ML17326A780

Monthly Operating Rept for Oct 1980

ML17326A780
Person / Time
Site:	Cook
Issue date:	11/04/1980
From:	Gillett W INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17326A778	List: ML17326A777 ML17326A780
References
NUDOCS 8011180625
Download: ML17326A780 (10)

Text

0?ERATIiG STATUS OPF<KTP'C DATAREPORT h

DOC:~T XO.

50-315 D~T=- ~>>-

COiiPL ZED BY ~~ett TEI'"~HONE Qil&JM901

'onald C. Cook October

1. Unit ihnte:

+~ Reporting

<<Mod S. Licmed Th 'f?owe." PIY/t)t

4. Yhtneofate Rating (Gross l>I)Ve):

S. Design Elean&~g (Net M)'>e)t

6. h~tntr Depcndabfe Capacity (Gross MÃe)t

7. >faxisnutn Dep=zdabf C-padty (Net Mme)t 1980 3250 1089 1044 itates S. IfChan"es Occur in Cxpac.".( Ratf"gs (Itas Yumber S Throg<

7) Since Last Report, Give Rcasanst

9. Powe= Levef Ta M&'tRestr

~, IfAny (Piet MKe):

10. Reasons For ~coons, IfAnyt This Month Yr.wo-Dat=

Cu~tive 724 5 272.3 0

463 0 2

. ~2 0

0 2,312,061 16,033,104 105 099 410 5,126,251 33 123 565 4,589

70. 9

76. 1

70. 9 7.1 8.9 IL Nutnoer Of Houm Reactor Yeas C.":nM

13. Re"ctor Reserve Snu down Ha~

I4. Hours Generator Qn~>

lS. Urdt Reeve Shutdown Ho~

16. Gross Th~af En:~y Cene.=ted P IWH)

17. Gross Eic~c"I Zne~ Gen=rat& (i'1WH)

IS. Yet H~cJ me~ Gener

" (; I'>'>"ri)

19. Unit Serric" Factor

96. 8

20. Unit A)&biTiryFactor

~. Unit Capacity Factor (Using DER Yet}

~Ra.~

Z4. Shutdowns Schedufed Over;"iex< 6 f fonths fiype. Date: and Duction of Each}t "S.'f Shut Down AtEnd'Of Report

~ iod. Estimated Date ai Stam.pt

~

.'S. Units la Test. Sums(?thor to Ce~-...~al Op

. tian}:

Fo~t Achieved fYITIAL CRITiCAUTY P41T1AL "=LeCTR!Cf' CO.'f~fERC}Ai QPERAT}OY I

>> }

~

~

~'ii

AVERAGE DAILY UNIT POWER LEVEL DQCIIETIIO'.~

UNIT 1

DATE 11-4-80 COMPLETED BY W. T. Gillett TELEPHONE 616-465-5901 MONTH OCTOBER 1980 DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 10 12 13 15 16 1038 1040 1029 1034 1048 1043 1045 1043 1048 1049 44 669 1047 1049 1048 1047 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 1044 1040 1044 1046 1047 1049 1049

,1038 1048 1050 1048 1049 1051 1051 1051 INSTRUCTIONS On this format list the average daily unit power level in MWe-Net for each day in the reporting month.

Compute to the near est whole megawatt.

REPORT hlONTII 80 UNITSIIUTI)01VNSAND PO)VER REI)UCTIONS l)OCKETNO.

UNITNAhlE D. C.

Cook U

1 I)ATF 11-12-80 TELFPIIONF 616 465-5901 NJ).

l)ale L

P c rX A~

JJ s U< r

~ LI)

A Liccoscc Eveol.

Rcpi)rl rr Cause k. Ci)rreclivc Action ti)

Prcvclll RccLIlrc))cc 168 801011 24 B

N.A.

zz zzzzzz While attempting to perform turbine control valve testing at 100% power, control valve oscillations became excessive.

The oscillations created steam generator pressure fluctuations which resulted in "high differential pressure between steam leads," causing safety injection actuation to occur.

The safety injection signal caused the reactor/turbine trip.

The safety in-jection was reset and the pumps shut down after 12 minutes of operation.

The reactor was brought critical the same day and the Unit returned to service on 801012.

1005 reactor power was reached on 801013.

I I'

Fi)fi;Cil S: Sclied<<lcil Reasi)n:

A-E Ioipmcnl Failure (Explaiii)

II-hlaliitcnance or Test C-Reft)elii)I, I)-RcI,I)latory Reslricliuli L-Operator Trainit)i, 8L Lice>>sc lixa)L)loation I"AdlillllisIIIIIivc G Oi)cralioilal hri)r (Explaiii)

II-Otller(I:xplaiii) t 3

hlelhod:

I.hlaliual 2 hlaoual Scraln.

3-Auli)o)alic Scraio.

4.0tl)cr (Explaoi) 4 I'xiiibilC lnslruclb)ns fi)r Preparaliinl of I)ala I:otry Slicels for Lice))scc Event Rcpi)rl (LI!R) File (NllREC~

0 I 6I )

I.'xl)ibit I

~ Saioe SL)urcc

UNITSHUTDOWNS AND POWER RE IONS INSTRUCTIONS This report should describe aQ plant shutdowns during the report period.

In addition, it should be the source of explan-ation oi signiticant dips in average power levels.

Each signi ~

ftcant reduction in power level (>treater 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 reduction should be listed as 4 (Other), and the Cause and Corrective Action to Prevent Recurrenc.

column should explain.

The Cause and Corrective Action to Prevent Recurrence column should be used to provide any needed explanation to fuQy 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 aQ shutdowns or significant power reductions are reported.

UntQ a unit has achieved its first power generation, no num-ber shouid be assigned to each entry.

DATE.

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

TYPE.. Use "F" or "S" to indicate either "Forced" or "Sche-duled," respectivclv, 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 acuon was taken.

DURATION.

Self~xplanatoty.

When a shutdown extends beyond the end of a rapport period, count only the time to the end of the report'period and pick up the ensuing down time in the foQowing.report periods.

Rcport duratiOn of outages rounded to thc nearest tenth ofan hour to facilitate summation.

The sum or the total outage hours pius the hours the genera-tor was on line should equal the gross hours in thc reporting period.

REASON.

Categorize by letter >Iesi>tnativn in accordance with the table appearing on the report form. Ifcategory H must he used. supply briei'comments.

METHOD OF SHUTTING DOWN THE REACTOR OR

" REDUCING POWER.

Categorize by number designation iNvte that this differs i'rom the Edison Electric Institute tEEI) deimitions ot'Forced Partial Outage-and

-Sche-duled Partial Outage.-

F>>r these t<>~. FEI uses a change vi'.0 MW as the break p>>int.

F>>r larger power reactors.30 MW is t>><> small a <<hange t>> warrant expianati>>>>.

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 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 Preparauon of Data Entry Sheets. for Licensee Event Report (LER) File (NUREG416}).

This information may not be immediately evident for aQ such shutdowns, of course, since further investigation may be required to ascertain whether vr 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).

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).

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

~ Instructions for Preparation of Data Entq 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

faQure, 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 mai-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 Prcvcnt 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 b 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 specific cause for each shut-down or significant power reduction and the immediate and contemplated iong term corrective action taken. ifappropri-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 a<<tivity and a report of any single release of radioactivity vr sin>tie radiation exposure spe<<iti<<aQy asso<<i.

ated with the outage which accounts for more than 10 percent oi the allowable annual values.

For long textual reports <<ontinue narrative on separate paper an>l reterence the shutdown or power reduction iv> thi>

narrat!ve.

a

~

~

et No.:

nit Name:

Completed By:

Telephone:

Date:

Page:

50-315 D.

C.

Cook Unit Pl C.

E. Murphy (616) 465-5901 November 10, 1980 10f2 MONTHLY OPERA I G

C IVITIES -- OC R,

1 8 The Unit entered this reporting period operating at 99K power.

This being the last step in power escalation following the Unit refueling.

There was one outage of the Reactor and Turbine Generator Unit accompanied by a Safety Injection during the reporting period.

This is also detailed in the Summary.

Total electrical generation for the month was 771,050 mwh.

10/01/80 - The Unit was loaded to 100Ã power at 1905.

This was the first operation at 1005 for this Core.

10/02/80 - The South half of "C" Condenser was out of service for a 6.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> period for checking of tube leaks.

10/03/80 - The South half of "A" Condenser was out of service for a 6.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period for checking of tube leaks.

Power was reduced to 905 for testing of Turbine Valves.

Total time below 100Ã was 10.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

10/04/80 - The 50'ind Direction Recorder was out of service for a 5.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period for repairs.

10/06/80 - The North half of "A" Condenser was out of service for a 9 hour1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> period for checking of tube leaks.

10/07/80 The South half of "B" Condenser was out of service for a 8.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> periodfor checking of tube leaks.

10/08/80 - Condensers removed from service for leak testing and repairs were as follows:

",I "B" North Condenser'or 9.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.

"C" South Condenser for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

10/09/80 - The North half of "C" Condenser was out of service for a 7.75 hour8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> period for checking of tube leaks.

1

'J F

C t No.:

it Name:

Completed By:

Telephone:

Date:

Page:

50-315 D.

C.

Cook Unit 81 C.

E. Murphy (616) 465-5901 November 10, 1980 2of2

. Summar'::

-'n 10/10/80 - Power was reduced to 97K for testing of Turbine Valves.

Total time below 1005 was 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

10/11/80 - An attempt to check Turbine Valves at lOOX was performed which resulted in some extreme oscill-ations of the Turbine Control Valves.

The oscill-ations created a High Steam Line differential pressure which resulted in a Safety Injection with reactor and turbine trip at 0202.

The Safety In-jection was reset and the pumps stopped after a

12 minute interval.

An inspection of the Containment was performed and a leak was located on the Loop 4 Cold Leg RTD orifice fl'ange.

The leak was repaired and the Reactor returned to critical at 2304.

10/12/80 10/13/80

- The Unit was paralleled with the system at 0159 and loaded to 99/ power by 1955.

Insufficient F(Zt) margin prevented going to 1005 power at this time.

I

- The Unit was loaded to 1005 power over a 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ramp starting at 0805.

10/14/80 - The 50'ind Direction Instrument was inoper-able for a 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period while repairs were made.

10/17/80 - Power was reducedito 90% for testing of Turbine Valves.

Total time below 100K was 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

An inadvertant Radioactive Gas release occurred at 1410 when the Reactor Coolant filter was valved in. It was determined that the filter drain valve had failed open.

The filter was valved out at 1425, repairs were made, and the filter returned to service at 1813.

10/18/80 - The North half of "B" Condenser was out of service for a 5.75 hour8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> period for checking of tube leaks.

10/24/80 - Power was reduced to 90K for testing of Turbine Valves.

Total time below 1005 was 3'.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

10/29/80 - At 0106, the 813 Circulating Water pump tripped on Overload.

Investigation at the pump and the breaker found nothing abnormal.

The pump was restored to service with no further trouble.

C'V J

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50 - 315 ook - Unit No..l 11-12-80 B. A. Svensson 616 465-5901 1 of 1

MAJOR SAFETY-RELATED MAINTENANCE

OCTOBER, 1980 M-2 C&I-1 The sample pump for radiation monitor R-25 and R-26 would not provide sufficient flow.

Replaced the pump with a rebuilt pump.

The sample flow was adjusted and proper operation verified.

lAB emergency diesel engine jacket water system was leaking.

Replaced gaskets on No.

1 and No.

2 rear bank cylinder.

A flange on reactor coolant system loop-4, RTD bypass loop was leaking.

The leak was repaired by replacing the flexitallic gasket.

The 50 ft. wind speed indication failed to function.

The sec-ondary 50 ft. wind speed system was placed into operation.

A wire was found broken in the PBX room on a terminal board.

The repairs were completed and the primary wind speed system was returned to service.

C&I-2 C&I-3 Annunciator No. 7, drop 46, reactor coolant pump No.

2 thermal barrier cooling water temperature high alarm was received and would not clear.

Transmission alarm instrument, CTA-452 failed.

A failed capacitor was replaced and CTA-452 calibration was per-formed.

The actual measure temperature was 93 F.

(PI-416, boric acid transfer pump discharge pressure indication indicated a high pressure.

The calibration of (PI-416 was tested and found to be out of specification.

(PI-416 and (PI-417 were recalibrated and returned to service.

C&I-4 C&I-5 The turbine trip permissive P-7 was illuminated when the turbine was not tripped.

A memory board in the control board demulti>>

plexer had failed.

The board was replaced with a spare.

IFI-265, safety injection pump recirculation flow to the RWST did not indicate flow.

The indicating ring had slipped from the magnetic field.

The ring was repositioned and correct flow indication was verified.

f'g fl ~Q."J~'