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| | issue date = 07/24/1996 | | | issue date = 07/24/1996 |
| | title = 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 | | | title = 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 |
| | author name = BEMIS P R, FOLEY C J | | | author name = Bemis P, Foley C |
| | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM | | | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:~CATEGORYREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9607300145 DOC.DATE: | | {{#Wiki_filter:~ CATEGORY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| 96/07/24NOTARIZED: | | ACCESSION NBR:9607300145 DOC.DATE: 96/07/24 NOTARIZED: NO DOCKET g FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION FOLEYgC.J,. Washington Public Power Supply System BEMISgP.R. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION |
| NODOCKETgFACIL:50-397 WPPSSNuclearProject,Unit2,Washington PublicPowe05000397AUTH.NAMEAUTHORAFFILIATION FOLEYgC.J,.
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| Washington PublicPowerSupplySystemBEMISgP.R. | |
| Washington PublicPowerSupplySystemRECIP.NAME RECIPIENT AFFILIATION | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER96-005-00:on 960624,determined missedsurveillance testrechannelcheckofAveragePowerRangeMonitor.Causedbyinadequate procedures.
| | 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 A APRM checks must be performed.W/960724 ltr. |
| Revisedsurveillance procedure rewhenAPRMchecksmustbeperformed.W/960724 ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR ENCLSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTES:ATERECIP"ENT IDCODE/NAME PD4-2PDINTERNAL:
| | T DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: |
| ACRSAEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DSIR/EIB EXTERNAL:
| | TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. E NOTES: |
| LSTLOBBYWARDNOACMURPHYgG.A NRCPDRCOPIESLTTRENCL111111111111111111111111RECIPIENT IDCODE/NAME COLBURNgT DBFILECEEEBNRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN4FILE01LITCOBRYCEgJHNOACPOOREgW..NUDOCSFULLTXTCOPIESLTTRENCL1122~11111111111111221111RYD0UMENNOTETOALL"RIDS"RECIPIENTS:
| | RECIP"ENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 PD 1 1 COLBURNgT 1 1 R INTERNAL: ACRS 1 1 D B 2 2 Y AEOD/SPD/RRAB 1 1 FILE CE E ~ 1 1 NRR/DE/ECGB 1 1 E B 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DSIR/EIB 1 1 RGN4 FILE 01 1 1 D EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCEgJ H 2 2 0 NOAC MURPHYgG.A 1 1 NOAC POOREgW. 1 1 NRC PDR 1 1 .NUDOCS FULL TXT 1 1 U |
| PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFNSD-5(EXT.
| | M E |
| 415-2083) | | N NOTE TO ALL "RIDS" RECIPIENTS: |
| TOELIMINATE YOURNAMEFROMDISTRIBUTION LiSTSFORDOCUMENTS YOUDON'TNEED!FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
| | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LiSTS FOR DOCUMENTS YOU DON'T NEED! |
| LTTR26ENCL26 4tiWASHINGTON PUBLICPOWERSUPPLYSYSTEMP.O.Box968~3000George1Vashington 1Vay~Richland, 1Vashington 99352July24,1996G02-96-145 DocketNo.50-397DocumentControlDeskU.S.NuclearRegulatory Commission Washington, D.C.20555
| | FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 26 |
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| | WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George 1Vashington 1Vay ~ Richland, 1Vashington 99352 July 24, 1996 G02-96-145 Docket No. 50-397 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 |
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| ==Subject:== | | ==Subject:== |
| NUCLEARPLANTWNP-2,OPERATING LICENSENPF-21LICENSEEEVENTREPORTNO.96-005-00 Transmitted herewithisLicenseeEventReportNo.96-005-00 fortheWNP-2Plant.Thisreportissubmitted inresponsetothereporting requirements of10CFR50.73 anddiscusses theitemsofreportability, corrective actiontaken,andactiontakentoprecluderecurrence.
| | NUCLEAR PLANT WNP-2, OPERATING LICENSE NPF-21 LICENSEE EVENT REPORT NO. 96-005-00 Transmitted herewith is Licensee Event Report No. 96-005-00 for the WNP-2 Plant. This report is submitted in response to the reporting requirements of 10CFR50.73 and discusses the items of reportability, corrective action taken, and action taken to preclude recurrence. |
| Shouldyouhaveanyquestions ordesireadditional information, pleasecallmeorL.C.Fernandez at(509)377-4147.
| | Should you have any questions or desire additional information, please call me or L.C. Fernandez at (509) 377-4147. |
| full,P.R.misicePresident, NuclearOperations (MailDropPE23)PRB:CJF:lr Enclosure cc:LJCallan,NRC-RIVKEPerkins,Jr".,NRC-RIV,WalnutCreekFieldOfficeNSReynolds, Winston&StrawnTGColburn,NRRNRCSr.ResidentInspector (MailDrop927N,2Copies)INPORecordsCenter-Atlanta,GADLWilliams, BPA(MailDrop399)9607300i45 960724PDRADOCK05000397SPDR f1IIu | | full, P. R. mis ice President, Nuclear Operations (Mail Drop PE23) |
| >>a~0IIIRR)&NISSEIIII<<~.I<<I.~<<I~BaaaaaaI~IIIIII'IIIIIII'rt~rt~rtgrt~rI~rtIQI5S~III~~II'IiESRil'RiHilEliiHRSil | | PRB:CJF:lr Enclosure cc: LJ Callan, NRC-RIV KE Perkins, Jr"., NRC-RIV, Walnut Creek Field Office NS Reynolds, Winston & Strawn TG Colburn, NRR NRC Sr. Resident Inspector (Mail Drop 927N, 2 Copies) |
| 'RARER>iERiRSRIHERSII(iiiRIIIIHI RESRSIEIIHERiISEEEiIIIIHI I.i~'>;IIQl~EEEIIll~~~~<<I>>I~Il~~~~I>>~'III~I~~<<I~~I~~~aI<<~~I~~I~~al~~<<~~I~a~I~~Ii>>II~I~~~III~II~~'~~.~I~~~I~<<I~~I~I>>~I<<II~III~~III~I~~I'~i~'II~II>>~~I<<~
| | INPO Records Center - Atlanta, GA DL Williams, BPA (Mail Drop 399) 9607300i45 960724 PDR ADOCK 05000397 S PDR |
| i~LICENSEEEVENTREPORT(LER)TEXTCONTINUATION AGILITYNAHE(1)Washington NuclearPlant-Unit2OOCKETNUHBER(2)05000397LERNUHBER(8)earumberev.No.AGE(3)6050ITLE(4)FailuretoComplyWithTechnical Specification Surveillance Requirement DuetoInadeuateProcedures 2F3PIni'nPrirhEvn:Atthetimeoftheevent,theplantwasinMode1withthereactorapproximately atthe24%thermalpowerlevel.Theplantwasstartingupafteranunplanned reactorscram.Atapproximately 0900hoursonJune24,1996,anoperatorreviewing completed procedures governing activities beingperformed aspartofrestarting theplant,determined thatasurveillance testhadnotbeenconsistently performed withintheperiodrequiredbytheTechnical Specifications. | | |
| Therequiredsurveillance testwastoperformachannelcheckoftheAveragePowerRangeMonitor(APRM)PG]flowsignaltoverifyoperability oftheAPRMflowbiasedsimulated thermalpowerhighrangetripchannels.
| | f 1 |
| Thetestisrequiredtobeperformed onadailybasiswheninMode1,whichhadbeenenteredat0914hoursonJune20,1996.Therequiredtesthadbeencompleted onJune22,1996,andagainonJune24,1996.However,thetesthadnotbeenperformed onJune21or23,resulting inaviolation ofTechnical Specification 3.3.1.min:Therequiredsurveillance testhadbeencompleted approximately 7.3hoursearlier,at0139hoursonJune24,1996,demonstrating thatflowratedatawasbeingcorrectly receivedandutilizedbytheAPRMsystem.Consequently, noimmediate corrective actionwasnecessary.
| | I I |
| mRa&nm:Therootcauseofthiseventwasreactorplantstartupandsurveillance procedures thatwereincorrect oromittedrelevantinformation. | | u |
| Thesurveillance procedure beingusedcontainsthreeseparatepartscoveringthreedifferent surveillance requirements:
| | |
| jetpumptP]operability, RRCloopflowbalance,andtheAveragePowerRangeMonitorflowchannelcheck.The"Purpose" sectionofthissurveillance procedure includedthestatement, "Thissurveillance isperformed within24hoursofthermalpowerexceeding 25%ofratedthermalpower,inLEtlessthanorequalto]4hoursafteranidlerecirculation loopisreturnedtooperation, anddailythereafter whenthereactorisinoperational conditions 1or2.Thatisanincorrect statement sinceitdoesnotreflecttherequirement ofTechnical Specification 3.3.1toperformtheAPRMfiowsignalchannelcheckonadailybasiswheninMode1.Theprocedure governing reactorplantstartupstatedthattheparticular surveillance procedure wasrequiredafterreaching25%reactorpower,andtherefore alsodidnotaddresstheTechnical Specification requirement toperformtheAPRMflowsignalchannelcheckonadailybasisinMode1.Thesurveillance procedure governing shiftanddailyinstrument checksdidnotidentifytheAPRMflowsignalchannelcheckasbeingarequiredactionduringMode1~
| | >> a 0 |
| I AGILITYNAHE(i)Washington NuclearPlant-Unit2DOCKETNWBER(2)05000397earLERNONBER(8)umberev.No.6050AGE(3)3F31TLE(4)FailuretoComplyWithTechnical Specification Surveillance Requirement DuetoInadeuateProcedures Theseprocedural deficiencies requiredtheoperating stafftorelyonpastexperience andacquiredknowledge toassurethatallTechnical Specification requirements weremetfortheproperconditions. | | ~ |
| Thisledtotheinconsistent performance ofthesurveillance test.Consequently, therootcauseofthiseventwasreactorplantstartupandsurveillance procedures thatwereincorrect oromittedrelevantinformation.
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| hr.Corrective actionswereimplemented toprecluderecurrence.
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| Theimplementing surveillance procedure waschangedtoclearlyidentifythepurposesandconditions underwhichitisapplicable.
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| Theprocedure governing reactorplantstartupwaschangedtoclearlyidentifywhentheAPRMflowsignalchannelchecksmustbeperformed perTechnical Specification 3.3.1.Thesurveillance procedure governing shiftanddailyinstrument checksduringModes1,2,and3wasrevisedtorequirespecificverification thattheAPRMflowsignalchannelcheckwascompleted asrequiredbytheTechnical Specifications.
| | ~ I I I I I |
| Theeventhadnosafetysignificance.
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| Therequiredsurveillances hadbeenperformed onJune22and24verifying operability oftheAPRMflowsignalinput,andwereperformed asrequiredbyTechnical Specifications afterJune24.TheAPRMhighneutrontripfunctionwasfunctional duringthisentireperiod,assuringthattheReactorProtection System[JC]wouldscramthereactorinthe"eventofanunexpected neutronspike.LicenseeEventReport96-003-00 identified aneventinvolving asurveillance testinadvertently omittedduetothesameinadequate procedures duringaplantstartup.ThiseventhadoccurredonJune15,1996.Ifcorrective actionsforthispreviouseventhadbeencompleted priortotheLER96-005-00 event,theycouldhaveaffordedtheopportunity toidentifyandcorrecttheprocedural deficiencies thatledtoLER96-005-00.}}
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| | ~ LICENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION AGILITY NAHE (1) OOCKET NUHBER (2) LER NUHBER (8) AGE (3) ear umber ev. No. |
| | Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 6 05 0 2 F 3 ITLE (4) |
| | Failure to Comply With Technical Specification Surveillance Requirement Due to Inade uate Procedures PI ni'n Prir h Evn: |
| | At the time of the event, the plant was in Mode 1 with the reactor approximately at the 24% thermal power level. The plant was starting up after an unplanned reactor scram. |
| | At approximately 0900 hours on June 24, 1996, an operator reviewing completed procedures governing activities being performed as part of restarting the plant, determined that a surveillance test had not been consistently performed within the period required by the Technical Specifications. The required surveillance test was to perform a channel check of the Average Power Range Monitor (APRM) PG] flow signal to verify operability of the APRM flow biased simulated thermal power high range trip channels. |
| | The test is required to be performed on a daily basis when in Mode 1, which had been entered at 0914 hours on June 20, 1996. The required test had been completed on June 22, 1996, and again on June 24, 1996. However, the test had not been performed on June 21 or 23, resulting in a violation of Technical Specification 3.3.1. |
| | m i n: |
| | The required surveillance test had been completed approximately 7.3 hours earlier, at 0139 hours on June 24, 1996, demonstrating that flow rate data was being correctly received and utilized by the APRM system. Consequently, no immediate corrective action was necessary. |
| | mRa&nm: |
| | The root cause of this event was reactor plant startup and surveillance procedures that were incorrect or omitted relevant information. The surveillance procedure being used contains three separate parts covering three different surveillance requirements: jet pump tP] operability, RRC loop flow balance, and the Average Power Range Monitor flow channel check. The "Purpose" section of this surveillance procedure included the statement, "This surveillance is performed within 24 hours of thermal power exceeding 25% |
| | of rated thermal power, in LE tless than or equal to] 4 hours after an idle recirculation loop is returned to operation, and daily thereafter when the reactor is in operational conditions 1 or 2. That is an incorrect statement since it does not reflect the requirement of Technical Specification 3.3.1 to perform the APRM fiow signal channel check on a daily basis when in Mode 1. The procedure governing reactor plant startup stated that the particular surveillance procedure was required after reaching 25% reactor power, and therefore also did not address the Technical Specification requirement to perform the APRM flow signal channel check on a daily basis in Mode 1. The surveillance procedure governing shift and daily instrument checks did not identify the APRM flow signal channel check as being a required action during Mode 1 ~ |
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| | I AGILITY NAHE (i) DOCKET NWBER (2) LER NONBER (8) AGE (3) ear umber ev. No. |
| | Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 6 05 0 3 F 3 1TLE (4) |
| | Failure to Comply With Technical Specification Surveillance Requirement Due to Inade uate Procedures These procedural deficiencies required the operating staff to rely on past experience and acquired knowledge to assure that all Technical Specification requirements were met for the proper conditions. This led to the inconsistent performance of the surveillance test. Consequently, the root cause of this event was reactor plant startup and surveillance procedures that were incorrect or omitted relevant information. |
| | h r |
| | . Corrective actions were implemented to preclude recurrence. The implementing surveillance procedure was changed to clearly identify the purposes and conditions under which it is applicable. The procedure governing reactor plant startup was changed to clearly identify when the APRM flow signal channel checks must be performed per Technical Specification 3.3.1. The surveillance procedure governing shift and daily instrument checks during Modes 1, 2, and 3 was revised to require specific verification that the APRM flow signal channel check was completed as required by the Technical Specifications. |
| | The event had no safety significance. The required surveillances had been performed on June 22 and 24 verifying operability of the APRM flow signal input, and were performed as required by Technical Specifications after June 24. The APRM high neutron trip function was functional during this entire period, assuring that the Reactor Protection System [JC] would scram the reactor in the" event of an unexpected neutron spike. |
| | Licensee Event Report 96-003-00 identified an event involving a surveillance test inadvertently omitted due to the same inadequate procedures during a plant startup. This event had occurred on June 15, 1996. If corrective actions for this previous event had been completed prior to the LER 96-005-00 event, they could have afforded the opportunity to identify and correct the procedural deficiencies that led to LER 96-005-00.}} |
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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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ACCESSION NBR:9607300145 DOC.DATE: 96/07/24 NOTARIZED: NO DOCKET g FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION FOLEYgC.J,. Washington Public Power Supply System BEMISgP.R. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
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 A APRM checks must be performed.W/960724 ltr.
T DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. E NOTES:
RECIP"ENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 PD 1 1 COLBURNgT 1 1 R INTERNAL: ACRS 1 1 D B 2 2 Y AEOD/SPD/RRAB 1 1 FILE CE E ~ 1 1 NRR/DE/ECGB 1 1 E B 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DSIR/EIB 1 1 RGN4 FILE 01 1 1 D EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCEgJ H 2 2 0 NOAC MURPHYgG.A 1 1 NOAC POOREgW. 1 1 NRC PDR 1 1 .NUDOCS FULL TXT 1 1 U
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WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George 1Vashington 1Vay ~ Richland, 1Vashington 99352 July 24, 1996 G02-96-145 Docket No. 50-397 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
NUCLEAR PLANT WNP-2, OPERATING LICENSE NPF-21 LICENSEE EVENT REPORT NO. 96-005-00 Transmitted herewith is Licensee Event Report No. 96-005-00 for the WNP-2 Plant. This report is submitted in response to the reporting requirements of 10CFR50.73 and discusses the items of reportability, corrective action taken, and action taken to preclude recurrence.
Should you have any questions or desire additional information, please call me or L.C. Fernandez at (509) 377-4147.
full, P. R. mis ice President, Nuclear Operations (Mail Drop PE23)
PRB:CJF:lr Enclosure cc: LJ Callan, NRC-RIV KE Perkins, Jr"., NRC-RIV, Walnut Creek Field Office NS Reynolds, Winston & Strawn TG Colburn, NRR NRC Sr. Resident Inspector (Mail Drop 927N, 2 Copies)
INPO Records Center - Atlanta, GA DL Williams, BPA (Mail Drop 399) 9607300i45 960724 PDR ADOCK 05000397 S PDR
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~ LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION AGILITY NAHE (1) OOCKET NUHBER (2) LER NUHBER (8) AGE (3) ear umber ev. No.
Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 6 05 0 2 F 3 ITLE (4)
Failure to Comply With Technical Specification Surveillance Requirement Due to Inade uate Procedures PI ni'n Prir h Evn:
At the time of the event, the plant was in Mode 1 with the reactor approximately at the 24% thermal power level. The plant was starting up after an unplanned reactor scram.
At approximately 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> on June 24, 1996, an operator reviewing completed procedures governing activities being performed as part of restarting the plant, determined that a surveillance test had not been consistently performed within the period required by the Technical Specifications. The required surveillance test was to perform a channel check of the Average Power Range Monitor (APRM) PG] flow signal to verify operability of the APRM flow biased simulated thermal power high range trip channels.
The test is required to be performed on a daily basis when in Mode 1, which had been entered at 0914 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.47777e-4 months <br /> on June 20, 1996. The required test had been completed on June 22, 1996, and again on June 24, 1996. However, the test had not been performed on June 21 or 23, resulting in a violation of Technical Specification 3.3.1.
m i n:
The required surveillance test had been completed approximately 7.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> earlier, at 0139 hours0.00161 days <br />0.0386 hours <br />2.29828e-4 weeks <br />5.28895e-5 months <br /> on June 24, 1996, demonstrating that flow rate data was being correctly received and utilized by the APRM system. Consequently, no immediate corrective action was necessary.
mRa&nm:
The root cause of this event was reactor plant startup and surveillance procedures that were incorrect or omitted relevant information. The surveillance procedure being used contains three separate parts covering three different surveillance requirements: jet pump tP] operability, RRC loop flow balance, and the Average Power Range Monitor flow channel check. The "Purpose" section of this surveillance procedure included the statement, "This surveillance is performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of thermal power exceeding 25%
of rated thermal power, in LE tless than or equal to] 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after an idle recirculation loop is returned to operation, and daily thereafter when the reactor is in operational conditions 1 or 2. That is an incorrect statement since it does not reflect the requirement of Technical Specification 3.3.1 to perform the APRM fiow signal channel check on a daily basis when in Mode 1. The procedure governing reactor plant startup stated that the particular surveillance procedure was required after reaching 25% reactor power, and therefore also did not address the Technical Specification requirement to perform the APRM flow signal channel check on a daily basis in Mode 1. The surveillance procedure governing shift and daily instrument checks did not identify the APRM flow signal channel check as being a required action during Mode 1 ~
I AGILITY NAHE (i) DOCKET NWBER (2) LER NONBER (8) AGE (3) ear umber ev. No.
Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 6 05 0 3 F 3 1TLE (4)
Failure to Comply With Technical Specification Surveillance Requirement Due to Inade uate Procedures These procedural deficiencies required the operating staff to rely on past experience and acquired knowledge to assure that all Technical Specification requirements were met for the proper conditions. This led to the inconsistent performance of the surveillance test. Consequently, the root cause of this event was reactor plant startup and surveillance procedures that were incorrect or omitted relevant information.
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. Corrective actions were implemented to preclude recurrence. The implementing surveillance procedure was changed to clearly identify the purposes and conditions under which it is applicable. The procedure governing reactor plant startup was changed to clearly identify when the APRM flow signal channel checks must be performed per Technical Specification 3.3.1. The surveillance procedure governing shift and daily instrument checks during Modes 1, 2, and 3 was revised to require specific verification that the APRM flow signal channel check was completed as required by the Technical Specifications.
The event had no safety significance. The required surveillances had been performed on June 22 and 24 verifying operability of the APRM flow signal input, and were performed as required by Technical Specifications after June 24. The APRM high neutron trip function was functional during this entire period, assuring that the Reactor Protection System [JC] would scram the reactor in the" event of an unexpected neutron spike.
Licensee Event Report 96-003-00 identified an event involving a surveillance test inadvertently omitted due to the same inadequate procedures during a plant startup. This event had occurred on June 15, 1996. If corrective actions for this previous event had been completed prior to the LER 96-005-00 event, they could have afforded the opportunity to identify and correct the procedural deficiencies that led to LER 96-005-00.
