ML17317B014

Monthly Operating Rept for Feb 1979

ML17317B014
Person / Time
Site:	Cook
Issue date:	03/01/1979
From:	Gillett W INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17317B013	List: ML17317B012 ML17317B014
References
NUDOCS 7903210214
Download: ML17317B014 (10)

Text

AVER.<GE DAILYUN1YPOKER LM~

DOCK=-i NO.

UN1T OAT=-

3-1-79 COMPLETED gY M T.

~ Gi11'et:t:

61 6 465 5901 Febr uar DAY AVERAGE DAlLYPO4ER LEVEL (M'h'meet) 1070 106 DAY AVERAGE DAlLYPOWER LEVEL (MWe-. set )

10 877 13 IS 16 1070 1073 1070 1070 1067 1066 1014 735 1062 1056 1066 1055 1057 19 20 30 31 1060 1067 1004 1001 1025 1013 948

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OPERATING DATAREPORT OPERATING STATUS I. UnitN~,t Doll~id C.

Cook 2

Reporting period:

Februa 1 9

3. Licensed Thermal Power (MWt):-

3 391 4.. Nameplate Racing, (Gross MWc):

1 +133 S. Design Electricd Rating (Net MWe)t

6. Maximum Dependable Capacity (Gross hfWe)t 1

1 8

7 Maximum Dependable Capacity (Net MWe)t 1

082 Notes DOCKET NO.

DATE ~~9 CODIPLETED BY ~W~ett TEL'EPHONE 516=~~901 S. IfChanges Occur in Capacity Ratings (Ite~ Number 3 Through 7) Since Last Report. Give Reasons:

9. Power Levd To Which Restricted, IfAny (Net MWe):

10. Reasons For Restrictions, ifAny:

Ttus Month Yr:to-Date Cumuhtive 101 6

6 613.2 0

1362.6 6 090.2 0

0 17 566 383 1,393.039 5 207 038 81.8

96. 2 100 81.8 96.2 71.6 90.9 70.4 6.0 3.8 12

13. Re"ctor Reserve Shutdown Hours 0

14. Hours Generator On~

2 222 IS. ilet Electricai Ene~ Generated (hfWH}

19. Unit.Serrate= Factor

20. Unit Asaihbility Factor 100

~D. Unit Forced Outage Rate 0

24. Shutdowns Scheduled Over iNext 6 Months (Type. Date.and Duration of Eachl:

5. IfShut Dov'n At nd Of Report Period. Estimated Dare oi Startupt

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5. Units ln Test Status (Prior to Commercial Opemrion):

Forecast Achieved I/ITIAL CRITICAI.ITY INITIAI ELECTRICITY CO:.'I~IERCIALOPERATION

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REP MO Nn OIV fii << rua En CTI NS 19 9 UNITNAh nA COMPLETED TELEPIIO fEy

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Sv nsson 5-5901 616 46 nocKET No.

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Dale CI IA CgQ A<<J x 5C U< s

~ Vl Cl Llccttscc Event Rcport rr 0

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O CJ Cause h. Corrective Action lo Prcvcnl Rccurrcncc 50 51 790210 S

790218 S

0 0

N/A N/A HH VALVEX ZZ Zzzzzz Reactoi power reduced to 51% to re-move east main feed pump from ser-vice to permit repacking the pump emergency leak-off -valves.

Reactor power returned to 100% 790211.

Reactor power reduced to 80K to con-duct moisture separator tests.

Re-actor power returned to 100K 790218.

I. r: ror"d S: Suited<<lcrl Reason:

A-Equipment Failure (Explaitt)

D.hlaltttcnancc or Test C-Rcruciitri; D-Reiudalory Reslriclton E.Operator Trainini; Ec License Exallliltalioll F-Administrative G Opcratiottal Error (I'.xplaittl II Ollter (Explain) hlelltod:

I-Manual 2 Manual Scratn.

3-Automatic Scram.

4 Olllef(Explallli Exhibit G - Instructions ror Preparation of Data Ltttry Sltcets for Liccttsee Event Rcport (I.I!R)File INIIRI.'G.

OI 6I )

5 Txhiblt I - Saute Source

INSTRUCTIONS This report should describe all plant shutdowns during the report period.

In addition, it should bc the source ofexplan-ation of significant dips in average power levels.

Each signi ~

ficant reduction in power level (greater than 20% reduction 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 reducuon should be listed as 4 (Other), and the CauM and Corrective Action to Prevent Recurrence column should exphin.

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 coluinn 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 Jl shutdowns or significant power reductions are reported.

Until a unit has achieved its first power generation,'o rium-ber should be assigned to each entry.

DATE.

This column should indicate the date of the start of each shutdown or significant 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 significant power reductions are reported.

TYPE.

Use "F" or "S" to indicate either "Forced" or "Sche-duled," respecriively, 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 oifwormal 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.

Seifwxplanatory.

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 following report periods.

Report duratiOn of outages rounded to the nearest tenth vfanhour to facilitate summation.

The sum of the, total outage hours plus the hours the genera-tor was on line should equal ihe gross hours in the reporting period.

REASON.

Categorize by letter designation in accordance with the table appearing on the report form. Ifcategory H must be used. supply briei'comments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Caieaorize by number designation INoie that this difiers i'rom the Edison Electric Institute tEEI).defmitions of -Fore'ed Partial Outage" and

-Sche-duled Partial Outage."

Fair these tern>>. I:FI uses a change of

.0 MW as the break. point, For larger pow'er reactors. 30 MW is l>><i small a change io warrant cxpianaiion.

in accordance with the table appearing on the report iorm.

Ifcategory 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 cours, since further investigation may be required to ascertain whether or not a reportable occurrence was involved.) Ifthe 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).

SYSTFM 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 desiana-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 Rcport (LER) File (NUREG4161).

using the followingcritieria:

A. Ifa 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 fiat component to mai-funcuon should be listed. The sequence of events. includ-ing the other components which fail, should be described under thc Cause and Corrective Action to Prevent Recur-rence column.

Components that do not fit any exisung code should be de.

signated XXXXXX. The code ZZZZZZ should be used for events where a

component designation is not applicable.

CAUSE &, CORRECTIVE ACTION TO,PREYED'ECUR-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. ifappropri ~

ate.

This column should also be used for a description of the major safety. related corrective maintenance performed durina the outage or power reduction including an identification of the critical path activity and a report of any single release oi radioactivity vr sinale radiation exposure specitic~ily associ-ated with the outage which accounts for more than 10 percent of the al!owable annual values.

For long textual reports continue narrative on separate paper and reference ilie shutdown or power reduction ior ibis llarfailvc.

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DOCKET NO.

50 316 UNIT NAME D. C. Cook - Unit No.

2 DATE 3-14-79 COMPLETED BY B. A. Svensson TELEPHONE 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE FEBRUARY 1979 M M-2 M-3 Unit 82 650'levation outer airlock door had a broken gear tooth.

Replaced broken gear and tested door and interlock.

ESW supply check valve to 2AB diesel, ESW-143, failed to seat during test.

Valve was disassembled and rebuilt using new parts.

Due to improper certification, parts were removed until proper documentation could be obtained.

The parts were accepted by subsequent receipt in-spection.

The valve was reassembled, tested and returned to service.

The 2W CCW pump outboard bearing was running hot.

Replaced bearing.

Inspected oil pump, pump shaft and housing.

Tested CCW pump and returned to service.

M-6 C&I-1 C&I C&I-3

- ClkI-4 During inspection of aux. feedwater motor operated

valves, FMO-222 was found to have a broken wire on switch terminal

//49.

Repaired wire, had valve tested and returned to service.

East ESW pump performance data indicated some degradation.

Adjusted impeller clearances and had pump retested.

Circuit breaker 21PHC6 for pressurizer variable heaters was tripping.

Replaced solid state trip device with a new one and tested breaker.

The containment fire detection system would not test or alarm.

A 3 mfd capacitor in the 12 volt power supply was replaced and the 15 volt power supply was adjusted for the correct output level.

The "Nuclear Instrumentation System Tilt or Rod Sequence Violated" alarm was received.

The computer indication for Control Bank B was lower than 228 steps.

The Nuclear Section reset the computer to the correct indication.

The computer error was caused by the Rod Control Logic Cabinet.

A job order is presently on hold for an outage, to

-repair the problem within the logic cabinet.

Radiation monitoring system channel R-25, paper drive failed.

The filter paper drum was tightened and a rubber clutch gromet repaired.

During the performance of the monthly surveillance test 2PB-935B, con-tainment pressure high bistable, was determined to be out of specifi-cations.

The instrument was removed and replaced with a spare duplex bistable.

The removed instrument is currently being observed to de-termine the cause of the set point drift.

0

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50 - 316 D. C.

Cook - Unit No.

2 3-4-79 B. A. Svensson 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE FEBRUARY, 1979 IFI-265, recirculation flow indication of the safety injection pumps to the RNST, failed.

The flow instrument was removed, cleaned and flange tightened.

The instrument was returned to service and verified operational.