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| | issue date = 09/28/1988 | | | issue date = 09/28/1988 |
| | title = LER 88-009-00:on 880829,while Technician Changing Out Particle Filters & Iodine Cartridges,Open Pathway from Containment Atmosphere to Auxiliary Bldg Established.Caused by Inadequate Procedure.Procedure revised.W/880928 Ltr | | | title = LER 88-009-00:on 880829,while Technician Changing Out Particle Filters & Iodine Cartridges,Open Pathway from Containment Atmosphere to Auxiliary Bldg Established.Caused by Inadequate Procedure.Procedure revised.W/880928 Ltr |
| | author name = SMITH W G, WOJCIK J T | | | author name = Smith W, Wojcik J |
| | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG | | | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:gCCELZRABUTlONDEMONS.TIONSYFI'EMREGULAZNEORNAZONDZSTRZBUTZOt'EN(RZDS)QACCESSZONNBR:8810070042DOC.DATE:88/09/28NOTARZZED:NODOCKETFACIL:5G-315DonaldC.CookNuclearPowerPlant,Unit1,Indiana&0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,Indiana&05000316AUTH.NAMEAUTHORAFFILIATIONWOJCIKzJ.T.IndianaMichiganPowerCo.(formerlyIndiana&MichiganEle.SMZTHgW.G.IndianaMichiganPowerCo.(formerlyIndiana&MichiganEleRECIP.NAMERECIPIENTAFFILIATION | | {{#Wiki_filter:gC CELZRA BUTlON DZSTRZBUTZOt'EN DEMONS. TION SYFI'EM REGULA ZNEORNA ZON (RZDS) |
| | QACCESSZON NBR:8810070042 DOC.DATE: 88/09/28 NOTARZZED: NO DOCKET FACIL:5G-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana & 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME AUTHOR AFFILIATION WOJCIKzJ.T. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele. |
| | SMZTHgW.G. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION |
|
| |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER88-009-00:on880829,non-compliancew/TechSpecsduetoopenpathwayfromcontainmentduringcorealteration.W/8ltr.DISTRIBUTIONCODE:ZE22DCOPIESRECEIVED:LTR'ENCLJSIZE:TITLE:50.73LicenseeEventReport(LER),IncidentRpt,etc.NOTES:RECIPIENTZDCODE/NAMEPD3-1LASTANGzJINTERNAL:ACRSMICHELSONACRSWYLIEAEOD/DSP/NASAEOD/DSP/TPABDEDRONRR/DEST/CEB8HNRR/DEST/ICSB7NRR/DEST/MTB9HNRR/DEST/RSB8ENRR/DLPQ/HFB10NRR/DOEA/EABllNRR/DREP/RPB10NUDOCS-ABSTRACTRESTELFORD,JRES/DSZR/EIBEXTERNAL'G&GWILLIAMSESHSTLOBBYWARDNRCPDRNSICMAYS,GCOPIESLTTRENCL11111-1111111111111111111112211111144111111RECIPIENTIDCODE/NAMEPD3-1PDACRSMOELLERAEOD/DOAAEOD/DSP/ROABARM/DCTS/DABNRR/DEST/ADS7ENRR/DEST/ESB8DNRR/DEST/MEB9H'RR/DEST/PSB8DNRR/DEST/SGB8DNRR/DLPQ/QAB10NRR/DREP/RAB10SSIB9AREGFI'2~SIRDEPYRGN3FILE01FORDBLDGHOY,ALPDRNSZCHARRIS,JCOPIESLTTRENCL11221122111011.11111111111111111111111TOTALNUMBER'OFCOPIESREQUIRED:LTTR46ENCL45 0~\
| | LER 88-009-00:on 880829,non-compliance w/Tech Specs due to open pathway from containment during core alteration. |
| NRCForm388(94)3ILICENSEEEVENTREPORT(LER)U.S.NUCLEARREOULATORYCOMMISSIONAPPROVEDOMBNO.31504104EXPIRES:8/31/88FACILITYNAME(1)D.C.CookNuclearPlant,Unit2DOCKETNUMBER(2)PAGE3osooo316ioF03Non-complianceWithTechnicalSpecificationsDuetoOpenPathwayPromContainmentDuringCoreAlteration'andFuelMovementEVENTDATE(5ILERNUMBER(8)REPORTDATE(7)01'HERFACILITIESINVOLVED(8)MONTHOAYYEARYEARSEOUENTIALNUMBER:REVS~MONTH8::NUMBEROAYYEARFACILITYNAMESD.C.Cook,Unit1DOCKETNUMBER(S)osooo31502988880090009288805000OPERATINQMODE(8)POWERLEVEL(10)20.402(bl20.405(eI(1)(i)20.405(e)(1)(ii)20.405(~l(1)illl)20AOS(II(1)(iv)20.405(el(1)(vl20.405(c)SOW(cl(I)50.38(cl(2)XSODS(el(2)ID50.73(~l(2)(Q)50.73(e)12)IIIIILICENSEECONTACTFORTHISLER(12)50.73(eI(2)IIv)50.73(e)l2)(v)50.73(e)(2)(vil)50.73(el(2)(vill)(A)50.73(el(2)(villi(BI50.73le)(21(e)0THEAEOUIAEMENTSOF10CFR():/C/seekoneormorrofrhefo/fovf/np/(11THISREPORTISSUBMITTEDPURSUANTT73.71(b)73.71(clDTHER/specify/n4osrrectorfovrend/nTrrrt,f/RCForm366A)NAMEJ.T.Wojcik-TechnicalPhysicalSciencesSuperintendentTELFPHONENUMBERAREACODE616465-5901COMPLETEONELINEFOREACHCOMPONENTFAILUREDESCRIBEDINTHISREPORT(13)CAUSESYSTEMCOMPONENTMAHUFACTURERREPD1TR8LR',)~MINIg;,~MCAUSESYSTEMCOMPONENTMANUFAC.TUREREPORTABLETONPADSI!&<NISUPPLEMENTALRFPORTEXPECTED(14)YE5/lfyrs,complerrEXPECTEDSl/Bet/$$/DIVDATE/NOAssTAAcT/Limitto/coosprees,fr.,rppror/merelyfifteenslnple.specstyprvr/Itenlines/(18)EXPECTEDSU8MISSIONDATE(15)MONTHOAYYEAROnAugust29,1988,it'asidentifiedthatforshortperiodsoftime(typicallytwotofiveminutes)whilearadiationprotectiontechnicianwaschangingouttheparticulatefiltersandiodinecartridgesforthelowercontainmentmonitors,anopenpathwayfromthecontainmentatmospheretotheauxiliarybuildingwasestablished.Thechangeoutisperformedatleastonceperday,andthesameprocedurehasbeenfollowedsincethesemonitorswereinstalledonUnit1andUnit2in1985.Theconditionisuniquetothecontainmentintegrityrequirementsduringcorealterationsduetothefactthatthereisnoautomaticcontainmentisolationsignaloperable.forthe'radiationmonitoringsystemduringthismodeofoperation.Thecauseofthiseventwasaninadequateprocedurewhichallowedtheparticulatefiltersandiodinecartridgestobechangedduringcorealterationconditionswithoutfirstestablishingpositivecontainmentisolation.WhenthisconditionwasidentifiedcorealterationandfuelmovementforthecurrentUnit2refuelingoutagehadceased.Aspreventiveaction,procedurer:"12THP6010RADR124hasbeenrevisedtoincludestepstoisolatethesampleinletpriortochangingparticulatefiltersandiodinecartridges.CglOQsrQos,7r3j)r7pr3PDRi'IDQ:;IF.0,/000."3)7Sr/)qt)NRCForm388(94)3)
| | W/8 ltr. |
| )SNCForm38M(94)3)LICENSEENTREPORT(LER)TEXTCONTINUANU.S.NUCLEARREGULATORYCOMMISSIONAPPROVEOOMBNO.3(SBM(84EXPIRES:8/31/88ACILITYNAME(11D.C.CookNuclearPlant,Unit2TEXT//P/INYsEPscs/4/sES)sI/,//Ss/dE/4/M////ICFem/38849/(17)COCKETNUMBER(2)060003]YEAR88LERNUMBER(6)SEGVENTIALNVMSER009REVISIONNUMBER0002PAGE(3)OF03ConditionsPriortoOccurrenceUnit1at90percentreactorthermalpower,Unit2refueling..DescritionofEventOnAugust29,1988,duringadrawingreviewforarefuelingintegrityprocedurerevision,itwasidentifiedthatforshortperiodsoftime(typicallytwotofiveminutes)whilearadiationprotectiontechnicianwaschangingouttheparticulatefiltersandiodinecartridgesforthelowercontainmentradiationmonitors(ERS-1300andERS-1400inUnit1andERS-2300andERS-2400inUnit2)(EIIS/IL-MON)anopenpathwayfromthecontainmentatmospheretotheauxiliarybuildingwasestablished.Theparticulatefilterandiodinecartridgechangeoutwasperformedperanapprovedprocedurewiththeradiationprotectiontechnicianpresentthroughtheentirechangeoutprocedure.Thechangeoutisperformedatleastonceperday,,andthesameprocedurehasbeenfollowedsincethesemonitorswereinstalledonUnit1andonUnit2in1985.Theconditionisuniquetothecontainmentintegrityrequirementsduringcorealterationsdue-tothefactthatthereisnoautomaticcontainmentisolationsignaloperablefortheradiationmonitoringsystemduringthismodeofoperation.Sincethisconditionwasnotrecognizedduringpreviousrefuelingoutages,itisverylikelythattheopenpathwaymayhaveexistedduringpreviouscorealterationsormovementofirradiatedfuelwithinthecontainmentbuilding.Noinoperablestructures,components,orsystemscontributedtothesignificanceofthisevent.CauseofEventThiseventwascausedbytheproceduralinadequacywhichallowedtheparticulatefiltersandiodinecartridgestobechangedduringcorealterationconditionswithoutfirstestablishingpositivecontainmentisolation.AnalsisoftheEventThiseventisconsideredafailuretocomplywithTechnicalSpecification3.9.4ActionStatementrequirementsinthatcorealterationsormovementofirradiatedfuelwithinthecontainmentbuildingwerenotsuspendedwhiletheparticulatefiltersandiodinecartridgeswerebeingchangedandthereforereportableunder10CFR50.73(a)(2)(i).NRCFORMSSSA(983)'*U.S.GPO:19860624538/455 oCFore38oA(883(LICENSEENTREPORT(LER)TEXTCONTINUANU.S.NUCLEARREGULATORYCOMMISSIONAPPROVEOOMBNO.3150M(04EXPIRES:8/31/88ACILITYNAME(11OOCKETNUMBER(21LERNUMBER(BIYEARNS?:SEOVENTIAL'r8REVISIONNSNUMBER'iNSNUMBERPAGE(3)D.C.CookNuclearPlant,Unit2TEXT///'/Roro<<oco/4'////rorLIrro//I/orN//VRC%%dr(II38843/(17)osooo31688-0090003oF03Theexistenceofthedirectpathwayfromthecontainmentatmosphereforthetwotofiveminuteswhiletheparticulatefiltersandiodinecartridgeswerebeingchangedwouldnotsignificantlyincreasetheoffsitedoefromafuelhandlingaccidentwithinthecontainmentbasedonthefollowingfacts;(1)theshortdurationthattheopenpathwayexisted,(2)therewasalwaysaradiationprotectiontechnicianpresentthatimmediatelycouldhaveisolatedthepathway,(3)thesmallsizeofthepenetration(oneinchdiameterpipe)and(4)similarevolutionssuchasopeningamanualisolationvalveincontainmentatmospheresamplinglineonanintermittentbasisunderadministrativecontroltoobtaingrabsamplesispermittedbytheTechnicalSpecifications.Thusthehealthandsafetyofthepublicwerenotaffectedbythisevent.CorrectiveActionWhenthisconditionwasidentifiedcorealterationandfuelmovementforthecurrentUnit2,refuelingoutagehadceased.Aspreventiveactionprocedure"'"12THP6010RAD.124hasbeenrevisedtoincludestepstoisolatethesampleinletlinepriortochangingparticulatefiltersandiodinecartridges.FailedComonent'dentificationNocomponentfailureswereidentifiedduringthisevent.PreviousSimilarEventsNone.NRCFORMSSEA(84LII*U.S.GPO:10880.824538/455 IndianaMichiganPowerCompanyCookNuclearPlant~P.O.Box458Bridgman,Ml49106~6164655901Z2NEMAR$4MCMCMHPCbVGRSeptember28,1988UnitedStatesNuclearRegulatoryCommissionDocumentControlDeskWashington,D.C.20555OperatingLicenseDPR-58DocketNo.50-316DocumentControlManager:Inaccordancewiththecriteriaestablishedby10CFR50.73entitledLicenseeEventReortinSstem,thefollowingreportisbeingsubmitted:88-009-00Sincerely,PlantManagerWGS:clwAttachmentcc:D.H.Williams,Jr.A.B.Davis,RegionIIIM.P.AlexichP.A.BarrettJ.E.BorggrenR.F.KroegerNRCResidentInspectorJ.F.Stang,NRCR.C.CallenG.Charnoff,Esq.DottieSherman,ANILibraryD.HahnINPOPNSRCA.A.BlindS.J.Brewer/B.P.Lauzau.}} | | DISTRIBUTION CODE: ZE22D COPIES RECEIVED:LTR ENCL J SIZE: |
| | TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc. |
| | NOTES: |
| | RECIPIENT COPIES RECIPIENT COPIES ZD CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 STANGzJ 1 1 INTERNAL: ACRS MICHELSON 1 - 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 . |
| | NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB 9H 1 1 8D 9H'RR/DEST/PSB 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 ll 1 1 NRR/DLPQ/QAB 10 1 1 NRR/DOEA/EAB NRR/DREP/RPB 10 NUDOCS-ABSTRACT RES TELFORD,J 1 |
| | 2 1 |
| | 1 1 |
| | 2 1 |
| | 1 REG FI |
| | ~SIR |
| | '2 NRR/DREP/RAB 10 S SIB 9A DEPY 1 |
| | 1 1 |
| | 1 1 |
| | 1 1 |
| | 1 RES/DSZR/EIB 1 1 RGN3 FILE 01 1 1 EXTERNAL 'G&G WILLIAMS S E 4 4 FORD BLDG HOY,A 1 1 H ST LOBBY WARD 1 1 LPDR 1 NRC PDR 1 1 NSZC HARRIS,J 1 1 NSIC MAYS,G 1 1 TOTAL NUMBER 'OF COPIES REQUIRED: LTTR 46 ENCL 45 |
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| | 0 |
| | ~ \ |
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| | NRC Form 388 U.S. NUCLEAR REOULATORY COMMISSION (94)3 I APPROVED OMB NO. 31504104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMBER (2) PAGE 3 D. C. Cook Nuclear Plant, Unit 2 o s o o o 316 ioF03 Non-compliance With Technical Specifications Due to Open Pathway Prom Containment During Core Alteration'and Fuel Movement EVENT DATE (5I LER NUMBER (8) REPORT DATE (7) 01'HER FACILITIES INVOLVED (8) |
| | SEOUENTIAL REVS~ |
| | MONTH OAY YEAR YEAR 8: : |
| | : NUMBER MONTH OAY YEAR FACILITYNAMES DOCKET NUMBER(S) |
| | NUMBER D. C. Cook, Unit 1 o so o o315 0 29 88 88 0 0 9 0 0 0 9 2 8 8 8 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THE AEOUIAEMENTS OF 10 CFR (): /C/seek one or morr of rhe fo/fovf/np/ (11 OPERATINQ MODE (8) 20.402(bl 20.405(c) 50.73(e I (2) I Iv) 73.71(b) |
| | POWER 20.405(e I (1)(i) SOW(cl(I) 50.73(e) l2)(v) 73.71(cl LEVEL (10) 20.405(e)(1) (ii) 50.38(cl(2) 50.73(e) (2)(vil) DTHER /specify /n 4osrrect orfovrend /n Trrrt, f/RC Form 20.405( ~ l(1) illl) X SODS(el(2)ID 50.73(el(2)(villi(BI 50.73(el(2) (vill)(A) 366A) 20AOS (I I (1)(iv) 50.73( ~ l(2)(Q) 20.405(el(1)(vl 50.73(e) 12) IIIII 50.73 le) (21(e) |
| | LICENSEE CONTACT FOR THIS LER (12) |
| | NAME TELFPHONE NUMBER J. T. Wojcik Technical Physical Sciences AREA CODE Superintendent 6 16 465 -59 01 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
| | MAHUFAC REPD1 TR8 LR',)~MINIg;, MANUFAC. EPORTABLE CAUSE SYSTEM COMPONENT TURER CAUSE SYSTEM COMPONENT TURER TO NPADS I!&<NI |
| | ~M SUPPLEMENTAL RFPORT EXPECTED (14) MONTH OAY YEAR EXPECTED SU 8 MISSION DATE (15) |
| | YE5/lf yrs, complerr EXPECTED Sl/Bet/$ $ /DIV DATE/ NO AssTAAcT /Limit to /coo sprees, fr., rppror/merely fifteen slnple.specs typrvr/Iten lines/ (18) |
| | On August 29, 1988, it'as identified that for short periods of time (typically two to five minutes) while a radiation protection technician was changing out the particulate filters and iodine cartridges for the lower containment monitors, an open pathway from the containment atmosphere to the auxiliary building was established. The change out is performed at least once per day, and the same procedure has been followed since these monitors were installed on Unit 1 and Unit 2 in 1985. The condition is unique to the containment integrity requirements during core alterations due to the fact that there is no automatic containment isolation signal operable |
| | .for the'radiation monitoring system during this mode of operation. |
| | The cause of this event was an inadequate procedure which allowed the particulate filters and iodine cartridges to be changed during core alteration conditions without first establishing positive containment isolation. |
| | When this condition was identified core alteration and fuel movement for the current Unit 2 refueling outage had ceased. As preventive action, procedure r:"12 THP 6010 RADR124 has been revised to include steps to isolate the sample inlet prior to changing particulate filters and iodine cartridges. |
| | Cgl OQsr Qos,7 PDR i'IDQ:;IF. 0,/000."3) r3 j )r7pr3 7 |
| | S r/)qt) |
| | NRC Form 388 (94)3) |
| | |
| | )SNC Form 38M U.S. NUCLEAR REGULATORY COMMISSION (94)3) |
| | LICENSEE NT REPORT (LER) TEXT CONTINUA N APPROVEO OMB NO. 3(SBM(84 EXPIRES: 8/31/88 ACILITYNAME (11 COCK ET NUMBE R (2) LER NUMBER (6) PAGE (3) |
| | YEAR SEGVENTIAL REVISION NVMSER NUMBER D. C. Cook Nuclear Plant, Unit 2 0 6 0 0 0 3 ] 8 0 0 0 2 OF 0 3 8 0 0 9 TEXT //P/INYs EPscs /4 /sES)sI/, //Ss /dE/4/M////IC Fem/38849/ (17) |
| | Conditions Prior to Occurrence Unit 1 at 90 percent reactor thermal power, Unit 2 refueling.. |
| | Descri tion of Event On August 29, 1988, during a drawing review for a refueling integrity procedure revision, it was identified that for short periods of time (typically two to five minutes) while a radiation protection technician was changing out the particulate filters and iodine cartridges for the lower containment radiation monitors (ERS-1300 and ERS-1400 in Unit 1 and ERS-2300 and ERS-2400 in Unit |
| | : 2) (EIIS/IL-MON) an open pathway from the containment atmosphere to the auxiliary building was established. The particulate filter and iodine cartridge change out was performed per an approved procedure with the radiation protection technician present through the entire change out procedure. The change out is performed at least once per day,, and the same procedure has been followed since these monitors were installed on Unit 1 and on Unit 2 in 1985. The condition is unique to the containment integrity requirements during core alterations due- to the fact that there is no automatic containment isolation signal operable for the radiation monitoring system during this mode of operation. Since this condition was not recognized during previous refueling outages, the open pathway may have existed during previous core alterations or movement it is very likely that of irradiated fuel within the containment building. |
| | No inoperable structures, components, or systems contributed to the significance of this event. |
| | Cause of Event This event was caused by the procedural inadequacy which allowed the particulate filters and iodine cartridges to be changed during core alteration conditions without first establishing positive containment isolation. |
| | Anal sis of the Event This event is considered a failure to comply with Technical Specification 3.9.4 Action Statement requirements in that core alterations or movement of irradiated fuel within the containment building were not suspended while the particulate filters and iodine cartridges were being changed and therefore reportable under 10 CFR 50.73(a)(2)(i). |
| | NRC FORM SSSA '*U.S.GPO:1986 0 624 538/455 (983) |
| | |
| | oC Fore 38oA U.S. NUCLEAR REGULATORY COMMISSION (883( |
| | LICENSEE NT REPORT (LER) TEXT CONTINUA N APPROVEO OMB NO. 3150M(04 EXPIRES: 8/31/88 ACILITYNAME (11 OOCKET NUMBER (21 LER NUMBER (BI PAGE (3) |
| | YEAR NS?: SEOVENTIAL 'r 8 REVISION NS NUMBER 'iNS NUMBER D. C. Cook Nuclear Plant, Unit 2 o s o o o 3 1 6 8 8 0 0 9 0 0 0 3 oF 0 3 TEXT ///'/Roro <<oco /4 '////rorL Irro //I/orN//VRC %%dr(II 38843 / (17) |
| | The existence of the direct pathway from the containment atmosphere for the two to five minutes while the particulate filters and iodine cartridges were being changed would not significantly increase the offsite doe from a fuel handling accident within the containment based on the following facts; (1) the short duration that the open pathway existed, (2) there was always a radiation protection technician present that immediately could have isolated the pathway, (3) the small size of the penetration (one inch diameter pipe) and (4) similar evolutions such as opening a manual isolation valve in containment atmosphere sampling line on an intermittent basis under administrative control to obtain grab samples is permitted by the Technical Specifications. Thus the health and safety of the public were not affected by this event. |
| | Corrective Action When this condition was identified core alteration and fuel movement for the current Unit 2,refueling outage had ceased. As preventive action procedure |
| | "'"12 THP 6010 RAD.124 has been revised to include steps to isolate the sample inlet line prior to changing particulate filters and iodine cartridges. |
| | Failed Com onent'dentification No component failures were identified during this event. |
| | Previous Similar Events None. |
| | NRC FORM SSEA *U.S.GPO:1088 0.824 538/455 (84LII |
| | |
| | Indiana Michigan Power Company Cook Nuclear Plant P.O. Box 458 |
| | ~ |
| | ~ |
| | Bridgman, Ml 49106 616 465 5901 Z |
| | 2NEMAR$4 MCMCMH PCbVGR September 28, 1988 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Operating License DPR-58 Docket No. 50-316 Document Control Manager: |
| | In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ortin S stem, the following report is being submitted: |
| | 88-009-00 Sincerely, Plant Manager WGS:clw Attachment cc: D. H. Williams, Jr. |
| | A. B. Davis, Region M. P. Alexich III P. A. Barrett J. E. Borggren R. F. Kroeger NRC Resident Inspector J. F. Stang, NRC R. C. Callen G. Charnoff, Esq. |
| | Dottie Sherman, ANI Library D. Hahn INPO PNSRC A. A. Blind S. J. Brewer/B. P. Lauzau.}} |
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LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
ML17335A5171999-02-11011 February 1999
LER 99-002-00:on 990112,determined That RCS Pressurizer PORVs Had Not Been Tested,Per Ts.Caused by Inadequate Scheduling Controls Allowing Personnel Error.Surveillance Procedure Was Completed & Updated LER Will Be Submitted
ML17335A5141999-02-10010 February 1999
LER 99-001-00:on 990106,noted That GE Hfa Relays Installed in EDGs May Not Meet Seismic Qualification.Caused by Operating Experience Info Incorrectly Dispositioned in 1985. Updated LER Will Be Submitted by 990405
ML17335A5011999-02-0101 February 1999
LER 98-060-00:on 981231,identified That Rt Sys Response Time Testing Did Not Comply with TS Definition.Caused by Inadequate Procedures.Corrective Actions Will Be Developed & Update to LER Will Be Submitted by 990415.With 990201 Ltr
ML17335A4951999-01-29029 January 1999
LER 98-059-00:on 981230,interim LER -single Failure in Containment Spray Sys Could Result in Containment Spray Ph Outside Design Occurred.Investigation Into Condition Continuing.Update Will Be Submitted by 990514 Ltr
ML17335A4961999-01-27027 January 1999
LER 98-057-00:on 981228,discovered That AFW Valves Were Not Tested IAW Inservice Testing Program.Caused by Failure to Recognize Design Bases Features Re Afws by Personnel. Updated LER Will Be Submittted by 990415.With 990127 Ltr
ML17335A4921999-01-19019 January 1999
LER 98-052-01:on 981128,no Analysis for NSR Sc Manual Loader for Tdafwp Could Be Found in Original Design.Cause Due to All Failure Modes Not Considered When Compressed Air Sys Originally Designed.Performed Review of Components
ML17335A4721999-01-0606 January 1999
LER 98-055-00:on 981207,potential for Condition Outside of Design Bases for Rod Control Sys Was Noted.Caused by Calibration Error Coupled with Single Rod Failure.Condition Rept Investigation Is Ongoing
ML17335A4691999-01-0606 January 1999
LER 98-056-00:on 981211,hot Leg Nozzle Gaps Resulted in Plant Being in Unanalyzed Condition.Analyses Are Being Performed by W to Resolve Problem.Updated LER Will Be Submitted by 990211.With 990106 Ltr
ML17335A4661999-01-0505 January 1999
LER 98-049-00:on 981020,emergency Boron Injection Flow Path Was Inoperable.Caused by Original Design Deficiency. Engineering Evaluation of Event Is Continuing
ML17335A4631999-01-0404 January 1999
LER 98-054-00:on 981202,discovered That at Least One MSSV Had Not Been Reset as Required by Ts.Engineering Is Continuing Review of Extent of Condition for Event.Updated LER Will Be Submitted by 990129.With 990104 Ltr
ML17335A4481998-12-30030 December 1998
LER 98-053-00:on 981130,discovered Use of Inoperable Substitute Subcooling Margin Monitor.Caused by Condition Existing Since Installation of Plant Process Computer in 1992.Updated LER Will Be Submitted.With 981230 Ltr
ML17335A4581998-12-28028 December 1998
LER 98-052-00:on 981128,turbine Driven AFW Pump Speed Controller Failure Mode Occurred.Caused Because Not All Failure Modes Were Considered When Compressed Air Sys Was Originally Designed.Verified Current Design Change Process
ML17335A4281998-12-22022 December 1998
LER 98-051-00:on 981122,reactor Trip Signal from Manual Safety Injection Not Verified as Required by TS Surveillance,Was Discovered.Maintenance Currently Evaluating Significance & Cause of Event
ML17335A4111998-12-17017 December 1998
LER 98-047-00:on 981117,potential for Increase Leakage from Reactor Coolant Pump Seals Was Identified.Util Is Working with W to Resolve Issue.Current Expectations Are to Submit Update to LER by 990215.With 981217 Ltr
ML17335A4141998-12-16016 December 1998
LER 98-058-00:on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122
ML17335A4181998-12-16016 December 1998
LER 98-050-00:on 980814,ancillary Equipment Installed in Ice Condenser Was Not Designed to Withstand Design Basis Accident/Earthquake Loads.Caused by Lack of Established Design Criteria.Developed Design Criteria
ML17335A3871998-12-11011 December 1998
LER 98-031-01:on 980610,potential Common Mode Failure of RHR Pumps Were Noted.Caused by Inaccurate Values.Accurate Miniflow Numbers Have Been Determined by Flow Testing
ML17335A3821998-12-0808 December 1998
LER 98-039-01 Re EOP Step Conflicts with Small Break LOCA Analysis.Ler 98-039-00 Has Been Canceled.With 981208 Ltr
ML17335A3781998-12-0707 December 1998
LER 98-007-00:on 981106,high Energy Line Break Effects in Auxiliary FW Sys Was Noted.Cause of Event Is Under Investigation & Will Be Completed by 990220.Updated LER Will Be Submitted by 990310.With 981207 Ltr
ML17335A3771998-12-0303 December 1998
LER 98-046-00:on 981103,determined That Afs Was Unable to Meet Design Flow Requirements During Special Test.Caused by Failure to Consider All Aspects of Sys Operation in Design of Suction Basket Strainers.Sys Will Be Redesigned
ML17335A3741998-12-0202 December 1998
LER 97-011-02:on 970822,operation Was Noted Outside Design Bases for ECCS & CSP for Switchover to Recirculation Sump Suction.Caused by Ineffective Change Mgt.Revised Procedure for Switchover 01(02) Ohp 4023.ES-1.3
1999-09-17
[Table view]
Category:RO)
MONTHYEARML17335A5641999-10-18018 October 1999
LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr
ML17335A5531999-10-0707 October 1999
LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented
ML17326A1291999-09-17017 September 1999
LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
ML17326A1121999-08-27027 August 1999
LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
ML17326A1011999-08-26026 August 1999
LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
ML17326A0911999-08-16016 August 1999
LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
ML17326A0771999-08-0404 August 1999
LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830
ML17326A0741999-07-29029 July 1999
LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
ML17326A0661999-07-26026 July 1999
LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr
ML17326A0651999-07-22022 July 1999
LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis
ML17326A0491999-07-13013 July 1999
LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr
ML17326A0331999-07-0101 July 1999
LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
ML17326A0151999-06-18018 June 1999
LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified
ML17325B6311999-06-0101 June 1999
LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions
ML17325B6421999-06-0101 June 1999
LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
ML17325B6351999-05-28028 May 1999
LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
ML17335A5171999-02-11011 February 1999
LER 99-002-00:on 990112,determined That RCS Pressurizer PORVs Had Not Been Tested,Per Ts.Caused by Inadequate Scheduling Controls Allowing Personnel Error.Surveillance Procedure Was Completed & Updated LER Will Be Submitted
ML17335A5141999-02-10010 February 1999
LER 99-001-00:on 990106,noted That GE Hfa Relays Installed in EDGs May Not Meet Seismic Qualification.Caused by Operating Experience Info Incorrectly Dispositioned in 1985. Updated LER Will Be Submitted by 990405
ML17335A5011999-02-0101 February 1999
LER 98-060-00:on 981231,identified That Rt Sys Response Time Testing Did Not Comply with TS Definition.Caused by Inadequate Procedures.Corrective Actions Will Be Developed & Update to LER Will Be Submitted by 990415.With 990201 Ltr
ML17335A4951999-01-29029 January 1999
LER 98-059-00:on 981230,interim LER -single Failure in Containment Spray Sys Could Result in Containment Spray Ph Outside Design Occurred.Investigation Into Condition Continuing.Update Will Be Submitted by 990514 Ltr
ML17335A4961999-01-27027 January 1999
LER 98-057-00:on 981228,discovered That AFW Valves Were Not Tested IAW Inservice Testing Program.Caused by Failure to Recognize Design Bases Features Re Afws by Personnel. Updated LER Will Be Submittted by 990415.With 990127 Ltr
ML17335A4921999-01-19019 January 1999
LER 98-052-01:on 981128,no Analysis for NSR Sc Manual Loader for Tdafwp Could Be Found in Original Design.Cause Due to All Failure Modes Not Considered When Compressed Air Sys Originally Designed.Performed Review of Components
ML17335A4721999-01-0606 January 1999
LER 98-055-00:on 981207,potential for Condition Outside of Design Bases for Rod Control Sys Was Noted.Caused by Calibration Error Coupled with Single Rod Failure.Condition Rept Investigation Is Ongoing
ML17335A4691999-01-0606 January 1999
LER 98-056-00:on 981211,hot Leg Nozzle Gaps Resulted in Plant Being in Unanalyzed Condition.Analyses Are Being Performed by W to Resolve Problem.Updated LER Will Be Submitted by 990211.With 990106 Ltr
ML17335A4661999-01-0505 January 1999
LER 98-049-00:on 981020,emergency Boron Injection Flow Path Was Inoperable.Caused by Original Design Deficiency. Engineering Evaluation of Event Is Continuing
ML17335A4631999-01-0404 January 1999
LER 98-054-00:on 981202,discovered That at Least One MSSV Had Not Been Reset as Required by Ts.Engineering Is Continuing Review of Extent of Condition for Event.Updated LER Will Be Submitted by 990129.With 990104 Ltr
ML17335A4481998-12-30030 December 1998
LER 98-053-00:on 981130,discovered Use of Inoperable Substitute Subcooling Margin Monitor.Caused by Condition Existing Since Installation of Plant Process Computer in 1992.Updated LER Will Be Submitted.With 981230 Ltr
ML17335A4581998-12-28028 December 1998
LER 98-052-00:on 981128,turbine Driven AFW Pump Speed Controller Failure Mode Occurred.Caused Because Not All Failure Modes Were Considered When Compressed Air Sys Was Originally Designed.Verified Current Design Change Process
ML17335A4281998-12-22022 December 1998
LER 98-051-00:on 981122,reactor Trip Signal from Manual Safety Injection Not Verified as Required by TS Surveillance,Was Discovered.Maintenance Currently Evaluating Significance & Cause of Event
ML17335A4111998-12-17017 December 1998
LER 98-047-00:on 981117,potential for Increase Leakage from Reactor Coolant Pump Seals Was Identified.Util Is Working with W to Resolve Issue.Current Expectations Are to Submit Update to LER by 990215.With 981217 Ltr
ML17335A4141998-12-16016 December 1998
LER 98-058-00:on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122
ML17335A4181998-12-16016 December 1998
LER 98-050-00:on 980814,ancillary Equipment Installed in Ice Condenser Was Not Designed to Withstand Design Basis Accident/Earthquake Loads.Caused by Lack of Established Design Criteria.Developed Design Criteria
ML17335A3871998-12-11011 December 1998
LER 98-031-01:on 980610,potential Common Mode Failure of RHR Pumps Were Noted.Caused by Inaccurate Values.Accurate Miniflow Numbers Have Been Determined by Flow Testing
ML17335A3821998-12-0808 December 1998
LER 98-039-01 Re EOP Step Conflicts with Small Break LOCA Analysis.Ler 98-039-00 Has Been Canceled.With 981208 Ltr
ML17335A3781998-12-0707 December 1998
LER 98-007-00:on 981106,high Energy Line Break Effects in Auxiliary FW Sys Was Noted.Cause of Event Is Under Investigation & Will Be Completed by 990220.Updated LER Will Be Submitted by 990310.With 981207 Ltr
ML17335A3771998-12-0303 December 1998
LER 98-046-00:on 981103,determined That Afs Was Unable to Meet Design Flow Requirements During Special Test.Caused by Failure to Consider All Aspects of Sys Operation in Design of Suction Basket Strainers.Sys Will Be Redesigned
ML17335A3741998-12-0202 December 1998
LER 97-011-02:on 970822,operation Was Noted Outside Design Bases for ECCS & CSP for Switchover to Recirculation Sump Suction.Caused by Ineffective Change Mgt.Revised Procedure for Switchover 01(02) Ohp 4023.ES-1.3
1999-09-17
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17335A5641999-10-18018 October 1999
LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr
ML17335A5531999-10-0707 October 1999
LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented
ML17335A5631999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 1.With 991012 Ltr
ML17335A5621999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 2.With 991012 Ltr
ML17335A5481999-09-30030 September 1999
Non-proprietary DC Cook Nuclear Plant Units 1 & 2 Mods to Containment Sys W SE (Secl 99-076,Rev 3).
ML17335A5451999-09-28028 September 1999
Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios.
ML17326A1291999-09-17017 September 1999
LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
ML17326A1481999-09-17017 September 1999
Independent Review of Control Rod Insertion Following Cold Leg Lbloca,Dc Cook,Units 1 & 2.
ML17326A1211999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 2.With 990915 Ltr
ML17326A1201999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 1.With 990915 Ltr
ML17326A1121999-08-27027 August 1999
LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
ML17326A1011999-08-26026 August 1999
LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
ML17326A0911999-08-16016 August 1999
LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
ML17326A0771999-08-0404 August 1999
LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830
ML17335A5461999-08-0202 August 1999
Rev 0 to Evaluation of Cook Recirculation Sump Level for Reduced Pump Flow Rates.
ML17326A0871999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Unit 1.With 990812 Ltr
ML17326A0861999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Units 2.With 990812 Ltr
ML17326A0741999-07-29029 July 1999
LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
ML17326A0661999-07-26026 July 1999
LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr
ML17326A0651999-07-22022 July 1999
LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis
ML17326A0491999-07-13013 July 1999
LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr
ML17326A0331999-07-0101 July 1999
LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
ML17326A0511999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 2.With 990709 Ltr
ML17326A0501999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 1.With 990709 Ltr
ML17326A0151999-06-18018 June 1999
LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified
ML17325B6421999-06-0101 June 1999
LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
ML17325B6311999-06-0101 June 1999
LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions
ML17326A0061999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Dcp.With 990609 Ltr
ML17326A0071999-05-31031 May 1999
Monthly Operating Rept for May 1999 for DC Cook Nuclear Plant,Unit 2.With 990609 Ltr
ML17325B6351999-05-28028 May 1999
LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17335A5301999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 1.With 990508 Ltr
ML17335A5291999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 2.With 990508 Ltr
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5491999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant Unit 2.With 990408 Ltr
ML17325B5441999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant,Unit 1.With 990408 Ltr
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B5671999-03-0202 March 1999
Summary of Unit 1 Steam Generator Layup Chemistry from 980101 to 990218.
ML17325B4631999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Power Station,Unit 2.With 990308 Ltr
ML17325B4621999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Plant,Unit 1.With 990308 Ltr
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
1999-09-30
[Table view] |
Text
gC CELZRA BUTlON DZSTRZBUTZOt'EN DEMONS. TION SYFI'EM REGULA ZNEORNA ZON (RZDS)
QACCESSZON NBR:8810070042 DOC.DATE: 88/09/28 NOTARZZED: NO DOCKET FACIL:5G-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana & 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME AUTHOR AFFILIATION WOJCIKzJ.T. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele.
SMZTHgW.G. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 88-009-00:on 880829,non-compliance w/Tech Specs due to open pathway from containment during core alteration.
W/8 ltr.
DISTRIBUTION CODE: ZE22D COPIES RECEIVED:LTR ENCL J SIZE:
TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ZD CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 STANGzJ 1 1 INTERNAL: ACRS MICHELSON 1 - 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 .
NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB 9H 1 1 8D 9H'RR/DEST/PSB 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 ll 1 1 NRR/DLPQ/QAB 10 1 1 NRR/DOEA/EAB NRR/DREP/RPB 10 NUDOCS-ABSTRACT RES TELFORD,J 1
2 1
1 1
2 1
1 REG FI
~SIR
'2 NRR/DREP/RAB 10 S SIB 9A DEPY 1
1 1
1 1
1 1
1 RES/DSZR/EIB 1 1 RGN3 FILE 01 1 1 EXTERNAL 'G&G WILLIAMS S E 4 4 FORD BLDG HOY,A 1 1 H ST LOBBY WARD 1 1 LPDR 1 NRC PDR 1 1 NSZC HARRIS,J 1 1 NSIC MAYS,G 1 1 TOTAL NUMBER 'OF COPIES REQUIRED: LTTR 46 ENCL 45
0
~ \
NRC Form 388 U.S. NUCLEAR REOULATORY COMMISSION (94)3 I APPROVED OMB NO. 31504104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMBER (2) PAGE 3 D. C. Cook Nuclear Plant, Unit 2 o s o o o 316 ioF03 Non-compliance With Technical Specifications Due to Open Pathway Prom Containment During Core Alteration'and Fuel Movement EVENT DATE (5I LER NUMBER (8) REPORT DATE (7) 01'HER FACILITIES INVOLVED (8)
SEOUENTIAL REVS~
MONTH OAY YEAR YEAR 8: :
- NUMBER MONTH OAY YEAR FACILITYNAMES DOCKET NUMBER(S)
NUMBER D. C. Cook, Unit 1 o so o o315 0 29 88 88 0 0 9 0 0 0 9 2 8 8 8 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THE AEOUIAEMENTS OF 10 CFR (): /C/seek one or morr of rhe fo/fovf/np/ (11 OPERATINQ MODE (8) 20.402(bl 20.405(c) 50.73(e I (2) I Iv) 73.71(b)
POWER 20.405(e I (1)(i) SOW(cl(I) 50.73(e) l2)(v) 73.71(cl LEVEL (10) 20.405(e)(1) (ii) 50.38(cl(2) 50.73(e) (2)(vil) DTHER /specify /n 4osrrect orfovrend /n Trrrt, f/RC Form 20.405( ~ l(1) illl) X SODS(el(2)ID 50.73(el(2)(villi(BI 50.73(el(2) (vill)(A) 366A) 20AOS (I I (1)(iv) 50.73( ~ l(2)(Q) 20.405(el(1)(vl 50.73(e) 12) IIIII 50.73 le) (21(e)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELFPHONE NUMBER J. T. Wojcik Technical Physical Sciences AREA CODE Superintendent 6 16 465 -59 01 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
MAHUFAC REPD1 TR8 LR',)~MINIg;, MANUFAC. EPORTABLE CAUSE SYSTEM COMPONENT TURER CAUSE SYSTEM COMPONENT TURER TO NPADS I!&<NI
~M SUPPLEMENTAL RFPORT EXPECTED (14) MONTH OAY YEAR EXPECTED SU 8 MISSION DATE (15)
YE5/lf yrs, complerr EXPECTED Sl/Bet/$ $ /DIV DATE/ NO AssTAAcT /Limit to /coo sprees, fr., rppror/merely fifteen slnple.specs typrvr/Iten lines/ (18)
On August 29, 1988, it'as identified that for short periods of time (typically two to five minutes) while a radiation protection technician was changing out the particulate filters and iodine cartridges for the lower containment monitors, an open pathway from the containment atmosphere to the auxiliary building was established. The change out is performed at least once per day, and the same procedure has been followed since these monitors were installed on Unit 1 and Unit 2 in 1985. The condition is unique to the containment integrity requirements during core alterations due to the fact that there is no automatic containment isolation signal operable
.for the'radiation monitoring system during this mode of operation.
The cause of this event was an inadequate procedure which allowed the particulate filters and iodine cartridges to be changed during core alteration conditions without first establishing positive containment isolation.
When this condition was identified core alteration and fuel movement for the current Unit 2 refueling outage had ceased. As preventive action, procedure r:"12 THP 6010 RADR124 has been revised to include steps to isolate the sample inlet prior to changing particulate filters and iodine cartridges.
Cgl OQsr Qos,7 PDR i'IDQ:;IF. 0,/000."3) r3 j )r7pr3 7
S r/)qt)
NRC Form 388 (94)3)
)SNC Form 38M U.S. NUCLEAR REGULATORY COMMISSION (94)3)
LICENSEE NT REPORT (LER) TEXT CONTINUA N APPROVEO OMB NO. 3(SBM(84 EXPIRES: 8/31/88 ACILITYNAME (11 COCK ET NUMBE R (2) LER NUMBER (6) PAGE (3)
YEAR SEGVENTIAL REVISION NVMSER NUMBER D. C. Cook Nuclear Plant, Unit 2 0 6 0 0 0 3 ] 8 0 0 0 2 OF 0 3 8 0 0 9 TEXT //P/INYs EPscs /4 /sES)sI/, //Ss /dE/4/M////IC Fem/38849/ (17)
Conditions Prior to Occurrence Unit 1 at 90 percent reactor thermal power, Unit 2 refueling..
Descri tion of Event On August 29, 1988, during a drawing review for a refueling integrity procedure revision, it was identified that for short periods of time (typically two to five minutes) while a radiation protection technician was changing out the particulate filters and iodine cartridges for the lower containment radiation monitors (ERS-1300 and ERS-1400 in Unit 1 and ERS-2300 and ERS-2400 in Unit
- 2) (EIIS/IL-MON) an open pathway from the containment atmosphere to the auxiliary building was established. The particulate filter and iodine cartridge change out was performed per an approved procedure with the radiation protection technician present through the entire change out procedure. The change out is performed at least once per day,, and the same procedure has been followed since these monitors were installed on Unit 1 and on Unit 2 in 1985. The condition is unique to the containment integrity requirements during core alterations due- to the fact that there is no automatic containment isolation signal operable for the radiation monitoring system during this mode of operation. Since this condition was not recognized during previous refueling outages, the open pathway may have existed during previous core alterations or movement it is very likely that of irradiated fuel within the containment building.
No inoperable structures, components, or systems contributed to the significance of this event.
Cause of Event This event was caused by the procedural inadequacy which allowed the particulate filters and iodine cartridges to be changed during core alteration conditions without first establishing positive containment isolation.
Anal sis of the Event This event is considered a failure to comply with Technical Specification 3.9.4 Action Statement requirements in that core alterations or movement of irradiated fuel within the containment building were not suspended while the particulate filters and iodine cartridges were being changed and therefore reportable under 10 CFR 50.73(a)(2)(i).
NRC FORM SSSA '*U.S.GPO:1986 0 624 538/455 (983)
oC Fore 38oA U.S. NUCLEAR REGULATORY COMMISSION (883(
LICENSEE NT REPORT (LER) TEXT CONTINUA N APPROVEO OMB NO. 3150M(04 EXPIRES: 8/31/88 ACILITYNAME (11 OOCKET NUMBER (21 LER NUMBER (BI PAGE (3)
YEAR NS?: SEOVENTIAL 'r 8 REVISION NS NUMBER 'iNS NUMBER D. C. Cook Nuclear Plant, Unit 2 o s o o o 3 1 6 8 8 0 0 9 0 0 0 3 oF 0 3 TEXT ///'/Roro <<oco /4 '////rorL Irro //I/orN//VRC %%dr(II 38843 / (17)
The existence of the direct pathway from the containment atmosphere for the two to five minutes while the particulate filters and iodine cartridges were being changed would not significantly increase the offsite doe from a fuel handling accident within the containment based on the following facts; (1) the short duration that the open pathway existed, (2) there was always a radiation protection technician present that immediately could have isolated the pathway, (3) the small size of the penetration (one inch diameter pipe) and (4) similar evolutions such as opening a manual isolation valve in containment atmosphere sampling line on an intermittent basis under administrative control to obtain grab samples is permitted by the Technical Specifications. Thus the health and safety of the public were not affected by this event.
Corrective Action When this condition was identified core alteration and fuel movement for the current Unit 2,refueling outage had ceased. As preventive action procedure
"'"12 THP 6010 RAD.124 has been revised to include steps to isolate the sample inlet line prior to changing particulate filters and iodine cartridges.
Failed Com onent'dentification No component failures were identified during this event.
Previous Similar Events None.
NRC FORM SSEA *U.S.GPO:1088 0.824 538/455 (84LII
Indiana Michigan Power Company Cook Nuclear Plant P.O. Box 458
~
~
Bridgman, Ml 49106 616 465 5901 Z
2NEMAR$4 MCMCMH PCbVGR September 28, 1988 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Operating License DPR-58 Docket No. 50-316 Document Control Manager:
In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ortin S stem, the following report is being submitted:
88-009-00 Sincerely, Plant Manager WGS:clw Attachment cc: D. H. Williams, Jr.
A. B. Davis, Region M. P. Alexich III P. A. Barrett J. E. Borggren R. F. Kroeger NRC Resident Inspector J. F. Stang, NRC R. C. Callen G. Charnoff, Esq.
Dottie Sherman, ANI Library D. Hahn INPO PNSRC A. A. Blind S. J. Brewer/B. P. Lauzau.
