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| {{#Wiki_filter:CATEGORY1RlREGULAINFORMATION DISTRIBUTIO YSTEM(RIDS),'PA'CCESSIOA | | {{#Wiki_filter:CATEGORY 1 Rl REGULA INFORMATION DISTRIBUTIO YSTEM (RIDS),'P A'CCESSIOA |
| &BR:9901220118 DOC.DATE: | | &BR:9901220118 DOC.DATE: 99/Ol/15 NOTARIZED: |
| 99/Ol/15NOTARIZED: | | NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH.NAME~AUTHOR AFFILIATION RICKARD,I.C. |
| NODOCKETFACIL:50-397 WPPSSNuclearProject,Unit2,Washington PublicPowe05000397AUTH.NAME~AUTHORAFFILIATION RICKARD,I.C.
| | ABB Combustion Engineering Nuclear Fuel (formerly Combustio RICKARD, I.C.ABB Atom, Inc.(formerly ASEA Atom, Inc.)RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk) |
| ABBCombustion Engineering NuclearFuel(formerly Combustio RICKARD,I.C.ABBAtom,Inc.(formerly ASEAAtom,Inc.)RECIP.NAME RECIPIENT AFFILIATION RecordsManagement Branch(Document ControlDesk)
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| ==SUBJECT:== | | ==SUBJECT:== |
| Part21reptreXL-S96CPRcorrelation forSVEA-96fuel.DefectappliesonlytoWNP-2,during Cycles12,13&14operation.
| | Part 21 rept re XL-S96 CPR correlation for SVEA-96 fuel.Defect applies only to WNP-2,during Cycles 12,13&14 operation. |
| Evaluations ofdefectperformed byABB-CE.DISTRIBUTION CODE:IEISTCOPIESRECEIVED: | | Evaluations of defect performed by ABB-CE.DISTRIBUTION CODE: IEIST COPIES RECEIVED: LTR I ENCL)SIZE: TITLE: Part 21 Rept (50 DKT)NOTES: RECIPIENT ID CODE/NAME PD4-2 PD INTERNA FIL S 0 NRR DRPM/PECB/B RES/DET/EIB RGN2 RGN4 COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME POSLUSNY,C NRR/DRPM/PECB PDR WARD, M.RGNl RGN3 COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 EXTERNAL: INPO RECORD CTR NRC PDR 1 1 1 1 NOAC SILVER,E NUDOCS FULL TXT 1 1 1-.1 D.u NOTE TO ALL"RIDS" RECIPIENTS: |
| LTRIENCL)SIZE:TITLE:Part21Rept(50DKT)NOTES:RECIPIENT IDCODE/NAME PD4-2PDINTERNAFILS0NRRDRPM/PECB/B RES/DET/EIB RGN2RGN4COPIESLTTRENCL111111111111RECIPIENT IDCODE/NAME POSLUSNY,C NRR/DRPM/PECB PDRWARD,M.RGNlRGN3COPIESLTTRENCL111111111EXTERNAL:
| | PLEASE HELP US TO REDUCE WASTETH TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DZSTRIBUTZON LISTS OR REDUCE THE NUMBER OF COP Z ES RECE I VED BY YOU OR YOUR ORGAN I ZAT ION g CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 15 |
| INPORECORDCTRNRCPDR1111NOACSILVER,ENUDOCSFULLTXT111-.1D.uNOTETOALL"RIDS"RECIPIENTS:
| | 'k I LqW'J~p(mp.a APE p QR q'4~Cj'le 8 c'"'s~ti".y~~.PC.& |
| PLEASEHELPUSTOREDUCEWASTETHTOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDZSTRIBUTZON LISTSORREDUCETHENUMBEROFCOPZESRECEIVEDBYYOUORYOURORGANIZATIONgCONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
| | January 15, 1999 LD-99-003 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Subject'.Report of a Oefect Pursuant to 10 CFR 21 Concerning the XL96 CPR Correlation for SVEA-96 Fuel The purpose of this letter is to notify the Nuclear Regulatory Commission of a defect as defined in 10 CFR 21,"Reporting of Defects and Noncompliance." The defect concerns the XL-S96 Critical Power Ratio (CPR)correlation for ABB SYEA-96 fuel assemblies for Boiling Water Reactors (BWRs).Specifically, the defect concerns the XL-SS6 CPR correlation, which is based solely on a cosine axial povrer shape.The defect could lead~to non-conservative Operating Limit MCPRs and monitored CPRs for top-peaked axial power shapes.The Enclosure summarizes the evaluation performed by ABB Combustion Engineering (ABB-CE).If you have any questions, please feel free to contact me or Mr.Yirgil Paggen of my staff at (860)285<700.Very truly yours, COMBUSTION ENGINEERING, INC.lan C.Rickard, Director Nuclear Licensing |
| LTTR15ENCL15
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| 'kILqW'J~p(mp.aAPEpQRq'4~Cj'le8c'"'s~ti".y~~.PC.& | |
| January15,1999LD-99-003 U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Subject'.
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| ReportofaOefectPursuantto10CFR21Concerning theXL96CPRCorrelation forSVEA-96FuelThepurposeofthisletteristonotifytheNuclearRegulatory Commission ofadefectasdefinedin10CFR21,"Reporting ofDefectsandNoncompliance."
| |
| ThedefectconcernstheXL-S96CriticalPowerRatio(CPR)correlation forABBSYEA-96fuelassemblies forBoilingWaterReactors(BWRs).Specifically, thedefectconcernstheXL-SS6CPRcorrelation, whichisbasedsolelyonacosineaxialpovrershape.Thedefectcouldlead~tonon-conservative Operating LimitMCPRsandmonitored CPRsfortop-peaked axialpowershapes.TheEnclosure summarizes theevaluation performed byABBCombustion Engineering (ABB-CE).
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| Ifyouhaveanyquestions, pleasefeelfreetocontactmeorMr.YirgilPaggenofmystaffat(860)285<700.Verytrulyyours,COMBUSTION ENGINEERING, INC.lanC.Rickard,DirectorNuclearLicensing
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| ==Enclosure:== | | ==Enclosure:== |
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| Asstatedcc:M.A.Bamoski(ABB-CE)ABBCombustion Engineering NuclearPowerCambveeen Rn{{{eeerin{t.
| | As stated cc: M.A.Bamoski (ABB-CE)ABB Combustion Engineering Nuclear Power Cambveeen Rn{{{eeerin{t. |
| tee.P.O,Bex500Tetephono | | tee.P.O, Bex 500 Tetephono{{{80)663 19t t 2000 Day Htt Rd.Fax{060)285-5203 Windsor, CT Ot0954500'ti'ti0%220118 |
| {{{80)66319tt2000DayHttRd.Fax{060)285-5203Windsor,CTOt0954500 | | 'ti90i%5 PDR ADOCK 05000397 PDR ABB Combustion Engineering Nuclear Power 10 CFR21 Re ortofa Defector Failure to Corn I The following information is provided pursuant to the requirements s t e forth in 10 CFR 21.21(c)(4): (i)Name and address of theindividualsinfoiming the Commission: |
| 'ti'ti0%220118 | | lan C.Rickard, Director Nuclear Licensing Combustion Engineering, inc.2000 Day HiH Road Vfindsor, CT 06095-0500 (ii)Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United Slates which fails to comply or contains a defect: The activity for which this report is being filed is the use of the XL-S96 CPR correlation in determining Safety and Operating Limit MCPRs and in monitoring of CPRs in SVEA-96 Boiling Water Reactor (BNIR)fuef assemblies, This defect applies only to the Washington Public Power Supply System Nuclear Project Unit 2 nuclear power plant during Cycles 12, 13, and 14 operation.(iii)Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect: Combustion Engineering, Inc.'2000 Day HHi Road Windsor, CT 06095-0500 (iv)Nature of the defect or failure to comply and the safety ha ard which is created or could be created by such defect or failure to comply: The defect fdentffied is associated with the use of the XL-S96 CPR correlation in determining Safety and Operating Limit MCPRs and in monitoring of CPRs in SVEA-96 BWR fuel assemblies. |
| 'ti90i%5PDRADOCK05000397PDR ABBCombustion Engineering NuclearPower10CFR21ReortofaDefectorFailuretoCornIThefollowing information isprovidedpursuanttotherequirements steforthin10CFR21.21(c)(4): | | For top-peaked axial power shapes, the use of this CPR.correlation could yield non-conservative Operating Limit MCPRs or non-conservative-monitored CPR values.(v)The date on which the information of such defect or failure to comply was obtained: ABB-CE determined that a defect in the CPR correlation existed on January 15, 1999. |
| (i)Nameandaddressoftheindividualsinfoiming theCommission: | | ~I~N'V Page20f2 WE (vi)In the case of a basic component which contains a defect or fails to comply, the number and location of all such components in use at, supplied for, or being supplied for one or more facilities or activities subject to the regulations ln this part: The defect applies only to BWR reload fuel assemblies currently in operation at WNP-2.(vii)The corrective action which has been, is being, or will be taken;the name of the tnd)vidual or organitation responsible for the action;and the length of time that has been or will be taken to complete the action: Evaluations of the defect have been performed by ABB-CE, lt has been determined the use of the correlation in determining Safety and Operating Limit MCPRs for Cycles 12, 13, and 14 is acceptable. |
| lanC.Rickard,DirectorNuclearLicensing Combustion Engineering, inc.2000DayHiHRoadVfindsor, CT06095-0500 (ii)Identification ofthefacility, theactivity, orthebasiccomponent suppliedforsuchfacilityorsuchactivitywithintheUnitedSlateswhichfailstocomplyorcontainsadefect:TheactivityforwhichthisreportisbeingfiledistheuseoftheXL-S96CPRcorrelation indetermining SafetyandOperating LimitMCPRsandinmonitoring ofCPRsinSVEA-96BoilingWaterReactor(BNIR)fuefassemblies, ThisdefectappliesonlytotheWashington PublicPowerSupplySystemNuclearProjectUnit2nuclearpowerplantduringCycles12,13,and14operation.
| | Furthermore, the use of the correlation in monitoring CPR in Cycles 12 and 13 has been adequate.For Cycle 14, the use of the correlation for'onitoring CPR in the core is acceptable prior to 5,600 MWd/MtU.From 5,600 MWd/MtU to the end of Cycle 14 the use of the correlation for monitoring CPR in the core may become non-conservative. |
| (iii)Identification ofthefirmconstructing thefacilityorsupplying thebasiccomponent whichfailstocomplyorcontainsadefect:Combustion Engineering, Inc.'2000DayHHiRoadWindsor,CT06095-0500 (iv)Natureofthedefectorfailuretocomplyandthesafetyhaardwhichiscreatedorcouldbecreatedbysuchdefectorfailuretocomply:Thedefectfdentffied isassociated withtheuseoftheXL-S96CPRcorrelation indetermining SafetyandOperating LimitMCPRsandinmonitoring ofCPRsinSVEA-96BWRfuelassemblies. | | The utility currently projects that WNP-2 will reach 5,600 MWd/MTU in February 1999, ABB-GE has provided the Washington Public Power~Supply System with recommended corrective actions to ensure that sufficient margin for monitoring the core CPR is maintained. |
| Fortop-peaked axialpowershapes,theuseofthisCPR.correlation couldyieldnon-conservative Operating LimitMCPRsornon-conservative-monitored CPRvalues.(v)Thedateonwhichtheinformation ofsuchdefectorfailuretocomplywasobtained:
| | fviii)Any advice related to the defect or failure to comply about thefacility, activity, or basic component that has been, is being, or will be gi ven to purchasers or licensees: |
| ABB-CEdetermined thatadefectintheCPRcorrelation existedonJanuary15,1999. | | The Nfashingtan Public Power Supply System has been notified of the defect and has been provided with necessary information and recommendations, TOTAL P.84 |
| ~I~N'VPage20f2WE(vi)Inthecaseofabasiccomponent whichcontainsadefectorfailstocomply,thenumberandlocationofallsuchcomponents inuseat,suppliedfor,orbeingsuppliedforoneormorefacilities oractivities subjecttotheregulations lnthispart:ThedefectappliesonlytoBWRreloadfuelassemblies currently inoperation atWNP-2.(vii)Thecorrective actionwhichhasbeen,isbeing,orwillbetaken;thenameofthetnd)vidual ororganitation responsible fortheaction;andthelengthoftimethathasbeenorwillbetakentocompletetheaction:Evaluations ofthedefecthavebeenperformed byABB-CE,lthasbeendetermined theuseofthecorrelation indetermining SafetyandOperating LimitMCPRsforCycles12,13,and14isacceptable. | |
| Furthermore, theuseofthecorrelation inmonitoring CPRinCycles12and13hasbeenadequate. | |
| ForCycle14,theuseofthecorrelation for'onitoring CPRinthecoreisacceptable priorto5,600MWd/MtU.From5,600MWd/MtUtotheendofCycle14theuseofthecorrelation formonitoring CPRinthecoremaybecomenon-conservative.
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| Theutilitycurrently projectsthatWNP-2willreach5,600MWd/MTUinFebruary1999,ABB-GEhasprovidedtheWashington PublicPower~SupplySystemwithrecommended corrective actionstoensurethatsufficient marginformonitoring thecoreCPRismaintained.
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| fviii)Anyadvicerelatedtothedefectorfailuretocomplyaboutthefacility, | |
| : activity, orbasiccomponent thathasbeen,isbeing,orwillbegiventopurchasers orlicensees:
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| TheNfashingtan PublicPowerSupplySystemhasbeennotifiedofthedefectandhasbeenprovidedwithnecessary information andrecommendations, TOTALP.84
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| 0 January15,1999LD-99-003 U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555 | | 0 January 15, 1999 LD-99-003 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 |
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| ==Subject:== | | ==Subject:== |
| ReportofaDefectPursuantto10CFR21Concerning theXL-S96CPRCorrelation forSVEA-96FuelThepurposeofthisletteristonotifytheNuclearRegulatory Commission ofadefectasdefinedin10CFR21,"Reporting ofDefectsandNoncompliance."
| | Report of a Defect Pursuant to 10 CFR 21 Concerning the XL-S96 CPR Correlation for SVEA-96 Fuel The purpose of this letter is to notify the Nuclear Regulatory Commission of a defect as defined in 10 CFR 21,"Reporting of Defects and Noncompliance." The defect concerns the XL-S96 Critical Power Ratio (CPR)correlation for ABB SVEA-96 fuel assemblies for Boiling Water Reactors (BWRs).Specifically, the defect concerns the XL-S96 CPR correlation, which is based solely on a cosine axial power shape.The defect could lead to non-conservative Operating Limit MCPRs and monitored CPRs for top-peaked axial powershapes. |
| ThedefectconcernstheXL-S96CriticalPowerRatio(CPR)correlation forABBSVEA-96fuelassemblies forBoilingWaterReactors(BWRs).Specifically, thedefectconcernstheXL-S96CPRcorrelation, whichisbasedsolelyonacosineaxialpowershape.Thedefectcouldleadtonon-conservative Operating LimitMCPRsandmonitored CPRsfortop-peaked axialpowershapes.
| | The Enclosure summarizes the evaluation performed by ABB Combustion Engineering (ABB-CE).If you have any questions, please feel free to contact me or Mr.Virgil Paggen of my staff at (860)285-4700.Very truly yours, COMBUSTION ENGINEERING, INC.lan C.Rickard, Director Nuclear Licensing |
| TheEnclosure summarizes theevaluation performed byABBCombustion Engineering (ABB-CE).
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| Ifyouhaveanyquestions, pleasefeelfreetocontactmeorMr.VirgilPaggenofmystaffat(860)285-4700.
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| Verytrulyyours,COMBUSTION ENGINEERING, INC.lanC.Rickard,DirectorNuclearLicensing
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| ==Enclosure:== | | ==Enclosure:== |
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| Asstatedcc:M.A.Barnoski(ABB-CE)gQQQOPiJABBCombustion Engineering NuclearPowerCombustion Engineering, Inc.P.O.Box5002000DayHillRd.Windsor,CT06095-0500 Telephone (860)688-1911Fax(860)285.5203 0tEnclosure toLD-99-003 Page1of2ABBCombustion Engineering NuclearPower10CFR21ReortofaDefectorFailuretoComIThefollowing information isprovidedpursuanttotherequirements setforthin10CFR21.21(c)(4):
| | As stated cc: M.A.Barnoski (ABB-CE)gQQQO PiJ ABB Combustion Engineering Nuclear Power Combustion Engineering, Inc.P.O.Box 500 2000 Day Hill Rd.Windsor, CT 06095-0500 Telephone (860)688-1911 Fax (860)285.5203 0 t Enclosure to LD-99-003 Page 1 of 2 ABB Combustion Engineering Nuclear Power 10 CFR 21 Re ort of a Defect or Failure to Com I The following information is provided pursuant to the requirements set forth in 10 CFR 21.21(c)(4): (i)Name and address of tike indi viduals informing tike Commission: |
| (i)Nameandaddressoftikeindividualsinforming tikeCommission: | | lan C.Rickard, Director Nuclear Licensing Combustion Engineering, Inc.2000 Day Hill Road Windsor, CT 06095-0500 (ii)Identification of tike facility, the activity, or the basic component supplied for such facility or such activity witlkin tike United States wlkiclk fails to comply or contains a defect: The activity for which this report is being filed is the use of the XL-S96 CPR correlation in determining Safety and Operating Limit MCPRs and in monitoring of CPRs in SVEA-96 Boiling Water Reactor (BWR)fuel assemblies. |
| lanC.Rickard,DirectorNuclearLicensing Combustion Engineering, Inc.2000DayHillRoadWindsor,CT06095-0500 (ii)Identification oftikefacility, theactivity, orthebasiccomponent suppliedforsuchfacilityorsuchactivitywitlkintikeUnitedStateswlkiclkfailstocomplyorcontainsadefect:TheactivityforwhichthisreportisbeingfiledistheuseoftheXL-S96CPRcorrelation indetermining SafetyandOperating LimitMCPRsandinmonitoring ofCPRsinSVEA-96BoilingWaterReactor(BWR)fuelassemblies.
| | This defect applies only to the Washington Public Power Supply System Nuclear Project Unit 2 nuclear power plant during Cycles 12, 13, and 14 operation.(iii)Identification of tike firm constructing the facility or supplying the basic component which fails to comply or contains a defect: Combustion Engineering, Inc.2000 Day Hill Road Windsor, CT 06095-0500 (iv)Nature of the defect or failure to comply and the safety/kazard whicli is created or could be created by suclk defect or failure to comply: The defect identified is associated with the use of the XL-S96 CPR correlation in determining Safety and Operating Limit MCPRs and in monitoring of CPRs in SVEA-96 BWR fuel assemblies. |
| ThisdefectappliesonlytotheWashington PublicPowerSupplySystemNuclearProjectUnit2nuclearpowerplantduringCycles12,13,and14operation.
| | For top-peaked axial power shapes, the use of this CPR correlation could yield non-conservative Operating Limit MCPRs or non-conservative monitored CPR values.(v)The date on which theinformation of such defect or failure to comply was obtained: ABB-CE determined that a defect in the CPR correlation existed on January 15, 1999. |
| (iii)Identification oftikefirmconstructing thefacilityorsupplying thebasiccomponent whichfailstocomplyorcontainsadefect:Combustion Engineering, Inc.2000DayHillRoadWindsor,CT06095-0500 (iv)Natureofthedefectorfailuretocomplyandthesafety/kazardwhicliiscreatedorcouldbecreatedbysuclkdefectorfailuretocomply:Thedefectidentified isassociated withtheuseoftheXL-S96CPRcorrelation indetermining SafetyandOperating LimitMCPRsandinmonitoring ofCPRsinSVEA-96BWRfuelassemblies. | | Enclosure to LD-99-003 Page2of2 (vi)In the case of a basic component whic/t contains a defect or fails to comply, the number and location of all such components in use at, supplied for, or being supplied for one or more facilities or acti vities subject to the regulations in this part: The defect applies only to BWR reload fuel assemblies currently in operation at WNP-2.(vii)T/te corrective action which has been, is being, or will be taken;the name of theindividual or organization responsible for the action;and the length of time that has been or will be taken to complete the action: Evaluations of the defect have been performed by ABB-CE.It has been determined the use of the correlation in determining Safety and Operating Limit MCPRs for Cycles 12, 13, and 14 is acceptable. |
| Fortop-peaked axialpowershapes,theuseofthisCPRcorrelation couldyieldnon-conservative Operating LimitMCPRsornon-conservative monitored CPRvalues.(v)Thedateonwhichtheinformation ofsuchdefectorfailuretocomplywasobtained:
| | Furthermore, the use of the correlation in monitoring CPR in Cycles 12 and 13 has been adequate.For Cycle 14, the use of the correlation for monitoring CPR in the core is acceptable prior to 5,600 MWd/MtU.From 5,600 MWd/MtU to the end of Cycle 14 the use of the correlation for monitoring CPR in the core may become non-conservative. |
| ABB-CEdetermined thatadefectintheCPRcorrelation existedonJanuary15,1999. | | The utility currently projects that WNP-2 will reach 5,600 MWd/MTU in February 1999.ABB-CE has provided the Washington Public Power Supply System with recommended corrective actions to ensure that sufficient margin for monitoring the core CPR is maintained.(viii)Any advice related to the defect or failure to comply about the facility, activity, or basic"component that has been, is being, or will be given to purcltasers or licensees: |
| Enclosure toLD-99-003 Page2of2(vi)Inthecaseofabasiccomponent whic/tcontainsadefectorfailstocomply,thenumberandlocationofallsuchcomponents inuseat,suppliedfor,orbeingsuppliedforoneormorefacilities oractivitiessubjecttotheregulations inthispart:ThedefectappliesonlytoBWRreloadfuelassemblies currently inoperation atWNP-2.(vii)T/tecorrective actionwhichhasbeen,isbeing,orwillbetaken;thenameoftheindividual ororganization responsible fortheaction;andthelengthoftimethathasbeenorwillbetakentocompletetheaction:Evaluations ofthedefecthavebeenperformed byABB-CE.Ithasbeendetermined theuseofthecorrelation indetermining SafetyandOperating LimitMCPRsforCycles12,13,and14isacceptable. | | The Washington Public Power Supply System has been notified of the defect and has been provided with necessary information and recommendations.}} |
| Furthermore, theuseofthecorrelation inmonitoring CPRinCycles12and13hasbeenadequate. | |
| ForCycle14,theuseofthecorrelation formonitoring CPRinthecoreisacceptable priorto5,600MWd/MtU.From5,600MWd/MtUtotheendofCycle14theuseofthecorrelation formonitoring CPRinthecoremaybecomenon-conservative.
| |
| Theutilitycurrently projectsthatWNP-2willreach5,600MWd/MTUinFebruary1999.ABB-CEhasprovidedtheWashington PublicPowerSupplySystemwithrecommended corrective actionstoensurethatsufficient marginformonitoring thecoreCPRismaintained.
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| (viii)Anyadvicerelatedtothedefectorfailuretocomplyaboutthefacility, | |
| : activity, orbasic"component thathasbeen,isbeing,orwillbegiventopurcltasers orlicensees:
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| TheWashington PublicPowerSupplySystemhasbeennotifiedofthedefectandhasbeenprovidedwithnecessary information andrecommendations.}}
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML17292B5331999-01-15015 January 1999
Part 21 Rept Re XL-S96 CPR Correlation for SVEA-96 Fuel. Defect Applies Only to WNP-2,during Cycles 12,13 & 14 Operation.Evaluations of Defect Performed by ABB-CE
ML17292B5341999-01-15015 January 1999
Part 21 Rept Re Incorrect Modeling of BWR Lower Plenum Vol in Bison.Defect Applies Only to Reload Fuel Assemblies Currently in Operation at WNP-2.BISON Code Model for WNP-2 Has Been Revised to Correct Error
ML20198E0631998-01-0707 January 1998
Part 21 Rept Re Shipment by Dubose National Energy Svcs,Inc, of 40 Pieces of 4 inch,90 Degree Elbows Which Did Not Meet ASME Section II SA-234 Requirements
ML20140G4481997-05-0101 May 1997
Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages
ML17292A2141996-05-0808 May 1996
Part 21 Rept Re Capscrews Supplied to Wppss by Now Defunct Cardinal Industrial Products,Lp (CIP) Having Nonconforming Hardness.Failed Lots & Any Remaining Product Found to Have Been Heat Treated by CIP Scrapped & Removed from Premises
ML20094M6251995-11-21021 November 1995
Final Part 21 Rept of Investigation & Analysis of Suspect Fasteners Event 29257.B&G-Cardinal Discontinued Using Heat Treatment Equipment at Cardinal Facility Until Such Time That Satisfactory Mods Made to Hardware & Procedures
ML17291A2571994-07-22022 July 1994
Part 21 Rept Re Westinghouse Containment Penetration Modules Scotchcast Strain Relief & Varglas Insulated Conductors. Replaced Six of 12 RPIS Scotchcast/Varglas Modules & Three Scotchcast/Okonite Modules During Refueling Outage (R-9)
ML17291A2351994-07-15015 July 1994
Deficiency Rept Re Material Defects in Facility Containment Penetration Modules.Initially Reported on 940715.Modules Were Replaced
ML17290B2001994-05-26026 May 1994
Part 21 Rept Re Automatic Switch Co Replacement Solenoid Pilot Valve Diaphragms Supplied by GE Nuclear Energy.Unusual Combination of Scram Soleniod Pilot Valve Pressure & Exhaust Diaphragm Degradation Caused Failure of Rod to Scram
ML20044G5011993-05-26026 May 1993
Part 21 Rept Re Buffer Amplifier Modules Mfg by Bailey Controls Co Containing Suspect Negative Ref Power Supply Having Safety Implications.Caused by Design Error in Circuitry.Modules Would Not Result in Miscalibration
ML20044G5311993-05-26026 May 1993
Suppl to 921207 Part 21 Rept Re Declutch Sys Anomaly in Certain Types of Valve Actuators Supplied by Limitorque Corp.Limitorque Designed New Declutch Lever Which Will Be Available in First Quarter 1993
ML20127H2301993-01-15015 January 1993
Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites
ML20126D7211992-12-16016 December 1992
Potential Part 21 Rept Re Actual Performance of Rosemount Supplied Bailey Bq Differential Pressure Transmitters Differing from Rosemount Original Spec.Bailey Controls Encl.Evaluation Not Yet Performed
ML20127P5861992-11-23023 November 1992
Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl
ML20118B4391992-09-11011 September 1992
Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option
ML17289A8241992-08-14014 August 1992
Part 21 Rept Re Undersized Yoke Clamps on Three HPCS motor- Operated Valves Supplied by Anchor/Darling Valve Co.Nde Will Be Performed on All Clamps to Determine If Condition Affects Valve Operability.Clamps to Be Replaced by 921031
ML17289A8061992-08-14014 August 1992
Part 21 Rept Re Undersized Yoke Clamps in Three Anchor Darling HPCS motor-operated Valves.Clamps Located on Return Lines to Condensate Storage Tanks & Suppression Pool.Clamps Will Be Replaced by Util by 921031
ML17289A7991992-08-13013 August 1992
Part 21 Rept Re Limitorque Failure to Use Grade 5 Housing Cap to motor-operator Housing,Per Generic Ltr 89-10. Initially Reported on 920730.Seven GL 89-10 Category Valves Could Have Failed Due to Condition
ML17289A7721992-08-0606 August 1992
Interim Part 21 Rept Re Discrepancy in Procedure Used by Siemens Nuclear Power Corp to Analyze Feedwater Controller Failure Event w/COTRANSA2 Computer Code.Initially Reported on 920709.Analysis for Cycle 8 Revised & Incorporated
ML17289A7851992-07-30030 July 1992
Part 21 Rept 23965:on 920730,determined That Limitorque motor-operators Had Upper Housing Cover Cap Screws Set at 100% of Mfg Rated Thrust Which Could Fail in Svc.Caused by Installation of Grade 1 or 2 Instead of Grade 5 or 7 Screws
ML17289A7521992-07-0909 July 1992
Part 21 Rept Re Discrepancy in Procedure Used to Analyze Feedwater Controller Failure Event Using COTRANSA2 Code. Initially Reported by Siemens Nuclear Power Corp on 920617. Caused by Transient Analysis Error
ML17289A8591992-07-0808 July 1992
Part 21 Rept Re Delta CPR Transient Analysis Error for Feedwater Controller Failure Event Performed by Siemens Nuclear Power Corp.Feedwater Transient Actually Occurred on 911119.Fuel Cladding Failure Not Possible
ML17289A6971992-06-26026 June 1992
Amend 1 to Part 21 Rept 158 Re gear-wear Induced Failures in engine-driven Jacket Water Pump in DSRV-16-4 Standby DG Sys. Initially Reported on 911029.Grand Gulf Station Observed Wear Characteristics in as Little as 500 Operating Hours
ML17286B2501991-11-14014 November 1991
Part 21 Rept Re Potential Deficiency W/Asl Dry Type Transformers.Initially Reported on 910610.Recommends Issue Be Pursued W/Abb Since Westinghouse Did Not Have Necessary Technical Info or Expertise to Identify Cause or Solution
ML20079B8591991-06-10010 June 1991
Interim Deviation/Noncompliance Rept 067 Re dry-type Insulator Cracking in Transformer Supplied by Westinghouse.Initially Reported on 910513.Util Notified Vendor on 910430 That Problem Affects Class 1E Transformer
ML20248E0121989-09-13013 September 1989
Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating
GO2-89-144, Part 21 Rept Re Defect in Fault Tripping Design for Class 1E safety-related 480 Volt Divs 1 & 2 Ac Power Distribution Sys for Motor Control Ctrs.Caused by Improperly Designed Volt Electrical Distribution Sys.Circuit Breakers Replaced1989-08-21021 August 1989
Part 21 Rept Re Defect in Fault Tripping Design for Class 1E safety-related 480 Volt Divs 1 & 2 Ac Power Distribution Sys for Motor Control Ctrs.Caused by Improperly Designed Volt Electrical Distribution Sys.Circuit Breakers Replaced
ML17285A5001989-06-0202 June 1989
Part 21 Rept Re Defect Discovered in Valve Motor Operator of RCIC Inboard Containment Isolation Valve RCIC-V-63.Upper Housing Cover Will Be Machined to Remove Excess Matl to Provide Required Recess
ML17285A4771989-05-19019 May 1989
Part 21 Rept Re Defects in Target Rock Actuator Kits (Part 300562-1).Initially Reported on 890516.Defects Noted in Cold Solder Condition,Insufficient Solder Joints & Failed Solder Joints.Defective Kits Returned to Mfg for Repair
ML17285A4321989-04-26026 April 1989
Part 21 Rept Re Defect in Limitorque Valve Motor Operator Model SMB-2 W/Soft Worm Shaft Clutch Gear Assembly.Caused by Failure to Install Split Spacer of Worm Shaft Clutch Gear assembly.Safety-related Valves Manually Operated
ML20205F3211988-10-10010 October 1988
Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07
ML20154J4101988-05-12012 May 1988
Addendum 1 to Supplemental Part 21 Rept 145 Re Potential Problem w/F-573-156 Pressure Sensor/Lube Oil Trip.Initially Reported on 880429.Addl 1-1/8-inch Diameter W/Deep Counterbone in Pressure Head Added to Activate Valve
ML20153B6191988-04-29029 April 1988
Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generators Supplied to Utils.Recommends Return of Subj Components in Onsite Warehouse Storage & Suggests Surveillance of Devices Already Installed
ML20212A5601986-12-17017 December 1986
Part 21 Rept Re Amplified Response Spectra.Applicable Floor & Wall Mounted safety-related Equipment Reviewed & as-built Geometry & Mass of Seismic Category I Structures Compared to Original Use in Generating Amplified Response Spectra
ML20215G6801986-10-10010 October 1986
Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing
ML20215G5351986-10-10010 October 1986
Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing
ML20215B9681986-09-26026 September 1986
Part 21 & Deficiency Rept Re Synchro-Start Type Essb Speed Switches.Initially Reported on 860822.Speed Switches Currently in Svc or Designated for Svc Will Be Tested for Relay Contact Closure & Relay Contact Condition
ML20210F4741986-09-16016 September 1986
Part 21 Rept Re Possible Sticking in Closed or Partially Open Position on Dresser 3050 Diaphragm Valves.Initially Reported on 850118.Disc Caps,Including Chamfers on Outside Diameter,Will Be Modified
ML20206S0841986-06-30030 June 1986
Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires
ML20195E4881986-05-23023 May 1986
Part 21 Rept Re Potential Failure of Ite/Gould Disconnect Switch,Type 7860 Ds Series.Instructions for Verification of Proper Operation of Switches Included in Notification to Plants.New Switches Available by 860901
ML20205L0921986-03-21021 March 1986
Part 21 Rept Re Throttling Requirements & Capabilities of HPI Valves Supplied to Bellefonte,Units 1 & 2 & Washington Nuclear Project.Utils Notified & B&W Suggested Listed Options for Resolving Concern
ML20141F6111986-01-0303 January 1986
Interim Part 21 Rept Re Error in Computer Program Used in Analysis of Component Supports.Nuclear Pipe Support Design Guidelines Revised to Require Conversion to Another Computer Program.Final Rept by 860307
ML20137W2611985-09-30030 September 1985
Update to Part 21 Rept Re Insp for Cracked Welds Discovered in Generator Brackets.Insp for Callaway Unit 1 Postponed Until Next Refueling Outage (Probably Apr 1986).No Cracks Discovered During Insp at Wolf Creek
ML20135E1161985-09-0505 September 1985
Part 21 Rept Re Use of Connectron non-IEEE Qualified Matl in Spare Part Terminal Blocks Supplied to Facilities. Appropriate Customers Notified.Terminal Blocks Should Be Reviewed to Identify Defective Matl
ML20116E8481985-04-23023 April 1985
Part 21 Rept Forwarding Rev 1 to Insp Procedure for Investigating Emergency Diesel Generators for Fractured Welds on Air Deflectors.Rev Will Be Forwarded to Each Facility
ML20100E0651985-03-29029 March 1985
Part 21 Rept Re Series of Cracked Welds Discovered in Generators.Welds Occurred in Conical Baffle Section of Coil Guards.All Units Will Be Inspected.Affected Plants Listed
ML20113D7061985-01-15015 January 1985
Final Part 21 Rept Re Defective Valve Operators.Initially Reported on 841030.Control Valve Failures Resulted from Hydraulic Fluid Contamination & Improper Maint Procedures Which Allowed Aeration of Hydraulic Fluid
ML20084K0111984-05-0303 May 1984
Potential Part 21 & Deficiency Rept 84-04 Re Failure to Protect Certain Cables in Dedicated Shutdown Sys.Wppss Presently Design Control Authority.Procedures Revised
GO2-83-117, Final Deficiency Rept,Condition 307 Re Target Rock Isolation Valve 82M-002 on Loop B Not Closing When Deenergized. Initially Reported on 831219.Twelve Valves Disassembled, Readjusted & Reinstalled Under Vendor Supervision1983-12-20020 December 1983
Final Deficiency Rept,Condition 307 Re Target Rock Isolation Valve 82M-002 on Loop B Not Closing When Deenergized. Initially Reported on 831219.Twelve Valves Disassembled, Readjusted & Reinstalled Under Vendor Supervision
ML20083G6981983-12-20020 December 1983
Revised Final Deficiency Rept,Condition 260 Re Insufficient Flow to HXs in Standby Svc Water Loops a & B.B&R Evaluating Design Error.Also Reported Per Part 21
1999-01-15
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17284A9001999-10-31031 October 1999
Rev 0 to COLR 99-15, WNP-2 Cycle 15,COLR
GO2-99-177, LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With1999-10-0101 October 1999
LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With
ML17284A8941999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for WNP-2.With 991012 Ltr
ML17284A8801999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for WNP-2.With 990910 Ltr
ML17284A8691999-07-31031 July 1999
Monthly Operating Rept for July 1999 for WNP-2.With 990813 Ltr
ML17292B7421999-07-20020 July 1999
LER 99-001-00:on 990628,ESF Signal Closed All Eight MSIVs While Plant Was Shutdown.Caused by Failure of Relay RPS-RLY-K10D.Subject Relay Was Replaced & Tested on 990630. with 990720 Ltr
ML17292B7271999-06-30030 June 1999
Monthly Operating Rept for June 1999 for WNP-2.With 990707 Ltr
ML17292B6961999-05-31031 May 1999
Monthly Operating Repts for May 1999 for WNP-2.With 990608 Ltr
ML17292B6641999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for WNP-2.With 990507 Ltr
ML17292B6391999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for WNP-2.With 990413 Ltr
ML17292B5871999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for WNP-2.With 990311 Ltr
ML17292B5571999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for WNP-2.With 990210 Ltr
ML17292B5621999-01-31031 January 1999
Rev 1 to COLR 98-14, WNP-2 Cycle 14 Colr.
ML17292B5341999-01-15015 January 1999
Part 21 Rept Re Incorrect Modeling of BWR Lower Plenum Vol in Bison.Defect Applies Only to Reload Fuel Assemblies Currently in Operation at WNP-2.BISON Code Model for WNP-2 Has Been Revised to Correct Error
ML17292B5331999-01-15015 January 1999
Part 21 Rept Re XL-S96 CPR Correlation for SVEA-96 Fuel. Defect Applies Only to WNP-2,during Cycles 12,13 & 14 Operation.Evaluations of Defect Performed by ABB-CE
ML17292B4791998-12-31031 December 1998
Washington Public Power Supply Sys 1998 Annual Rept. with 981215 Ltr
ML17292B5351998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for WNP-2.With 990112 Ltr
ML17292B5741998-12-31031 December 1998
WNP-2 1998 Annual Operating Rept. with 990225 Ltr
ML17284A8231998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for WNP-2.With 981207 Ltr
ML17284A8081998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for WNP-2.With 981110 Ltr
ML17292B4451998-10-27027 October 1998
LER 98-012-01:on 980715,failure to Comply with Requirements of TS SR 3.8.4.7 Was Noted.Caused by Inadequate Work Practices.Training Session Was Held with Personnel.With 981027 Ltr
ML17284A7831998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for WNP-2.With 981007 Ltr
ML17284A7491998-09-10010 September 1998
WNP-2 Inservice Insp Summary Rept for Refueling Outage RF13 Spring,1998.
ML17284A7561998-09-0303 September 1998
LER 98-013-00:on 980805,ESF Actuations Were Noted Due to Deenergization of Vital Electrical Bus SM-8.Caused by Inadequate Direction in Troubleshooting Plan.Will Conduct Training for Engineering Personnel.With 980903 Ltr
ML17284A7571998-09-0202 September 1998
LER 98-014-00:on 980807,completion of TS 3.8.1.F Required Shutdown Due to Inoperability of EDG-2 Was Noted.Caused by Degraded Voltage Regulator for DG-2.Replaced Voltage Regulator & Associated Scrs.With 980902 Ltr
ML17284A7551998-09-0202 September 1998
LER 98-015-00:on 980808,discovered Reactor Coolant Pressure Boundary Leak During Shutdown Conditions.Caused by Leakage from Socket Weld (Fwb 63) on Elbow Connection.Failed Piping Connection Was Replaced.With 980902 Ltr
ML17284A7681998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for WNP-2.With 980915 Ltr
ML17284A7311998-08-17017 August 1998
LER 98-012-00:on 980716,determined That 24-month SR 3.8.4.7 Had Not Been Fulfilled within Specified Frequency.Caused by Inadequate Work Practices.License Requested & Received Enforcement Discretion Re Battery Svc test.W/980817 Ltr
ML17284A7261998-07-31031 July 1998
Monthly Operating Rept for July 1998 for WNP-2.W/980810 Ltr
ML17284A7121998-07-23023 July 1998
LER 98-006-01:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of 10CFR50,App R Calculations for High Impedance Faults.Caused by Inadequate Work Practices.Implemented Procedural Changes
ML17284A6951998-07-17017 July 1998
LER 98-011-00:on 980617,ECCS Pump Room Flooding Was Noted Due to FP Sys Pipe Break.Caused by Inadequate Design of FP Sys.Detailed Review of FP Sys Design Was Conducted. W/980717 Ltr
ML17284A6961998-07-15015 July 1998
LER 98-010-00:on 980615,TS Required Shutdown Due to Inoperability of TIP Sys Isolation Valve Was Noted.Caused by Improper Installation of TIP Tubing.Reattached Affected Tubing & Inspected Other TIP tubing.W/980715 Ltr
ML17284A6731998-07-0101 July 1998
LER 98-009-00:on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in preparation.W/980701 Ltr
ML17284A6751998-06-30030 June 1998
Ro:On 980617,flooding of RB Northeast Stairwell with Consequential Flooding of Two ECCS Pump Rooms.Caused by Inadequate Fire Protection Sys Design.Pumped Out Water from Affected Areas to Point Below Berm Areas of Pump Rooms
ML17284A6641998-06-24024 June 1998
LER 98-008-00:on 980531,inadvertent Full Scram During RPV Leak Testing in Mode 4 Was Noted.Caused by Change in Mgt Techniques.Revised Procedures to Take Into Account Addl Water Head in Pressure Sensing lines.W/980624 Ltr
ML17284A6651998-06-24024 June 1998
LER 98-007-00:on 980530,inadvertent Full Scram & Division 1 ECCS Injection Was Noted.Caused by Failure to Meet Mgt Work Practice Expectation When Encountering Deficient Procedure. Incident Review Board Convened to Review event.W/980624 Ltr
ML17284A6631998-06-19019 June 1998
LER 98-006-00:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of App R Calculations for High Impedance Fault Analysis.Caused Indeterminate. Implemented Procedural Changes Involving Operator Action
ML17284A6551998-06-0404 June 1998
LER 98-005-00:on 980506,potential for Failure of RHR Sys Valve to Close on Isolation Signal Was Noted.Caused by Design Deficiency.Caution Tag Was Placed on RHR-V-40 Control Switch to Inform Plant Operators of limitation.W/980604 Ltr
ML17284A6421998-06-0101 June 1998
LER 98-004-00:on 980502,determined That Primary Containment Penetration Overcurrent Protection Does Not Meet Reg Guide 1.63 Requirements.Caused by Inadequate Design Changes. Installed Addl Fuse in RHR-MO-9 circuit.W/980601 Ltr
ML17284A6491998-05-31031 May 1998
Rev 0 to COLR 98-14, WNP-2,Cycle 14 Colr.
ML17292B4031998-05-31031 May 1998
Monthly Operating Rept for May 1998 for WNP-2.W/980608 Ltr
ML17292B3921998-04-30030 April 1998
Monthly Operating Rept for Apr 1998 for WNP-2.W/980513 Ltr
ML17292B3291998-04-0909 April 1998
LER 98-003-00:on 980311,WNP-2 Experienced SCRAM Signal as Result of Low Rpv.Caused by Less than post-SCRAM Operational Strategy for Resetting SCRAM Signal in Conditions.Changes in post-SCRAM Operational Strategy implemented.W/980409 Ltr
ML17292B3281998-04-0909 April 1998
LER 98-002-00:on 980311,reactor Scram & Plant Transient Occurred,Due to Failed Closed Main Steam Isolation Valve. Caused by Loss of Pneumatic Actuating Supply Pressure. Problem Evaluation Request Written for Failure of MS-V-22D
ML17292B3371998-03-31031 March 1998
Monthly Operating Rept for Mar 1998 for WNP-2.W/980409 Ltr
ML17292B2641998-03-0404 March 1998
Performance Self Assessment,WNP-2.
ML17292B2661998-03-0404 March 1998
LER 98-001-00:on 980203,automatic Start of HPCS EDG Was Noted.Caused by Operator Error.Operations Crew Stabilized Plant at Approximately 75% Reactor Power & Investigation of Event Was initiated.W/980304 Ltr
ML17292B2911998-02-28028 February 1998
Monthly Operating Rept for Feb 1998 for WNP-2.W/980313 Ltr
ML17284A7971998-02-17017 February 1998
Rev 28 to Operational QA Program Description, WPPSS-QA-004.With Proposed Rev 29
ML17292B3591998-02-12012 February 1998
WNP-2 Cycle 14 Reload Design Rept.
1999-09-30
[Table view] |
Text
{{#Wiki_filter:CATEGORY 1 Rl REGULA INFORMATION DISTRIBUTIO YSTEM (RIDS),'P A'CCESSIOA
&BR:9901220118 DOC.DATE: 99/Ol/15 NOTARIZED:
NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH.NAME~AUTHOR AFFILIATION RICKARD,I.C.
ABB Combustion Engineering Nuclear Fuel (formerly Combustio RICKARD, I.C.ABB Atom, Inc.(formerly ASEA Atom, Inc.)RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)
SUBJECT:
Part 21 rept re XL-S96 CPR correlation for SVEA-96 fuel.Defect applies only to WNP-2,during Cycles 12,13&14 operation.
Evaluations of defect performed by ABB-CE.DISTRIBUTION CODE: IEIST COPIES RECEIVED: LTR I ENCL)SIZE: TITLE: Part 21 Rept (50 DKT)NOTES: RECIPIENT ID CODE/NAME PD4-2 PD INTERNA FIL S 0 NRR DRPM/PECB/B RES/DET/EIB RGN2 RGN4 COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME POSLUSNY,C NRR/DRPM/PECB PDR WARD, M.RGNl RGN3 COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 EXTERNAL: INPO RECORD CTR NRC PDR 1 1 1 1 NOAC SILVER,E NUDOCS FULL TXT 1 1 1-.1 D.u NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTETH TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DZSTRIBUTZON LISTS OR REDUCE THE NUMBER OF COP Z ES RECE I VED BY YOU OR YOUR ORGAN I ZAT ION g CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 15
'k I LqW'J~p(mp.a APE p QR q'4~Cj'le 8 c'"'s~ti".y~~.PC.&
January 15, 1999 LD-99-003 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Subject'.Report of a Oefect Pursuant to 10 CFR 21 Concerning the XL96 CPR Correlation for SVEA-96 Fuel The purpose of this letter is to notify the Nuclear Regulatory Commission of a defect as defined in 10 CFR 21,"Reporting of Defects and Noncompliance." The defect concerns the XL-S96 Critical Power Ratio (CPR)correlation for ABB SYEA-96 fuel assemblies for Boiling Water Reactors (BWRs).Specifically, the defect concerns the XL-SS6 CPR correlation, which is based solely on a cosine axial povrer shape.The defect could lead~to non-conservative Operating Limit MCPRs and monitored CPRs for top-peaked axial power shapes.The Enclosure summarizes the evaluation performed by ABB Combustion Engineering (ABB-CE).If you have any questions, please feel free to contact me or Mr.Yirgil Paggen of my staff at (860)285<700.Very truly yours, COMBUSTION ENGINEERING, INC.lan C.Rickard, Director Nuclear Licensing
Enclosure:
As stated cc: M.A.Bamoski (ABB-CE)ABB Combustion Engineering Nuclear Power Cambveeen Rn{{{eeerin{t.
tee.P.O, Bex 500 Tetephono{{{80)663 19t t 2000 Day Htt Rd.Fax{060)285-5203 Windsor, CT Ot0954500'ti'ti0%220118
'ti90i%5 PDR ADOCK 05000397 PDR ABB Combustion Engineering Nuclear Power 10 CFR21 Re ortofa Defector Failure to Corn I The following information is provided pursuant to the requirements s t e forth in 10 CFR 21.21(c)(4): (i)Name and address of theindividualsinfoiming the Commission:
lan C.Rickard, Director Nuclear Licensing Combustion Engineering, inc.2000 Day HiH Road Vfindsor, CT 06095-0500 (ii)Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United Slates which fails to comply or contains a defect: The activity for which this report is being filed is the use of the XL-S96 CPR correlation in determining Safety and Operating Limit MCPRs and in monitoring of CPRs in SVEA-96 Boiling Water Reactor (BNIR)fuef assemblies, This defect applies only to the Washington Public Power Supply System Nuclear Project Unit 2 nuclear power plant during Cycles 12, 13, and 14 operation.(iii)Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect: Combustion Engineering, Inc.'2000 Day HHi Road Windsor, CT 06095-0500 (iv)Nature of the defect or failure to comply and the safety ha ard which is created or could be created by such defect or failure to comply: The defect fdentffied is associated with the use of the XL-S96 CPR correlation in determining Safety and Operating Limit MCPRs and in monitoring of CPRs in SVEA-96 BWR fuel assemblies.
For top-peaked axial power shapes, the use of this CPR.correlation could yield non-conservative Operating Limit MCPRs or non-conservative-monitored CPR values.(v)The date on which the information of such defect or failure to comply was obtained: ABB-CE determined that a defect in the CPR correlation existed on January 15, 1999.
~I~N'V Page20f2 WE (vi)In the case of a basic component which contains a defect or fails to comply, the number and location of all such components in use at, supplied for, or being supplied for one or more facilities or activities subject to the regulations ln this part: The defect applies only to BWR reload fuel assemblies currently in operation at WNP-2.(vii)The corrective action which has been, is being, or will be taken;the name of the tnd)vidual or organitation responsible for the action;and the length of time that has been or will be taken to complete the action: Evaluations of the defect have been performed by ABB-CE, lt has been determined the use of the correlation in determining Safety and Operating Limit MCPRs for Cycles 12, 13, and 14 is acceptable.
Furthermore, the use of the correlation in monitoring CPR in Cycles 12 and 13 has been adequate.For Cycle 14, the use of the correlation for'onitoring CPR in the core is acceptable prior to 5,600 MWd/MtU.From 5,600 MWd/MtU to the end of Cycle 14 the use of the correlation for monitoring CPR in the core may become non-conservative.
The utility currently projects that WNP-2 will reach 5,600 MWd/MTU in February 1999, ABB-GE has provided the Washington Public Power~Supply System with recommended corrective actions to ensure that sufficient margin for monitoring the core CPR is maintained.
fviii)Any advice related to the defect or failure to comply about thefacility, activity, or basic component that has been, is being, or will be gi ven to purchasers or licensees:
The Nfashingtan Public Power Supply System has been notified of the defect and has been provided with necessary information and recommendations, TOTAL P.84
0 January 15, 1999 LD-99-003 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555
Subject:
Report of a Defect Pursuant to 10 CFR 21 Concerning the XL-S96 CPR Correlation for SVEA-96 Fuel The purpose of this letter is to notify the Nuclear Regulatory Commission of a defect as defined in 10 CFR 21,"Reporting of Defects and Noncompliance." The defect concerns the XL-S96 Critical Power Ratio (CPR)correlation for ABB SVEA-96 fuel assemblies for Boiling Water Reactors (BWRs).Specifically, the defect concerns the XL-S96 CPR correlation, which is based solely on a cosine axial power shape.The defect could lead to non-conservative Operating Limit MCPRs and monitored CPRs for top-peaked axial powershapes.
The Enclosure summarizes the evaluation performed by ABB Combustion Engineering (ABB-CE).If you have any questions, please feel free to contact me or Mr.Virgil Paggen of my staff at (860)285-4700.Very truly yours, COMBUSTION ENGINEERING, INC.lan C.Rickard, Director Nuclear Licensing
Enclosure:
As stated cc: M.A.Barnoski (ABB-CE)gQQQO PiJ ABB Combustion Engineering Nuclear Power Combustion Engineering, Inc.P.O.Box 500 2000 Day Hill Rd.Windsor, CT 06095-0500 Telephone (860)688-1911 Fax (860)285.5203 0 t Enclosure to LD-99-003 Page 1 of 2 ABB Combustion Engineering Nuclear Power 10 CFR 21 Re ort of a Defect or Failure to Com I The following information is provided pursuant to the requirements set forth in 10 CFR 21.21(c)(4): (i)Name and address of tike indi viduals informing tike Commission:
lan C.Rickard, Director Nuclear Licensing Combustion Engineering, Inc.2000 Day Hill Road Windsor, CT 06095-0500 (ii)Identification of tike facility, the activity, or the basic component supplied for such facility or such activity witlkin tike United States wlkiclk fails to comply or contains a defect: The activity for which this report is being filed is the use of the XL-S96 CPR correlation in determining Safety and Operating Limit MCPRs and in monitoring of CPRs in SVEA-96 Boiling Water Reactor (BWR)fuel assemblies.
This defect applies only to the Washington Public Power Supply System Nuclear Project Unit 2 nuclear power plant during Cycles 12, 13, and 14 operation.(iii)Identification of tike firm constructing the facility or supplying the basic component which fails to comply or contains a defect: Combustion Engineering, Inc.2000 Day Hill Road Windsor, CT 06095-0500 (iv)Nature of the defect or failure to comply and the safety/kazard whicli is created or could be created by suclk defect or failure to comply: The defect identified is associated with the use of the XL-S96 CPR correlation in determining Safety and Operating Limit MCPRs and in monitoring of CPRs in SVEA-96 BWR fuel assemblies.
For top-peaked axial power shapes, the use of this CPR correlation could yield non-conservative Operating Limit MCPRs or non-conservative monitored CPR values.(v)The date on which theinformation of such defect or failure to comply was obtained: ABB-CE determined that a defect in the CPR correlation existed on January 15, 1999.
Enclosure to LD-99-003 Page2of2 (vi)In the case of a basic component whic/t contains a defect or fails to comply, the number and location of all such components in use at, supplied for, or being supplied for one or more facilities or acti vities subject to the regulations in this part: The defect applies only to BWR reload fuel assemblies currently in operation at WNP-2.(vii)T/te corrective action which has been, is being, or will be taken;the name of theindividual or organization responsible for the action;and the length of time that has been or will be taken to complete the action: Evaluations of the defect have been performed by ABB-CE.It has been determined the use of the correlation in determining Safety and Operating Limit MCPRs for Cycles 12, 13, and 14 is acceptable.
Furthermore, the use of the correlation in monitoring CPR in Cycles 12 and 13 has been adequate.For Cycle 14, the use of the correlation for monitoring CPR in the core is acceptable prior to 5,600 MWd/MtU.From 5,600 MWd/MtU to the end of Cycle 14 the use of the correlation for monitoring CPR in the core may become non-conservative.
The utility currently projects that WNP-2 will reach 5,600 MWd/MTU in February 1999.ABB-CE has provided the Washington Public Power Supply System with recommended corrective actions to ensure that sufficient margin for monitoring the core CPR is maintained.(viii)Any advice related to the defect or failure to comply about the facility, activity, or basic"component that has been, is being, or will be given to purcltasers or licensees:
The Washington Public Power Supply System has been notified of the defect and has been provided with necessary information and recommendations.}}
