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| | issue date = 05/17/1999 | | | issue date = 05/17/1999 |
| | title = Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested | | | title = Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested |
| | author name = WIDAY J A | | | author name = Widay J |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:CATEGORYREGULATORY INFORMATION DZSTRXBUTZON SYSTEM(RXDS)ACCESSION NBR:9905280047 DOC.DATE:99/05/17NOTARIZED: | | {{#Wiki_filter:CATEGORY REGULATORY INFORMATION DZSTRXBUTZON SYSTEM (RXDS) |
| NODOCKETFACZL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester G05000244AUTH.NAMEAUTHORAFFILIATION WZDAY,J.A.
| | ACCESSION NBR: 9905280047 DOC. DATE: 99/05/17 NOTARIZED: NO DOCKET FACZL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION WZDAY,J.A. Rochester Gas &. Electric Corp. |
| Rochester Gas&.ElectricCorp.RECXP.NAME RECIPIENT AFFILIATION NRC-NoDetailedAffiliation Givenlq | | RECXP.NAME RECIPIENT AFFILIATION NRC - No Detailed Affiliation Given lq |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Part21reptrerelaydeficiency dtectedduringpre-installation testing.Causedby'incorrectly wiredrelaycoil.RelayswerereturnedtoEatonCorpforinvestigation.
| | Part 21 rept re relay deficiency dtected during pre-installation testing. Caused by'incorrectly wired relay coil. Relays were returned to Eaton Corp for investigation. |
| Relayswererepaired&retested.
| | Relays were repaired & retested. |
| DISTRIBUTION CODE:IE28TCOPIESRECEIVED:LTR ENCLSIZE:TITLE:LicenseeEventReport(LER)6Part21ReptCombination (50NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72) | | DISTRIBUTION CODE: IE28T COPIES RECEIVED:LTR ENCL SIZE: T TITLE: Licensee Event Report (LER) 6 Part 21 Rept Combination (50 Dkt) |
| .TDkt)E05000244GRECIPIENT IDCODE/NAME LPD1-1LAVZSSING,G.
| | E NOTES:License Exp date in accordance with 10CFR2,2 .109(9/19/72) . 05000244 G |
| COPIESLTTRENCL1111RECIPIENT XDCODE/NAME LPD1-1PDCOPIESLTTRENCL11INTERNAL:
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL XD CODE/NAME LTTR ENCL LPD1-1 LA 1 1 LPD1-1 PD 1 1 VZSSING,G. 1 1 INTERNAL: ACNW 1 AEOD SPD/RRAB 1 1 DEDRO 1 =FXL'E CENTERS 1 1 NRR/DE/EEIB 1 NRR/DE/EMCB 1 1 NRR/DE/EMEB 1 NRR/DXPM/ZOLB 1 1 NRR/DIPM/XQMB 1 NRR/DLPM 1 1 NRR/DRIP/REXB 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SPSB 1 RES/DET/EZB 1 1 RGN 1 1 RGN 2 1 1 RGN 3 1 RGN 4 1 1 RGN1 FXLE 01 1 EXTERNAL: INPO RECORD CTR 1 1 L ST LOBBY WARD 1 1 LXTCO STUART, VA 1 1 NOAC MAYS,G 1 1 U NOAC QUEENER, D 1 1 . NRC PDR 1 1 NUDOCS FULL TXT 1 1 M NOTE TO ALL "RIDS" RECZPZENTS: |
| ACNWDEDRONRR/DE/EEIB NRR/DE/EMEB NRR/DIPM/XQMB NRR/DRIP/REXB NRR/DSSA/SPSB RGN1RGN3RGN1FXLE011AEODSPD/RRAB1=FXL'ECENTERS1NRR/DE/EMCB 1NRR/DXPM/ZOLB 1NRR/DLPM1NRR/DSSA/SPLB 1RES/DET/EZB 1RGN21RGN41111111111111111111EXTERNAL:
| | PLEASE HELP US TO REDUCE HASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, DISTRIBUTION LISTS CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 FULL TEXT CONVERSXON REQUIRED TOTAL NUMBER OF COPXES REQUIRED: LTTR 29 ENCL 29 |
| INPORECORDCTRLXTCOSTUART,VANOACQUEENER,DNUDOCSFULLTXT11LSTLOBBYWARD11NOACMAYS,G11.NRCPDR11111111UMNOTETOALL"RIDS"RECZPZENTS:
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| PLEASEHELPUSTOREDUCEHASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083FULLTEXTCONVERSXON REQUIREDTOTALNUMBEROFCOPXESREQUIRED:
| | ROCHESTERGASANDEIECTRICCORPORATION.S9EASTAVEiYIJE, ROCHESTER, III Y f46494001 AREA CODE 716.%6.2700 May 17, 1999 U.S. Nuclear Regulatory Commission Operations Center Facsimile Number 301-816-5151 Telephone Number 301-816-5100 |
| LTTR29ENCL29 ROCHESTERGASANDEIECTRICCORPORATION.S9EASTAVEiYIJE, ROCHESTER, IIIYf46494001 AREACODE716.%6.2700 May17,1999U.S.NuclearRegulatory Commission Operations CenterFacsimile Number301-816-5151 Telephone Number301-816-5100
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| ==Subject:== | | ==Subject:== |
| InitialNotification of10CFRPart21DefectR.E.GinnaNuclearPowerPlantDocketNo.50-244Theenclosedinitialnotification isprovidedinaccordance with10CFRPart21,Reporting ofDefectsandNoncompliance, Section21(d)(3){i),whichrequires"Initialnotification byfacsimile".
| | Initial Notification of 10 CFR Part 21 Defect R.E. Ginna Nuclear Power Plant Docket No. 50-244 The enclosed initial notification is provided in accordance with 10 CFR Part 21, Reporting of Defects and Noncompliance, Section 21 (d) (3) {i), which requires "Initial notification by facsimile". written notification, in accordance with 10 CFR Part 21, Section 21 {d) (3) (ii), will be provided by June 16, 1999. |
| writtennotification, inaccordance with10CFRPart21,Section21{d)(3)(ii),willbeprovidedbyJune16,1999.Verytrulyyours,Q.dshA.Wida.Enclosures 9905280047 990517PDRADOCK050002448 10CFR21INITIALFACSIMILE NOTIFICATION
| | Very truly yours, Q.d s h A. Wida |
| 'NAMEANDADDRESSOFTHEINDIVIDUAL INFORMING THECOMMISSZO¹ NAME:JosephA.WidayPlantManagerADDRESS:Rochester Gas&ElectricCorporation 89EastAvenueRochester, New-York14649IDENTIFICATI9N OFTHEFACILITY'HE ACTIVITY'R THEBASICCOMPONENT SUPPLIEDFORSUCHFACILITYWHICHFAILSTOCOMPLYORCONTAINSADEFECT:Thebasiccomponent istheNBPD65NRControlRelay,suppliedbyEATONCorporation, Inc.Thiscomponent wasPurchased SafetyRelatedforuseinvariouslocations atGinnaStation.IDENTIFICATION OFTHEFIRMCONSTRUCTING THEFACILITYORSUPPLYING THEBASICCOMPONENT WHICHFAILSTOCOMPLYORCONTAINSADEFECTsTheRelaysweresuppliedtoRG&EbyEATONCorporation EATONCorporatiod. | | .Enclosures 9905280047 990517 PDR ADOCK 05000244 8 |
| Inc.21SouthStDanbury,Ct06810NATUREOFTHEDEFECTORFAILURETOCOMPLYANDTHESAFETYRLSARDWHICHXSCREATEDORCOULDBECREATEDBYSUCHDEFECTORFAILURETOCOMPLY''he natureofthedefectconsisted ofamanufacturing deficiency. | | |
| Uponinvestigation, byEATON,itwasdetermined thattherelaycoilhadbeenincorrectly wiredsuchthattheinternalrelaydesign,whichincludesapickupandaholdcoil,wouldopposeeachotheratlowervoltagesandprohibitholdingcoilactuation whichresultedinexcessive relaychatter.Theincorrect wiringwasattributed toinsufficient trainingandsubsequent poorworkmanship ofanewemployee.
| | 10CFR21 INITIALFACSIMILE NOTIFICATION |
| Thefactorytestingdidnotdetectthechattering relays.Thedeficiency wasdetectedbyRG&Eduringpre-installation testingpriortoinstallation intoreactortriplogic.Noactualsafetyhazardexisted.
| | 'NAME AND ADDRESS OF THE INDIVIDUAL INFORMING THE COMMISSZO¹ NAME: Joseph A. Widay Plant Manager ADDRESS: Rochester Gas & Electric Corporation 89 East Avenue Rochester, New-York 14649 IDENTIFICATI9N OF THE FACILITY'HE ACTIVITY'R THE BASIC COMPONENT SUPPLIED FOR SUCH FACILITY WHICH FAILS TO COMPLY OR CONTAINS A DEFECT: |
| | The basic component is the NBPD65NR Control Relay, supplied by EATON Corporation, Inc. This component was Purchased Safety Related for use in various locations at Ginna Station. |
| | IDENTIFICATION OF THE FIRM CONSTRUCTING THE FACILITY OR SUPPLYING THE BASIC COMPONENT WHICH FAILS TO COMPLY OR CONTAINS A DEFECTs The Relays were supplied to RG&E by EATON Corporation EATON Corporatiod. Inc. |
| | 21 South St Danbury, Ct 06810 NATURE OF THE DEFECT OR FAILURE TO COMPLY AND THE SAFETY RLSARD WHICH XS CREATED OR COULD BE CREATED BY SUCH DEFECT OR FAILURE TO COMPLY''he nature of the defect consisted of a manufacturing deficiency. Upon investigation, by EATON, determined that the relay coil had been incorrectly it was wired such that the internal relay design, which includes a pick up and a hold coil, would oppose each other at lower voltages and prohibit holding coil actuation which resulted in excessive relay chatter. |
| | The incorrect wiring was attributed to insufficient training and subsequent poor workmanship of a new employee. The factory testing did not detect the chattering relays. |
| | The deficiency was detected by RG&E during pre-installation testing prior to installation into reactor trip logic. No actual safety hazard existed. |
| | |
| | THE DATE ON ERICH THE ZNFORMJiTZON OF SUCH DEFECT OR FAILURE TO COMPLY WAS OBTAXNIlD~ |
| | The 'infoxmation was obtained on April 2, 1999, during the pre-installation testing of the relays. |
| | IN THE CASE OF A BASIC COMPONENT WHICH CONTAINS A DEFECT OR FAXLS TO COMPLYI THE NUMBER AND LOCATION OF ALL SUCH COMPONENTS IN USE AT, SUPPLXED FORp OR BEING SUPPLXED FOR GXNNA STATIONS There are numerous NBFD65NR relays, permanently installed at Ginna Station. None of the deficient relays were installed. |
| | THE CORRECTXVE ACTXON 7%1CH HAS PEEN'S BEINQs OR RILL BE TAKEN; THE NAMg OF THE XNDIVZDUAL OR ORGANISATION RESPONSXBLE FOR THE ACTIONS AND THE LENGTH OF TIME THAT HAS BEEN OR NXLL BE TAKEN TO COMPLETE THE ACTIONS After the deficiency was discovered by RG&E, the relays were returned to EATON for evaluation and root cause analysis. An RG&E QA Engineer was present during 'the root cause investigation. At EATON's factory, it was discovered that one of the two relay coils was wired up backwards on all the relays in question. The relays were tested by EATON and passed their bench test, but the factory noise masked the sound of the relays chattering. |
| | The relays were repaired and retested using enhanced test procedures which included checking for relay chatter. |
| | RG&E has changed their vendor requirements to include Source Surveillance on future orders with EATON. RG&E will perform receipt testing of'elays purchased from EATON. |
| | ANY ADVICE RELATED TO THE DEFECT OR FAILURE TO COMPLY ABOUT THE FACZLXTY, ACTIVITY, OR BASIC COMPONENT THAT HAS BEEN, IS BEING, OR WILL BE GIVEN TO PURCHASERS OR LICENSEES< |
| | RG&E's advice would be to perform receipt inspection testing of relays or perform a source surveillance of the vendor's testing practices. |
| | TOTRL P.84 |
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| | ROCHFSTER GA8 AND ELECTRIC CORPORA 7ION R.E. GINNh NUCLEAR POKER PIANOS Gieut Wfnfstrnlipn 1503 Dtkc R08 Onbvfo, HY 10519 Contact Name: |
| | Company Name: |
| | Telecopy Number: |
| | Sender: |
| | |
| | == Description:== |
| | |
| | Number of pages, includlrfg cover sheet: |
| | 0 .S.: |
| | lf you have not received all pages, or if you have any questions or problems with receiving, contact: |
| | Sharon Sortino or Wendy Merkel Verification Number: 716-771-3548 or 716-771-3102 Telecopy Number: 716-771-3943 |
| | |
| | ROCHESTER GA8 AND EI.ECTRIC CORPORA T/ON R.E. GINNh NUCLEAR POKER PEDANT Gieut ~Mtratisn 1503 En& W8 06trf0, NY 1%519 Contact Name: |
| | Company Name: |
| | Telecopy Number: |
| | Sender: |
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| THEDATEONERICHTHEZNFORMJiTZON OFSUCHDEFECTORFAILURETOCOMPLYWASOBTAXNIlD~
| | == |
| The'infoxmation wasobtainedonApril2,1999,duringthepre-installation testingoftherelays.INTHECASEOFABASICCOMPONENT WHICHCONTAINSADEFECTORFAXLSTOCOMPLYITHENUMBERANDLOCATIONOFALLSUCHCOMPONENTS INUSEAT,SUPPLXEDFORpORBEINGSUPPLXEDFORGXNNASTATIONSTherearenumerousNBFD65NRrelays,permanently installed atGinnaStation.Noneofthedeficient relayswereinstalled.
| | Description:== |
| THECORRECTXVE ACTXON7%1CHHASPEEN'SBEINQsORRILLBETAKEN;THENAMgOFTHEXNDIVZDUAL ORORGANISATION RESPONSXBLE FORTHEACTIONSANDTHELENGTHOFTIMETHATHASBEENORNXLLBETAKENTOCOMPLETETHEACTIONSAfterthedeficiency wasdiscovered byRG&E,therelayswerereturnedtoEATONforevaluation androotcauseanalysis.
| |
| AnRG&EQAEngineerwaspresentduring'therootcauseinvestigation.
| |
| AtEATON'sfactory,itwasdiscovered thatoneofthetworelaycoilswaswiredupbackwards onalltherelaysinquestion.
| |
| TherelaysweretestedbyEATONandpassedtheirbenchtest,butthefactorynoisemaskedthesoundoftherelayschattering.
| |
| Therelayswererepairedandretestedusingenhancedtestprocedures whichincludedcheckingforrelaychatter.RG&Ehaschangedtheirvendorrequirements toincludeSourceSurveillance onfutureorderswithEATON.RG&Ewillperformreceipttestingof'elayspurchased fromEATON.ANYADVICERELATEDTOTHEDEFECTORFAILURETOCOMPLYABOUTTHEFACZLXTY,
| |
| : ACTIVITY, ORBASICCOMPONENT THATHASBEEN,ISBEING,ORWILLBEGIVENTOPURCHASERS ORLICENSEES< | |
| RG&E'sadvicewouldbetoperformreceiptinspection testingofrelaysorperformasourcesurveillance ofthevendor'stestingpractices.
| |
| TOTRLP.84
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| ROCHFSTER GA8ANDELECTRICCORPORA7IONR.E.GINNhNUCLEARPOKERPIANOSGieutWfnfstrnli pn1503DtkcR08Onbvfo,HY10519ContactName:CompanyName:TelecopyNumber:Sender:Description:
| | Number of pages, including cover skeet: |
| Numberofpages,includlrfg coversheet:0.S.:lfyouhavenotreceivedallpages,orifyouhaveanyquestions orproblemswithreceiving, contact:SharonSortinoorWendyMerkelVerification Number:716-771-3548 or716-771-3102 TelecopyNumber:716-771-3943
| | Date Sent: |
| ,ROCHESTER GA8ANDEI.ECTRIC CORPORAT/ONR.E.GINNhNUCLEARPOKERPEDANTGieut~Mtratisn 1503En&W806trf0,NY1%519ContactName:CompanyName:TelecopyNumber:Sender:Description:
| | If you have not received all pages, or if you have any questions or problems with receiving, contact: |
| Numberofpages,including coverskeet:DateSent:Ifyouhavenotreceivedallpages,orifyouhaveanyquestions orproblemswithreceiving, contact:SharonSortinoorWendyMerkelVerification Number:716-771-3548 or716-771-3102 TelecopyNumber:716-771-3943
| | Sharon Sortino or Wendy Merkel Verification Number: 716-771-3548 or 716-771-3102 Telecopy Number: 716-771-3943 |
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| 0$flh'1999U.S.NuclearRegulatory Cotnntlsslon Operations CenterEventReport~PaelPowerReactorEvent035731Site:GINNAUnit:1ReactorType:(1)W-2-LPContainment Type:DRYAMBNotification Date/Time:05/18/1999 12:47(EDT)Region'.1State:NYEventDate/Time:05/18/1999 (EDT)LastModification: | | 0$flh'1999 U.S. Nuclear Regulatory Cotnntlsslon Operations Center Event Report ~Pa el Power Reactor Event 0 35731 Site: GINNA Notification Date / Time: 05/18/1999 12:47 (EDT) |
| 05/18/1999 UNSPECIFIED PARAGRAPH NRCNotifiedby: | | Unit: 1 Region'. 1 State: NY Event Date /Time: 05/18/1999 (EDT) |
| JOSEPHA.WIDAY(VIA FHQOpsOfficer.STEVESANDINEmergency Class:NONEMERGENCY 10CFRSection:21.21Notifications:
| | Reactor Type: (1) W-2-LP Last Modification: 05/18/1999 Containment Type: DRY AMB NRC Notifiedby: JOSEPH A. WIDAY(VIAF Notifications: PETER ESELGROTH R1 HQ Ops Officer. STEVE SANDIN VERN HODGE NRR Emergency Class: NON EMERGENCY 10 CFR Section: |
| PETERESELGROTH R1VERNHODGENRRUnitScramCodeRXCritInitPowerYes98InitialRXModePowerOperation 98PowerOperation CurrPowerCurrentRXModeDEFICIENT CONTROLRELAYSIDENTIFIED DURINGPRE-INSTALLATION TESTING.ON4/2/99,THELICENSEEIDENTIFIED THATCONTROLRELAYS(NBF065NR)
| | 21.21 UNSPECIFIED PARAGRAPH Unit Scram Code RX Crit Init Power Initial RX Mode Curr Power Current RX Mode Yes 98 Power Operation 98 Power Operation DEFICIENT CONTROL RELAYS IDENTIFIED DURING PRE-INSTALLATIONTESTING. |
| MANUFACTURED BYEATONCORPORATION CONTAINED AMANUFACTURING DEFICIENCY, I.E.,"THERELAYCOILHADBEENINCORRECTLY WIREDSUCHTHATTHEINTERNALRELAYDESIGN,WHICHINCLUDESAP(CKUPANDAHOLDCOlL,WOULDOPPOSEEACHOTHERATLOWERVOLTAGESANDPROHIBITHOLDINGCOILACTUATION WHICHRESULTEDINEXCESSIVE RELAYCHATTER." | | ON 4/2/99, THE LICENSEE IDENTIFIEDTHAT CONTROL RELAYS (NBF065NR) MANUFACTURED BY EATON CORPORATION CONTAINED A MANUFACTURINGDEFICIENCY, I.E., "THE RELAY COIL HAD BEEN INCORRECTLY WIRED SUCH THAT THE INTERNAL RELAY DESIGN, WHICH INCLUDES A P(CK UP AND A HOLD COlL, WOULD OPPOSE EACH OTHER AT LOWER VOLTAGES AND PROHIBIT HOLDING COIL ACTUATIONWHICH RESULTED IN EXCESSIVE RELAY CHATTER." THIS DEFECT WAS IDENTIFIED DURING PRE-INSTAI LATION TESTING PRIOR TO USE IN THE REACTOR TRIP LOGIC. NO DEFICIENT RELAYS ARE INSTALLED. |
| THISDEFECTWASIDENTIFIED DURINGPRE-INSTAI LATIONTESTINGPRIORTOUSEINTHEREACTORTRIPLOGIC.NODEFICIENT RELAYSAREINSTALLED.
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| ROCHESTER GASANOEIECTRICCORPORATIOI 89EASTAVEIIIUE, ROCHESTER, NV<4&94OO~hREACOOE716.54S.2700 May17,1999U.S.NuclearRegulatory Commission Operations CenterFacsimile Number301-816-5151 Telephone Number301-816-5100 | | ROCHESTER GAS ANOEI ECTRIC CORPORATIOI 89EASTAVEIIIUE, ROCHESTER, NV <4&94OO~ |
| | hREA COOE 716.54S.2700 May 17, 1999 U.S. Nuclear Regulatory Commission Operations Center Facsimile Number 301-816-5151 Telephone Number 301-816-5100 |
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| ==Subject:== | | ==Subject:== |
| InitialNotification of10CPRPart21DefectR.E.GinnaNuclearPowerPlantDocketNo.50-244Theenclosedinitialnotification isprovidedinaccordance with10CFRPart21,Reporting ofDefectsandNoncompliance, Section21(d)(3)(i),whichrequires"Initialnotification byfacsimile".
| | Initial Notification of 10 CPR Part 21 Defect R.E. Ginna Nuclear Power Plant Docket No. 50-244 The enclosed initial notification is provided in accordance with 10 CFR Part 21, Reporting of Defects and Noncompliance, Section 21 (d) (3) (i), which requires "Initial notification by facsimile". Written notification, in accordance with 10 CFR Part 21, Section 21 (d) (3) (ii), will be provided by June 16, 1999. |
| Writtennotification, inaccordance with10CFRPart21,Section21(d)(3)(ii),willbeprovidedbyJune16,1999.Verytrulyyours,a.dshA.WidaEnclosures
| | Very truly yours, a.d s h A. Wida Enclosures |
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| 10CFR21INITI.'0FACSIMILE NOTIFICATION, NAMEANDADDRESSOFTHEXNDXUIDUAL XNFORMING THECOMMISSXONs NAME:ADDRESS:JosephA.NidayPlantManagerRochester Gas&ElectricCorporation 89EastAvenueRochester, NewYork14649ZZ.IDENTIFXCATION OFTHEFACILITY, THEACTIVZTY, ORTHEBASICCOMPONENT SUPPLZEDFORSUCHFACILITYWHICHFAILSTOCOMPLYORCONTAINSADEFECT:Thebasiccomponent istheNBFD6SNRControlRelay,suppliedbyEATONCorporation, Inc.Thiscomponent wasPurchased SafetyRelatedforuseinvariouslocations atGinnaStation.III.IDENTIFICATXON OFTHEFXRMCONSTRUCTZNQ THEFACILITYORSUPPLYING THEBASICCOMPONENT WHICHFAILSTOCOMPLYORCONTAINSADEFECTsIV-TheRelaysweresuppliedtoRG&EbyEATONCorporation EATONCorporation Inc.21SouthStDanbury,Ct06810,NATUREOFTHEDEFECTORFAILURETOCOMPLYANDTHESAFETYHAZARDNBXCHXSCREATEDORCOULDBECREATEDBYSUCHDEFECTORFAILURETOCOMPLYtThenatureofthedefectconsisted ofamanufacturing deficiency.
| | 10CFR21 INITI.'0 FACSIMILE NOTIFICATION, NAME AND ADDRESS OF THE XNDXUIDUAL XNFORMING THE COMMISSXONs NAME: Joseph A. Niday Plant Manager ADDRESS: Rochester Gas & Electric Corporation 89 East Avenue Rochester, New York 14649 ZZ. IDENTIFXCATION OF THE FACILITY, THE ACTIVZTY, OR THE BASIC COMPONENT SUPPLZED FOR SUCH FACILITY WHICH FAILS TO COMPLY OR CONTAINS A DEFECT: |
| Uponinvestigation, byEATON,itwasdetermined thattherelaycoilhadbeenincorrectly wiredsuchthattheinternalrelaydesign,whichincludesapickupandaholdcoil,wouldopposeeachotheratlowervoltagesandprohibitholdingcoilactuation whichresultedinexcessive relaychatter.Theincorrect wiringwasattributed toinsufficient trainingandsubsequent poorworkmanship ofanewemployee.
| | The basic component is the NBFD6SNR Control Relay, supplied by EATON Corporation, Inc. This component was Purchased Safety Related for use in various locations at Ginna Station. |
| Thefactorytestingdidnotdetectthechattering relays.Thedeficiency wasdetectedbyRG&Eduringpre-installation testingpriortoinstallation intoreactortriplogic.Noactualsafetyhazardexisted.
| | III. IDENTIFICATXON OF THE FXRM CONSTRUCTZNQ THE FACILITY OR SUPPLYING THE BASIC COMPONENT WHICH FAILS TO COMPLY OR CONTAINS A DEFECTs The Relays were supplied to RG&E by EATON Corporation EATON Corporation Inc. |
| | 21 South St Danbury, Ct 06810, IV- NATURE OF THE DEFECT OR FAILURE TO COMPLY AND THE SAFETY HAZARD NBXCH XS CREATED OR COULD BE CREATED BY SUCH DEFECT OR FAILURE TO COMPLYt The nature of the defect consisted of a manufacturing deficiency. Upon investigation, by EATON, it was determined that the relay coil had been incorrectly wired such that the internal relay design, which includes a pick up and a hold coil, would oppose each other at lower voltages and prohibit holding coil actuation which resulted in excessive relay chatter. |
| | The incorrect wiring was attributed to insufficient training and subsequent poor workmanship of a new employee. The factory testing did not detect the chattering relays. |
| | The deficiency was detected by RG&E during pre-installation testing prior to installation into reactor trip logic. No actual safety hazard existed. |
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| THEDATEONWHICHTHEINFORMATION OFSUCHDEFECTORFAILURETQCOMPLYWASOBTAXNRDa The'nformation wasobtainedonApril2,1999,duringthepre-installation testingoftherelays.INTHECASEOFABASICCOMPONENT WHXCHCONTAINSADEFECTORFAXLSTQCOMPLYITHENUMBERANDLOCATIONOFALLSUCHCOMPONENTS INUSEAT,SUPPLXEDFORORBEXNGSUPPLIEDFQRGZNNASTATIONSTherearenumerousNBPD65NRrelays,permanently installed atGinnaStation.Noneofthedeficient relayswereinstalled.
| | THE DATE ON WHICH THE INFORMATION OF SUCH DEFECT OR FAILURE TQ COMPLY WAS OBTAXNRDa The'nformation was obtained on April 2, 1999, during the pre-installation testing of the relays. |
| THECORRECTIVE ACTXONWHICHHASBEEN,ISBEING,OR'WILLBETARENgTHENAKEOlPTHEXNDXUXDUAL ORQRGANXEATXON RESPQNSXBLE FORTHEACTIONSANDTHELENGTHOPTIMETHATHASBEENORWXLLBETAKENTOCOMPLETETHEACTION!Afterthedeficiency wasdiscover'ed byRG&E,therelayswerereturned, toEATONforevaluation androotcauseanalysis.
| | IN THE CASE OF A BASIC COMPONENT WHXCH CONTAINS A DEFECT OR FAXLS TQ COMPLYI THE NUMBER AND LOCATION OF ALL SUCH COMPONENTS IN USE AT, SUPPLXED FOR OR BEXNG SUPPLIED FQR GZNNA STATIONS There are numerous NBPD65NR relays, permanently installed at Ginna Station. None of the deficient relays were installed. |
| AnRG&EQAEngineerwaspresentduringtherootcauseinvestigation.
| | THE CORRECTIVE ACTXON WHICH HAS BEEN, IS BEING, OR 'WILL BE TARENg THE NAKE OlP THE XNDXUXDUAL OR QRGANXEATXON RESPQNSXBLE FOR THE ACTIONS AND THE LENGTH OP TIME THAT HAS BEEN OR WXLL BE TAKEN TO COMPLETE THE ACTION! |
| AtEATON'sfactory,itwasdiscovered thatoneofthetworelaycoilswaswiredupbackwards onalltherelaysinquestion.
| | After the deficiency was discover'ed by RG&E, the relays were returned, to EATON for evaluation and root cause analysis. An RG&E QA Engineer was present during the root cause investigation. At EATON's factory, discovered that one of the two relay coils was wired up it was backwards on all the relays in question. The relays were tested by EATON and passed their bench test, but the factory noise masked the sound of the relays chattering. |
| TherelaysweretestedbyEATONandpassedtheirbenchtest,butthefactorynoisemaskedthesoundoftherelayschattering.
| | The relays were repaired and retested using enhanced test procedures which included checking for relay chatter. |
| Therelayswererepairedandretestedusingenhancedtestprocedures whichincludedcheckingforrelaychatter.RG&Ehaschangedtheirvendorrequirements toincludeSourceSurveillance onfutureorderswithEATON.RG&Ewillperformreceipttestingofrelayspurchased fromEATON.ANYADVICERELATEDTOTHE'DEFECT ORFAILURETQCOMPLYABOUTTHEFACILITY,
| | RG&E has changed their vendor requirements to include Source Surveillance on future orders with EATON. RG&E will perform receipt testing of relays purchased from EATON. |
| : ACTIVITY, ORBASXCCOMPONENT THATHASBEEN,ISBEING,ORWILLBEGIVENTOPURCHASERS QRLICENSEES'G&E's advicewouldbetoperformreceiptinspection testingofrelaysorperformasourcesurveillance.
| | ANY ADVICE RELATED TO THE'DEFECT OR FAILURE TQ COMPLY ABOUT THE FACILITY, ACTIVITY, OR BASXC COMPONENT THAT HAS BEEN, IS BEING, OR WILL BE GIVEN TO PURCHASERS QR LICENSEES'G&E's advice would be to perform receipt inspection testing of relays or perform a source surveillance. of the vendor's testing practices. |
| ofthevendor'stestingpractices.
| | TOTRL P.84}} |
| TOTRLP.84}}
| |
Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested| ML17265A659 |
| Person / Time |
|---|
| Site: |
Ginna  |
|---|
| Issue date: |
05/17/1999 |
|---|
| From: |
Widay J
ROCHESTER GAS & ELECTRIC CORP. |
|---|
| To: |
NRC |
|---|
| References |
|---|
| REF-PT21-99 NUDOCS 9905280047 |
| Download: ML17265A659 (16) |
|
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|---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML17265A7601999-10-0505 October 1999
Part 21 Rept Re W2 Switch Supplied by W Drawn from Stock, Did Not Operate Properly After Being Installed on 990409. Switch Returned to W on 990514 for Evaluation & Root Cause Analysis
ML17265A7531999-09-23023 September 1999
Part 21 Rept Re Corrective Action & Closeout of 10CFR21 Rept of Noncompliance Re Unacceptable Part for 30-4 Connector. Unacceptable Parts Removed from Stock & Scrapped
ML17265A7291999-07-29029 July 1999
Interim Part 21 Rept Re safety-related DB-25 Breaker Mechanism Procured from W Did Not Pas Degradatin Checks When Drawn from Stock to Be Installed Into BUS15/03A.Holes Did Not line-up & Tripper Pan Bent
ML17265A6761999-06-16016 June 1999
Part 21 Rept Re Defects & noncompliances,10CFR21(d)(3)(ii), Which Requires Written Notification to NRC on Identification of Defect or Failure to Comply. Relays Were Returned to Eaton for Evaluation & Root Cause Analysis
ML17265A6651999-05-27027 May 1999
Interim Rept Re W2 Control Switch,Procured from W,Did Not Operate Satisfactorily When Drawn from Stock to Be Installed in Main Control Board for 1C2 Safety Injection Pump. Estimated That Evaluation Will Be Completed by 991001
ML17265A6591999-05-17017 May 1999
Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested
ML17265A6381999-05-0707 May 1999
Part 21 Rept Re Replacement Turbocharger Exhaust Turbine Side Drain Port Not Functioning as Design Intended.Caused by Manufacturing Deficiency.Turbocharger Was Reaasembled & Reinstalled on B EDG
ML17265A6361999-04-23023 April 1999
Part 21 Rept Re Power Supply That Did Not Work Properly When Drawn from Stock & Installed in -25 Vdc Slot.Power Supply Will Be Sent to Vendor to Perform Failure Mode Assessment.Evaluation Will Be Completed by 991001
ML17265A6551999-04-0909 April 1999
Initial Part 21 Rept Re Mfg Deficiency in Replacement Turbocharger for B EDG Supplied by Coltec Industries. Deficiency Consisted of Missing Drain Port in Intermediate Casing.Required Oil Drain Port Machined Open
ML17265A4151998-09-10010 September 1998
Part 21 Rept Re 980325 Discovery of Missing Tripper Bar Tabs During Troubleshooting of DB-75 Breaker Failure.Caused by Failure to Notify Technician of Revised Procedure to Reinstall Tabs.Inspected All DB-75 Breakers
ML17265A4031998-08-12012 August 1998
Part 21 Rept Re W DB-75 Circuit Breakers W/Missing Tripper Bar Tabs.Caused by Intermittent Failure to Close in DB-75 B EDG Supply Circuit Breaker to Bus #16.Licensee Nuclear Engineering Personnel Are Performing Vendor Document Review
ML20236J1051998-06-29029 June 1998
Part 21 30 Day Written Rept Re Refurbished DB-25 Circuit Breaker Returned W/Missing Pin in Operating Mechanism.Spare DB-25 Circuit Breaker Was Inspected,Tested & Installed to Restore B Service Water Pump to Service
ML17265A3181998-06-0808 June 1998
Part 21 Rept Re Receipt of Refurbished DB-25 Circuit Breaker W/Missing Part from W Replacement Components Svcs on 980608. Spare DB-25 Circuit Breaker Was Inspected,Tested & Installed to Restore B Swp to Svc
ML20248F3531998-05-21021 May 1998
Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted
ML17309A6241998-01-15015 January 1998
Deficiency Rept Re Failure of Shunt Trip Coil Plunger to Return to Deenergized Position Resulting in Breaker Tripper Bar Being Maintained in Trip Free Position,Preventing DB-75 Air Circuit Breaker from Closing.Failed Assembly Replaced
ML17264B1401997-12-22022 December 1997
Part 21 Rept Re Binding Plunger of Assembly Shunt Trip Coil on 971114.Failed Shunt Trip Coil Was Replaced W/Spare from Stock
ML17309A6211997-09-29029 September 1997
Part 21 Rept Re Final Disposition of Masterflow 713 & Embeco 636 Grout Nonconformance Reported by Master Builders,Inc. Licensee Continuing to Monitor shelf-life of Masterflow 713 & Embeco 636 Grouts Produced at Rancho Cucamonga
ML17264A9381997-07-10010 July 1997
Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process
ML20133E8001997-01-0808 January 1997
Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause
ML17264A7301996-11-0606 November 1996
Part 21 Rept Re Defective 350 HP,1800 RPM,460 VAC,3 Phase, 5006P Frame,1.15 Sf,Vertical Hollow Shaft Motor Used as Service Water Pump motor.Safety-Relayed Cgiee Revised to Enhance Steps for Exam of Windings & Workmanship
ML17264A7331996-10-10010 October 1996
Part 21 Rept Re Defect in 350 HP,1800 RPM,460 VAC,3 Phase, 500GP frame,1.15 Sf Vertical Hollow Shaft Motor for Use as Svc Water Pump Motor.Motor Removed,Disassembled,Inspected, Refurbished,Reinstalled & Satisfactorily Tested
ML20115J3981996-07-22022 July 1996
Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl
ML20115F2471996-07-0303 July 1996
Part 21 Rept Re Piping (Small Portion of Unmelted Matl Drawn Lengthwise Into Bar During Drawing Process) Defect That Existed in Bar as Received from Mill.Addl Insp Procedure for Raw Matl Instituted
ML17264A1701995-09-28028 September 1995
Part 21 Rept Re Fuel Oil Booster Pump post-maint Testing Revealed Fuel Oil Sys Pressure Readings of 32 PSIG in Required Action Low Range.Plant Personnel Installed Rebuilt Fuel Oil Booster Pump on B EDG
ML20095K0361995-08-28028 August 1995
Part 21 Rept Re Failure of Diesel Min Operating Fuel Oil Pressure Pump Mfg by Tuthill Corp.Safety Hazard May Be Created If Emergency DG B Not Able to Maintain Design Load Rating.Pump End Play Clearance Adjusted
ML17264A1091995-07-14014 July 1995
Part 21 Rept Re 14 Inch air-operated Butterfly Valve,Used as SW Outlet Valve AOV-4561 Supplied by Fisher Controls Co.On 950418,found That Valve Actuated Opposite from Required Configuration.Actuator Lever Reinstalled
ML17309A5801995-06-16016 June 1995
Initial Part 21 Rept Re air-operated Butterfly Valve Mfg by Fisher Controls Co.Actuator Lever Altered
ML17263A3311993-07-20020 July 1993
Part 21 Rept Re CCW HXs Mfg by Atlas Industrial Mfg Co.As Result of Eddy Current Exam Performed During 1993 Refueling Outage,Tubes W/Measurable Defects at Tube Plate Locations That Exceeded 70% of Tube Wall Thickness Removed from Svc
ML17263A3231993-06-22022 June 1993
Initial Part 21 Rept Re High Component Cooling Water Flow Results in flow-induced Vibration of HX Tubes Mfg by Atlas Industrial Mfg Co & Subsequent Tube Degradation.Tubes W/ Through Wall Indications Greater than 70% Plugged
ML20126J5961992-12-31031 December 1992
Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl
ML20125C7161992-12-0707 December 1992
Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl
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
ML17262A9821992-08-28028 August 1992
Interim Part 21 Rept Re Weld Overlap Area on body-to-bonnet Weld on 1/2-inch ASME Class II Valve Purchased from Henry Vogt Machine Co.Weld Will Be liquid-penetrant Tested Per ASME Class 2 Requirements.Completion Scheduled by 911215
ML17262A8341992-05-0404 May 1992
Interim Part 21 Rept Re 920313 Discovery of Potential Inaccuracies Associated W/Using Open Calibr Approach to Measure Closing Stem Thrust of Movs.Program for re- Evaluation of Previous Test Results in Progress
ML17262A7811992-03-23023 March 1992
Part 21 Rept Re Victoreen,Inc Failure to Perform Calibr on Field Calibr Source Series 877 Detector Used in Radiation Monitoring Sys.Quality of Receipt Insp Will Be Improved Through Use of Health Physics Representative
ML17262A7751992-03-23023 March 1992
Interim Part 21 Rept Re Deficiencies W/Movs V826B,V738B & V871A & Two Two Inch Velan Manual 1500 ASME Class II Valves. Further Investigation Being Conducted by Noncompliance Repts Processing Group
ML17262A7691992-02-24024 February 1992
Part 21 Re Victoreen Field Calibr Source Being Accepted W/O Meeting Purchase Order Requirements.Initially Reported on 920220.Field Source Will Be Calibr & Returned in Apr 1992
ML17250B2491991-09-0404 September 1991
Forwards 10CFR21 Evaluation & Notification Re Design Defect of Solid State Switch Printed Circuit Cards for 480 Volt Safeguards Undervoltage Monitoring/Protection Sys
ML17262A2621990-11-30030 November 1990
Part 21 Rept Re Chilled Water Sys.Initially Reported on 901030.Evaluation of Perry Plant Will Be Sent by 901230
ML17261B0781990-06-15015 June 1990
Part 21 Rept Re Potential Common Mode Failure of OT-2 Type Reset Switches Supplied by Westinghouse.Plungers for Listed OT-2 Type Reset Switches Verified to Be in Proper Position. Separate Independent Switches for Each Train Will Be Added
ML17250B1831990-05-31031 May 1990
Part 21 Rept Re Potential Matl Defect of SMA Type Torque Switches Supplied by Limitorque During Late 1960s.Loose Torque Switch Mounting Socket Head Bolts &/Or Wire Termination Bolts Found on 19 of 26 Valve Actuators
ML17251A4981989-05-12012 May 1989
Part 21 Rept Re Degradation to Pumping Ring from RHR Pumps Supplied by Pacific Pump,Inc & Mechanical Seal Supplied by Crane Packing Co.Conditon Technically Not 10CFR21 Reportable Due to 1978 Date of Occurrence
ML20246K7401989-04-26026 April 1989
Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves
ML17261A8711989-02-28028 February 1989
Part 21 Rept Re Crimping Indentor Component Not Machined to Proper Dimensions Causing Tool to Be Out of Calibr Specs. Qualified Tool Furnished by Vendor as Replacement for Defective Item.Crimping Tools Satisfactorily Tested
ML17261A5301987-06-18018 June 1987
Part 21 Rept Re Potential Util Failure to Comply W/Component Containment Isolation Licensing Commitment If Proposed Mods to Component Cooling Water Sys Instituted.Utils Advised to Evaluate Containment Isolation Sys
ML20134Q1741985-08-29029 August 1985
Part 21 Rept Re Potential Maint Issues Associated w/Anker-Holth Snubbers.Owners of Anker-Holth Snubbers Will Be Informed of Problems & Sent Revs to Technical Instruction Manuals to Include Procedures for Seal & Fluid Maint
ML20134H0091985-08-23023 August 1985
Part 21 Rept Re Micro Instrument Corp Design Error When Upgrading Auxiliary Bldg Main Hoist Backup Hydraulic Brake Sys.Design Mod Incorporated Hydraulic Valve Which Prevented Hydraulic Pressure Release & Backup Brake Engagement
ML20106C2681984-12-0303 December 1984
Part 21 Rept Re Design Error When Upgrading Catalytic,Inc post-accident Filter Duct Butterfly Valve Solenoids.Design Spec Called for Wrong Failure Position for Solenoids. Solenoids Replaced
ML20010C6881981-08-0606 August 1981
Interim Deficiency Rept Re Potentially Reportable Diesel Generator Starting Air Sys Design,Initially Reported 810803. Generator Supplier Will Be Contacted to Determine Whether Deficiency Exists.Problem Suspected to Be Generic in Nature
1999-09-23
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17265A7601999-10-0505 October 1999
Part 21 Rept Re W2 Switch Supplied by W Drawn from Stock, Did Not Operate Properly After Being Installed on 990409. Switch Returned to W on 990514 for Evaluation & Root Cause Analysis
ML17265A7621999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Re Ginna Npp.With 991008 Ltr
ML17265A7531999-09-23023 September 1999
Part 21 Rept Re Corrective Action & Closeout of 10CFR21 Rept of Noncompliance Re Unacceptable Part for 30-4 Connector. Unacceptable Parts Removed from Stock & Scrapped
ML17265A7541999-09-22022 September 1999
LER 99-011-00:on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With 990922 Ltr
ML17265A7471999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Re Ginna Npp.With 990909 Ltr
ML17265A7431999-08-24024 August 1999
LER 99-004-01:on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed
ML17265A7341999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Re Ginna Npp.With 990806 Ltr
ML17265A7291999-07-29029 July 1999
Interim Part 21 Rept Re safety-related DB-25 Breaker Mechanism Procured from W Did Not Pas Degradatin Checks When Drawn from Stock to Be Installed Into BUS15/03A.Holes Did Not line-up & Tripper Pan Bent
ML17265A7181999-07-23023 July 1999
LER 99-007-01:on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians
ML17265A7081999-07-22022 July 1999
LER 98-003-02:on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored
ML17265A7131999-07-22022 July 1999
Special Rept:On 990407,radiation Monitor RM-14A Was Declared Inoperable.Caused by Failed Communication Link from TSC to Plant Process Computer Sys.Communication Link Was re-established & RM-14A Was Declaed Operable on 990521
ML17265A7031999-07-19019 July 1999
LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr
ML17265A7211999-07-19019 July 1999
ISI Rept for Third Interval (1990-1999) Third Period, Second Outage (1999) at Re Ginna Npp.
ML17265A7021999-07-15015 July 1999
LER 99-010-00:on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With 990715 Ltr
ML17265A7661999-06-30030 June 1999
1999 Rept of Facility Changes,Tests & Experiments Conducted Without Prior NRC Approval for Jan 1998 Through June 1999, Per 10CFR50.59.With 991020 Ltr
ML17265A7011999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Re Ginna Npp.With 990712 Ltr
ML17265A6851999-06-21021 June 1999
LER 99-001-01:on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With 990621 Ltr
ML17265A6761999-06-16016 June 1999
Part 21 Rept Re Defects & noncompliances,10CFR21(d)(3)(ii), Which Requires Written Notification to NRC on Identification of Defect or Failure to Comply. Relays Were Returned to Eaton for Evaluation & Root Cause Analysis
ML17265A6661999-06-0202 June 1999
LER 99-009-00:on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With 990602 Ltr
ML17265A6681999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Re Ginna Nuclear Power Plant.With 990608 Ltr
ML17265A6651999-05-27027 May 1999
Interim Rept Re W2 Control Switch,Procured from W,Did Not Operate Satisfactorily When Drawn from Stock to Be Installed in Main Control Board for 1C2 Safety Injection Pump. Estimated That Evaluation Will Be Completed by 991001
ML17309A6541999-05-27027 May 1999
LER 99-008-00:on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With 990527 Ltr
ML17265A6631999-05-24024 May 1999
LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved
ML17265A6601999-05-21021 May 1999
LER 99-006-00:on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With 990521 Ltr
ML17265A6591999-05-17017 May 1999
Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested
ML17265A6441999-05-13013 May 1999
LER 99-005-00:on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With 990513 Ltr
ML17265A6431999-05-12012 May 1999
LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed
ML17265A6381999-05-0707 May 1999
Part 21 Rept Re Replacement Turbocharger Exhaust Turbine Side Drain Port Not Functioning as Design Intended.Caused by Manufacturing Deficiency.Turbocharger Was Reaasembled & Reinstalled on B EDG
ML17265A6391999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Re Ginna Nuclear Power Plant.With 990510 Ltr
ML17265A6361999-04-23023 April 1999
Part 21 Rept Re Power Supply That Did Not Work Properly When Drawn from Stock & Installed in -25 Vdc Slot.Power Supply Will Be Sent to Vendor to Perform Failure Mode Assessment.Evaluation Will Be Completed by 991001
ML17265A6301999-04-18018 April 1999
Rev 1 to Cycle 28 COLR for Re Ginna Npp.
ML17265A6251999-04-15015 April 1999
Special Rept:On 990309,halon Systems Were Removed from Svc & Fire Door F502 Was Blocked Open.Caused by Mods Being Made to CR Emergency Air Treatment Sys.Continuous Fire Watch Was Established with Backup Fire Suppression Equipment
ML17265A6551999-04-0909 April 1999
Initial Part 21 Rept Re Mfg Deficiency in Replacement Turbocharger for B EDG Supplied by Coltec Industries. Deficiency Consisted of Missing Drain Port in Intermediate Casing.Required Oil Drain Port Machined Open
ML17265A6291999-03-31031 March 1999
Rev 0 to Cycle 28 COLR for Re Ginna Npp.
ML17265A6241999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Ginna Station.With 990409 Ltr
ML17265A6141999-03-31031 March 1999
LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr
ML17265A6131999-03-29029 March 1999
LER 99-002-00:on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With 990329 Ltr
ML17265A6061999-03-24024 March 1999
LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp
ML17265A5661999-03-0101 March 1999
Rev 26 to QA Program for Station Operation.
ML17265A5961999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Ginna Nuclear Power Plant.With 990310 Ltr
ML17265A5371999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Re Ginna Nuclear Power Plant.With 990205 Ltr
ML17265A5951998-12-31031 December 1998
Rg&E 1998 Annual Rept.
ML17265A5001998-12-21021 December 1998
Rev 26 to QA Program for Station Operation.
ML17265A4951998-12-21021 December 1998
LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr
ML17265A4931998-12-17017 December 1998
LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery
ML17265A4761998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Re Ginna Nuclear Power Plant.With 981210 Ltr
ML17265A4691998-11-25025 November 1998
LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR
ML17265A4531998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Re Ginna Nuclear Power Plant.With 981110 Ltr
ML17265A4271998-10-0505 October 1998
LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr
ML17265A4291998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Re Ginna Nuclear Power Plant.With 981009 Ltr
1999-09-30
[Table view] |
Text
CATEGORY REGULATORY INFORMATION DZSTRXBUTZON SYSTEM (RXDS)
ACCESSION NBR: 9905280047 DOC. DATE: 99/05/17 NOTARIZED: NO DOCKET FACZL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION WZDAY,J.A. Rochester Gas &. Electric Corp.
RECXP.NAME RECIPIENT AFFILIATION NRC - No Detailed Affiliation Given lq
SUBJECT:
Part 21 rept re relay deficiency dtected during pre-installation testing. Caused by'incorrectly wired relay coil. Relays were returned to Eaton Corp for investigation.
Relays were repaired & retested.
DISTRIBUTION CODE: IE28T COPIES RECEIVED:LTR ENCL SIZE: T TITLE: Licensee Event Report (LER) 6 Part 21 Rept Combination (50 Dkt)
E NOTES:License Exp date in accordance with 10CFR2,2 .109(9/19/72) . 05000244 G
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL XD CODE/NAME LTTR ENCL LPD1-1 LA 1 1 LPD1-1 PD 1 1 VZSSING,G. 1 1 INTERNAL: ACNW 1 AEOD SPD/RRAB 1 1 DEDRO 1 =FXL'E CENTERS 1 1 NRR/DE/EEIB 1 NRR/DE/EMCB 1 1 NRR/DE/EMEB 1 NRR/DXPM/ZOLB 1 1 NRR/DIPM/XQMB 1 NRR/DLPM 1 1 NRR/DRIP/REXB 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SPSB 1 RES/DET/EZB 1 1 RGN 1 1 RGN 2 1 1 RGN 3 1 RGN 4 1 1 RGN1 FXLE 01 1 EXTERNAL: INPO RECORD CTR 1 1 L ST LOBBY WARD 1 1 LXTCO STUART, VA 1 1 NOAC MAYS,G 1 1 U NOAC QUEENER, D 1 1 . NRC PDR 1 1 NUDOCS FULL TXT 1 1 M NOTE TO ALL "RIDS" RECZPZENTS:
PLEASE HELP US TO REDUCE HASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, DISTRIBUTION LISTS CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 FULL TEXT CONVERSXON REQUIRED TOTAL NUMBER OF COPXES REQUIRED: LTTR 29 ENCL 29
ROCHESTERGASANDEIECTRICCORPORATION.S9EASTAVEiYIJE, ROCHESTER, III Y f46494001 AREA CODE 716.%6.2700 May 17, 1999 U.S. Nuclear Regulatory Commission Operations Center Facsimile Number 301-816-5151 Telephone Number 301-816-5100
Subject:
Initial Notification of 10 CFR Part 21 Defect R.E. Ginna Nuclear Power Plant Docket No. 50-244 The enclosed initial notification is provided in accordance with 10 CFR Part 21, Reporting of Defects and Noncompliance, Section 21 (d) (3) {i), which requires "Initial notification by facsimile". written notification, in accordance with 10 CFR Part 21, Section 21 {d) (3) (ii), will be provided by June 16, 1999.
Very truly yours, Q.d s h A. Wida
.Enclosures 9905280047 990517 PDR ADOCK 05000244 8
10CFR21 INITIALFACSIMILE NOTIFICATION
'NAME AND ADDRESS OF THE INDIVIDUAL INFORMING THE COMMISSZO¹ NAME: Joseph A. Widay Plant Manager ADDRESS: Rochester Gas & Electric Corporation 89 East Avenue Rochester, New-York 14649 IDENTIFICATI9N OF THE FACILITY'HE ACTIVITY'R THE BASIC COMPONENT SUPPLIED FOR SUCH FACILITY WHICH FAILS TO COMPLY OR CONTAINS A DEFECT:
The basic component is the NBPD65NR Control Relay, supplied by EATON Corporation, Inc. This component was Purchased Safety Related for use in various locations at Ginna Station.
IDENTIFICATION OF THE FIRM CONSTRUCTING THE FACILITY OR SUPPLYING THE BASIC COMPONENT WHICH FAILS TO COMPLY OR CONTAINS A DEFECTs The Relays were supplied to RG&E by EATON Corporation EATON Corporatiod. Inc.
21 South St Danbury, Ct 06810 NATURE OF THE DEFECT OR FAILURE TO COMPLY AND THE SAFETY RLSARD WHICH XS CREATED OR COULD BE CREATED BY SUCH DEFECT OR FAILURE TO COMPLYhe nature of the defect consisted of a manufacturing deficiency. Upon investigation, by EATON, determined that the relay coil had been incorrectly it was wired such that the internal relay design, which includes a pick up and a hold coil, would oppose each other at lower voltages and prohibit holding coil actuation which resulted in excessive relay chatter.
The incorrect wiring was attributed to insufficient training and subsequent poor workmanship of a new employee. The factory testing did not detect the chattering relays.
The deficiency was detected by RG&E during pre-installation testing prior to installation into reactor trip logic. No actual safety hazard existed.
THE DATE ON ERICH THE ZNFORMJiTZON OF SUCH DEFECT OR FAILURE TO COMPLY WAS OBTAXNIlD~
The 'infoxmation was obtained on April 2, 1999, during the pre-installation testing of the relays.
IN THE CASE OF A BASIC COMPONENT WHICH CONTAINS A DEFECT OR FAXLS TO COMPLYI THE NUMBER AND LOCATION OF ALL SUCH COMPONENTS IN USE AT, SUPPLXED FORp OR BEING SUPPLXED FOR GXNNA STATIONS There are numerous NBFD65NR relays, permanently installed at Ginna Station. None of the deficient relays were installed.
THE CORRECTXVE ACTXON 7%1CH HAS PEEN'S BEINQs OR RILL BE TAKEN; THE NAMg OF THE XNDIVZDUAL OR ORGANISATION RESPONSXBLE FOR THE ACTIONS AND THE LENGTH OF TIME THAT HAS BEEN OR NXLL BE TAKEN TO COMPLETE THE ACTIONS After the deficiency was discovered by RG&E, the relays were returned to EATON for evaluation and root cause analysis. An RG&E QA Engineer was present during 'the root cause investigation. At EATON's factory, it was discovered that one of the two relay coils was wired up backwards on all the relays in question. The relays were tested by EATON and passed their bench test, but the factory noise masked the sound of the relays chattering.
The relays were repaired and retested using enhanced test procedures which included checking for relay chatter.
RG&E has changed their vendor requirements to include Source Surveillance on future orders with EATON. RG&E will perform receipt testing of'elays purchased from EATON.
ANY ADVICE RELATED TO THE DEFECT OR FAILURE TO COMPLY ABOUT THE FACZLXTY, ACTIVITY, OR BASIC COMPONENT THAT HAS BEEN, IS BEING, OR WILL BE GIVEN TO PURCHASERS OR LICENSEES<
RG&E's advice would be to perform receipt inspection testing of relays or perform a source surveillance of the vendor's testing practices.
TOTRL P.84
ROCHFSTER GA8 AND ELECTRIC CORPORA 7ION R.E. GINNh NUCLEAR POKER PIANOS Gieut Wfnfstrnlipn 1503 Dtkc R08 Onbvfo, HY 10519 Contact Name:
Company Name:
Telecopy Number:
Sender:
Description:
Number of pages, includlrfg cover sheet:
0 .S.:
lf you have not received all pages, or if you have any questions or problems with receiving, contact:
Sharon Sortino or Wendy Merkel Verification Number: 716-771-3548 or 716-771-3102 Telecopy Number: 716-771-3943
ROCHESTER GA8 AND EI.ECTRIC CORPORA T/ON R.E. GINNh NUCLEAR POKER PEDANT Gieut ~Mtratisn 1503 En& W8 06trf0, NY 1%519 Contact Name:
Company Name:
Telecopy Number:
Sender:
==
Description:==
Number of pages, including cover skeet:
Date Sent:
If you have not received all pages, or if you have any questions or problems with receiving, contact:
Sharon Sortino or Wendy Merkel Verification Number: 716-771-3548 or 716-771-3102 Telecopy Number: 716-771-3943
0$flh'1999 U.S. Nuclear Regulatory Cotnntlsslon Operations Center Event Report ~Pa el Power Reactor Event 0 35731 Site: GINNA Notification Date / Time: 05/18/1999 12:47 (EDT)
Unit: 1 Region'. 1 State: NY Event Date /Time: 05/18/1999 (EDT)
Reactor Type: (1) W-2-LP Last Modification: 05/18/1999 Containment Type: DRY AMB NRC Notifiedby: JOSEPH A. WIDAY(VIAF Notifications: PETER ESELGROTH R1 HQ Ops Officer. STEVE SANDIN VERN HODGE NRR Emergency Class: NON EMERGENCY 10 CFR Section:
21.21 UNSPECIFIED PARAGRAPH Unit Scram Code RX Crit Init Power Initial RX Mode Curr Power Current RX Mode Yes 98 Power Operation 98 Power Operation DEFICIENT CONTROL RELAYS IDENTIFIED DURING PRE-INSTALLATIONTESTING.
ON 4/2/99, THE LICENSEE IDENTIFIEDTHAT CONTROL RELAYS (NBF065NR) MANUFACTURED BY EATON CORPORATION CONTAINED A MANUFACTURINGDEFICIENCY, I.E., "THE RELAY COIL HAD BEEN INCORRECTLY WIRED SUCH THAT THE INTERNAL RELAY DESIGN, WHICH INCLUDES A P(CK UP AND A HOLD COlL, WOULD OPPOSE EACH OTHER AT LOWER VOLTAGES AND PROHIBIT HOLDING COIL ACTUATIONWHICH RESULTED IN EXCESSIVE RELAY CHATTER." THIS DEFECT WAS IDENTIFIED DURING PRE-INSTAI LATION TESTING PRIOR TO USE IN THE REACTOR TRIP LOGIC. NO DEFICIENT RELAYS ARE INSTALLED.
ROCHESTER GAS ANOEI ECTRIC CORPORATIOI 89EASTAVEIIIUE, ROCHESTER, NV <4&94OO~
hREA COOE 716.54S.2700 May 17, 1999 U.S. Nuclear Regulatory Commission Operations Center Facsimile Number 301-816-5151 Telephone Number 301-816-5100
Subject:
Initial Notification of 10 CPR Part 21 Defect R.E. Ginna Nuclear Power Plant Docket No. 50-244 The enclosed initial notification is provided in accordance with 10 CFR Part 21, Reporting of Defects and Noncompliance, Section 21 (d) (3) (i), which requires "Initial notification by facsimile". Written notification, in accordance with 10 CFR Part 21, Section 21 (d) (3) (ii), will be provided by June 16, 1999.
Very truly yours, a.d s h A. Wida Enclosures
10CFR21 INITI.'0 FACSIMILE NOTIFICATION, NAME AND ADDRESS OF THE XNDXUIDUAL XNFORMING THE COMMISSXONs NAME: Joseph A. Niday Plant Manager ADDRESS: Rochester Gas & Electric Corporation 89 East Avenue Rochester, New York 14649 ZZ. IDENTIFXCATION OF THE FACILITY, THE ACTIVZTY, OR THE BASIC COMPONENT SUPPLZED FOR SUCH FACILITY WHICH FAILS TO COMPLY OR CONTAINS A DEFECT:
The basic component is the NBFD6SNR Control Relay, supplied by EATON Corporation, Inc. This component was Purchased Safety Related for use in various locations at Ginna Station.
III. IDENTIFICATXON OF THE FXRM CONSTRUCTZNQ THE FACILITY OR SUPPLYING THE BASIC COMPONENT WHICH FAILS TO COMPLY OR CONTAINS A DEFECTs The Relays were supplied to RG&E by EATON Corporation EATON Corporation Inc.
21 South St Danbury, Ct 06810, IV- NATURE OF THE DEFECT OR FAILURE TO COMPLY AND THE SAFETY HAZARD NBXCH XS CREATED OR COULD BE CREATED BY SUCH DEFECT OR FAILURE TO COMPLYt The nature of the defect consisted of a manufacturing deficiency. Upon investigation, by EATON, it was determined that the relay coil had been incorrectly wired such that the internal relay design, which includes a pick up and a hold coil, would oppose each other at lower voltages and prohibit holding coil actuation which resulted in excessive relay chatter.
The incorrect wiring was attributed to insufficient training and subsequent poor workmanship of a new employee. The factory testing did not detect the chattering relays.
The deficiency was detected by RG&E during pre-installation testing prior to installation into reactor trip logic. No actual safety hazard existed.
THE DATE ON WHICH THE INFORMATION OF SUCH DEFECT OR FAILURE TQ COMPLY WAS OBTAXNRDa The'nformation was obtained on April 2, 1999, during the pre-installation testing of the relays.
IN THE CASE OF A BASIC COMPONENT WHXCH CONTAINS A DEFECT OR FAXLS TQ COMPLYI THE NUMBER AND LOCATION OF ALL SUCH COMPONENTS IN USE AT, SUPPLXED FOR OR BEXNG SUPPLIED FQR GZNNA STATIONS There are numerous NBPD65NR relays, permanently installed at Ginna Station. None of the deficient relays were installed.
THE CORRECTIVE ACTXON WHICH HAS BEEN, IS BEING, OR 'WILL BE TARENg THE NAKE OlP THE XNDXUXDUAL OR QRGANXEATXON RESPQNSXBLE FOR THE ACTIONS AND THE LENGTH OP TIME THAT HAS BEEN OR WXLL BE TAKEN TO COMPLETE THE ACTION!
After the deficiency was discover'ed by RG&E, the relays were returned, to EATON for evaluation and root cause analysis. An RG&E QA Engineer was present during the root cause investigation. At EATON's factory, discovered that one of the two relay coils was wired up it was backwards on all the relays in question. The relays were tested by EATON and passed their bench test, but the factory noise masked the sound of the relays chattering.
The relays were repaired and retested using enhanced test procedures which included checking for relay chatter.
RG&E has changed their vendor requirements to include Source Surveillance on future orders with EATON. RG&E will perform receipt testing of relays purchased from EATON.
ANY ADVICE RELATED TO THE'DEFECT OR FAILURE TQ COMPLY ABOUT THE FACILITY, ACTIVITY, OR BASXC COMPONENT THAT HAS BEEN, IS BEING, OR WILL BE GIVEN TO PURCHASERS QR LICENSEES'G&E's advice would be to perform receipt inspection testing of relays or perform a source surveillance. of the vendor's testing practices.
TOTRL P.84