendorandcoredesignerWestinghouse ElectricCorporation and>asdescribed below<havereachedtheconclusion thatthestatedconcernsarenotapplicable toGinnaFrom1978through1983>GinnareloadfuelwassuppliedbyENC.ThemostrecentENClossofcoolantaccidentanalysisforGinnawasperformed inSpring1982andwassubmitted totheNRCwithourletterdatedAugust9<1982.Thatanalysisresultedinacalculated peakcladtemperature (PCT)of1928F.ENChasconfirmed tousthatthespecificmodelsusedfortheGinnaanalysisdidnotcontainanyofthethreeerrorswhichtheNRCStaffhasidentified tousregarding heattransfercorrelations andaugmentation factorsandmixingassumptions.
Regarding thefourthconcernraisedbytheNRCStaff>thefollowing background information andconclusions areprovided.
In1984<RG6Ebeganatransition toWestinghouse fuel.Intheanalysisperformed byWestinghouse forthattransition<
theyevaluated theplantresponsetoalltransients whichmaybeaffectedbyfueltype>including thelossofcoolantaccident.
Westinghouse wasprovidedwithdetailedfuelparameters suchasdimensions>
densities andenrichments.
Westinghouse performed detailedpressuredropmeasurements onWestinghouse optimized fuelassembly(OFA)designfuelandENCfuelassemblies.
Westinghouse concluded thatanalyzing acompletecoreofOFAunderLOCAconditions wasconservative withrespecttoanypotential combination andconfiguration ofWestinghouse andENCassemblytypes.Theassumption ofmodelingafullcoreofOFAwasdetermined tobeconservative fortransition cyclesfortwomajorreasons:8504OSOO7S 850S2SlPDRADOCK05000244PPDRADO),)O ROCHESTER GASANDELECTRICCORP.DATEMarch26>1985TOMr.JohnA.Zwolinski SHEETNO.2Theincreaseincoreflowareaassociated withOFAduetothesmallerroddiameterhasanimportant impactonfloodingratesduringreflood.AfullOFAcoreconfiguration decreases corefloodingrateswhichreducesheattransfercoefficients andresultsinearliersteamcooling.2.TheOFAhasahighervolumetric heatgeneration ratethantheENCfuel.Theanalysisassumestha'tanOFAassemblyhasthehottestrodandmaximumFHwhichmaximizes thecalculated PCT.Westinghouse alsoevaluated theimpactofanyhydraulic resistance difference.
TheonlyportionoftheLOCAevaluation modelimpactedbythesmallhydraulic resistance difference whichexistsbetweentheENCandOFAfuelisthecorerefloodtransient.
Sincethehydraulic mismatchissosmall>onlycrossflows duetosmallerrodsizeandgriddesignsneedtobeevaluated.
Themaximumrefloodaxialflowreduction fortheOFAatanypossiblepeakcladtemperature locationinthecore<resulting fromcrossflows toadjacentENCassemblies<
hasbeenconservatively calculated tobeonepercent.Analyseswereperformed whichdemonstrated thatthemaximumPCTpenaltypossibleofOFAfuelduringthetransition periodis4F.Afterthistransition>
the0Westinghouse ECCSanalysiswillapplytoafull-core OFAwithoutthecrossflowpenalty.Inadditiontothefactorsidentified above<theburnuplevelsand/orpowerlevelsoftheENCfuelfurtherassurethatthelimitingfuelistheOFAfuel.ThelastregionofENCfuelwasloadedin1983.Fourofthesefuelassemblies haveburnupsofatleast11,000MWD/MTU<whiletheotherassemblies inthisregionhaveburnuplevelsinexcessof20>000MWD/MTU.EightfreshENCfuelassemblies wereloadedduringtheSpring1984refueling out-ageandcurrently haveburnupsinexcessofll>000MWD/MTU.Maxi-mumburnupswillremainbelowthedesignlimitsestablished byENC.TheENCassemblies arenotlocatedinpeakpowerlocations forCycle15buthaveFvaluesatleast5%belowthatinthelimitingOFAlocations.
TheminimummargintotheFlimitpre-0dietedforanENCassemblyoccursatanelevation wheretheFlimitis2.29andthepredicted Fis2.125.Itshouldben8tedthatthisvalueispredicted b2sedonloadfollowoperation<
whileGinnatypically operatesbaseloaded.Asdescribed inourletterdatedApril10<1984<wehaveloadedfourENCannularfuelpelletdemonstration assemblies duringthecurrentCycle14-15refueling outage.Inadditiontothefueltemperature andstoredenergybenefitswhichderivefromtheuseofanannularfuelpellet,theseassemblies areloadedinthecoreperiphery andhaveassemblypowerlevelslessthan0.8timescoreaveragepower.Theseassemblies havebeenexplicitly modeledinthemostrecentWestinghouse reloadanalysis.
Thus>theseassemblies alsoareboundedbytheOFAfuelanalysis.
ROCHESTER GASANPELECTRICCORP.pATENarch26,l985ToNr.JohnA.zwolinski SHEETNO.Forthereasonsstatedaboveiwehaveconcluded thattheanalysesperformed byWestinghouse withtheapprovedWestinghouse evaluation modelsboundallfuelcurrently loadedintheGinnareactor.Thisevaluation demonstrates thatthelimitingfueltypeistheWestinghouse OFAfuel.Thus<norelianceiscurrently madebytheENCLOCAmodelsandpotential concernsregarding thosecodesdonotapplytoGinna.ytrulyyoursiRogerW.Kober