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| {{#Wiki_filter:ee.~OPe<<TLXC DaTARe~ORTDOCK:-TiO.DAT:"CO~IPL"=D"~'HL:->HOi:- | | {{#Wiki_filter:ee.~OPe<<TLXC DaTA Re~ORT DOCK:-T iO.DAT:" CO~IPL"=D"~'HL:->HOi:- |
| 50-315S-4-BO~B.~t0~5,6.I~02:-RA:T~4 GSiAiMD.C.CookUnctiforesUnitifan"'eporting P-":odtThe..al?o (I)IYt)tNaaet)late Mg(GsossI')DYe)tDesignBeadR"ing(NetsbIYr'e)tmaxim~DMeMC='c-"ePhsUM'Ne)i:IfCrw"esOcarinCape:.(.'ht y(Item(tickerJu1325010541080SThou~>I)Siac"LastRepor..GiveRwonst'"--"-9'.-Paore~vel'opi | | 50-315 S-4-BO~B.~t 0~5, 6.I~02:-RA:T~4 G S i A iM D.C.Cook Unct i fores Unit i fan"'eporting P-":odt The..al?o (I)IYt)t Naaet)late Mg (Gsoss I')DYe)t Design Bead R" ing (Net sbIYr'e)t maxim~D MeM C='c-"e Phs UM'Ne)i: If Crw"es Ocar in Cape:.(.'ht y (Item (ticker Ju1 3250 1054 1080 S Thou~>I)Siac" Last Repor..Give Rwonst'"--"-9'.-Paore~vel'opi |
| 'zR<<sŽ~,IfAny(';ietADYe):IO;R~wa'."m~chas,IfAny:Thisit)oathYr.wo-Dat=. | | 'z R<<sŽ~, If Any (';iet ADYe): IO;R~wa'."m~chas, If Any: This it)oath Yr.wo-Dat=. |
| Ci)~L.tive. | | Ci)~L.tive. |
| '1;Ho~I.".Rt~r)A-.iag P.":odIZ.ife"..o~~Qf'EoGeRe"ctor Yf~w.C;:WI~.;Reau~~~4ha<ovvn Ho'-'aI.'oa~am~~iMe tRU."it5~~hatdo~ | | '1;Ho~I.".Rt~r)A-.iag P.":od IZ.i fe"..o~~Qf'EoGeRe"ctor Yf~w.C;:W I~.;Re au~~~4ha<ovvn Ho'-'a I.'oa~am~~iMe tR U."it5~~hatdo~ |
| Hots'M:GrossIt)'~tR.".=~y Cene.=tdPI%)'7.Groscia'Wm~e~ | | Hots'M: Gross It)'~tR.".=~y Cene.=td PI%)'7.Gros cia'Wm~e~Gcaewt~('I)YH)te.4a'et~aJ=".=~Geant~(I'IYc-.)-'l9-.Unirlerrt"" ra):tor--t)-.'ai~~'IaalL~L"cror~Ua~aae~sar(Usia MDC Her)~UriMztadg&~tor (Using DeR 4c:)~Uni&n-Coat:e Rat'4.Shatdo~xsSchedaied Over icxt 6."Ioa'.hs 0 3 207.9 0 0 0 0 0 10,118,931 3 245 802 62.6.6 60.'0.3 11.6{Type.Date.aa Datcuon of E"ch)t 463 99 185 236 31 24 1 75.4 75.4 61.8 7.3 t)~~L c.ad Of R" ort Pe:iod..Btiracted Date oi Stamp S.Units la Test Sea)as I P.":or to Ce.-..-...e~i l Ope-.tioa): |
| Gcaewt~('I)YH)te.4a'et~aJ=".=~Geant~(I'IYc-.)-'l9-.Unirlerrt"" | | A Foist Ac.'".ieved IliITIS,L Ca.ii)C,'ITT INTIA L"=LeCTR!CITY 8 0 08>.80550't)s',,) |
| ra):tor-- | | AVERAGE DAILY UNIT POWER LEVEL DOCKET"NO.'ATE 8-1-80 COMPLETED BY W.T.Gi llett TELEPHONE 616-465-5901 MONTH Jul DAY.AVERAGE DAILY POWER LEVEL (MWE-Net)5 10 12 13-15 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 INSTRUCTIONS On this'format list the average daily unit power level in MWe-Net for each day in the reporting month.Compute to the nearest whole megawatt. |
| t)-.'ai~~'IaalL~L "cror~Ua~aae~sar(Usia MDCHer)~UriMztadg&~tor (UsingDeR4c:)~Uni&n-Coat:eRat'4.Shatdo~xsSchedaied Overicxt6."Ioa'.hs 03207.90000010,118,931 324580262.6.660.'0.311.6{Type.Date.aaDatcuonofE"ch)t463991852363124175.475.461.87.3t)~~Lc.adOfR"ortPe:iod..Btiracted DateoiStampS.UnitslaTestSea)asIP.":ortoCe.-..-...e~i lOpe-.tioa): | | UNIT SIIUTDOlUNS AND PO)UER REDUCTIONS |
| AFoistAc.'".ieved IliITIS,L Ca.ii)C,'ITT INTIAL"=LeCTR!CITY8008>.80550't)s',,
| | ~J1.1999 DOCKET NO.'rVZmtmn TEI.EPilONE 616 465-5901 9 C~No.l)ate 99)9 CS L r)499 o 9>)~91)~C/l g Llccnscc Event Rcpl>rt Jr c~o 9))Q D C~0 Cause&(.orrc<<tlvc Action tl>Prcvcnt Rccurrcncc 160 800530 S 744 BII)C N.A.ZZ ZZZZZZ The Unit was removed from service for Cycle IV-V refueling outage at 2228 hours EDT on 800530.The Unit remained out of service the entire month.~, I': For<<cd S: Sched>>lcd ())/77)Rc Json: A-f<luipnlcnt Faihlrc (Explain)II-hlaitttcrtance nr Test C-Rcfuclin(9 D-RCI,tllatory Restri<<lion E-Operator Train(I>I,&.Llccnsc Exanlhlation F-Administ rat ivc G.Operational Lrn>r (Iixplaitt) |
| ) | | I I Other (Explahl)hlethod: I-Manual 2.Manual Scfanl.3-Autolnatic Scram.4-Other (Explain)4 Exhibit G-Instructions I'or Prcparathn> |
| AVERAGEDAILYUNITPOWERLEVELDOCKET"NO.'ATE 8-1-80COMPLETED BYW.T.GillettTELEPHONE 616-465-5901 MONTHJulDAY.AVERAGEDAILYPOWERLEVEL(MWE-Net) 5101213-15DAYAVERAGEDAILYPOWERLEVEL(MWe-Net) 171819202122232425262728293031INSTRUCTIONS Onthis'format listtheaveragedailyunitpowerlevelinMWe-Netforeachdayinthereporting month.Computetothenearestwholemegawatt.
| | oi Data Lorry Shccts for Li<<ctlsec Event Rcport (LI!R)File (NURI.'G-016I)'LXhibit I-Salne Soul<<e UNIT SHUTDOWNS AND POWER REDUC i ONS INSTRUCTIONS This report should describe all plant shutdowns during the report period.In addition.it should be the source of explan-ation of significant dips in average power levels.Each signi~ficant reduction in power level (greater than 207'eduction in average daily power level for the preceding 24 hours)should be noted, even though the unit may not have been shut down cornpletelyl. |
| UNITSIIUTDOlUNS ANDPO)UERREDUCTIONS
| | For such reductions in power level, the duration should be listed as zero, the method of reduction should be listed as 4 (Other), and the Cause and Corrective Action to Prevent Recurrence column should explain.The Cause and Corrective Action to Prevent Recurrence column should be used to provide any needed explanation to fully describe the circumstances of the outage or power reduction. |
| ~J1.1999DOCKETNO.'rVZmtmnTEI.EPilONE 616465-59019C~No.l)ate99)9CSLr)499o9>)~91)~C/lgLlccnsccEventRcpl>rtJrc~o9))QDC~0Cause&(.orrc<<tlvc Actiontl>PrcvcntRccurrcncc 160800530S744BII)CN.A.ZZZZZZZZTheUnitwasremovedfromserviceforCycleIV-Vrefueling outageat2228hoursEDTon800530.TheUnitremainedoutofservicetheentiremonth.~,I':For<<cdS:Sched>>lcd | | NUMBER.This column should indicate the sequential num-ber assigned to each shutdown or significant reduction in power for that calendar year.When a shutdown or significant power reduction begins in one report period and ends in another, an entry should be made for both report periods to be sure all shutdowns or significant power reductions are reported.Until a unit has achieved its first power generation, no num-ber should be assigned to each entry.DATE.This column should indicate the date of the start of each shutdown or signiiicant power reduction. |
| ())/77)RcJson:A-f<luipnlcnt Faihlrc(Explain) | | Report as year.month, and day.August i4.1977 would be reported as 770814.When a shutdown or significant power reduction begins in one report period and ends in another, an entry should be made for both report periods to be sure all shutdowns or signiticant power reductions are reported.TYPE.Use"F" or"S" to indicate either"Forced" or"Sche-duled," respectively, for each shutdown or significant power reduction. |
| II-hlaitttcrtance nrTestC-Rcfuclin(9 D-RCI,tllatory Restri<<lion E-Operator Train(I>I, | | Forced shutdowns include those required to be initiated by no later than the weekend following discovery of an off-normal condition. |
| &.LlccnscExanlhlation F-Administ rativcG.Operational Lrn>r(Iixplaitt) | | It is recognized that some judg-ment is required in categorizing shutdowns in this way.In general, a forced shutdown is one that would not have been completed in the absence of the condition for which corrective action was taken.DURATION.Seifwxplanatoiy. |
| IIOther(Explahl) hlethod:I-Manual2.ManualScfanl.3-Autolnatic Scram.4-Other(Explain) 4ExhibitG-Instructions I'orPrcparathn>
| | When a shutdown extends beyond the end of a report period, count only the time to the end oi the report period and pick up the ensuing down time in the folio'wing report periods.Report duration of outages rounded to the nearest tenth of an hour to facilitate summation. |
| oiDataLorryShcctsforLi<<ctlsec EventRcport(LI!R)File(NURI.'G-016I)'LXhibitI-SalneSoul<<e UNITSHUTDOWNS ANDPOWERREDUCiONSINSTRUCTIONS Thisreportshoulddescribeallplantshutdowns duringthereportperiod.Inaddition.
| | The sum of the total outage hours plus the hours the genera-tor was on line should equal the gross hours in the reporting period.REASON.Categorize by letter designation in accordance with the table appearing Un the report t'orm.If category H must be used.supply briei'comments. |
| itshouldbethesourceofexplan-ationofsignificant dipsinaveragepowerlevels.Eachsigni~ficantreduction inpowerlevel(greaterthan207'eduction inaveragedailypowerlevelforthepreceding 24hours)shouldbenoted,eventhoughtheunitmaynothavebeenshutdowncornpletelyl.
| | METHOD OF SHUTTINC DOWN THE REACTOR OR REDUCING POWER.Categt>rize by number designation INoie that this differs i'rom the Edison'Electric Institute (EEI)definitions of-Forced Partial Outage" and-Sche-duled Partial Outage." F>>r these tLrnis.I:Fl uses a change of..0 NIW as the break pL>int.FL>r larger pL>>ver reactors.30 MW is u>>>small a change t>>warrant cxpianatiL>>i. |
| Forsuchreductions inpowerlevel,thedurationshouldbelistedaszero,themethodofreduction shouldbelistedas4(Other),andtheCauseandCorrective ActiontoPreventRecurrence columnshouldexplain.TheCauseandCorrective ActiontoPreventRecurrence columnshouldbeusedtoprovideanyneededexplanation tofullydescribethecircumstances oftheoutageorpowerreduction.
| | in accordance with the table appearing on the report torm.If category 4 must be used, supply brief comments.LICENSEE EVENT REPORT='.Reference the applicable reportable occurrence pertaining to the outage or power reduction. |
| NUMBER.Thiscolumnshouldindicatethesequential num-berassignedtoeachshutdownorsignificant reduction inpowerforthatcalendaryear.Whenashutdownorsignificant powerreduction beginsinonereportperiodandendsinanother,anentryshouldbemadeforbothreportperiodstobesureallshutdowns orsignificant powerreductions arereported. | | Enter the first four parts (event year.sequential report number, occurrence code and report type)of the five part designation as described in Item 17 of Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)File (NUREG416l). |
| Untilaunithasachieveditsfirstpowergeneration, nonum-bershouldbeassignedtoeachentry.DATE.Thiscolumnshouldindicatethedateofthestartofeachshutdownorsigniiicant powerreduction.
| | This information may not be immediately evident for all such shutdowns, of course, since further investigation may be required to ascertain whether or not a reportable occurrence was involved.) |
| Reportasyear.month,andday.Augusti4.1977wouldbereportedas770814.Whenashutdownorsignificant powerreduction beginsinonereportperiodandendsinanother,anentryshouldbemadeforbothreportperiodstobesureallshutdowns orsigniticant powerreductions arereported.
| | If the outage or power reduction will not result in a reportable occurrence. |
| TYPE.Use"F"or"S"toindicateeither"Forced"or"Sche-duled,"respectively, foreachshutdownorsignificant powerreduction. | | the positive indication of this lack of correlation should be noted as not applicable (N/A).SYSTEM CODE.The system in which the outage or power reduction originated should be noted by the two digit code of Exhibit G-Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)File (NUREG416I). |
| Forcedshutdowns includethoserequiredtobeinitiated bynolaterthantheweekendfollowing discovery ofanoff-normal condition.
| | Systems that do not fit any existing code should be designa-ted XX.The code ZZ should be used for those events where a system is not applicable. |
| Itisrecognized thatsomejudg-mentisrequiredincategorizing shutdowns inthisway.Ingeneral,aforcedshutdownisonethatwouldnothavebeencompleted intheabsenceofthecondition forwhichcorrective actionwastaken.DURATION.
| | CO>>IPONENT CODE.Select the most appropriate component from Exhibit I-Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)File (NUREG416I). |
| Seifwxplanatoiy. | | using the following critieria: |
| Whenashutdownextendsbeyondtheendofareportperiod,countonlythetimetotheendoithereportperiodandpickuptheensuingdowntimeinthefolio'wing reportperiods.Reportdurationofoutagesroundedtothenearesttenthofanhourtofacilitate summation.
| | A.If a component failed,use the component directly involved B.If not a component failure, use the related component: |
| Thesumofthetotaloutagehoursplusthehoursthegenera-torwasonlineshouldequalthegrosshoursinthereporting period.REASON.Categorize byletterdesignation inaccordance withthetableappearing Unthereportt'orm.IfcategoryHmustbeused.supplybriei'comments.
| | e.g.>wrong valve operated through error: list valve as"component. |
| METHODOFSHUTTINCDOWNTHEREACTORORREDUCINGPOWER.Categt>rize bynumberdesignation INoiethatthisdiffersi'romtheEdison'Electric Institute (EEI)definitions of-ForcedPartialOutage"and-Sche-duledPartialOutage."F>>rthesetLrnis.I:Flusesachangeof..0NIWasthebreakpL>int.FL>rlargerpL>>verreactors.
| | C.If a chain of failures occurs, the first component to mal-function should be listed.The sequence of events.includ-ing the other components which fail, should be described under the Cause and Corrective Action to Prevent Recur-rence column.Components that do not fit any existing code should be de.,signated XXXXXX.The code.ZZZZZZ should.be used.'or events where a component designation is not applicable. |
| 30MWisu>>>smallachanget>>warrantcxpianatiL>>i.
| | CAUSE Sc CORRECTIVE ACTION TO PREVENT"RECUR-RENCE.Use the column in a narrative fashion to ampiify or explain the circumstances of the shutdown or power reduction. |
| inaccordance withthetableappearing onthereporttorm.Ifcategory4mustbeused,supplybriefcomments.
| | The column should include the soecific cause for each shut~down or significant power reduction and the immediate and contemplated long term corrective action taken.if appropri-ate.This column should also be used for a description of the major safety.related corrective maintenance performed during the outage or power reduction including an identification of the critical path activity and a report of any single release of radioactivity L>r single radiation exposure speciiically associ~ated with the outage which accounts for more than 10 percent oi the allowable annual values.For long textual reports continue narrative on separate naper and reference tlie shutdown or power reduction for tins lla rfa tive.(L)/7 I cket No.: Unit Name: Completed By: Telephone: |
| LICENSEEEVENTREPORT='.Reference theapplicable reportable occurrence pertaining totheoutageorpowerreduction.
| | Date: Page: 50-315 ,D.,C.Cook Unit 81 R,.S.Lease (616)465-5901 August 7, 1980 lof 1 MONTHLY OPERATING ACTIVITIES |
| Enterthefirstfourparts(eventyear.sequential reportnumber,occurrence codeandreporttype)ofthefivepartdesignation asdescribed inItem17ofInstructions forPreparation ofDataEntrySheetsforLicenseeEventReport(LER)File(NUREG416l).
| | --JULY, 1980 Hi hli hts The Unit has been shut down the entire reporting period for its fourth Refueling Outage.The time of shut down was 2228 hours 5/30/80.Electrical generation for the month was 0.Summary 7/2/80--Reactor Head was set on the vessel at 0530 hours.7/9/80--The Reactor Plant entered Mode 5 with the initial bolting of the reactor head.7/20/80--Safety Train"A" blackout testing was successfully completed. |
| Thisinformation maynotbeimmediately evidentforallsuchshutdowns, ofcourse,sincefurtherinvestigation mayberequiredtoascertain whetherornotareportable occurrence wasinvolved.)
| | 7/21/80--Safety Train"B" blackout testing was successfully completed. |
| Iftheoutageorpowerreduction willnotresultinareportable occurrence.
| | 7/23/80-Filling and venting of the Reactor Coolant System, from the~~loop level was initiated at 1812 hours.7/26/80-7/27/80--A steam bubble was formed in the Pressurizer at 0310 hours.System pressure was increased to 325 psig for hand rotation of the four Reactor Coolant Pumps.The 0'14 pump would not rotate when the maximum recommended manual force was applied.Reactor Coolant System pressure was reduced to 0 and the system drained to the 4 loop level by 0830 hours.This was to allow inspection of the thrust bearing of the 5'14 Reactor Coolant Pump.7/30/80-Filling and venting of the Reactor Coolant System was initiated at 0048 hours and completed at 1928 hours 3/31/80. |
| thepositiveindication ofthislackofcorrelation shouldbenotedasnotapplicable (N/A).SYSTEMCODE.Thesysteminwhichtheoutageorpowerreduction originated shouldbenotedbythetwodigitcodeofExhibitG-Instructions forPreparation ofDataEntrySheetsforLicenseeEventReport(LER)File(NUREG416I).
| | ~~'e f DOCKET NO.UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50-315 D.C.Cook-Unit No.1 8-6-80 B.A.Svensson 616 465-5901 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE JULY, 1980, M-1 The stem on DG-227C,'1CD diesel jacket water sample valve was broken with the valve open.The valve was replaced.NSW-244-3, non-essential service water containment isolation check valve failed Type C leak test.Seat and disc were lapped and valve reassembled. |
| Systemsthatdonotfitanyexistingcodeshouldbedesigna-tedXX.ThecodeZZshouldbeusedforthoseeventswhereasystemisnotapplicable.
| | NSW-415-2, non-essential service water containment isolation check yylye failed Type C leak test.Yalye body cleaned and new disc in-stalled.M-4 M-6 M-8 No.1 steam generator blowdown regulating valve, DRV-311, had a body to bonnet leak.Disassembled valve, repaired steam cuts and re-assembled with new gaskets.Had valve tested.The reciprocating charging pump discharge valve, CS-386, was leaking by.Disassembled valve and lapped seat.Reassembled with a new stem and plug.The sample pump for radiation monitors R-11 and R-12 would not run.Replaced the pump and had it tested.The motor driven auxiliary feedpump was inspected to check condition ,of the outboard pump bearing.Replaced the rotating assembly and tested the pump.The west centrifugal charging pump had a broken shaft.Replaced the rotating assembly and retested the pump.Safety injection check valves on the lines to the reactor coolant hot legs of all four loops, SI-158Ll, L2, L3 and L4 had body to bonnet leaks.Replaced bonnet gaskets in all four valves. |
| CO>>IPONENT CODE.Selectthemostappropriate component fromExhibitI-Instructions forPreparation ofDataEntrySheetsforLicenseeEventReport(LER)File(NUREG416I). | | e~~'A t e t}} |
| usingthefollowing critieria:
| |
| A.Ifacomponent failed,use thecomponent directlyinvolvedB.Ifnotacomponent failure,usetherelatedcomponent: | |
| e.g.>wrongvalveoperatedthrougherror:listvalveas"component. | |
| C.Ifachainoffailuresoccurs,thefirstcomponent tomal-functionshouldbelisted.Thesequenceofevents.includ-ingtheothercomponents whichfail,shouldbedescribed undertheCauseandCorrective ActiontoPreventRecur-rencecolumn.Components thatdonotfitanyexistingcodeshouldbede.,signated XXXXXX.Thecode.ZZZZZZshould.beused.'oreventswhereacomponent designation isnotapplicable. | |
| CAUSEScCORRECTIVE ACTIONTOPREVENT"RECUR-RENCE.Usethecolumninanarrative fashiontoampiifyorexplainthecircumstances oftheshutdownorpowerreduction.
| |
| Thecolumnshouldincludethesoecificcauseforeachshut~downorsignificant powerreduction andtheimmediate andcontemplated longtermcorrective actiontaken.ifappropri-ate.Thiscolumnshouldalsobeusedforadescription ofthemajorsafety.relatedcorrective maintenance performed duringtheoutageorpowerreduction including anidentification ofthecriticalpathactivityandareportofanysinglereleaseofradioactivity L>rsingleradiation exposurespeciiically associ~atedwiththeoutagewhichaccountsformorethan10percentoitheallowable annualvalues.Forlongtextualreportscontinuenarrative onseparatenaperandreference tlieshutdownorpowerreduction fortinsllarfative.(L)/7I cketNo.:UnitName:Completed By:Telephone:
| |
| Date:Page:50-315,D.,C.CookUnit81R,.S.Lease(616)465-5901August7,1980lof1MONTHLYOPERATING ACTIVITIES | |
| --JULY,1980HihlihtsTheUnithasbeenshutdowntheentirereporting periodforitsfourthRefueling Outage.Thetimeofshutdownwas2228hours5/30/80.Electrical generation forthemonthwas0.Summary7/2/80--ReactorHeadwassetonthevesselat0530hours.7/9/80--TheReactorPlantenteredMode5withtheinitialboltingofthereactorhead.7/20/80--SafetyTrain"A"blackouttestingwassuccessfully completed. | |
| 7/21/80--SafetyTrain"B"blackouttestingwassuccessfully completed. | |
| 7/23/80-FillingandventingoftheReactorCoolantSystem,fromthe~~looplevelwasinitiated at1812hours.7/26/80-7/27/80-- | |
| AsteambubblewasformedinthePressurizer at0310hours.Systempressurewasincreased to325psigforhandrotationofthefourReactorCoolantPumps.The0'14pumpwouldnotrotatewhenthemaximumrecommended manualforcewasapplied.ReactorCoolantSystempressurewasreducedto0andthesystemdrainedtothe4looplevelby0830hours.Thiswastoallowinspection ofthethrustbearingofthe5'14ReactorCoolantPump.7/30/80-FillingandventingoftheReactorCoolantSystemwasinitiated at0048hoursandcompleted at1928hours3/31/80.
| |
| ~~'ef DOCKETNO.UNITNAMEDATECOMPLETED BYTELEPHONE PAGE50-315D.C.Cook-UnitNo.18-6-80B.A.Svensson616465-59011of1MAJORSAFETY-RELATED MAINTENANCE JULY,1980,M-1ThestemonDG-227C,'1CD dieseljacketwatersamplevalvewasbrokenwiththevalveopen.Thevalvewasreplaced. | |
| NSW-244-3, non-essential servicewatercontainment isolation checkvalvefailedTypeCleaktest.Seatanddiscwerelappedandvalvereassembled. | |
| NSW-415-2, non-essential servicewatercontainment isolation checkyylyefailedTypeCleaktest.Yalyebodycleanedandnewdiscin-stalled.M-4M-6M-8No.1steamgenerator blowdownregulating valve,DRV-311,hadabodytobonnetleak.Disassembled valve,repairedsteamcutsandre-assembled withnewgaskets.Hadvalvetested.Thereciprocating chargingpumpdischarge valve,CS-386,wasleakingby.Disassembled valveandlappedseat.Reassembled withanewstemandplug.Thesamplepumpforradiation monitorsR-11andR-12wouldnotrun.Replacedthepumpandhadittested.Themotordrivenauxiliary feedpumpwasinspected tocheckcondition | |
| ,oftheoutboardpumpbearing.Replacedtherotatingassemblyandtestedthepump.Thewestcentrifugal chargingpumphadabrokenshaft.Replacedtherotatingassemblyandretestedthepump.Safetyinjection checkvalvesonthelinestothereactorcoolanthotlegsofallfourloops,SI-158Ll, L2,L3andL4hadbodytobonnetleaks.Replacedbonnetgasketsinallfourvalves. | |
| e~~'Atet}} | |
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ML17326A0071999-05-31031 May 1999 Monthly Operating Rept for May 1999 for DC Cook Nuclear Plant,Unit 2.With 990609 Ltr ML17326A0061999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Dcp.With 990609 Ltr 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 ML17325B5441999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant,Unit 1.With 990408 Ltr ML17325B5491999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant Unit 2.With 990408 Ltr 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 ML17335A5201999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Dccnp Unit 1.With 990208 Ltr ML17335A5191999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Dccnp,Unit 2.With 990208 Ltr ML17335A4831998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for DC Cook Nuclear Plant,Unit 2.With 990108 Ltr ML17335A4841998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for DC Cook Nuclear Plant,Unit 1.With 990108 Ltr ML17335A3951998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for DC Cook Nuclear Plant,Unit 2.With 981207 Ltr ML17335A3941998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for DC Cook Nuclear Plant,Unit 1.With 981207 Ltr ML17335A3331998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for DC Cook Nuclear Plant,Unit 1.With 981105 Ltr ML17335A3381998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for DC Cook Nuclear Power,Unit 2.With 981105 Ltr ML17335A2931998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for DC Cook Nuclear Plant,Unit 2.With 981005 Ltr ML17335A2941998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for DC Cook Nuclear Plant,Unit 1.With 981005 Ltr ML17335A2131998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for DC Cook Nuclear Plant,Unit 2.W/980903 Ltr ML17335A2151998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for DC Cook Nuclear Plant,Unit 1.W/980903 Ltr ML17335A1741998-07-31031 July 1998 Monthly Operating Rept for July 1998 for DC Cook Nuclear Plant Unit 2.W/980806 Ltr ML17335A1731998-07-31031 July 1998 Monthly Operating Rept for July 1998 for DC Cook Nuclear Plant Unit 1.W/980806 Ltr ML17334B8171998-06-30030 June 1998 Monthly Operating Rept for June 1998 for DC Cook Nuclear Plant Unit 2.W/980706 Ltr ML17334B8131998-06-30030 June 1998 Monthly Operating Rept for June 1998 for DC Cook Nuclear Station,Unit 1.W/980706 Ltr ML17334A7511998-05-31031 May 1998 Monthly Operating Rept for May 1998 for DC Cook Nuclear Plant,Unit 2.W/980609 ML17334A7521998-05-31031 May 1998 Monthly Operating Rept for May 1998 for DC Cook Nuclear Plant,Unit 1.W/980609 Ltr ML17334B7921998-04-30030 April 1998 Addendum to Monthly Operating Rept for Apr 1998 for DC Cook Nuclear Station,Unit 2 ML17334B7721998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for DC Cook Nuclear Plant,Unit 1.W/980506 Ltr ML17334B7911998-03-31031 March 1998 Addendum to Monthly Operating Rept for Mar 1998 for DC Cook Nuclear Plant,Unit 2 ML17334B7171998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Donald C Cook Nuclear Plant,Unit 1.W/980407 Ltr ML17334B7181998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Donald C Cook Nuclear Plant,Unit 2.W/980407 Ltr ML17334A6831998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Donald C Cook Nuclear Plant,Unit 2.W/980309 Ltr ML17334A6811998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Donald C Cook Nuclear Plant,Unit 1.W/980309 Ltr ML17334B7901998-02-28028 February 1998 Addendum to Monthly Operating Rept for Feb 1998 for DC Cook Nuclear Plant,Unit 2 ML17334A6481998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for DC Cook Nuclear Plant,Unit 2.W/980209 Ltr ML17334B7891998-01-31031 January 1998 Addendum to Monthly Operating Rept for Jan 1998 for DC Cook Nuclear Plant,Unit 2 ML17334A6051997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Donald C Cook Nuclear Plant,Unit 2 ML17334A6021997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Donald C Cook Nuclear Plant,Unit 1.W/980108 Ltr ML17334B6711997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for DC Cook Nuclear Plant,Unit 2.W/971208 Ltr ML17334A6061997-11-30030 November 1997 Revised Monthly Operating Rept for Nov 1997 for DC Cook Nuclear Station,Unit 2 ML17334B6651997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for DC Cook Nuclear Plant,Unit 1.W/971208 Ltr ML17333B1421997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Donald C Cook Nuclear Plant,Unit 1.W/971110 Ltr 1999-09-30
[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
ee.~OPe<<TLXC DaTA Re~ORT DOCK:-T iO.DAT:" CO~IPL"=D"~'HL:->HOi:-
50-315 S-4-BO~B.~t 0~5, 6.I~02:-RA:T~4 G S i A iM D.C.Cook Unct i fores Unit i fan"'eporting P-":odt The..al?o (I)IYt)t Naaet)late Mg (Gsoss I')DYe)t Design Bead R" ing (Net sbIYr'e)t maxim~D MeM C='c-"e Phs UM'Ne)i: If Crw"es Ocar in Cape:.(.'ht y (Item (ticker Ju1 3250 1054 1080 S Thou~>I)Siac" Last Repor..Give Rwonst'"--"-9'.-Paore~vel'opi
'z R<<sŽ~, If Any (';iet ADYe): IO;R~wa'."m~chas, If Any: This it)oath Yr.wo-Dat=.
Ci)~L.tive.
'1;Ho~I.".Rt~r)A-.iag P.":od IZ.i fe"..o~~Qf'EoGeRe"ctor Yf~w.C;:W I~.;Re au~~~4ha<ovvn Ho'-'a I.'oa~am~~iMe tR U."it5~~hatdo~
Hots'M: Gross It)'~tR.".=~y Cene.=td PI%)'7.Gros cia'Wm~e~Gcaewt~('I)YH)te.4a'et~aJ=".=~Geant~(I'IYc-.)-'l9-.Unirlerrt"" ra):tor--t)-.'ai~~'IaalL~L"cror~Ua~aae~sar(Usia MDC Her)~UriMztadg&~tor (Using DeR 4c:)~Uni&n-Coat:e Rat'4.Shatdo~xsSchedaied Over icxt 6."Ioa'.hs 0 3 207.9 0 0 0 0 0 10,118,931 3 245 802 62.6.6 60.'0.3 11.6{Type.Date.aa Datcuon of E"ch)t 463 99 185 236 31 24 1 75.4 75.4 61.8 7.3 t)~~L c.ad Of R" ort Pe:iod..Btiracted Date oi Stamp S.Units la Test Sea)as I P.":or to Ce.-..-...e~i l Ope-.tioa):
A Foist Ac.'".ieved IliITIS,L Ca.ii)C,'ITT INTIA L"=LeCTR!CITY 8 0 08>.80550't)s',,)
AVERAGE DAILY UNIT POWER LEVEL DOCKET"NO.'ATE 8-1-80 COMPLETED BY W.T.Gi llett TELEPHONE 616-465-5901 MONTH Jul DAY.AVERAGE DAILY POWER LEVEL (MWE-Net)5 10 12 13-15 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 INSTRUCTIONS On this'format list the average daily unit power level in MWe-Net for each day in the reporting month.Compute to the nearest whole megawatt.
UNIT SIIUTDOlUNS AND PO)UER REDUCTIONS
~J1.1999 DOCKET NO.'rVZmtmn TEI.EPilONE 616 465-5901 9 C~No.l)ate 99)9 CS L r)499 o 9>)~91)~C/l g Llccnscc Event Rcpl>rt Jr c~o 9))Q D C~0 Cause&(.orrc<<tlvc Action tl>Prcvcnt Rccurrcncc 160 800530 S 744 BII)C N.A.ZZ ZZZZZZ The Unit was removed from service for Cycle IV-V refueling outage at 2228 hours0.0258 days <br />0.619 hours <br />0.00368 weeks <br />8.47754e-4 months <br /> EDT on 800530.The Unit remained out of service the entire month.~, I': For<<cd S: Sched>>lcd ())/77)Rc Json: A-f<luipnlcnt Faihlrc (Explain)II-hlaitttcrtance nr Test C-Rcfuclin(9 D-RCI,tllatory Restri<<lion E-Operator Train(I>I,&.Llccnsc Exanlhlation F-Administ rat ivc G.Operational Lrn>r (Iixplaitt)
I I Other (Explahl)hlethod: I-Manual 2.Manual Scfanl.3-Autolnatic Scram.4-Other (Explain)4 Exhibit G-Instructions I'or Prcparathn>
oi Data Lorry Shccts for Li<<ctlsec Event Rcport (LI!R)File (NURI.'G-016I)'LXhibit I-Salne Soul<<e UNIT SHUTDOWNS AND POWER REDUC i ONS INSTRUCTIONS This report should describe all plant shutdowns during the report period.In addition.it should be the source of explan-ation of significant dips in average power levels.Each signi~ficant reduction in power level (greater than 207'eduction in average daily power level for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)should be noted, even though the unit may not have been shut down cornpletelyl.
For such reductions in power level, the duration should be listed as zero, the method of reduction should be listed as 4 (Other), and the Cause and Corrective Action to Prevent Recurrence column should explain.The Cause and Corrective Action to Prevent Recurrence column should be used to provide any needed explanation to fully describe the circumstances of the outage or power reduction.
NUMBER.This column should indicate the sequential num-ber assigned to each shutdown or significant reduction in power for that calendar year.When a shutdown or significant power reduction begins in one report period and ends in another, an entry should be made for both report periods to be sure all shutdowns or significant power reductions are reported.Until a unit has achieved its first power generation, no num-ber should be assigned to each entry.DATE.This column should indicate the date of the start of each shutdown or signiiicant power reduction.
Report as year.month, and day.August i4.1977 would be reported as 770814.When a shutdown or significant power reduction begins in one report period and ends in another, an entry should be made for both report periods to be sure all shutdowns or signiticant power reductions are reported.TYPE.Use"F" or"S" to indicate either"Forced" or"Sche-duled," respectively, for each shutdown or significant power reduction.
Forced shutdowns include those required to be initiated by no later than the weekend following discovery of an off-normal condition.
It is recognized that some judg-ment is required in categorizing shutdowns in this way.In general, a forced shutdown is one that would not have been completed in the absence of the condition for which corrective action was taken.DURATION.Seifwxplanatoiy.
When a shutdown extends beyond the end of a report period, count only the time to the end oi the report period and pick up the ensuing down time in the folio'wing report periods.Report duration of outages rounded to the nearest tenth of an hour to facilitate summation.
The sum of the total outage hours plus the hours the genera-tor was on line should equal the gross hours in the reporting period.REASON.Categorize by letter designation in accordance with the table appearing Un the report t'orm.If category H must be used.supply briei'comments.
METHOD OF SHUTTINC DOWN THE REACTOR OR REDUCING POWER.Categt>rize by number designation INoie that this differs i'rom the Edison'Electric Institute (EEI)definitions of-Forced Partial Outage" and-Sche-duled Partial Outage." F>>r these tLrnis.I:Fl uses a change of..0 NIW as the break pL>int.FL>r larger pL>>ver reactors.30 MW is u>>>small a change t>>warrant cxpianatiL>>i.
in accordance with the table appearing on the report torm.If category 4 must be used, supply brief comments.LICENSEE EVENT REPORT='.Reference the applicable reportable occurrence pertaining to the outage or power reduction.
Enter the first four parts (event year.sequential report number, occurrence code and report type)of the five part designation as described in Item 17 of Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)File (NUREG416l).
This information may not be immediately evident for all such shutdowns, of course, since further investigation may be required to ascertain whether or not a reportable occurrence was involved.)
If the outage or power reduction will not result in a reportable occurrence.
the positive indication of this lack of correlation should be noted as not applicable (N/A).SYSTEM CODE.The system in which the outage or power reduction originated should be noted by the two digit code of Exhibit G-Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)File (NUREG416I).
Systems that do not fit any existing code should be designa-ted XX.The code ZZ should be used for those events where a system is not applicable.
CO>>IPONENT CODE.Select the most appropriate component from Exhibit I-Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)File (NUREG416I).
using the following critieria:
A.If a component failed,use the component directly involved B.If not a component failure, use the related component:
e.g.>wrong valve operated through error: list valve as"component.
C.If a chain of failures occurs, the first component to mal-function should be listed.The sequence of events.includ-ing the other components which fail, should be described under the Cause and Corrective Action to Prevent Recur-rence column.Components that do not fit any existing code should be de.,signated XXXXXX.The code.ZZZZZZ should.be used.'or events where a component designation is not applicable.
CAUSE Sc CORRECTIVE ACTION TO PREVENT"RECUR-RENCE.Use the column in a narrative fashion to ampiify or explain the circumstances of the shutdown or power reduction.
The column should include the soecific cause for each shut~down or significant power reduction and the immediate and contemplated long term corrective action taken.if appropri-ate.This column should also be used for a description of the major safety.related corrective maintenance performed during the outage or power reduction including an identification of the critical path activity and a report of any single release of radioactivity L>r single radiation exposure speciiically associ~ated with the outage which accounts for more than 10 percent oi the allowable annual values.For long textual reports continue narrative on separate naper and reference tlie shutdown or power reduction for tins lla rfa tive.(L)/7 I cket No.: Unit Name: Completed By: Telephone:
Date: Page: 50-315 ,D.,C.Cook Unit 81 R,.S.Lease (616)465-5901 August 7, 1980 lof 1 MONTHLY OPERATING ACTIVITIES
--JULY, 1980 Hi hli hts The Unit has been shut down the entire reporting period for its fourth Refueling Outage.The time of shut down was 2228 hours0.0258 days <br />0.619 hours <br />0.00368 weeks <br />8.47754e-4 months <br /> 5/30/80.Electrical generation for the month was 0.Summary 7/2/80--Reactor Head was set on the vessel at 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br />.7/9/80--The Reactor Plant entered Mode 5 with the initial bolting of the reactor head.7/20/80--Safety Train"A" blackout testing was successfully completed.
7/21/80--Safety Train"B" blackout testing was successfully completed.
7/23/80-Filling and venting of the Reactor Coolant System, from the~~loop level was initiated at 1812 hours0.021 days <br />0.503 hours <br />0.003 weeks <br />6.89466e-4 months <br />.7/26/80-7/27/80--A steam bubble was formed in the Pressurizer at 0310 hours0.00359 days <br />0.0861 hours <br />5.125661e-4 weeks <br />1.17955e-4 months <br />.System pressure was increased to 325 psig for hand rotation of the four Reactor Coolant Pumps.The 0'14 pump would not rotate when the maximum recommended manual force was applied.Reactor Coolant System pressure was reduced to 0 and the system drained to the 4 loop level by 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />.This was to allow inspection of the thrust bearing of the 5'14 Reactor Coolant Pump.7/30/80-Filling and venting of the Reactor Coolant System was initiated at 0048 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and completed at 1928 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.33604e-4 months <br /> 3/31/80.
~~'e f DOCKET NO.UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50-315 D.C.Cook-Unit No.1 8-6-80 B.A.Svensson 616 465-5901 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE JULY, 1980, M-1 The stem on DG-227C,'1CD diesel jacket water sample valve was broken with the valve open.The valve was replaced.NSW-244-3, non-essential service water containment isolation check valve failed Type C leak test.Seat and disc were lapped and valve reassembled.
NSW-415-2, non-essential service water containment isolation check yylye failed Type C leak test.Yalye body cleaned and new disc in-stalled.M-4 M-6 M-8 No.1 steam generator blowdown regulating valve, DRV-311, had a body to bonnet leak.Disassembled valve, repaired steam cuts and re-assembled with new gaskets.Had valve tested.The reciprocating charging pump discharge valve, CS-386, was leaking by.Disassembled valve and lapped seat.Reassembled with a new stem and plug.The sample pump for radiation monitors R-11 and R-12 would not run.Replaced the pump and had it tested.The motor driven auxiliary feedpump was inspected to check condition ,of the outboard pump bearing.Replaced the rotating assembly and tested the pump.The west centrifugal charging pump had a broken shaft.Replaced the rotating assembly and retested the pump.Safety injection check valves on the lines to the reactor coolant hot legs of all four loops, SI-158Ll, L2, L3 and L4 had body to bonnet leaks.Replaced bonnet gaskets in all four valves.
e~~'A t e t