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| {{#Wiki_filter:OPEKKTQC DATA ReoORT DOCN=T XQ.DATE CO~I?K ZiD BY Tii""~H 0Ã:" 50-316 0 M-.Iett 901 ,---"---":--.'02:-'rLaiEBG S iATUS 1.Unit 1'Ianse.Reportin Pe.'od MAY-1 8 S.Licensed Thc.M?ower PIVls}t 4.Hmaeplate Rating (Gross i;DV e): S.Desi@H~U~g (Net MKe)t 6.hhxiznuar Dependable Capacity (Gross 5INe}t 7.ZaZniias ETc a<bio~at@(Nct)IAVe}t 1100~~7 S.If Ganges Ocmr in Cxpac:..I ResŽg, (It~Ymaber S Through 7)Sine=Last Rcpor Give Rcwons 9:.n~e MvcITts Mti~&Rest~,If Arty (Net biNe): 10;R~tsnsYtsr Rat-caaas, lf Any: This bionth Yr.wo-Dat= | | {{#Wiki_filter:}} |
| COL.tive 3 647 3~1 1.5 0 3,096.3 0 0',rl.84.9 0.5 79.2 744 7--"-D.-Rc"t.-.U~ese~e Shn:dovva Ho~0----'-1>>.HomrGam"tarOa:Lne
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| ----IS-..UrdrR~WInsrdtsvtn Ho~, M6.Grosr7ltmnaI'E..
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| ~Ccrc.=t&PIVlH)'.-.'-9''9:" UaiWervi~hetor 2flUdr-.rdhtril~
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| Frrrllr 100 97.9~'m.*~9>>i..:;-Un~os.~mm Rat""4.Shutdovas Schednlcd Over Ncx.: 6 Moa:hs IType, Date, and Dv=tion of Each l: 21 16 14,261.4 13 8.2 0 42,230,796 446 0.0.2.C!ant.~rMOf Re-ort P iod.Btnaatcd 0 te of Stamps~.-'6.Units Ia Test Statns l?nor to Ce~;..~hi Ope.-rior.
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| I: Fo~t Achieved IYITIA L CRITICALITY i~a'ITIA L:-LeCT?lCI~i~(<!r s I<0061'F.O%0, j.
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| A RAGE DAILY UNIT POWER LEVEL OOCKE7'O." 50-316 UNIT 2 DATE 6-2-80 COMPLETED BY W.T.Gi lie<<TELEPHONE 616-465-5901 MONTH DAY.AVERAGE DAILY POWER LEVEL (MWE-Net)10 8 1081 10 8 1061 1057 OAY AVERAGE DAILY POWER LEVEL (MWe-Net)17 18 19 20 21 10 12 13 15 16 io48 1069 1063 1o48 1060 1070 1069 1069.1o68 1o68 894 22 23 25~26 27 28 29 30 31 1067 1067 1o66 1067 1070 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..
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| UNIT SIIUTDOMtNS AND POPOVER REDUCTIONS
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| ~N198 0 DOCKET NO.DA TF 6-11-80 COhIPLETED DY TELEPIIONE 616 465-5901~~N)).Ihtc hK a-0~C/)Lice>>sce I'.vent Rcport Jr OJ~0 Q E~O Ca>>sc Et, Cuff ective Aetio>>lo Prcvc>>t Rccurrc>>cc 77 800516 F 0 A 4 H.A.ZZ ZZZZZZ Reactor power reduced to 605 to remove the east main feedpump turbine from service to check for feedpump turbine condenser tube leaks.One tube was plugged.Reactor power returned to 100Ã800517.I I': Forced S: Scllcdulcd (9/77)Reaso>>: A-EI)uipmcnt Failure (f xplai>>)II hlai>>tc>>ance or Test C-Rcfucli>>g D-Regulatory Rest f let lo>>I:-Operator Training&Ucc>>sc I.'xa>>li>>atio>>
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| F-Administ ra I ivc G.Opcratiu>>al Error (lixplai>>)
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| I I Olllcr (Explai>>)hlethod: I MJ>>>>al 2 hlanual Scraln.3-Autonlalic Sc>>J>>l.A.Otllcr (Explain)f xllibil G-Instructions for Preparatio>>
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| oi Data L>>try Sllccts for Lice>>scc Event Rcp<)rt (LI R)File (NURI!G.OI6I)'Exllibit I-Saloe Source UNIT SHUTDOWNS AND POWER RED IONS INSTRUCTIONS This report should describe all plant shutdowns during the report period.In addition.it should be the source oiexplan-ation of significant dips in average power levels.Each sieni~ftcant reduction in power level (greater than 207'eduction in averaee daily power level for the preceding 24 hours)should be noted, even though the unit may not have been shut down cornpletelyi.
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| 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.
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| NUMBER.This column should indicate the sequential num-ber assigned to each shutdown or sienificant reduction in power for that calendar year.When a shutdown or significant power reduction beeins in one report period and ends in another.an entry should be made for both report periods to be sure Jl 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 signiricant power reduction.
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| 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 significant power reductions are reported.TYPE.Use"F" or"S" to indicate either"Forced" or"Sche-duled," respectively, for each shutdown or significant power reduction.
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| Forced shutdowns include those required to be initiated by no later, than the weekend following'discovery of an oii-normal condition.
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| 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.Seif~xplanatory.
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| When a shutdown extends beyond the end of a report period, count only the time to the end of the report period and pick up the ensuing down time in the following report periods.Report duration of outages rounded to the nearest tenth of an hour to facilitate summation.
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| 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 on the report t'orm.If category H must be used, supply briei'comments.
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| METHOD OF SHUTTING DOWiV THE REACTOR OR REDUCING POWER.Cateeorize by number desienation INoie that this difters irom the Edison Electric Institute IEEI)definitions of-Forced Partial Outage" and-Sche-duled Partial Outage." For these tern>>.EFI uses a change oi'0~IW as ihe break p~iint.For larger pov er reactors.~0 MW is neo small a chance io warrant cxplanaiion.
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| in accordance with the table appearing on the report form.If category 4 must be used, supply brief comments.LICENSEE., EVENT REPORT-.Reference the applicable reportable occurrence pertaining to the outage or power reduction.
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| 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 (NUREG4161).
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| 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.)
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| If the outage or power reduction will not result in a reportable
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| 'occurrence.
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| 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<<ode of Exhibit G-Instructions for Preparation of Data Entry'Sheets for Licensee Event Report (LER)File (NUREG4161).
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| 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.
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| COMPONENT CODE.Select the most appropriate component from Exhibit I-Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)File (NUREG4161).
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| using the following critieria:
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| A.If a component failed, use the component directly involved.B.If not a component failure, use the related component:
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| e.g..wrong valve operated through error: list valve as component.
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| '.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 ftt any existing code should be de.signated XXXXXX.'he code ZZZZZZ should be,.used for events where a component designation, is,not applicable.
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| CAUSE&, CORRECTIVE ACTION TO PREVENT RECUR-RENCE.Use the column in a narrative fashion to amplify or explain the circumstances of the shutdown or power reduction.
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| The column should include the specific cause for each shut-down or significant power reduction and the immediate and contemplated Iong term corrective action taken.if appropri-ate.This column should also be used for a description of the major safety.rehted corrective maintenance performed during the ouiaee or power reduction including an identification of the critical path activity and a report of any sinele release of radioa<<tiviiv vr single radiation exposure speciti<<ally associ-ated with the outaee which accounts for more than 10 percent of the allowable annual values.For long textual reports continue narrative on separate paper and ret'erence the shutdown or power reduction for this n Jrr J tive.<9/77 Dock o.: Unit~me: Completed By: 'Telephone:
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| Date: Page: 50-316 D.C.Cook Unit 82 R.S.Lease (616)465-5901 June 9, 1980 1 Of,3 MONTHLY OPERATING ACTIVITIES
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| --MAY, 1980 Hi hli hts The Unit operated 100/power the entire reporting period except as detailed in the Summary.Total electrical generation for the month was 815,330 mwh.~Sunna r 5/1/80 The Turbine Driven Auxiliary Feedwater Pump was in-operable for a 5 hour period for, testing of trip and throttle valve.5/3/80 5/5/80 Containment Radiation Monitor R-11 5 R-12 were inoper-able foi a 17 hour period for replacement of the sample pump.Reactor power was lowered to 96/to return the Reheater Coils to service following an automatic isolation of the Reheater Coils.After several unsuccessful attempts to return the coils to service the Unit was reloaded to 100Ãpower and operated non-reheat.
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| Total time below 100Ãpower was 13.5 hours.Reactor power was again reduced to 96K for a 5 hour period to attempt to return the Reheater Coils to service.5/6/80 Through testing it was determined that there was a tube.leak in the north set of Reheater Coils.Unit power was reduced to 965 and the south set of Reheater Coils were pl,aced.in service.Total time below 100/power was 8.5 hours.5/9/80 5/10/80 The south set of Reheater Coils were isolated due to a high level in one of the Coil Drain Tanks.Power was reduced to 97/and three unsuccessful attempts were made to return these coils to service.Further testing indicated the coils to have failed tubes.Reactor power was returned to, 1005.Total time below 100K was 11.25 hours.Unit operation continues in the non-reheat mode.Reactor power increased to 101/when a non-borated demineralizer was mistakenly valved in to the Reactor Coolant System.Rapid response by the Control Room Operators using control rods and boration reduced the
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| ~~~~~~)
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| Dockg+Po.:
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| Uni~me: Completed By: Telephone:
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| Date: Page: 50-316 D.C.Cook Unit¹2 R.S.Lease (616)465-5901 June 9, 1980 20f3 5/10/80--(cont.)5/15/80--plant to 100%while the demineralizer was removed from service.Containment Radiation Monitor R-11 was inoperable for a 1.25 hour period due to the filter failing to move.5/16/80--The sample pump for Containment Radiation Monitors R-11 and R-12 failed at 0750.Repairs were made and the mon-itors were again operable at 0617, 5/17/80.Reactor power was reduced to 60%over a 1.25 hour ramp starting at 1330 to remove the East Main Feed Pump from service so the Condenser for this feed pump could be checked for a tube leak.One leak was located and plugged.The pump was returned to service and the unit loaded to 100Ãpower over a 4 ho'ur ramp starting at 2100 the same day..5/20/80--5/27/80--5/28/80--5/29/80--E ESF Vent Fan 2-HV-AS-2 was inoperable for a 11.75 hour period for replacement of the ruffing filter.The Turbine Driven Auxiliary Feedwater Pump tripped.This was while the pump was in it's normal standby (not running)condition.
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| The turbine was reset, test run, and declared operable.A review of ISI test data sheets indicated that the Turbine Driven Auxiliary Feed Pump had not met the minimum required discharge pressure.Since the 72 hour time interval for an"inoperable pump" specified in the Action statement had been exceeded, the pump had to be proven operable or the unit placed in hot standby within one hour.Unloading of the unit was initiated while retesting of the pump was under way.Unit unloading was stopped at 97'/when the pump was proven operable.The unit was reloaded to 1005 power.Total time below 100%power was 1.25 hours.The Steam Jet Air Ejector Radiation Monitor R-15 was removed from service at 1004 for moisture proofing of the detector tube.'This detector was returned to service at 0917, 5/29/80.Vent Stack Radiation Monitor R-25 was inoperable for a.4.75 hour period for replacement of the Filter Drive Motor.5/31/80-A 1%load reduction was experienced following turbine valve testing.The load could not be returned to 100Ãdue to a false indication of th'e turbine operating device 8
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| Docke~o.: Uni~me: CompletŽed By: Telephone:
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| Date: Page: 50-316 D.C.Cook.Unit 82 R.S.Lease (616)465-5901 June 9, 1980 30f 3 5/31/80--high limit switch.The load was returned to 100%(cont.)by briefly by-passing the switch function.Total time at.,99Ãwas 13.5 hours.Condenser halves were taken out of service, one half at a time, for a total of 57.5 hours during the report-ing period.This was for identification and repairs of leaking tubes.
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| I E/l DOCKET NO.UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50-316 D.C.Cook-Unit No.2 6-11-80'BBB.svensson 616 465-5901 1 of 2 MAJOR SAFETY-RELATED MAINTENANCE MAY, 1980 M-3 CSI-1 CRI-2 CSI-3Low flow was detected from the sample pump for R-25, containment air particulate detector.Replaced the pump and verified operability.
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| The CCW sparge tank east level recorder isolation valve, CLR-410V2 was'leaking.'.
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| Replaced valve and tubing.'o.
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| 3 steam generator power relief valve, MRV-233 was leaking by.All gaskets were replaced;disc,, pilot disc and pilot seats were machined.The valve was leak tested and operability verified.The pressurizer level control system would not maintain the set point level during automatic operation.
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| The reset action of level controller LC-459 was removed and flow controller FC-121 gain was reduced.The control system now responds and maintains pressurizer level at the pro-grammed set point.Steam generator level protection set III, steam generator No.3 level low-low and high level bistable LB-538AlB required replacement due to a drift problem in the high alarm set point.A spare bistable was installed and surveillance test 2 THP 4030 STP~117 was performed to verify the channel's operability.
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| Ice condenser temperature recorder SG-017 indicated off scale at the low end of travel.The servo motor, point selector switch and pen drive amplifier card were replaced.,The recorder was calibrated per 12 THP 6030 IMP.079 and returned to service.C&I-4 CSI-5 The comparator and rate drawer channels for the nuclear instrumentation system displayed a deviation alarm.The alarm was present with the deviation between.channels less than the required set point.The bistable card for channel deviation alarm actuation was replaced with a spare card and the calibration of the bistable was performed.
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| Radiation Monitoring System Channel Rll, containment air particulate monitor, air pump tripped without producing an alarm in the control room.The alarm bulb had been replaced with a neon type which was incorrect.
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| A filament type bulb was installed and operated properly.The air pump was tripping on low air flow.The air flow indication rotometer required replacement.
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| The alarm unit was calibrated for correct set points and the air flow rate was adjusted for 10 cfm flow.
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| E>l DOCKET NO.UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50-316 D.C.Cook-Unit No.2 6-11-80 B.A.Svensson 616 465-5901 2of2 MAJOR SAFETY-RELATED MAINTENANCE MAY, 1980 The analog rod position indication meter for control rod M-2 was in-dicating full scale.The panel meter was removed and a spare meter was installed.
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| Correct rod position indication returned.The pressurizer pressure control hand/automatic station was not oper-ating properly in either position.An out-of-balance condition in the pressurizer pressure master control module PC-455A was discovered.
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| This module tracks the hand/auto station when in the"manual" position, so that change-over to"auto" will not cause a step-change to the spray valve and other controllers following PC-455A.The module was balanced and retracked, and a set point dial calibration was performed.
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| Pressure control then was satisfactory.}}
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