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| {{#Wiki_filter:CcACCELERATE DOCUMENTDISTRIBUTION SYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9406100001 DOC.DATE: | | {{#Wiki_filter:Cc ACCELERATE DOCUMENT DISTRIBUTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9406100001 DOC.DATE: 94/05/31 NOTARIZED: |
| 94/05/31NOTARIZED: | | NO DOCKET FACIL:50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH.NAME AUTHOR AFFILIATION HODGE,W.M. |
| NODOCKETFACIL:50-316 DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION HODGE,W.M.
| | Indiana Michigan Power Co.(formerly Indiana&Michigan Ele BLIND,A.A. |
| IndianaMichiganPowerCo.(formerly Indiana&MichiganEleBLIND,A.A.
| | Indiana Michigan Power Co.(formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION |
| IndianaMichiganPowerCo.(formerly Indiana6MichiganEleRECIP.NAME RECIPIENT AFFILIATION
| |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| LER94-002-00:on 940430,fire watchtourwasomittedduetopersonnel error.Revisedpolicyforimplementing firewatchtour.W/940531 ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR ENCLSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTESDRECIPIENT IDCODE/NAME PD3-1PDINTERNAL:
| | LER 94-002-00:on 940430,fire watch tour was omitted due to personnel error.Revised policy for implementing fire watch tour.W/940531 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES D RECIPIENT ID CODE/NAME PD3-1 PD INTERNAL: AEOD/DSP/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB NRR/J3SSA/SPLB |
| AEOD/DSP/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB NRR/J3SSA/SPLB | | ~'EG FILE 02 RGN ILE 01 EXTERNAL EGGG BRYCE i J~H NRC PDR NSIC POOREiW COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1'1 1 RECIPIENT ID CODE/NAME HICKMAN,J AEOD/ROAB/DSP NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB L ST LOBBY WARD NSIC MURPHY,G.A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 D D D D NOTE TO ALL"RIDS" RECIPIENTS: |
| ~'EGFILE02RGNILE01EXTERNALEGGGBRYCEiJ~HNRCPDRNSICPOOREiWCOPIESLTTRENCL111111111111111111221'11RECIPIENT IDCODE/NAME HICKMAN,J AEOD/ROAB/DSP NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB LSTLOBBYWARDNSICMURPHY,G.A NUDOCSFULLTXTCOPIESLTTRENCL1122111111221111111111DDDDNOTETOALL"RIDS"RECIPIENTS: | | PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 26 D Indiana Michigan~Power Gontpany Cook Nuclear Plant One Cook Place Bridgrnan, Mi 49106 616 465 5901 May 31, 1994 United States Nuclear Regulatory Commission Document Control Desk Rockville, Maryland 20852 Operating Licenses DPR-74 Docket No.50-316 Document Control Manager: In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ort S stem the following report is being submitted: |
| PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.504-2065)
| | 94-002-00 Sincerely,.'.Blind Plant Manager/sb Attachment c'.B.Martin, Region III E.E.Fitzpatrick P.A.Barrett R.F.Kroeger M.A.Bailey-Ft.Wayne NRC Resident Inspector J.B.Hickman-NRC J.R.Padgett G.Charnoff, Esq.D.Hahn INPO S.J.Brewer 9406100001 940531 PDR ADOCK 05000316 S PDR NRC FORM 366 (5.92).S.NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO.3150.0104 EXPIRES 5/31/95 I LICENSEE EVENT REPORT (LER)(See reverse for required number of digits/characters for each block)ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REOUEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 77I4), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555400 I, AND TO THE PAPERWORK REDUCTlON PROJECT (3(504)104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACIUTY NAME (I)D.C.COOK NUCLEAR PLANT-UNIT 2 TITLE (4)FIRE WATCH TOUR OMITTED DUE TO PERSONNEL ERROR DOCKET NUMBER (2)05000 316 PAGE (3)1 OF 3 MONTH DAY YEAR EVENT DATE 5 LER NUMBER 6 SEOUENTIAL NUMBER REVISION NUMBER REPORT NUMBER 7 MONTH OAY FACIUTY NAME DOCKET NUMBER'05000 OTHER FACILITIES INVOLVED 8 04 30 94 94 002 00 05 31 94 FACIUTY NAME DOCKET NUMBER 05000 OPERATING MODE (9)POWER LEVEL (10)063 20.402(b)20.405(a)(1)(i)20.405(a)(1)(ii)20.405(a)(1)(iii)20.405(a)(1)(iv)20.405(c)50.36(c)(1)50.36(c)(2)50.73(a)(2)(i)50.73(a)(2)(ii)50.73(a)(2)(iv)50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A)50.73(a)(2)(viii)(B)73.71(b)73.71(c)OTHER (Speci ty in Abetract below and in Text, NRC Form 366A)NT TO THE REQUIREMENTS OF 10 CFR 5: Check one or m THIS REPORT IS SUBMITTED PURSUA ore 11 NAME 20.405(a)(1)(v)50.73(a)(2)(iii)LICENSEE CONTACT FOR THIS LER 12 50.73(a)(2)(x)TELEPHONE NUMBER Bndude Area Code)W.M.HODGE-PLANT PROTECTION SUPERINTENDENT 616-465-5901 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS CAUSE SYSTEM COMPONENT MANUFACTURER REPORfABLE To NPRDS SUPPLEMENTAL REPORT EXPECTED 14 YES (tt yea, complete EXPECTED SUBMISSION DATE)ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single.spaced typewritten lines)(16)EXP FCTE0 MONTH DAY YEAR SUBMISSION DATE (15)On 01<<21-94 at 1015,.Fire Door 2-DR-AUX344 for the 609'levation (elev.)of the Turbine (Tur.)Building (Bldg.)was declared inoperable (which rendered the CO, suppression system for Fire Zones 46A, 46B 46C and 46D inoperable). |
| TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEEDIFULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
| | Technical Specifications (TS)3.7.9.3 and 3.7.10 required Action items were established. |
| LTTR26ENCL26D IndianaMichigan~PowerGontpanyCookNuclearPlantOneCookPlaceBridgrnan, Mi491066164655901May31,1994UnitedStatesNuclearRegulatory Commission DocumentControlDeskRockville, Maryland20852Operating LicensesDPR-74DocketNo.50-316DocumentControlManager:Inaccordance withthecriteriaestablished by10CFR50.73entitledLicenseeEventReortSstemthefollowing reportisbeingsubmitted:
| | On 04-29>>94 at 2308 an hourly FW toured the above described area.A shift turnover occurred at 2315 in which the tour point was omitted from the newly created tour sheet.The TS (3.7.9.3 and 3.7.10)required tour di.d not occur again until recognized and questioned by FW personnel to the FW Supervisor on 04-30-94 at 0030.The FW Supervisor recognized that the TS 3.7.9.3 and 3.7.10 action statements were not being met and contacted FW personnel and had the tour point added to the tour.A tour of the area was conducted on 04-30-94 at 0037.The U-2 4Kv CO2 system for Fire Zones (FZ)46Ae 46Be 46C and 46D, and Fire Door 2-DR-AUX344 were inoperable without a hourly FW for 1 hour 26 minutes.The poli.cy for implementing fire watch tour sheets has been revised to require a review and then an independent review prior to use.This event was discussed and reviewed with the personnel involved.NRC FORM 366 (5.92) |
| 94-002-00 Sincerely, | | NRC FORM 36SA (669)FACIMTY NAME ())U.S.NUCLEAR REGULATORY CON(MISSION LICENSEE EVENT REPORT (LER)TEXT CONTIN UATION DOCKET NUMBER (2)APPROVED 0MB NO.3)50010E EXPIRES: 4/30)92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50A)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (F430), U.S.NUCLEAR REGULATORY COMMISSION. |
| .'.BlindPlantManager/sbAttachment c'.B.Martin,RegionIIIE.E.Fitzpatrick P.A.BarrettR.F.KroegerM.A.Bailey-Ft.WayneNRCResidentInspector J.B.Hickman-NRCJ.R.PadgettG.Charnoff, Esq.D.HahnINPOS.J.Brewer9406100001 940531PDRADOCK05000316SPDR NRCFORM366(5.92).S.NUCLEARREGULATORY COMMISSION APPROVEDBYOMBNO.3150.0104 EXPIRES5/31/95ILICENSEEEVENTREPORT(LER)(Seereverseforrequirednumberofdigits/characters foreachblock)ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTION REOUEST:50.0HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(MNBB77I4),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555400I,ANDTOTHEPAPERWORK REDUCTlON PROJECT(3(504)104), | |
| OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, DC20503.FACIUTYNAME(I)D.C.COOKNUCLEARPLANT-UNIT2TITLE(4)FIREWATCHTOUROMITTEDDUETOPERSONNEL ERRORDOCKETNUMBER(2)05000316PAGE(3)1OF3MONTHDAYYEAREVENTDATE5LERNUMBER6SEOUENTIAL NUMBERREVISIONNUMBERREPORTNUMBER7MONTHOAYFACIUTYNAMEDOCKETNUMBER'05000OTHERFACILITIES INVOLVED80430949400200053194FACIUTYNAMEDOCKETNUMBER05000OPERATING MODE(9)POWERLEVEL(10)06320.402(b) 20.405(a)
| |
| (1)(i)20.405(a) | |
| (1)(ii)20.405(a) | |
| (1)(iii)20.405(a) | |
| (1)(iv)20.405(c) 50.36(c)(1)50.36(c)(2)50.73(a)(2)(i)50.73(a)(2)(ii)50.73(a)(2)(iv)50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A)50.73(a)(2)(viii)(B)73.71(b)73.71(c)OTHER(SpecityinAbetractbelowandinText,NRCForm366A)NTTOTHEREQUIREMENTS OF10CFR5:CheckoneormTHISREPORTISSUBMITTED PURSUAore11NAME20.405(a) | |
| (1)(v)50.73(a)(2)(iii)LICENSEECONTACTFORTHISLER1250.73(a)(2)(x)TELEPHONE NUMBERBndudeAreaCode)W.M.HODGE-PLANTPROTECTION SUPERINTENDENT 616-465-5901 COMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRIBED INTHISREPORT13CAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TONPRDSCAUSESYSTEMCOMPONENT MANUFACTURER REPORfABLE ToNPRDSSUPPLEMENTAL REPORTEXPECTED14YES(ttyea,completeEXPECTEDSUBMISSION DATE)ABSTRACT(Limitto1400spaces,i.e.,approximately 15single.spacedtypewritten lines)(16)EXPFCTE0MONTHDAYYEARSUBMISSION DATE(15)On01<<21-94at1015,.Fire Door2-DR-AUX344 forthe609'levation (elev.)oftheTurbine(Tur.)Building(Bldg.)wasdeclaredinoperable (whichrenderedtheCO,suppression systemforFireZones46A,46B46Cand46Dinoperable). | |
| Technical Specifications (TS)3.7.9.3and3.7.10requiredActionitemswereestablished. | |
| On04-29>>94at2308anhourlyFWtouredtheabovedescribed area.Ashiftturnoveroccurredat2315inwhichthetourpointwasomittedfromthenewlycreatedtoursheet.TheTS(3.7.9.3and3.7.10)requiredtourdi.dnotoccuragainuntilrecognized andquestioned byFWpersonnel totheFWSupervisor on04-30-94at0030.TheFWSupervisor recognized thattheTS3.7.9.3and3.7.10actionstatements werenotbeingmetandcontacted FWpersonnel andhadthetourpointaddedtothetour.Atouroftheareawasconducted on04-30-94at0037.TheU-24KvCO2systemforFireZones(FZ)46Ae46Be46Cand46D,andFireDoor2-DR-AUX344 wereinoperable withoutahourlyFWfor1hour26minutes.Thepoli.cyforimplementing firewatchtoursheetshasbeenrevisedtorequireareviewandthenanindependent reviewpriortouse.Thiseventwasdiscussed andreviewedwiththepersonnel involved.
| |
| NRCFORM366(5.92)
| |
| NRCFORM36SA(669)FACIMTYNAME())U.S.NUCLEARREGULATORY CON(MISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATIONDOCKETNUMBER(2)APPROVED0MBNO.3)50010EEXPIRES:4/30)92ESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REQUEST:50A)HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(F430),U.S.NUCLEARREGULATORY COMMISSION.
| |
| WASHINGTON. | | WASHINGTON. |
| DC20555.ANDTOTHEPAPERWORK REDUCTION PROJECT(3(504(04).
| | DC 20555.AND TO THE PAPERWORK REDUCTION PROJECT (3(504(04). |
| OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, DC20503.PAGE(3)LERNUMBER(6)D.C.COOKNUCLEARPLANT-UNIT2TEXTlllnordPlMcrllPNFdmd.N)PAddi5oeel llRCFdm)JSSA'sl(I7)YEARppppp31694SEQUENTIAL NUMER002REVNIONNUMER0002OF03escritoofEventOn01-21-94at1015,FireDoor2-DR<<AUX344 (EIIS/NM-DR) forthe609'levation (elev.)oftheTurbine(Tur.)Building(Bldg.)wasdeclaredinoperable(this doorwasinoperable becausethearea'sventilation systemhasmadeimpossible forthedoortocompletely close).ThisdooralsomadetheCO2systemforthelowerelev.ofthe4Kvroominoperable (FZs46A,46B,46Cand46D).TheCO2systemwasnotdesignedtoallowforperimeter leakageofthismagnitude (10'y12'~120sqft.)toeffectively extinguish the,fire.Arovingfirewatch(FW)patrolwasestablished totourtheaffectedfirezonesandFireDoor2-DR-AUX344 asrequiredbyTechnical Specifications (TS)3.7.9.3and3.7.10(U-2)~On04-29-94at2308aFWtouredtheabovedescribed area.Ashiftturnoveroccurredinwhichthetourpointwasomittedfromthenewlycreatedtoursheet.TheTS(3.7.9.3and3.7.10)requiredtourdidnotoccuragainuntilrecognized andquestioned byFWpersonnel totheFWSupervisor on04-30>>94at0030.TheFWSupervisor recognized thattheTSactionstatements werenotbeingmetandcontacted FWpersonnel andhadthetourpointaddedtothetour.Atouroftheareawasconducted on04-30-94at0037.CauseofEventThecauseofthiseventwaspersonnel error.TheinvolvedFWSupervisor failedtoreviewtheFWtoursheetsuponcompletion, priortothetoursbeingconducted.
| | OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.PAGE (3)LER NUMBER (6)D.C.COOK NUCLEAR PLANT-UNIT 2 TEXT lll nord PlMcr ll PNFdmd.N)P Addi5oeel llRC Fdm)JSSA'sl (I 7)YEAR p p p p p3 16 94 SEQUENTIAL NUM ER 0 0 2 REVNION NUM ER 0 002 OF 0 3 escri t o of Event On 01-21-94 at 1015, Fire Door 2-DR<<AUX344 (EIIS/NM-DR) for the 609'levation (elev.)of the Turbine (Tur.)Building (Bldg.)was declared inoperable(this door was inoperable because the area's ventilation system has made impossible for the door to completely close).This door also made the CO2 system for the lower elev.of the 4Kv room inoperable (FZs 46A, 46B, 46C and 46D).The CO2 system was not designed to allow for perimeter leakage of this magnitude (10'y 12'~120sq ft.)to effectively extinguish the, fire.A roving fire watch (FW)patrol was established to tour the affected fire zones and Fire Door 2-DR-AUX344 as required by Technical Specifications (TS)3.7.9.3 and 3.7.10 (U-2)~On 04-29-94 at 2308 a FW toured the above described area.A shift turnover occurred in which the tour point was omitted from the newly created tour sheet.The TS (3.7.9.3 and 3.7.10)required tour did not occur again until recognized and questioned by FW personnel to the FW Supervisor on 04-30>>94 at 0030.The FW Supervisor recognized that the TS action statements were not being met and contacted FW personnel and had the tour point added to the tour.A tour of the area was conducted on 04-30-94 at 0037.Cause of Event The cause of this event was personnel error.The involved FW Supervisor failed to review the FW tour sheets upon completion, prior to the tours being conducted. |
| Thisreviewwouldhaveidentified alltourpointswerenotincorporated ontothetoursheetsfortheshift.AnalsisofEventTheTS3.7.9.3actionstatement foraninoperable requiredCO2systemrequiresthat"...within 1hour:1)verifyatleastonezoneoffiredetection fortheaffectedareaisOPERABLEperSpecification 4.3.3.8,andestablish afirewatchpatroltoinspecttheaffectedareaonceperhour,or2)Establish acontinuous firewatchtopatroltheaffectedarea."TheTS3.7.10actionstatement foraninoperable fireratedassemblyrequiresthat"...within1hour:1)verifythatthefiredetectors and/orfiresuppression systemonatleastonesideoftheinoperable assemblyareOPERABLEandestablish anhourlyfirewatchpatrol,or2)establish acontinuous firewatchpatrolononesideofthepenetration...".
| | This review would have identified all tour points were not incorporated onto the tour sheets for the shift.Anal sis of Event The TS 3.7.9.3 action statement for an inoperable required CO2 system requires that"...within 1 hour: 1)verify at least one zone of fire detection for the affected area is OPERABLE per Specification 4.3.3.8, and establish a fire watch patrol to inspect the affected area once per hour, or 2)Establish a continuous fire watch to patrol the affected area." The TS 3.7.10 action statement for an inoperable fire rated assembly requires that"...within 1 hour: 1)verify that the fire detectors and/or fire suppression system on at least one side of the inoperable assembly are OPERABLE and establish an hourly fire watch patrol, or 2)establish a continuous fire watch patrol on one side of the penetration...". |
| FailuretomaintainanhourlyFWpatrolwas.aviolation ofTS3.7.9.3and3.7.10andisreportable under10CFR50.73(a)(2)(i)(B).
| | Failure to maintain an hourly FW patrol was.a violation of TS 3.7.9.3 and 3.7.10 and is reportable under 10 CFR 50.73(a)(2)(i)(B). |
| NRCFotm366A(669)
| | NRC Fotm 366A (669) |
| NRCFORM355A)589)US.NUCLEARREGULATORY COMMISSION 0.APPROVEDOMSNO,31500104LICENSEEEVENTREPORTILER)TEXTCONTINUATION ESTIMATED 8URDENPERRESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REOUEST:50.0HRS.FORWARDCOMMENTSREGARDLNG 8URDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT 8RANCHIP.530).U.S.NUCLEARREGULATORY COMMISSION.
| | NRC FORM355A)589)US.NUCLEAR REGULATORY COMMISSION 0.APPROVED OMS NO, 31500104 LICENSEE EVENT REPORT ILER)TEXT CONTINUATION ESTIMATED 8URDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUEST: 50.0 HRS.FORWARD COMMENTS REGARDLNG 8URDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT 8RANCH IP.530).U.S.NUCLEAR REGULATORY COMMISSION. |
| WASHINGTON. | | WASHINGTON. |
| DC30555,ANDTOTHEPAPERWORK REDUCTION PROJECT)31500104).
| | DC 30555, AND TO THE PAPERWORK REDUCTION PROJECT)31500104). |
| OFFICEOFMANAGEMENT ANO8UDGET,WASHINGTON, DC30503.FACILITYNAMEI'lDOCKETNUMSERll)LERNUMEERLEIYEAR,'OYI;55QUENTIAL:,YS
| | OFFICE OF MANAGEMENT ANO 8UDGET, WASHINGTON, DC 30503.FACILITY NAME I'l DOCKET NUMSER ll)LER NUMEER LEI YEAR ,'OYI;55QUENTIAL:,YS |
| +EV~S~ONHUMER7>>HUMPA~AGE131D.C.COOKNUCLEARPLANTTEXTIll)tuupForcp*)FFuuyd, u>>aAse'cdJYACAnn35848)l)3)osooo31694-002-0003OF03nasisofEvetco'dTheU-24KvCO3systemforFZs46A,46B,46Cand46D,andFireDoor2-DR-AUX344wereinoperable withoutahourlyFWpatrolfor1hour26minutes.Theanalysisofthiseventconcludes thatintheunlikelyeventofafire,personnel wouldhavebeenpromptlyawareofitspresenceandwouldhaveextinguished thefirewithoutsignificant spreading ofthefireorequipment damage.Thisconclusion isbasedonthefollowing: | | +EV~S~ON HUM ER 7>>HUM PA~AGE 131 D.C.COOK NUCLEAR PLANT TEXT Ill)tuup Forcp*)FFuuyd, u>>aAse'cd JYAC Ann 35848)l)3)o s o o o 3 1 6 94-00 2-0 0 0 3 OF 0 3 na sis of Eve t co'd The U-2 4Kv CO3 system for FZs 46A, 46B, 46C and 46D, and Fire Door 2-DR-AUX344 were inoperable without a hourly FW patrol for 1 hour 26 minutes.The analysis of this event concludes that in the unlikely event of a fire, personnel would have been promptly aware of its presence and would have extinguished the fire without significant spreading of the fire or equipment damage.This conclusion is based on the following: |
| Thedetection forFZs46A,46B,46Cand46Dwereinanoperablestate,intheeventofafire,thedetectors wouldhavealarmedintheU-2ControlRoom,whichismanned24hoursaday,thisalarmingcondition wouldhavebeeninvestigated andtheappropriate FireBrigaderesources wouldhavebeen'ispatched tomitigatethefire.AlthoughanhourlyFWpatrolwasnotconducted fora1hour26minuteperiod,itisconcluded thatthealarms/detection associated withaffectedfirezoneswouldhaveallowedtimelyidentification ofafire.Therefore, thiseventisnotconsidered'o havecreatedasignificant safetyconcern,nordiditcreateasignificant hazardtothehealthandsafetyofthegeneralpublic.Corrective Actions2~3.WhentheFWSupervisor wasmadeawareoftheomissionofthetourpoint,thetourpointwasaddedandtheaffectedarea/equipment immediately touredforcompliance withTS3.7.9.3and3.7.10.Thiseventwasdiscussed withtheinvolvedpersonnel.
| | The detection for FZs 46A, 46B, 46C and 46D were in an operable state, in the event of a fire, the detectors would have alarmed in the U-2 Control Room, which is manned 24 hours a day, this alarming condition would have been investigated and the appropriate Fire Brigade resources would have been'ispatched to mitigate the fire.Although an hourly FW patrol was not conducted for a 1 hour 26 minute period, it is concluded that the alarms/detection associated with affected fire zones would have allowed timely identification of a fire.Therefore, this event is not considered'o have created a significant safety concern, nor did it create a significant hazard to the health and safety of the general public.Corrective Actions 2~3.When the FW Supervisor was made aware of the omission of the tour point, the tour point was added and the affected area/equipment immediately toured for compliance with TS 3.7.9.3 and 3.7.10.This event was discussed with the involved personnel. |
| Thepersonnel arefullyawareoftheTS3.7.9.3and3.7.10requirements ofanhourlyFWpatrolforaninoperable CO3systemandfireratedassembly, respectively.
| | The personnel are fully aware of the TS 3.7.9.3 and 3.7.10 requirements of an hourly FW patrol for an inoperable CO3 system and fire rated assembly, respectively. |
| PriorissuingFireWatchtourssheetsforimplementation, theyarenowreviewedandindependently reviewedtoensureaccuracy.'revious SimilarEventsNoneNRCFone355A(589)}}
| | Prior issuing Fire Watch tours sheets for implementation, they are now reviewed and independently reviewed to ensure accuracy.'revious Similar Events None NRC F one 355A (589)}} |
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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: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
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Cc ACCELERATE DOCUMENT DISTRIBUTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9406100001 DOC.DATE: 94/05/31 NOTARIZED:
NO DOCKET FACIL:50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH.NAME AUTHOR AFFILIATION HODGE,W.M.
Indiana Michigan Power Co.(formerly Indiana&Michigan Ele BLIND,A.A.
Indiana Michigan Power Co.(formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 94-002-00:on 940430,fire watch tour was omitted due to personnel error.Revised policy for implementing fire watch tour.W/940531 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES D RECIPIENT ID CODE/NAME PD3-1 PD INTERNAL: AEOD/DSP/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB NRR/J3SSA/SPLB
~'EG FILE 02 RGN ILE 01 EXTERNAL EGGG BRYCE i J~H NRC PDR NSIC POOREiW COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1'1 1 RECIPIENT ID CODE/NAME HICKMAN,J AEOD/ROAB/DSP NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB L ST LOBBY WARD NSIC MURPHY,G.A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 D D D D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 26 D Indiana Michigan~Power Gontpany Cook Nuclear Plant One Cook Place Bridgrnan, Mi 49106 616 465 5901 May 31, 1994 United States Nuclear Regulatory Commission Document Control Desk Rockville, Maryland 20852 Operating Licenses DPR-74 Docket No.50-316 Document Control Manager: In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ort S stem the following report is being submitted:
94-002-00 Sincerely,.'.Blind Plant Manager/sb Attachment c'.B.Martin, Region III E.E.Fitzpatrick P.A.Barrett R.F.Kroeger M.A.Bailey-Ft.Wayne NRC Resident Inspector J.B.Hickman-NRC J.R.Padgett G.Charnoff, Esq.D.Hahn INPO S.J.Brewer 9406100001 940531 PDR ADOCK 05000316 S PDR NRC FORM 366 (5.92).S.NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO.3150.0104 EXPIRES 5/31/95 I LICENSEE EVENT REPORT (LER)(See reverse for required number of digits/characters for each block)ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REOUEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 77I4), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555400 I, AND TO THE PAPERWORK REDUCTlON PROJECT (3(504)104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACIUTY NAME (I)D.C.COOK NUCLEAR PLANT-UNIT 2 TITLE (4)FIRE WATCH TOUR OMITTED DUE TO PERSONNEL ERROR DOCKET NUMBER (2)05000 316 PAGE (3)1 OF 3 MONTH DAY YEAR EVENT DATE 5 LER NUMBER 6 SEOUENTIAL NUMBER REVISION NUMBER REPORT NUMBER 7 MONTH OAY FACIUTY NAME DOCKET NUMBER'05000 OTHER FACILITIES INVOLVED 8 04 30 94 94 002 00 05 31 94 FACIUTY NAME DOCKET NUMBER 05000 OPERATING MODE (9)POWER LEVEL (10)063 20.402(b)20.405(a)(1)(i)20.405(a)(1)(ii)20.405(a)(1)(iii)20.405(a)(1)(iv)20.405(c)50.36(c)(1)50.36(c)(2)50.73(a)(2)(i)50.73(a)(2)(ii)50.73(a)(2)(iv)50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A)50.73(a)(2)(viii)(B)73.71(b)73.71(c)OTHER (Speci ty in Abetract below and in Text, NRC Form 366A)NT TO THE REQUIREMENTS OF 10 CFR 5: Check one or m THIS REPORT IS SUBMITTED PURSUA ore 11 NAME 20.405(a)(1)(v)50.73(a)(2)(iii)LICENSEE CONTACT FOR THIS LER 12 50.73(a)(2)(x)TELEPHONE NUMBER Bndude Area Code)W.M.HODGE-PLANT PROTECTION SUPERINTENDENT 616-465-5901 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS CAUSE SYSTEM COMPONENT MANUFACTURER REPORfABLE To NPRDS SUPPLEMENTAL REPORT EXPECTED 14 YES (tt yea, complete EXPECTED SUBMISSION DATE)ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single.spaced typewritten lines)(16)EXP FCTE0 MONTH DAY YEAR SUBMISSION DATE (15)On 01<<21-94 at 1015,.Fire Door 2-DR-AUX344 for the 609'levation (elev.)of the Turbine (Tur.)Building (Bldg.)was declared inoperable (which rendered the CO, suppression system for Fire Zones 46A, 46B 46C and 46D inoperable).
Technical Specifications (TS)3.7.9.3 and 3.7.10 required Action items were established.
On 04-29>>94 at 2308 an hourly FW toured the above described area.A shift turnover occurred at 2315 in which the tour point was omitted from the newly created tour sheet.The TS (3.7.9.3 and 3.7.10)required tour di.d not occur again until recognized and questioned by FW personnel to the FW Supervisor on 04-30-94 at 0030.The FW Supervisor recognized that the TS 3.7.9.3 and 3.7.10 action statements were not being met and contacted FW personnel and had the tour point added to the tour.A tour of the area was conducted on 04-30-94 at 0037.The U-2 4Kv CO2 system for Fire Zones (FZ)46Ae 46Be 46C and 46D, and Fire Door 2-DR-AUX344 were inoperable without a hourly FW for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 26 minutes.The poli.cy for implementing fire watch tour sheets has been revised to require a review and then an independent review prior to use.This event was discussed and reviewed with the personnel involved.NRC FORM 366 (5.92)
NRC FORM 36SA (669)FACIMTY NAME ())U.S.NUCLEAR REGULATORY CON(MISSION LICENSEE EVENT REPORT (LER)TEXT CONTIN UATION DOCKET NUMBER (2)APPROVED 0MB NO.3)50010E EXPIRES: 4/30)92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50A)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (F430), U.S.NUCLEAR REGULATORY COMMISSION.
WASHINGTON.
DC 20555.AND TO THE PAPERWORK REDUCTION PROJECT (3(504(04).
OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.PAGE (3)LER NUMBER (6)D.C.COOK NUCLEAR PLANT-UNIT 2 TEXT lll nord PlMcr ll PNFdmd.N)P Addi5oeel llRC Fdm)JSSA'sl (I 7)YEAR p p p p p3 16 94 SEQUENTIAL NUM ER 0 0 2 REVNION NUM ER 0 002 OF 0 3 escri t o of Event On 01-21-94 at 1015, Fire Door 2-DR<<AUX344 (EIIS/NM-DR) for the 609'levation (elev.)of the Turbine (Tur.)Building (Bldg.)was declared inoperable(this door was inoperable because the area's ventilation system has made impossible for the door to completely close).This door also made the CO2 system for the lower elev.of the 4Kv room inoperable (FZs 46A, 46B, 46C and 46D).The CO2 system was not designed to allow for perimeter leakage of this magnitude (10'y 12'~120sq ft.)to effectively extinguish the, fire.A roving fire watch (FW)patrol was established to tour the affected fire zones and Fire Door 2-DR-AUX344 as required by Technical Specifications (TS)3.7.9.3 and 3.7.10 (U-2)~On 04-29-94 at 2308 a FW toured the above described area.A shift turnover occurred in which the tour point was omitted from the newly created tour sheet.The TS (3.7.9.3 and 3.7.10)required tour did not occur again until recognized and questioned by FW personnel to the FW Supervisor on 04-30>>94 at 0030.The FW Supervisor recognized that the TS action statements were not being met and contacted FW personnel and had the tour point added to the tour.A tour of the area was conducted on 04-30-94 at 0037.Cause of Event The cause of this event was personnel error.The involved FW Supervisor failed to review the FW tour sheets upon completion, prior to the tours being conducted.
This review would have identified all tour points were not incorporated onto the tour sheets for the shift.Anal sis of Event The TS 3.7.9.3 action statement for an inoperable required CO2 system requires that"...within 1 hour: 1)verify at least one zone of fire detection for the affected area is OPERABLE per Specification 4.3.3.8, and establish a fire watch patrol to inspect the affected area once per hour, or 2)Establish a continuous fire watch to patrol the affected area." The TS 3.7.10 action statement for an inoperable fire rated assembly requires that"...within 1 hour: 1)verify that the fire detectors and/or fire suppression system on at least one side of the inoperable assembly are OPERABLE and establish an hourly fire watch patrol, or 2)establish a continuous fire watch patrol on one side of the penetration...".
Failure to maintain an hourly FW patrol was.a violation of TS 3.7.9.3 and 3.7.10 and is reportable under 10 CFR 50.73(a)(2)(i)(B).
NRC Fotm 366A (669)
NRC FORM355A)589)US.NUCLEAR REGULATORY COMMISSION 0.APPROVED OMS NO, 31500104 LICENSEE EVENT REPORT ILER)TEXT CONTINUATION ESTIMATED 8URDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUEST: 50.0 HRS.FORWARD COMMENTS REGARDLNG 8URDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT 8RANCH IP.530).U.S.NUCLEAR REGULATORY COMMISSION.
WASHINGTON.
DC 30555, AND TO THE PAPERWORK REDUCTION PROJECT)31500104).
OFFICE OF MANAGEMENT ANO 8UDGET, WASHINGTON, DC 30503.FACILITY NAME I'l DOCKET NUMSER ll)LER NUMEER LEI YEAR ,'OYI;55QUENTIAL:,YS
+EV~S~ON HUM ER 7>>HUM PA~AGE 131 D.C.COOK NUCLEAR PLANT TEXT Ill)tuup Forcp*)FFuuyd, u>>aAse'cd JYAC Ann 35848)l)3)o s o o o 3 1 6 94-00 2-0 0 0 3 OF 0 3 na sis of Eve t co'd The U-2 4Kv CO3 system for FZs 46A, 46B, 46C and 46D, and Fire Door 2-DR-AUX344 were inoperable without a hourly FW patrol for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 26 minutes.The analysis of this event concludes that in the unlikely event of a fire, personnel would have been promptly aware of its presence and would have extinguished the fire without significant spreading of the fire or equipment damage.This conclusion is based on the following:
The detection for FZs 46A, 46B, 46C and 46D were in an operable state, in the event of a fire, the detectors would have alarmed in the U-2 Control Room, which is manned 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day, this alarming condition would have been investigated and the appropriate Fire Brigade resources would have been'ispatched to mitigate the fire.Although an hourly FW patrol was not conducted for a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 26 minute period, it is concluded that the alarms/detection associated with affected fire zones would have allowed timely identification of a fire.Therefore, this event is not considered'o have created a significant safety concern, nor did it create a significant hazard to the health and safety of the general public.Corrective Actions 2~3.When the FW Supervisor was made aware of the omission of the tour point, the tour point was added and the affected area/equipment immediately toured for compliance with TS 3.7.9.3 and 3.7.10.This event was discussed with the involved personnel.
The personnel are fully aware of the TS 3.7.9.3 and 3.7.10 requirements of an hourly FW patrol for an inoperable CO3 system and fire rated assembly, respectively.
Prior issuing Fire Watch tours sheets for implementation, they are now reviewed and independently reviewed to ensure accuracy.'revious Similar Events None NRC F one 355A (589)