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| {{#Wiki_filter:~CATEGORY1~~REGULATORY INFORMATION DISTRIBUTIQNWYSTEM (RIDS)ACCESSION NBR:9707300094 | | {{#Wiki_filter:~CATEGORY 1~~REGULATORY INFORMATION DISTR IBUTIQNWYSTEM (R IDS)ACCESSION NBR: 9707300094 |
| 'DOC.DATE:97/07/23NOTARIZED: | | 'DOC.DATE: 97/07/23 NOTARIZED: |
| NOFACIL:50-3>>7WPPSSNuclearProJect.Unit2>Washington PublicPoreAUTH.NAMEAUTHORAFFILIATION PFITZEP>B.'ashington PublicPoeerSupp1!JS!JstemBEMIS>P.R.Washington P0bliePoeerSupp1!JS!JstemRECIP.NAMERECIPIENT AFFILIATION DOCKET005000397
| | NO FACIL: 50-3>>7 WPPSS Nuclear Pro Ject.Unit 2>Washington Public Pore AUTH.NAME AUTHOR AFFILIATION PFITZEP>B.'ashington Public Poeer Supp 1!J S!Jstem BEMIS>P.R.Washington P0b lie Poeer Supp 1!J S!Jstem RECIP.NAME RECIPIENT AFFILIATION DOCKET 0 05000397 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER97-007-00:
| | LER 97-007-00: |
| on'>>70611> | | on'>>70611>voluntar!J rept oF automatic start oP DG-1 5 DG-2 was experienced. |
| voluntar!J reptoFautomatic startoPDG-15DG-2wasexperienced. | | Caused b!J undervoltage condition on electrical busses SM-7 b SM-8.Circulating eater pump CW-P-1C control switch eas placed in pull-to-lock. |
| Causedb!Jundervoltage condition onelectrical bussesSM-7bSM-8.Circulating eaterpumpCW-P-1Ccontrolswitcheasplacedinpull-to-lock.
| | DISTRIBUTION CODE: IE22T COPIES RECEIVED: LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER)>Incident Rpt>etc.NOTES: RECIPIENT ID CODE/NAME PD4-2 PD CQP IES LTTR ENCL 1 1 REC IP IENT ID CODE/NAME CQLBURN>T CQP IES LTTR ENCL 1 1 INTERNAL: ACRS AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HGMB NRR/DSSA/SPLR RES/DET/EIB AE J FILE CE ER L NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN4 FILE 01 1 1 1 1 1 1, 1 2 1 1 1 1 1 1 1 EXTERNAL: L ST LOBBY WARD 1 1 NOAC POORE>W.1 1 NRC PDR 1 1 LITCO BRYCE>J H NOAC GUEENER>DS NUDOCS FULL TXT NOTE TO ALL"RIDS" RECIPIENTS: |
| DISTRIBUTION CODE:IE22TCOPIESRECEIVED: | | PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FUL'EXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 25 WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~Richlanrl, 1Virshi>i@tow 99352-0968 July 23, 1997 G02-97-147 Docket No.50-397 Document Control Desk U.S.Nuclear Regulatory Commission Washington, D.C.20555 Gentlemen: |
| LTRENCLSIZE:TITLE:50.73/50.9LicenseeEventReport(LER)>IncidentRpt>etc.NOTES:RECIPIENT IDCODE/NAME PD4-2PDCQPIESLTTRENCL11RECIPIENTIDCODE/NAME CQLBURN>TCQPIESLTTRENCL11INTERNAL:
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| ACRSAEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HGMB NRR/DSSA/SPLR RES/DET/EIB AEJFILECEERLNRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN4FILE01111111,121111111EXTERNAL:
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| LSTLOBBYWARD11NOACPOORE>W.11NRCPDR11LITCOBRYCE>JHNOACGUEENER>DSNUDOCSFULLTXTNOTETOALL"RIDS"RECIPIENTS:
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| PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D-5(EXT.
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| 415-2083) | |
| TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!FUL'EXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
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| LTTR25ENCL25 WASHINGTON PUBLICPOWERSUPPLYSYSTEMP.O.Box968~Richlanrl, 1Virshi>i@tow 99352-0968 July23,1997G02-97-147 DocketNo.50-397DocumentControlDeskU.S.NuclearRegulatory Commission Washington, D.C.20555Gentlemen:
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| ==Subject:== | | ==Subject:== |
| NUCLEARPLANTWNP-2,OPERATING LICENSENPF-21,LICENSEKEVIPWREPORTNO.97-007-00 Transmitted herewithisvoluntary LicenseeEventReportNo.97-007-00 forWNP-2.Thisreportissubmitted inresponsetotherecommendations contained inNUREG-1022.
| | NUCLEAR PLANT WNP-2, OPERATING LICENSE NPF-21, LICENSEK EVIPW REPORT NO.97-007-00 Transmitted herewith is voluntary Licensee Event Report No.97-007-00 for WNP-2.This report is submitted in response to the recommendations contained in NUREG-1022. |
| Shouldyouhaveanyquestions ordesireadditional information regarding thismatter,pleasecallmeorMr.PaulInserraat(509)377-4147.
| | Should you have any questions or desire additional information regarding this matter, please call me or Mr.Paul Inserra at (509)377-4147.Respectfully, mls Vi President, Nuclear Operations Mail Drop PE23 Enclosure cc: EW Merschoff, NRC RIV KE Perkins, Jr., NRC RIV, WCFO TG Colburn, NRR PD Robinson, Winston&Strawn NRC Sr.Resident Inspector, MD927N (2)INPO Records Center-Atlanta, GA DL Williams, BPA, MD399 9707300094 970723 PDR ADQCK 05000397 S PDR llllllllllllllllllllllllllllllllllllllll LICENSEE EVENT REPORT (LER)FACILITY NAME (1)Washin ton Nuclear Plant-Unit 2 DOCKET NUMBER (2)50-397 PAGE (3)1 OF 3 TITLE (4)VOLUNTARY REPORT OF AUTOMATIC START OF DG-1 AND DG-2 DUE TO SM-7 AND SM-8 UNDERVOLTAGE EVENT DATE (5)LER NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (Bl DAY SEOUENIIAL NUMBER REV.NUMBER DAY YEAR FACILHY NAME 06 11 97 97 00 07 23 97 FACILHY NAME N/A DOCKET NUMBER 05000 OPERATING MODE THIs REpoRT Is sUBMITTED pURsUANT To THE REQUIRENENTs op 10 cpR 5I (check one or more)(11)0%20A02(b)20A05(a)(1)(I) 20.405(a)(1)(ii) 20A05(a)(1)(iii)20.405(a)(1)(iv) 20A05(a)(1)(v) 20A05(c)50.36(c)(1) 50.36(c)(2) 50.73(a)(2)0) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(iv)50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(x) |
| Respectfully, mlsViPresident, NuclearOperations MailDropPE23Enclosure cc:EWMerschoff, NRCRIVKEPerkins,Jr.,NRCRIV,WCFOTGColburn,NRRPDRobinson, Winston&StrawnNRCSr.ResidentInspector, MD927N(2)INPORecordsCenter-Atlanta,GADLWilliams, BPA,MD3999707300094 970723PDRADQCK05000397SPDRllllllllllllllllllllllllllllllllllllllll LICENSEEEVENTREPORT(LER)FACILITYNAME(1)WashintonNuclearPlant-Unit2DOCKETNUMBER(2)50-397PAGE(3)1OF3TITLE(4)VOLUNTARY REPORTOFAUTOMATIC STARTOFDG-1ANDDG-2DUETOSM-7ANDSM-8UNDERVOLTAGE EVENTDATE(5)LERNUMBER(6)REPORTDATE(7)OTHERFACILITIES INVOLVED(BlDAYSEOUENIIAL NUMBERREV.NUMBERDAYYEARFACILHYNAME0611979700072397FACILHYNAMEN/ADOCKETNUMBER05000OPERATING MODETHIsREpoRTIssUBMITTED pURsUANTToTHEREQUIRENENTs op10cpR5I(checkoneormore)(11)0%20A02(b)20A05(a)(1)(I) 20.405(a)(1)(ii) 20A05(a)(1) | | X 73.71(b)73.71(c)OTHER Voluntary NAME Bill Pfitzer, Licensing Engineer LICENSEE CONTACT FOR THIS LER (12)TELEPHONE NUMBER ((nclude Area Code)509-377-2419 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE COMPONENT MPIAIFACTURER REPORTABLE TO NPRDS CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14)YES corn le(ed EXPECTED SUBMISSION DATE NO EXPECTED MONTH DAY ABSTRACT On 6/11/97, with the plant in Operating Mode 4, Circulating Water Pump motor CW-M-P/1C experienced internal electrical faulting shortly after pump startup.The pump ran for approximately 15 seconds prior to tripping the CW-M-P/1C feeder breaker.due to phase differential current.The motor fault caused a momentary undervoltage condition on electrical busses SM-7 and SM-8 which initiated an automatic start of emergency diesel generators, EDG-1 and EDG-2.The diesel generators started and ran unloaded, as designed, until manually shutdown by operating personnel. |
| (iii)20.405(a)(1)(iv) 20A05(a)(1)(v) 20A05(c)50.36(c)(1) 50.36(c)(2) 50.73(a)(2)0) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2) | | The output breakers for EDG-1 and EDG-2 did not close and load the EDGs because the undervoltage condition was only momentary, and plant busses continued to be fed from the startup transformer, TR-S.Immediate corrective actions were to return EDG-1 and EDG-2 to standby readiness and initiate an investigation into the cause of CW-M-P/1C trip.The root cause of EDG-1 and EDG-2 auto start was an undervoltage condition on electrical busses SM-7 and SM-8 This event is voluntarily reported, The safety significance of this event is considered minimal. |
| (iv)50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(x) | | FACILITY NAME (I)LICENSEE EVENT REPORT (LER)TEXT CONT(NUATION DOCKET NUMBER (2)YEAR LER NUMBER (6)SEQUENT iAL NUMBER RCVI6 1 ON NJNB6R PAGE (3)Washington Nuclear Plant-Unit 2 50-397 97 007 00 2 OF 3 TEXT (If more space Is reqU(red, use additional copies of NRC Form 366A)(17)Even De cri ti n On 6/11/97, with the plant in Operating Mode 4 with electrical distribution being supplied by the startup transformer TR-S[XFMR], Circulating Water Pump motor CW-M-P/1C[KE][P][MO] |
| X73.71(b)73.71(c)OTHERVoluntary NAMEBillPfitzer,Licensing EngineerLICENSEECONTACTFORTHISLER(12)TELEPHONE NUMBER((ncludeAreaCode)509-377-2419 COMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRIBED INTHISREPORT(13)CAUSECOMPONENT MPIAIFACTURER REPORTABLE TONPRDSCAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TONPRDSSUPPLEMENTAL REPORTEXPECTED(14)YEScornle(edEXPECTEDSUBMISSION DATENOEXPECTEDMONTHDAYABSTRACTOn6/11/97,withtheplantinOperating Mode4,Circulating WaterPumpmotorCW-M-P/1C experienced internalelectrical faultingshortlyafterpumpstartup.Thepumpranforapproximately 15secondspriortotrippingtheCW-M-P/1C feederbreaker.due tophasedifferential current.Themotorfaultcausedamomentary undervoltage condition onelectrical bussesSM-7andSM-8whichinitiated anautomatic startofemergency dieselgenerators, EDG-1andEDG-2.Thedieselgenerators startedandranunloaded, asdesigned, untilmanuallyshutdownbyoperating personnel.
| | experienced internal electrical faulting shortly after pump startup.The pump ran for approximately 15 seconds prior to tripping the CW-M-P/1C feeder breaker[BKR]due to phase differential current.The motor fault caused a momentary undervoltage condition on electrical busses SM-7 and SM-8[BU]which initiated an automatic start of emergency diesel generators, EDG-1 and EDG-2[DGJ.The diesel generators started and ran unloaded, as designed, until manually shutdown by operating personnel. |
| TheoutputbreakersforEDG-1andEDG-2didnotcloseandloadtheEDGsbecausetheundervoltage condition wasonlymomentary, andplantbussescontinued tobefedfromthestartuptransformer, TR-S.Immediate corrective actionsweretoreturnEDG-1andEDG-2tostandbyreadiness andinitiateaninvestigation intothecauseofCW-M-P/1C trip.TherootcauseofEDG-1andEDG-2autostartwasanundervoltage condition onelectrical bussesSM-7andSM-8Thiseventisvoluntarily
| | The output breakers for EDG-1 and EDG-2 did not close and load the EDGs because the undervoltage condition was only momentary, and plant buses continued to be fed from the startup transformer, TR-S.This event was voluntarily reported within 4 hours, and this report is being voluntarily submitted since the EDGs are not engineered safety features at WNP-2.Immediate orr ive Acti n Circulating Water pump CW-P-1C control switch was placed in pull-to-lock. |
| : reported, Thesafetysignificance ofthiseventisconsidered minimal.
| | EDG-1 and EDG-2 were returned to standby readiness. |
| FACILITYNAME(I)LICENSEEEVENTREPORT(LER)TEXTCONT(NUATION DOCKETNUMBER(2)YEARLERNUMBER(6)SEQUENTiALNUMBERRCVI61ONNJNB6RPAGE(3)Washington NuclearPlant-Unit250-39797007002OF3TEXT(IfmorespaceIsreqU(red, useadditional copiesofNRCForm366A)(17)EvenDecritinOn6/11/97,withtheplantinOperating Mode4withelectrical distribution beingsuppliedbythestartuptransformer TR-S[XFMR],Circulating WaterPumpmotorCW-M-P/1C
| | Investigation was initiated into the cause of CW-M-P/1C trip.A significant Problem Evaluation Request was initiated to resolve this problem.h Control room personnel reported that CW-M-P/1C started normally with the expected starting current, and operated with a running current of approximately 600 amps for approximately 15 seconds prior to tripping.Following the trip, phase voltages on the bus supplying the motor were observed to be 4250, 4400, and 4300 volts on each of the A, B, and C phases respectively with the 230kV voltage at Ashe substation reported at 242kV.Throughout this event, plant busses continued to be fed from the startup transformer, TR-S.The WNP-2 electrical distribution system relay scheme operated as designed to isolate the fault and terminate the undervoltage condition on the affected busses.Had the undervoltage condition on SM-7 and SM-8 continued for approximately four seconds, the supply breakers from Backup Auxiliary Transformer, TR-B, would have auto closed and SM-7 and SM-8 would have been supplied by TR-B.If the undervoltage condition had continued for approximately 7 seconds the EDG output breakers would have auto closed and SM-7 and SM-8 would have been supplied by the EDGs. |
| [KE][P][MO] | |
| experienced internalelectrical faultingshortlyafterpumpstartup.Thepumpranforapproximately 15secondspriortotrippingtheCW-M-P/1C feederbreaker[BKR]duetophasedifferential current.Themotorfaultcausedamomentary undervoltage condition onelectrical bussesSM-7andSM-8[BU]whichinitiated anautomatic startofemergency dieselgenerators, EDG-1andEDG-2[DGJ.Thedieselgenerators startedandranunloaded, asdesigned, untilmanuallyshutdownbyoperating personnel. | |
| TheoutputbreakersforEDG-1andEDG-2didnotcloseandloadtheEDGsbecausetheundervoltage condition wasonlymomentary, andplantbusescontinued tobefedfromthestartuptransformer, TR-S.Thiseventwasvoluntarily reportedwithin4hours,andthisreportisbeingvoluntarily submitted sincetheEDGsarenotengineered safetyfeaturesatWNP-2.Immediate orriveActinCirculating WaterpumpCW-P-1Ccontrolswitchwasplacedinpull-to-lock.
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| EDG-1andEDG-2werereturnedtostandbyreadiness. | |
| Investigation wasinitiated intothecauseofCW-M-P/1C trip.Asignificant ProblemEvaluation Requestwasinitiated toresolvethisproblem.hControlroompersonnel reportedthatCW-M-P/1C startednormallywiththeexpectedstartingcurrent,andoperatedwitharunningcurrentofapproximately 600ampsforapproximately 15secondspriortotripping. | |
| Following thetrip,phasevoltagesonthebussupplying themotorwereobservedtobe4250,4400,and4300voltsoneachoftheA,B,andCphasesrespectively withthe230kVvoltageatAshesubstation reportedat242kV.Throughout thisevent,plantbussescontinued tobefedfromthestartuptransformer, TR-S.TheWNP-2electrical distribution systemrelayschemeoperatedasdesignedtoisolatethefaultandterminate theundervoltage condition ontheaffectedbusses.Hadtheundervoltage condition onSM-7andSM-8continued forapproximately fourseconds,thesupplybreakersfromBackupAuxiliary Transformer, TR-B,wouldhaveautoclosedandSM-7andSM-8wouldhavebeensuppliedbyTR-B.Iftheundervoltage condition hadcontinued forapproximately 7secondstheEDGoutputbreakerswouldhaveautoclosedandSM-7andSM-8wouldhavebeensuppliedbytheEDGs. | |
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| 0~LICENSEEEVENTREPORT(LER)TEXTCONTINUATION FACILITYNAMEtl)DOCKETNUMBER)2)LERNUMBERI6)SEQUENT)AL NUMBERA6V)ATIONNAQERPAGEI3)Washington NuclearPlant-Unit250-39797007003'F3TEXT(lfmorespaceisrequired, useadditional copiesofNRCForm366A)(17)InthiscasethefeederbreakerforCW-M-P/IC tripped,isolating thefaultimmediately, andthestandbysourcesdesignedtoautomatically supplythesafety-related electrical busseswerenotneeded.mRafXameTheautostartofEDG-1andEDG-2wascausedbyanundervoltage condition onSM-7andSM-8.Theundervoltage condition wascausedbyinternalfaultingofthenon-safety relatedCW-M-P/1C whichdeveloped shortlyafterstartofthemotor.FherorrtiveAcinNonerequired. | | 0~LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACILITY NAME tl)DOCKET NUMBER)2)LER NUMBER I6)SEQUENT)AL NUMBER A6V)ATION NAQER PAGE I 3)Washington Nuclear Plant-Unit 2 50-397 97 007 00 3'F 3 TEXT (lf more space is required, use additional copies of NRC Form 366A)(17)In this case the feeder breaker for CW-M-P/IC tripped, isolating the fault immediately, and the standby sources designed to automatically supply the safety-related electrical busses were not needed.mRafXame The auto start of EDG-1 and EDG-2 was caused by an undervoltage condition on SM-7 and SM-8.The undervoltage condition was caused by internal faulting of the non-safety related CW-M-P/1C which developed shortly after start of the motor.F her orr tive Ac i n None required.EDG response to the undervoltage condition was normal.Appropriate corrective actions associated with CW-P-P/IC have been taken.A e mn f fet n uence WNP-2's electrical distribution system relay scheme operated as designed to isolate the fault without unnecessary challenges to the plant electrical distribution system.In this case the feeder breaker for CW-M-P/IC tripped, isolating the fault immediately. |
| EDGresponsetotheundervoltage condition wasnormal.Appropriate corrective actionsassociated withCW-P-P/IC havebeentaken.AemnffetnuenceWNP-2'selectrical distribution systemrelayschemeoperatedasdesignedtoisolatethefaultwithoutunnecessary challenges totheplantelectrical distribution system.InthiscasethefeederbreakerforCW-M-P/IC tripped,isolating thefaultimmediately.
| | Offsite and onsite sources designed to automatically supply the safety-related electrical busses were available at the time from transformer TR-8 and the EDGs.The safety significance of this event is considered minimal.E There have been no similar previous events of motor faults causing starts of the EDGs.}} |
| Offsiteandonsitesourcesdesignedtoautomatically supplythesafety-related electrical busseswereavailable atthetimefromtransformer TR-8andtheEDGs.Thesafetysignificance ofthiseventisconsidered minimal.ETherehavebeennosimilarpreviouseventsofmotorfaultscausingstartsoftheEDGs.}}
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17292B7421999-07-20020 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
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
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
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
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
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
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
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
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
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
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
ML17292B1111997-11-10010 November 1997
LER 97-011-00:on 971010,HPCS Battery Charger Failed.Caused by Failure of a Phase Firing Control Circuit Board Due to Aging During 7 Yrs of Use.Hpcs Sys Was Immediately Declared inoperable.W/971110 Ltr
ML17292B1151997-11-0707 November 1997
LER 97-010-00:on 970906,discovered That TS SR 3.4.5.1 for Identified Portion of RCS Total Leakage Would Not Be Able to Perform within Time Limits of SR 3.0.2.Caused by Inadequate Methods.Method of Meeting SR 3.4.5.1 Established
ML17292B0641997-09-24024 September 1997
LER 97-004-01:on 970327,plant Operators Manually Scrammed Reactor as Required by TS Due to Indication of Entry Into Region a of power-to-flow Map.Caused by Inadequate Attention to Detail.Established Event Evaluation teams.W/970924 Ltr
ML17292B0241997-08-18018 August 1997
LER 97-009-00:on 970717,discovered Error in Recently Performed Inservice Testing procedure,OSP-TIP/IST-R701. Caused by Procedure Inadequacy.Plant Procedure OSP/TIP/IST-R701 Will Be changed.W/970818 Ltr
ML17292B0291997-08-15015 August 1997
LER 97-008-00:on 970716,wire Seal Used to Lock Containment Instrument Air Pressure Control valve,CIA-PCV-2B,found Not Intact.Cause of Misadjustment of CIA-PCV-2B Unknown.Event Will Be Communicated to Plant employees.W/970815 Ltr
ML17292B0201997-08-15015 August 1997
LER 97-S01-00:on 970718,failure to Take Compensatory Measure for Inoperative Microwave Security Zone Occurred. Caused by Personnel Error.Training Will Be Conducted W/ Appropriate Members of Security force.W/970815 Ltr
ML17292A9481997-07-23023 July 1997
LER 97-007-00:on 970611,voluntary Rept of Automatic Start of DG-1 & DG-2 Was Experienced.Caused by Undervoltage Condition on Electrical Busses SM-7 & SM-8.Circulating Water Pump CW-P-1C Control Switch Placed in pull-to-lock.W/970723 Ltr
ML17292A9201997-06-26026 June 1997
LER 97-006-00:on 970527,non-performance of Surveillance Requirement 3.6.1.3.2 for Blind Fanges,Was Noted.Caused Because Misunderstanding of Intent of Specs.Added Five Structural Assemblies for SP.W/970626 Ltr
ML17292A8331997-04-28028 April 1997
LER 97-004-00:on 970327,plant Operators Manually Scrammed Reactor as Required by TS Due to Entry Into Region a of power-to-flow Map Following Planned Trip of Single Mfp. Event Evaluation teams,established.W/970428 Ltr
ML17292A8311997-04-28028 April 1997
LER 97-005-00:on 970327,valid Reactor Scram Signal Received Due to Low Water Level Condition During Preparations for SRV Testing.Caused by Risks & Consequences of Decisions Not Completely Identified.Restored Water level.W/970428 Ltr
ML17292A8251997-04-21021 April 1997
LER 97-003-00:on 970320,notification of Noncompliance W/Ts as TS SRs for Response Time Testing Were Not Being Met for Specified Instrumentation in Rps,Pcis & Eccs.Requested Enforcement Discretion for One Time exemption.W/970421 Ltr
ML17292A7431997-03-20020 March 1997
LER 97-002-00:on 970218,determined That Rod Block Monitor (RBM) Calibr Values Were Not Set IAW Tech Specs.Caused by Calibr Procedures Inadequacies.Revised & re-performed RBM Channel Calibr procedures.W/970330 Ltr
ML17292A7401997-03-13013 March 1997
LER 97-001-00:on 970211,reactor Water Cleanup Sys Blowdown Flow Isolation Setpoint Was Slightly Above TS Allowable Valve Occurred Due to Calculation Error.Lds Fss LD-FS-15 LD-FS-16 Were Declared inoperable.W/970313 Ltr
ML17292A6641997-01-22022 January 1997
LER 96-009-00:on 961220,miscalculation of Instantaneous Overcurrent Relay Settings Resulted in Inoperability of safety-related Equipment.Caused by Utilization of Inappropriate Design.Testing Was completed.W/970122 Ltr
ML17292A6461997-01-0606 January 1997
LER 96-008-00:on 961205,failure to Comply with TS Action Requirement for Emergency Core Cooling Sys Actuation Instrumentation Occurred Due to Unidentified Inoperability Condition.Pmr initiated.W/970106 Ltr
ML17292A6371996-12-19019 December 1996
LER 96-007-00:on 961122,electrical Breakers Were Not Seismically Qualified in Test/Disconnect Position.Circuit Breaker Mfg Did Not Consider Raced Out Breaker Position During Testing.Relocated Circuit breakers.W/961217 Ltr
ML17292A4121996-08-0808 August 1996
LER 96-006-00:on 960709,average Power Range Monitor Rod Block Downscale Surveillance Not Performed Prior to Entry Into Mode 1.Caused by long-standing Misinterpretation of Requirements of Tss.Procedures revised.W/960808 Ltr
ML17292A3801996-07-24024 July 1996
LER 96-004-00:on 960624,plant Was Manually Scrammed by Control Room Personnel Due to Reactor Water Level Transient Experienced During Testing of Digital Feedwater Sys.Caused by Programming Error.Sys Was corrected.W/960724 Ltr
ML17292A3771996-07-24024 July 1996
LER 96-005-00:on 960624,determined Missed Surveillance Test Re Channel Check of Average Power Range Monitor.Caused by Inadequate Procedures.Revised Surveillance Procedure Re When APRM Checks Must Be performed.W/960724 Ltr
ML17292A3641996-07-12012 July 1996
LER 96-003-00:on 960615,required Surveillance Test Not Performed When Required by TS 3.4.1.3.Caused by Inadequate Procedures.Implementing Surveillance Procedure & Reactor Plant Startup Procedures revised.W/960712 Ltr
ML17292A3361996-06-20020 June 1996
LER 96-002-00:on 960504,critical Bus SM-8 Lost Power When Supply Breaker 3-8 Tripped.Caused by Personnel Error. Operators Counselled & Procedures revised.W/960620 Ltr
ML17292A2861996-05-24024 May 1996
LER 96-001-00:on 960425,inadvertent ESF Actuations Occurred Due to Tripping of Temporary Power Supply to IN-3.Caused by Personnel Error.Operations Restored to IN-3 Loads & Reset ESF actuations.W/960524 Ltr
ML17291B0891995-10-19019 October 1995
LER 95-011-00:on 950919,failed to Comply W/Ts SR for RCIC Sys Due to Analysis Deficiency That Resulted in Inadequate Surveillance Test Procedure.Surveillance Procedure Revised to Correct deficiency.W/951019 Ltr
ML17291A9021995-07-0707 July 1995
LER 95-010-00:on 950609,HPCS DG Declared Inoperable Due to Discovery That TS Test Method Incomplete.Caused by Inadequate Testing Procedure.Test Procedure for HPCS DG Reviewed & Special Test Procedures written.W/950707 Ltr
ML17291A9031995-07-0707 July 1995
LER 95-009-00:on 950607,inadvertent MSIV Closure Occurred During Surveillance Test Due to Poor Communication Between Test Team.Determined That MSIV Closure Not Valid Because Closure Not Triggered by Plant conditions.W/950707 Ltr
ML17291A8501995-06-0808 June 1995
LER 95-006-01:on 950405,reactor Scram Occurred During Surveillance Testing Due to Protective Sys Relay Failure. Replaced Failed Relay Before Plant Startup
ML17291A8101995-05-12012 May 1995
LER 95-008-00:on 940125,TS Wording Lead to Potential TS Violation.Caused by Lack of Clarity in Ts.Submitted Improved TS for Plant to Provide Addl clarity.W/950512 Ltr
ML17291A7841995-05-0505 May 1995
LER 95-007-00:on 950222,emergency Diesel Start Occurred Due to Voltage Transient on BPA Grid.Confirmation Was Received at 17:51 H That Disturbance Had Originated in BPA Grid
ML17291A7801995-05-0404 May 1995
LER 95-006-00:on 950405,main Turbine Trip Occurred During Performance of Surveillance Test Due to Protective Sys Relay Failed.Replaced Failed Relay Before Plant startup.W/950504 Ltr
ML17291A7851995-05-0303 May 1995
LER 95-005-00:on 950222,inoperable IRM Had Been Relied Upon to Meet TS Requirements During Reactor Startup.Caused by Lack of Neutron Source to Test Instrumentation. Sys Knowledge Gained Will Be incorporated.W/950503 Ltr
ML17291A7071995-03-25025 March 1995
LER 95-004-00:on 950226,malfunction in Main Turbine DEH Control Sys Caused All Four High Pressure Turbine Governor Valves to Rapidly Close.Caused by Blown Fuse.Suspected Faulty Circuit Card replaced.W/950325 Ltr
ML17291A7011995-03-20020 March 1995
LER 95-002-00:on 950218,automatic Reactor Scram Occurred. Caused by Erroneous Positioning of Control During Performance of Scheduled Periodic Functional Test.Control repositioned.W/950320 Ltr
1999-07-20
[Table view]
Category:RO)
MONTHYEARML17292B7421999-07-20020 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
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
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
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
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
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
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
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
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
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
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
ML17292B1111997-11-10010 November 1997
LER 97-011-00:on 971010,HPCS Battery Charger Failed.Caused by Failure of a Phase Firing Control Circuit Board Due to Aging During 7 Yrs of Use.Hpcs Sys Was Immediately Declared inoperable.W/971110 Ltr
ML17292B1151997-11-0707 November 1997
LER 97-010-00:on 970906,discovered That TS SR 3.4.5.1 for Identified Portion of RCS Total Leakage Would Not Be Able to Perform within Time Limits of SR 3.0.2.Caused by Inadequate Methods.Method of Meeting SR 3.4.5.1 Established
ML17292B0641997-09-24024 September 1997
LER 97-004-01:on 970327,plant Operators Manually Scrammed Reactor as Required by TS Due to Indication of Entry Into Region a of power-to-flow Map.Caused by Inadequate Attention to Detail.Established Event Evaluation teams.W/970924 Ltr
ML17292B0241997-08-18018 August 1997
LER 97-009-00:on 970717,discovered Error in Recently Performed Inservice Testing procedure,OSP-TIP/IST-R701. Caused by Procedure Inadequacy.Plant Procedure OSP/TIP/IST-R701 Will Be changed.W/970818 Ltr
ML17292B0291997-08-15015 August 1997
LER 97-008-00:on 970716,wire Seal Used to Lock Containment Instrument Air Pressure Control valve,CIA-PCV-2B,found Not Intact.Cause of Misadjustment of CIA-PCV-2B Unknown.Event Will Be Communicated to Plant employees.W/970815 Ltr
ML17292B0201997-08-15015 August 1997
LER 97-S01-00:on 970718,failure to Take Compensatory Measure for Inoperative Microwave Security Zone Occurred. Caused by Personnel Error.Training Will Be Conducted W/ Appropriate Members of Security force.W/970815 Ltr
ML17292A9481997-07-23023 July 1997
LER 97-007-00:on 970611,voluntary Rept of Automatic Start of DG-1 & DG-2 Was Experienced.Caused by Undervoltage Condition on Electrical Busses SM-7 & SM-8.Circulating Water Pump CW-P-1C Control Switch Placed in pull-to-lock.W/970723 Ltr
ML17292A9201997-06-26026 June 1997
LER 97-006-00:on 970527,non-performance of Surveillance Requirement 3.6.1.3.2 for Blind Fanges,Was Noted.Caused Because Misunderstanding of Intent of Specs.Added Five Structural Assemblies for SP.W/970626 Ltr
ML17292A8331997-04-28028 April 1997
LER 97-004-00:on 970327,plant Operators Manually Scrammed Reactor as Required by TS Due to Entry Into Region a of power-to-flow Map Following Planned Trip of Single Mfp. Event Evaluation teams,established.W/970428 Ltr
ML17292A8311997-04-28028 April 1997
LER 97-005-00:on 970327,valid Reactor Scram Signal Received Due to Low Water Level Condition During Preparations for SRV Testing.Caused by Risks & Consequences of Decisions Not Completely Identified.Restored Water level.W/970428 Ltr
ML17292A8251997-04-21021 April 1997
LER 97-003-00:on 970320,notification of Noncompliance W/Ts as TS SRs for Response Time Testing Were Not Being Met for Specified Instrumentation in Rps,Pcis & Eccs.Requested Enforcement Discretion for One Time exemption.W/970421 Ltr
ML17292A7431997-03-20020 March 1997
LER 97-002-00:on 970218,determined That Rod Block Monitor (RBM) Calibr Values Were Not Set IAW Tech Specs.Caused by Calibr Procedures Inadequacies.Revised & re-performed RBM Channel Calibr procedures.W/970330 Ltr
ML17292A7401997-03-13013 March 1997
LER 97-001-00:on 970211,reactor Water Cleanup Sys Blowdown Flow Isolation Setpoint Was Slightly Above TS Allowable Valve Occurred Due to Calculation Error.Lds Fss LD-FS-15 LD-FS-16 Were Declared inoperable.W/970313 Ltr
ML17292A6641997-01-22022 January 1997
LER 96-009-00:on 961220,miscalculation of Instantaneous Overcurrent Relay Settings Resulted in Inoperability of safety-related Equipment.Caused by Utilization of Inappropriate Design.Testing Was completed.W/970122 Ltr
ML17292A6461997-01-0606 January 1997
LER 96-008-00:on 961205,failure to Comply with TS Action Requirement for Emergency Core Cooling Sys Actuation Instrumentation Occurred Due to Unidentified Inoperability Condition.Pmr initiated.W/970106 Ltr
ML17292A6371996-12-19019 December 1996
LER 96-007-00:on 961122,electrical Breakers Were Not Seismically Qualified in Test/Disconnect Position.Circuit Breaker Mfg Did Not Consider Raced Out Breaker Position During Testing.Relocated Circuit breakers.W/961217 Ltr
ML17292A4121996-08-0808 August 1996
LER 96-006-00:on 960709,average Power Range Monitor Rod Block Downscale Surveillance Not Performed Prior to Entry Into Mode 1.Caused by long-standing Misinterpretation of Requirements of Tss.Procedures revised.W/960808 Ltr
ML17292A3801996-07-24024 July 1996
LER 96-004-00:on 960624,plant Was Manually Scrammed by Control Room Personnel Due to Reactor Water Level Transient Experienced During Testing of Digital Feedwater Sys.Caused by Programming Error.Sys Was corrected.W/960724 Ltr
ML17292A3771996-07-24024 July 1996
LER 96-005-00:on 960624,determined Missed Surveillance Test Re Channel Check of Average Power Range Monitor.Caused by Inadequate Procedures.Revised Surveillance Procedure Re When APRM Checks Must Be performed.W/960724 Ltr
ML17292A3641996-07-12012 July 1996
LER 96-003-00:on 960615,required Surveillance Test Not Performed When Required by TS 3.4.1.3.Caused by Inadequate Procedures.Implementing Surveillance Procedure & Reactor Plant Startup Procedures revised.W/960712 Ltr
ML17292A3361996-06-20020 June 1996
LER 96-002-00:on 960504,critical Bus SM-8 Lost Power When Supply Breaker 3-8 Tripped.Caused by Personnel Error. Operators Counselled & Procedures revised.W/960620 Ltr
ML17292A2861996-05-24024 May 1996
LER 96-001-00:on 960425,inadvertent ESF Actuations Occurred Due to Tripping of Temporary Power Supply to IN-3.Caused by Personnel Error.Operations Restored to IN-3 Loads & Reset ESF actuations.W/960524 Ltr
ML17291B0891995-10-19019 October 1995
LER 95-011-00:on 950919,failed to Comply W/Ts SR for RCIC Sys Due to Analysis Deficiency That Resulted in Inadequate Surveillance Test Procedure.Surveillance Procedure Revised to Correct deficiency.W/951019 Ltr
ML17291A9021995-07-0707 July 1995
LER 95-010-00:on 950609,HPCS DG Declared Inoperable Due to Discovery That TS Test Method Incomplete.Caused by Inadequate Testing Procedure.Test Procedure for HPCS DG Reviewed & Special Test Procedures written.W/950707 Ltr
ML17291A9031995-07-0707 July 1995
LER 95-009-00:on 950607,inadvertent MSIV Closure Occurred During Surveillance Test Due to Poor Communication Between Test Team.Determined That MSIV Closure Not Valid Because Closure Not Triggered by Plant conditions.W/950707 Ltr
ML17291A8501995-06-0808 June 1995
LER 95-006-01:on 950405,reactor Scram Occurred During Surveillance Testing Due to Protective Sys Relay Failure. Replaced Failed Relay Before Plant Startup
ML17291A8101995-05-12012 May 1995
LER 95-008-00:on 940125,TS Wording Lead to Potential TS Violation.Caused by Lack of Clarity in Ts.Submitted Improved TS for Plant to Provide Addl clarity.W/950512 Ltr
ML17291A7841995-05-0505 May 1995
LER 95-007-00:on 950222,emergency Diesel Start Occurred Due to Voltage Transient on BPA Grid.Confirmation Was Received at 17:51 H That Disturbance Had Originated in BPA Grid
ML17291A7801995-05-0404 May 1995
LER 95-006-00:on 950405,main Turbine Trip Occurred During Performance of Surveillance Test Due to Protective Sys Relay Failed.Replaced Failed Relay Before Plant startup.W/950504 Ltr
ML17291A7851995-05-0303 May 1995
LER 95-005-00:on 950222,inoperable IRM Had Been Relied Upon to Meet TS Requirements During Reactor Startup.Caused by Lack of Neutron Source to Test Instrumentation. Sys Knowledge Gained Will Be incorporated.W/950503 Ltr
ML17291A7071995-03-25025 March 1995
LER 95-004-00:on 950226,malfunction in Main Turbine DEH Control Sys Caused All Four High Pressure Turbine Governor Valves to Rapidly Close.Caused by Blown Fuse.Suspected Faulty Circuit Card replaced.W/950325 Ltr
ML17291A7011995-03-20020 March 1995
LER 95-002-00:on 950218,automatic Reactor Scram Occurred. Caused by Erroneous Positioning of Control During Performance of Scheduled Periodic Functional Test.Control repositioned.W/950320 Ltr
1999-07-20
[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
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~CATEGORY 1~~REGULATORY INFORMATION DISTR IBUTIQNWYSTEM (R IDS)ACCESSION NBR: 9707300094
'DOC.DATE: 97/07/23 NOTARIZED:
NO FACIL: 50-3>>7 WPPSS Nuclear Pro Ject.Unit 2>Washington Public Pore AUTH.NAME AUTHOR AFFILIATION PFITZEP>B.'ashington Public Poeer Supp 1!J S!Jstem BEMIS>P.R.Washington P0b lie Poeer Supp 1!J S!Jstem RECIP.NAME RECIPIENT AFFILIATION DOCKET 0 05000397
SUBJECT:
LER 97-007-00:
on'>>70611>voluntar!J rept oF automatic start oP DG-1 5 DG-2 was experienced.
Caused b!J undervoltage condition on electrical busses SM-7 b SM-8.Circulating eater pump CW-P-1C control switch eas placed in pull-to-lock.
DISTRIBUTION CODE: IE22T COPIES RECEIVED: LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER)>Incident Rpt>etc.NOTES: RECIPIENT ID CODE/NAME PD4-2 PD CQP IES LTTR ENCL 1 1 REC IP IENT ID CODE/NAME CQLBURN>T CQP IES LTTR ENCL 1 1 INTERNAL: ACRS AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HGMB NRR/DSSA/SPLR RES/DET/EIB AE J FILE CE ER L NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN4 FILE 01 1 1 1 1 1 1, 1 2 1 1 1 1 1 1 1 EXTERNAL: L ST LOBBY WARD 1 1 NOAC POORE>W.1 1 NRC PDR 1 1 LITCO BRYCE>J H NOAC GUEENER>DS NUDOCS FULL TXT NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FUL'EXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 25 WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~Richlanrl, 1Virshi>i@tow 99352-0968 July 23, 1997 G02-97-147 Docket No.50-397 Document Control Desk U.S.Nuclear Regulatory Commission Washington, D.C.20555 Gentlemen:
Subject:
NUCLEAR PLANT WNP-2, OPERATING LICENSE NPF-21, LICENSEK EVIPW REPORT NO.97-007-00 Transmitted herewith is voluntary Licensee Event Report No.97-007-00 for WNP-2.This report is submitted in response to the recommendations contained in NUREG-1022.
Should you have any questions or desire additional information regarding this matter, please call me or Mr.Paul Inserra at (509)377-4147.Respectfully, mls Vi President, Nuclear Operations Mail Drop PE23 Enclosure cc: EW Merschoff, NRC RIV KE Perkins, Jr., NRC RIV, WCFO TG Colburn, NRR PD Robinson, Winston&Strawn NRC Sr.Resident Inspector, MD927N (2)INPO Records Center-Atlanta, GA DL Williams, BPA, MD399 9707300094 970723 PDR ADQCK 05000397 S PDR llllllllllllllllllllllllllllllllllllllll LICENSEE EVENT REPORT (LER)FACILITY NAME (1)Washin ton Nuclear Plant-Unit 2 DOCKET NUMBER (2)50-397 PAGE (3)1 OF 3 TITLE (4)VOLUNTARY REPORT OF AUTOMATIC START OF DG-1 AND DG-2 DUE TO SM-7 AND SM-8 UNDERVOLTAGE EVENT DATE (5)LER NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (Bl DAY SEOUENIIAL NUMBER REV.NUMBER DAY YEAR FACILHY NAME 06 11 97 97 00 07 23 97 FACILHY NAME N/A DOCKET NUMBER 05000 OPERATING MODE THIs REpoRT Is sUBMITTED pURsUANT To THE REQUIRENENTs op 10 cpR 5I (check one or more)(11)0%20A02(b)20A05(a)(1)(I) 20.405(a)(1)(ii) 20A05(a)(1)(iii)20.405(a)(1)(iv) 20A05(a)(1)(v) 20A05(c)50.36(c)(1) 50.36(c)(2) 50.73(a)(2)0) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(iv)50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(x)
X 73.71(b)73.71(c)OTHER Voluntary NAME Bill Pfitzer, Licensing Engineer LICENSEE CONTACT FOR THIS LER (12)TELEPHONE NUMBER ((nclude Area Code)509-377-2419 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE COMPONENT MPIAIFACTURER REPORTABLE TO NPRDS CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14)YES corn le(ed EXPECTED SUBMISSION DATE NO EXPECTED MONTH DAY ABSTRACT On 6/11/97, with the plant in Operating Mode 4, Circulating Water Pump motor CW-M-P/1C experienced internal electrical faulting shortly after pump startup.The pump ran for approximately 15 seconds prior to tripping the CW-M-P/1C feeder breaker.due to phase differential current.The motor fault caused a momentary undervoltage condition on electrical busses SM-7 and SM-8 which initiated an automatic start of emergency diesel generators, EDG-1 and EDG-2.The diesel generators started and ran unloaded, as designed, until manually shutdown by operating personnel.
The output breakers for EDG-1 and EDG-2 did not close and load the EDGs because the undervoltage condition was only momentary, and plant busses continued to be fed from the startup transformer, TR-S.Immediate corrective actions were to return EDG-1 and EDG-2 to standby readiness and initiate an investigation into the cause of CW-M-P/1C trip.The root cause of EDG-1 and EDG-2 auto start was an undervoltage condition on electrical busses SM-7 and SM-8 This event is voluntarily reported, The safety significance of this event is considered minimal.
FACILITY NAME (I)LICENSEE EVENT REPORT (LER)TEXT CONT(NUATION DOCKET NUMBER (2)YEAR LER NUMBER (6)SEQUENT iAL NUMBER RCVI6 1 ON NJNB6R PAGE (3)Washington Nuclear Plant-Unit 2 50-397 97 007 00 2 OF 3 TEXT (If more space Is reqU(red, use additional copies of NRC Form 366A)(17)Even De cri ti n On 6/11/97, with the plant in Operating Mode 4 with electrical distribution being supplied by the startup transformer TR-S[XFMR], Circulating Water Pump motor CW-M-P/1C[KE][P][MO]
experienced internal electrical faulting shortly after pump startup.The pump ran for approximately 15 seconds prior to tripping the CW-M-P/1C feeder breaker[BKR]due to phase differential current.The motor fault caused a momentary undervoltage condition on electrical busses SM-7 and SM-8[BU]which initiated an automatic start of emergency diesel generators, EDG-1 and EDG-2[DGJ.The diesel generators started and ran unloaded, as designed, until manually shutdown by operating personnel.
The output breakers for EDG-1 and EDG-2 did not close and load the EDGs because the undervoltage condition was only momentary, and plant buses continued to be fed from the startup transformer, TR-S.This event was voluntarily reported within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and this report is being voluntarily submitted since the EDGs are not engineered safety features at WNP-2.Immediate orr ive Acti n Circulating Water pump CW-P-1C control switch was placed in pull-to-lock.
EDG-1 and EDG-2 were returned to standby readiness.
Investigation was initiated into the cause of CW-M-P/1C trip.A significant Problem Evaluation Request was initiated to resolve this problem.h Control room personnel reported that CW-M-P/1C started normally with the expected starting current, and operated with a running current of approximately 600 amps for approximately 15 seconds prior to tripping.Following the trip, phase voltages on the bus supplying the motor were observed to be 4250, 4400, and 4300 volts on each of the A, B, and C phases respectively with the 230kV voltage at Ashe substation reported at 242kV.Throughout this event, plant busses continued to be fed from the startup transformer, TR-S.The WNP-2 electrical distribution system relay scheme operated as designed to isolate the fault and terminate the undervoltage condition on the affected busses.Had the undervoltage condition on SM-7 and SM-8 continued for approximately four seconds, the supply breakers from Backup Auxiliary Transformer, TR-B, would have auto closed and SM-7 and SM-8 would have been supplied by TR-B.If the undervoltage condition had continued for approximately 7 seconds the EDG output breakers would have auto closed and SM-7 and SM-8 would have been supplied by the EDGs.
0~LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACILITY NAME tl)DOCKET NUMBER)2)LER NUMBER I6)SEQUENT)AL NUMBER A6V)ATION NAQER PAGE I 3)Washington Nuclear Plant-Unit 2 50-397 97 007 00 3'F 3 TEXT (lf more space is required, use additional copies of NRC Form 366A)(17)In this case the feeder breaker for CW-M-P/IC tripped, isolating the fault immediately, and the standby sources designed to automatically supply the safety-related electrical busses were not needed.mRafXame The auto start of EDG-1 and EDG-2 was caused by an undervoltage condition on SM-7 and SM-8.The undervoltage condition was caused by internal faulting of the non-safety related CW-M-P/1C which developed shortly after start of the motor.F her orr tive Ac i n None required.EDG response to the undervoltage condition was normal.Appropriate corrective actions associated with CW-P-P/IC have been taken.A e mn f fet n uence WNP-2's electrical distribution system relay scheme operated as designed to isolate the fault without unnecessary challenges to the plant electrical distribution system.In this case the feeder breaker for CW-M-P/IC tripped, isolating the fault immediately.
Offsite and onsite sources designed to automatically supply the safety-related electrical busses were available at the time from transformer TR-8 and the EDGs.The safety significance of this event is considered minimal.E There have been no similar previous events of motor faults causing starts of the EDGs.
