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Monthly Operating Rept for Jan 1981
	ML17319A698
Person / Time
Site:	Cook
Issue date:	02/12/1981
From:	Tetzlaff A; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17319A697	List: ML17319A696; ML17319A698;
References
	NUDOCS 8102180535
	Download: ML17319A698 (10)
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AYERAGE DAILY UNIT PDMER LEYELO DOCKET NO'.58-316 UNIT 2

DATE 2-5-81 COMPLETED SY A. L. Tetzlaff TELEPHONE 616 465-5901 MONTH Januar 1 81 OAY AVERAGE DAILY POWER LEVEL (MWE-Net)'AY AVERAGE DAILY POWER LEVEL (MWe-Net) 17 18 881 1047 1 50 1063 19 20 21 22 23 1060 106 10 12 13 15 16 1065 1059 1061 25 26 27 28 29 30 10 9

INSTRUCTIONS On this format list the average daily unit power level in MWe-Ilet for each day in the reporting month.

Compute to the neares. whole megawatt.

UNITSIIUTI)OWNS AND POWER REDUCTIONS IlEPORTMONTII January, 1981 DOCKET NO.

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N.A.

ZZ ZZZZZZ Reactor power reduced to 56Ã to re-move the east main feedpump turbine from service to check feedpump tur-bine condenser for tube leaks.

No leaky tubes were found.

Reactor power returned to 1005 the same day.

I.: Forced S: Sci)cd)dcd I9/77)

Reaso>>:

A-EII>>ipmcnt Fail>>rc (Explai>>)

I).hlal>>tc>>a>>ce ur Test C.Rcf>>cli>>g D Rcg>>I))lory IIcstricliu>>

E-Operator Training 8I Ucc>>sc lixamination r"AdIninislralivc G.Opcfalllonal L)rofII'xpl8)i>>)

I I Other (Explai>>)

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I -hla>>>>al 2.hla>>ual Sera)>>.

3-hulo)natic Sera>>).

4 Olllcf(Explai>>)

4 Exl)ibit G - Instr>>clio>>s I'or Preparatio>> of Data L>>try Sl)ccts fo) Lice>>scc rvc>>l Rcp )rl (I.I R) File INUIil:G-OI6 I )

5

'Lxl)ibit I - Sa)>>c Source

NITSHUTDOWNS AND POWER REDU S

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 20% reduction in average daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) should be noted, even though the unit may not have been shut down completeiyl.

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 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 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 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.

Tius column should indicate the date of the start of each shutdown or significant power reduction.

Report year. month. and day.

August i4. 1977 would be reported as 770S14.

When a shutdown or significant power reductior.

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 reducuons are reported.

TYPE.. Use "F" or "S" to indicate either "Forced" or "Sche.

duled," respectively, for each shutdown or significant power reducuon.

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.

Selfwxplanatory.

When a shutdown extends beyond the end of a rcport 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 duratil>n of outages rounded to the nearest tenth ofan hour to facilitate summation.

The sum oi 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 form. Ifcategory H must he used. supply brielcomments.

METHOD OF SHUTTING DOWN'HE REACTOR OR REDUCING POWER.

Categorize by number designation N<oie that this differs t'rom the Edison Electric Institute tEEI) delinitions ot'Forced Partial Outage" and

-Sche.

duled Partial Outage."

F<>r these tern>>. 1:El uses a change oi'0!>IW as the break p<>ini.

F<>r larger puN er reactors. ~0 MW is i<><> smail a change t<> warrant expianati<>>l.

in accordance with the table appearing on the report form.

Ifcategory 4 must be used, supply brief comments.

LICENSEE EVENT REPORT =.

Reference the applicable reportable occurrenc.

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 l7 of Instructions for Preparauon 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.) Ifthe outage or power reduction will,not result in a reportable occurrence.

the positive indication of this lack of correhtion 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 code ot 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 bc used for those events where a system is not applicable.

COMPONENT CODE. Select the most appropriate component from Exhibit I - Instrucuons for Preparation of Data Entry Sheets for Licensee Event Report (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 first component to rnai-funcuon should be listed. The sequence of events. includ-ing the other components which fail. should be described under the Cause and Correcuve 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 where a

component designation is not applicable.

CAUSE 8: CORRECTIVE ACTION TO PREVEI<IT RECUR-RENCE.

Use the column in,a narrative fashion to ampiify or explain the circumstanc s 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-rehted

'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 vr single radiation exposure specitically associ-ated with the outage which accounts for more than 10 percent of the allowable annual values.

For long textual reports continue narrative on separate paper anJ rer'erence the shutdown or power reductivn t'<>r illis narrative.

Docket No:

Unit Name:

Completed 'by:

Telephone:

Date:

Page:

50-316 D.

C.

Co'ok Unit 82 C.

E. Murphy (616) 465-5901 February 9, 1981 lof 2 MONTHLY OPERATING EXPERIENCES - JANUARY, 1981 The Unit Operated at 100% power the entire reporting period except as detailed in the summary.

Total electrical generation for the month was 814,240 mwh'.>>

~Summa@:

1/1/81 Radiation monitors R-25 and R-26 were inoperable for a 10 minute period for'he Techs.

to check the paper. drive.

1/2/81 The Pressurizer Protection Set - Channel 1 Bi-Stables were placed in the Trip position for a two hour period for the Techs. to calibrate.

The Pressurizer Protection Set - Channel 3 Bi-Stables were placed in the Trip position for a 1.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period for the Techs.

to calibrate.

1/3/81 Unit loading was reduced to 56% power starting at 1115 hours0.0129 days 0.31 hours 0.00184 weeks 4.242575e-4 months to remove the East Main Feed Pump from service because of a suspected tube leak in its condenser.

No leaks were found'and the Unit was returned to 100% power at 2330 hours0.027 days 0.647 hours 0.00385 weeks 8.86565e-4 months .

The East Motor Driven Auxiliary Feed Pump was inoperable for a 3.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period to adjust a Relief. Val.ve.setpoint;;.

The West Motor Driven Auxiliary Feed Pump was inoperable fol" a 10.75 hour8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months period to adjust a Relief Valve setpoint.

The West RHR Pump was inoperable for a 1.75 period'due to a problem in the Control Circuit.

I 1/4/81 The East'HR Pump was inoperable for a 1.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period while the pump was lined up to re-circ. to the Refueli,ng Water'torage Tank to remove air from the system.

The East Motor Driven Auxiliary Feed Pump was inoperable for a

'8.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period for repairs to the suction strainer.

1/13/81 The ESF Fan 2-HV-AES-1 was inoperable for a two hour period to change a rollamtic filter.

Docket No:

Unit Name:

Completed by:

Telephone:

Date:

Page:

50-316 D. -C.

Cook Unit 82 C.

E. Murphy (616). 465-5901 February 9,, 1981 2of2 Summar continued) 1/16/81 Unit loading was reduced to 98/ power starting at 2236-to perform Turbine Valve testing.

The Unit was returned to 1005 power at 0025 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months on 1/17/81.

1/26/81 The West Containment Spray Heat Exchanger was inoperable for a 31 hour3.587963e-4 days 0.00861 hours 5.125661e-5 weeks 1.17955e-5 months period to repair a leak on the Essential Service Water Safety Valve.

1/27/81 The West Motor Driven Auxiliary Feed Pump was inoperable for a 5.75 hour8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months period to repair the Check Valve on the Emergency leak-off line.

~ I DOCKET NO.

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

C.

Cook - Unit No.

2 2~10-81 B. A. Svensson 616 465-5901 of 2 MAJOR SAFETY-RELATED MAINTENANCE t

JANUARY, 1981 I(

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1 1

East motor driven auxiliary feedpump emergency leak-off check valve, FW-153, would not seat.

Ground off bonnet-seal weld and disassem-bled.

Replaced the disc and lapped the seat.

Reassembled and seal welded the bonnet.

The suction flange and mechanical seal of the No.

4 boric, acid

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transfer pump were leaking.

Rebuilt the pump using new mechanical seal, oil seals, bearings and gaskets.

Had the pump tested.

The west containment spray heat exchanger essential service water safety valve, SV-14, was leaking.

Cleaned the valve internals, lapped seat, had the setpoint checked and reinstalled.

No leakage detected during operational test.

The setpoint of 2 PB-457D, pressurizer pressure Protection Set III safety injection bistable, was retested based on recent surveillance test data.

The bistable was removed from service and a spare bi-stable (SN-244309) was installed and calibrated.

The setpoints of 2PB-455C and 2PB-455D, pressurizer pressure Pro-tection Set I, low pressure reactor trip and safety injection bi-stables respectively, were checked based on the recent surveillance test data.

2PB-455C bistable was removed from service and replaced with a spare instrument (SN 3806906).

The installed spare bistable calibration and the calibration of 2 PB-455D were performed.

Incore flux mapping system detector B was replaced.

The old de-tector cable was found damaged and would not permit the cable) and detector to be completely inserted.

Voltage, current and frequency spikes were observed on the critical control room power inverter.

Adjustment of synchronizing control R-5 on the synch circuit board brought the inverter into step with the 60 Hz reference source.

Proper operation of the inverter was verified.

Accumulator No. 4, high/low pressure alarm, would not clear.

The trip and reset of bistable PB 967AlB, low alarm, was found to be out of specification and actuating above the required pressure.

The bistable was recalibrated and the alarm was functionally tested.

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DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50 316 D.

C.

Cook - Unit No.

2 2-10-81 B. A. Svensson 616 465-5901 20f2 MAJOR SAFETY-RELATED MAINTENANCE JANUARY, 1981 Main turbine stop valves B and C did not produce closed indication in the control room during the valve testing.

The limit switches were disassembled and cleaned.

The limit switches were reassembled and mounted.

The switches were adjusted for correct operation during stop valve testing on January 30, 1981.

l<CR-903, non-essential service water valve, would not produce closed indication.

The limit switches required adjustment for correct operation.

The valve's closing time was measured and recorded.

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ML17319A698

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