ML17326A717

Monthly Operating Rept for Jul 1980

ML17326A717
Person / Time
Site:	Cook
Issue date:	08/04/1980
From:	Gillett B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17326A716	List: ML17326A715 ML17326A717
References
NUDOCS 8008150355
Download: ML17326A717 (11)

Text

s~OPEK<TLNG DATA REPORT DOCK:"T YO.DAT5E COifPL TED BY TE~~HOKE 50-316 8-4-80.~R.G11 t~~901--:---.OPERATIC!G~iA i L~S D: C.Jul l.Unit)lame: 2 Reporting Period: 3.Lfcaxsed The~sl Pov)er (liiY/t)t 4.Nmnephtc R ting (Gross fDVe)t S.Desi@a EiewU Mn~(Net s)DVe)t 6.5f~am DepentLtble Cspnc!Cy (Gross MYejt~sfamcaum XLa=~&Mc Cnuociry fHer b.'sYe)r 1980 3391 1100 1118 Not s a 8.If Ch~~esOcmrinCxFtci..r 8 t'~(items Yumbe SThrocgh I)SinceLsstReport.

GiveRewonst

'"9~oeMevel"Fa Vhi"'t Rester ct~, If Any (Net MEVe): 'O ReswsSorKschtfons, L Any:&month Yr.-to-Dat=

Cumulative II.Ho)f's lÃRep'6rautt'Period.

~'IX Nu'r'nb~OH.bT)~Re ctor Yfw CririM 1S.Re"cps?'geese'e Sh'6:doves H os=N~.Homs~~tttr Or)Zine kZ U."dt RMMe Sittittfttwn Ho~" 16: GraSG Tlat'nGEn~y Gene.t~'{bf>VH)T7.GrowEhe<~~c~y Gene~t&(i IWH}.I8.i aerie"~Mal

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"~0-.Un~~'hbil~nuctor I.Un?~Xc af Octo'L (Usinan M+C Yet).UalrCtsafofO sar sos (Usfn ORR Nos/~.Un@~asa-d'Oasaoa Ros-~'.Shutdowns Scheduled Over Next 6!tfonths 744 0 431.9 0 0'4 175.3 58.0 58.0 81..7.73.0 73.0 0 (Type.Dote.cn Du:stion of'cch It 1.4 10.3 MKB.K9=M~ZOMZ6 CamLas~.'5'5 5,'5 555 55 427,116 4,285,826 14 053 238.ffShaMere Sad Of R="o:5 f:tfod, Bsi5nnsod O so of Ss-::oo:~S.Units ln Test Situs IPrior to Ccw-.-erchl Ope.tion): Forec" st Achieved Ib ITIA L CRIT)ICA LITY I YI TIA L ELEC)R SCI~)~"CO.'t.'IERCIAL OPE:.ATION

008150 355.'

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO'.UNIT COMPLETED BY W.T.Gill tt TELEPHONE 616-465-5901 MONTH Jul v 1 80 DAY , AVERAGE DAILY POWER LEVEL (MWE-Net)DAY AVERAGE DAILY POWER LEVEL (MWe-Net)8 10 12 13 14 15 16 157 994 1016 1031 17 18 19 20 21 22 23 24 25 26 27 28 29'30 31 1020 980 368 1013 1018 1022 1044 1042 982 910 1042 1051 1031 1036 1032 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 SIIUTI)p)VNS AND Pp'SUER REDUCTIONS REPpRT MpN Tll JUlY s 1980 l)OCKET Np.UNIT NAhII D C Cook-Unit 2 DATE 8-6-80 Cph(PLETED I)y B.A.Svens son PllpNE 6 65-590 l)atc P)0 Vl J Liccnscc Event RcPort Jr O s Q D 2~O Cr Cause&.CoflccI Ivc Action to Prcvcot Rccurrcoce 78 79 80 800627 800719 800725 7.9 0 N.A.N.A.N.A.zz zz zz zzzzzz zzzzzz zzzzzz Outage, continued from previous month.Primary purpose for the outage was to complete auxiliary feedwater system modification.

Unit returned to ser-vice 800713.Reactor power at 100%800714.Reactor/Turbine trip.The reactor tripped due to low-low level in No.1 steam generator.

The low steam gen-erator level was caused by an appar-ent loss of steam supply to the east main feed pump turbine.The Unit was returned to power the same day.Reactor power increased to 1005 800720.Reactor power reduced to 60Ãto re-move the east main feed pump turbine from service to check for feed pump turbine condenser tube leaks.One tube was plugged.Reactor power was returned to'lOOX 800726.I': Forced S: Sclled<<lcd

(')/77)Reason A-Erluipo)cnt Failure (Explain)Il.hlalotcoance or Test C-Rcfucliog D.Rcgolatory Restriction E.OPeratl)r Training&License Lxaollolltloo F-Adolioistrative G Operational Llror (I:xplalo)

I l.ot lier (Lxl)I Jul)3 hictbod: I.Maoual 2.hlaoual Scraln.3-Autoo)atic Scralo.4-OII!cf (Exl)I Jn))Exllibit G-Instructions f))r Preparatio>>

of Dala I;otry Sllccts I'or Liccosec Event RePort (LI!R)File (NURI!G-016I)'Iixllibit I-Salo<<Soulce Ui fIT SHUTDOWNS AND POWER REDU ONS INSTRUCTIONS This report should describe all plant shutdowns during the report period.In addition, it should be the source ofexplan-ation of significant dips in average power levels.Each signi-ficant reduction in power level (greater than 2'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 completelyl.

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 futly describe the circumstances of the outage or power reduction.

NUMBER.This column should indicate the sequential num-ber assigned to each shutdov:n or signiiicant 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 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 signiticant power reduction.

Report as year.month.and day.August 14.1977 would be reported as 770814.When a shutdown or significant power reduction beginsin 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.

Forced shutdowns include those required to,be initiated by no later than the weekend following, discovery of an oif-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.Selfwxplanatory.

When a shutdown extends beyond the end of a report period, count only the time to the end ot'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.

The sum of the total outage hours pius 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 I'orm.If category H must he used.supply briei'omments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.Categorize by number designation I Note that this differs i'rom the Edison Electric Institute IEEI)definitions ot'Forced Partial Outage-and-Sche-duled Partial Outage." Fiir these tern>>.EEI uses a change oi'0 4IW as the break poini.For larger power reactors.30 MW is i>>o small a change t<>warrant explanatii>>i.

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.

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).

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).SYSTEiM 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).

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.

COMPONENT CODE.Select the most appropriate component from Exhibit I-Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)File (NUREG4161).

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 for events wnere a component designation is not applicable.

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.

The column should include the specific 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.rehted corrective maintenance performed during the outage or power reduction including an identification of the critical path ac:ivity and a report of any single release of radioactivity vr single radiation exposure spe<<itieally associ-ated with the outaae which accounts for more than 10 percent of the allowable annual values.For long textual reports continue narrative on separate paper and reterenee the shutdown or power reduction t'or this li J fr Jtlvc.

ket No.: Unit Name: Completed By: Telephone:

Date: Page: 50-316 D.C.Cook Unit g2 R.S, Lease (616)465-5901 August 7, 1980 Page 1 of 3 MONTHLY OPERATING ACTIVITIES

--JULY, 1980 Highlights The Unit entered the reporting period in a Cold Shutdown (Mode 5)outage.The Unit had been removed from service at 2307 hours0.0267 days <br />0.641 hours <br />0.00381 weeks <br />8.778135e-4 months <br /> 6/27/80 and cooled to Mode 5 by 0925 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br /> 6/28/80.The primary purpose for this outage was to permit comple-tion of the auxiliary feedwater modification, which will give each unit its independent auxiliary feedwater system.The Unit was returned to service 7/13/80 which is detailed in the su@vary.There was one other outage 7/19/80 when the flow reduced fromione'of the Mai'n Feed Pumps.This is also detailed in the summary.Total electrical generation for the month was 443,530 MWH.Summary 7/5/80--The Emergency Diesel Fire Pump was inoperable for a 29 hour3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> period, starting at 0647 hours0.00749 days <br />0.18 hours <br />0.00107 weeks <br />2.461835e-4 months <br />.This was for cleaning of the discharge strainer.7/ll/80-After completion of outage work, Unit Startup was ini ti ated at 2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br />.7/12/80--The Reactor Plant entered Mode 4 at 0608 hours0.00704 days <br />0.169 hours <br />0.00101 weeks <br />2.31344e-4 months <br />.The Reactor Plant entered Mode 3 at 1912 hours0.0221 days <br />0.531 hours <br />0.00316 weeks <br />7.27516e-4 months <br />.7/13/80--The Reactor was critical at 1235 hours0.0143 days <br />0.343 hours <br />0.00204 weeks <br />4.699175e-4 months <br />.The Turbine Generator Unit was rolled at 1418 hours0.0164 days <br />0.394 hours <br />0.00234 weeks <br />5.39549e-4 months <br /> and placed in parallel with the system at 1613 hours0.0187 days <br />0.448 hours <br />0.00267 weeks <br />6.137465e-4 months <br />.Loading was increased to 100Ãpower by 0510 hours0.0059 days <br />0.142 hours <br />8.43254e-4 weeks <br />1.94055e-4 months <br /> 7/14/80.7/17/80--The"CD" Emergency Diesel Generator was inoperable for a 7.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period for replacement of a faulted thermocouple.

I II C, h ket No.: nit Name': Completed By: Telephone:

Date: Page: 50-316.D.C.Cook Unit¹2.R.S, Lease ('616)465-5901 August 7, 1980 Page 2 of 3 7/19/80--The Unit tripped at 0004 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> due to Low-Low level in¹1 Steam Generator.

This was caused by reduced flow from the East Main Feed Pump which was seen to be losing speed.Power level at time of trip was near 100'A.An attempt was being made to reduce loading to match the reduced feed-water flow.Early analysis of the feed pump problem was that steam pressure regulating valve ARV-ll, which supplies steam to the feed pump turbine, had malfunctioned.

Thorough check-out of the feed pump turbine and its steam supply could not identify any problem, and this pump was returned to service with the Unit.The Reactor was retur ned to criticality at 0439 hours0.00508 days <br />0.122 hours <br />7.258598e-4 weeks <br />1.670395e-4 months <br />.4 The Turbine Generator Unit was rolled at 0626 hours0.00725 days <br />0.174 hours <br />0.00104 weeks <br />2.38193e-4 months <br /> and placed in parallel with the system at 0757 hours0.00876 days <br />0.21 hours <br />0.00125 weeks <br />2.880385e-4 months <br />.The Unit was loaded to 50!power by 1159 hours0.0134 days <br />0.322 hours <br />0.00192 weeks <br />4.409995e-4 months <br /> and held at this point while check-out of the East Main Feed Pump was taking place.Unit loading was initiated at 1740 hours0.0201 days <br />0.483 hours <br />0.00288 weeks <br />6.6207e-4 months <br />.7/20/80--Unit was loaded to 100$power by 0355 hours0.00411 days <br />0.0986 hours <br />5.869709e-4 weeks <br />1.350775e-4 months <br />.Valve IMO-910 (suction from Refueling Water Storage Tank to Charging Pumps)was inoperable for an 11.75 hour8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> period when the valve failed to stroke with power.7/21/80--Containment Radiation Monitors R-11 and R-12 were inoperable for a 7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> period while repairs were made to the filter paper drive.7/23/80--The East Residual Heat Removal, System was inoperable for a 17 hour1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> period for preventive maintenance.

7/25/80--The Fire Detection System of Engineered Safety Feature Ventilation Charcoal Filter HV-AES-1 was inoperable for a 3.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period for necessary repairs.

C R P

~~cket No.: nit Name: Completed By;Telephone:

Date: Page: 50-316 D.C.Cook Unit k2 ,R.,S.Lease (616)465-5901 August 7;1980 Page 3 of 3 7/25/80 Unit loading was reduced to 604 over a 1.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> ramp starting.at 2157 hours0.025 days <br />0.599 hours <br />0.00357 weeks <br />8.207385e-4 months <br /> to remove the East Hain Feed Pump from, service to check its,condenser for a:tube leak.7/26/80--After plugging one-leaking tube in the Condenser of;the East Hain Feed Pump, the pump was returned to service and the Unit Loaded to 100/power over a 5.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> ramp starting at 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br />.7/30/80--The"AB" Emergency Diesel Generator was inoperable for a 5.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> period for cleaning of relays.Hain condenser halfs were out of service, one-half at a time, for a total of 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> during the re-porting period for location and repairs to circu-lating water leaks.Prioi to the cold outage at the start of the report-ing period, the Unit was operating non-reheat due to,tube leaks in some of the reheater coils.Dur-ing the outage, four of the eight reheater coils were identified to have tube leaks.The leaking tubes were removed and tube sheets plugged.Several attempts have been made to place the'oils in service but this has been unsuccessful.

The Unit continues to.operate non-reheat.

DOCKET NO.UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50-316 D.C.Cook-Unit No.2~8-6-80 B.A.Svensson 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE JULY, 1980 No.1 steam generator blowdown regulating valve, DRV-312, had a body to bonnet leak.Lapped the valve seats and replaced all the gaskets.Had valve tested.M-2 CS I-l A weld leak was detected downstream of a newly installed test valve on the discharge of the motor driven auxiliary feedpump.The 1" socket weld connection was rewelded and NDE was completed.

Loop 3 protection channel II High Steam Line Flow status light was periodically received.MFP-130 calibration was performed and returned to service.CSI-2 ILA-121, accumulator level indication was cycling between 50 and 60 percent.The redundant channel ILA-120 was remaining constant.Transmitter ILA-121 was calibrated and returned to service.Normal control room indication was restored.CRI-3 C&I-4 FRV-240, steam generator No.4 feedwater regulating valve, was sticking in various positions.

The valve actuator was replaced and proper valve operation verified.The axial power distribution monitoring system failed to print the data.The power supply for the printer had failed.A spare power supply was installed and normal operation of the printer was verified.

S'A~~~'I t'1, 1