Text

Monthly Operating Rept for Sept 1980
	ML17319A648
Person / Time
Site:	Cook
Issue date:	10/06/1980
From:	Gillett W; INDIANA MICHIGAN POWER CO.
To:	;
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ML17319A647	List: ML17319A646; ML17319A648;
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.OPE~~i'G S iATUA OPF<kiPiG DATAREPORT

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COiIPr ~D =Y ~~Uett Ter ea~e~E 3~~01 6.

S.

Oonald C. Cook 1

Unit i amer Se tember 1980 Li~Thc. A7owe: (MY(t)t N~~eplate Ratirr (Grass lrOVe)r Desiipt K~M~g (Net KD'r'e)t

)barnum Dependable Capacity (Gross 5IVVe)t 1080 RFx7rnuraMc'dolf Qp~ (Net 5OVe)t IfChan~~

Ocmr in Capaci."g Rzrh~ (lt"~Yumb= S Thto~ r ) Sine= Las Rcport. Give P.casonst 9;Bnve. I'"vel Ta"VVhIAR~~, IfAny (Net hOVe}:

10;"%mons For ~ations. L'Any-This Month Yr.wo-Oat=

Cu~

~ tive 4 548.3 37 510 0

0 463 4,466 36,549.2

'0 321 0

13,721,043 102,787,349 75.7

67. 9 75.7

67. 9 89.5 63.8 66.5 63.

62.

-'l~ ÃuNaM~~uxor Was C;:aM 696 "IR Re"~a~'Shtr:dovva Ham 691. 7 I

1'~. U."a~aevFSImtrfawn Ha~.

~u.. GrasrTlte:nN E".. ~ Cerrc.=ted (WWH) 2,100,551 5-. U dGea'fe,B'cmr-

96. 1 96.1 I. Un~~>;azmr (Usin~~r~rC Yet}

~ UrdrCnetl~ra'or'(Usur~ D~~ Yet)

4; Shutdo irns Sc.'".~uled Over aiex 6 ~tant.'-.s (Type; Date."'nd Drr=tion of Each):

~i tfShe Do'e-~t'End'Of Re-ott P ~od..Brim ted D teoiStaaor.

. M. Units la Test Status.(Pmr ro Cc...;..~al Op. riorlr Fo~t Achieved li~ tTIAl'?'I i iCAI.ITY IYITIAL ELECT?!CI'i ~

CO.'f!ir"~ClAi QP"-:..~7IO~

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO'..

UNIT ATT COMPLETED BY W. T. Gillett TELEPHONE 616-465-5901 MONTH September 1980 OAY AVERAGE DAILY POWER LEVEL (MWE-Net) 670 976 998 999 1001 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 17 18 19 20 21 10 12 13 14 15.

16 1003 1015 1015 1016 1027 1031 1030 654 821 1023.

1028 22 23 24 25

.27 28 29 30 31 1008 1010 1026 1029 1'032 1032 1037 1030 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.

UNITSl IUTI)OWNS ANI)PO)VER REI)UCTIONS t,

REI'ORT hIONTII'eptember, 1980 l)OCKETNO.

TELEPIIONE 6

465-5901 Dale L

r>aK A~-

ri

~t(rj

=I> ~

a Q1 U< c

~ II)

A Liccosec Evcol.

Rcpi)fl 4 El~

0 a

Q D Eu e>

CJ Cause &. Ci)fle('Iivc Acliinllo Pfcvcnl Rccuffco(.'c 166 800913 167 800919 0

28.3 N.A.

1 80-023/03L ZZ ZZZZZZ IB INSTRU Reactor power reduced to 55K to re-move the west main feedpump turbine from service to repair oil leaks in the feedpump turbine lube-oil tank.

Reactor power returned to 985 800915.

Unit removed from service to repair suspected leak in sensing line for No.

2 steam generator narrow range level channel BLP-122.

Leak found to be pinhole leak in a socket weld downstream of root valve in the sensing line.

Unit returned to ser-vice 800921, and 97K reactor power reached 800922.

I': Fof<<ed S: Sclicdiilcd Itcas()n:

A.l'-Iluipn)cnl Failure (Explain)

II-hiah)tcnancc or Test C-Rcfuclint, D Itettolalofy Reslriclloil E.Opcfal )f Tfalnint,'

Uccosc Exanlinall )n F-Adn)h)lstfi)llvc G Oticraliunal Llror(I'.xplaii))

II.Other (Expiah) )

3 hielhi>d:

I-Manual 2 Manual Scraln.

3-Auli)ola lie Scranl.

0-Olher (Explain)

Fxhibil G Inslfuclions fi)r Pfcparalion ol'Dala Lolry Slicels fof Ll<<eosce Evcol Rcpi>rl (I I!R) File INUltlG-OI61)

'I:xhihil I ~ Sa)ne Suui<<e

NITSHUTDOWNS AND POWER REDU NS 1

~

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/a reduction in average daily power level for the preceding 24 houis) should be noted, even though the unit may not have been shut down completelyi.

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 Cause and Correcuve 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.

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 all 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 st of each shutdown or significant power reduction.

Report as year. month. and day.

Auaust i4. 1977 would bc reported as 770814.

When a shutdown or significant power reducrion 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 reducrions are reported.

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

duled," respectiveiv, 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 action was taken.

DURATION.

Se}explanatory.

When a shutdown extends beyond the end of a'cport period. count only the time to the end ot the report period'nd pic'p the ensuing down time in the following report periods.

Report duratit>n of outages rounded tu the nearest tenth ut an hour to facilitate summation.

Thc suin 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 un the report form. Ifcategory H must be used. supply briei'comments.

'ETHOD OF, SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by number designation 1Noie that this ditfers i'rom the Edison Electric Institute tEEI) definitions of -Forced Partial Outage-and

-Sche-duled Partial Outage."

F>>r these tenn>>. FFl uses a change oi

0 ~IW as the break p>>int.

For larger power reactors. 30 MW is n>i> small a change t>> warrant explanatii>>>.

in accordance with the table appearing on the report torm.

Ifcategory 4 must be used, supply brief comments.

LICENSEE EVENT REPORT =.

Reference the applicable reportable occurrence pertaining to the outage or powe.

'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 occurtencc.

the positive indication of this lack of correiation should be noted as not applicable (N/A).

SYSTFM CODE.

Thc system in which the outage or power reduction originated should be noted by the two digit code ot Exhibit G - Instructions for Preparauon 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 bc used for those events where a system is not appiicable.

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 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 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 where a

component designation is not applicable.

CAUSE 8; CORRECTIVE ACTION TO PREVENT RECUR-RENCE.

Use thc column in a narrative fashion to ampiify or explain the circumstanc s of the shutdown or power reduction.

The column should include the speciTiic cause for each shut-down or significant power reduction and the immediate and contemplated lung 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 outaae or power reduction including an identification of the critical pith activity and a report of any single reiease ot radioactivity ur single radiation exposure speciiically associ-ated with the outaae which accounts for more than 10 oercent

'r the allowable annual vaiues.

For long textual reports continue narrative on separate naper and rer'ercnee the shutdown or power reduction ioi ihi>>

liaffalive.

(9!7

D et No.:

Unit Name:

Completed By:

Telephone:

Date.

Page:

50-315 D.

C.

Cook Unit 81 R.

S.

Lease (616) 465-5901 October 14, 1980 1of3 MONTHLY OPERATING ACTIVITIES -- SEPTEMBER, 1980 Highlights The Unit entered the reporting period operating at 45%

power, in recovery from a reactor trip from 95K power that occurred at 0447 hours0.00517 days 0.124 hours 7.390873e-4 weeks 1.700835e-4 months 8/31/80.

There was one outage during the reporting period which is detailed in the Summary.

Gross electrical generation for the month was 698,140 wmh.

9/Ol/80 The Unit was returned to 95Ã power over a

13 hour1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ramp starting at 0725 hours0.00839 days 0.201 hours 0.0012 weeks 2.758625e-4 months .

The 50'ind Speed and Direction Instruments were inoperable for a 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months period, while repairs were made.

This instrument is common to both Units.

9/02/80 Reactor power was increased from 95K to 974.

over a

5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ramp star ting at 1736 hours0.0201 days 0.482 hours 0.00287 weeks 6.60548e-4 months .

9/06/80 -- Containment Radiation Monitors R-11 and R-12 were inoperable for a 7 hour8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months period to replace the sample pump.

9/09/80 -- The North Control Rod Drive Motor Generator Set was removed from service at 0447 hours0.00517 days 0.124 hours 7.390873e-4 weeks 1.700835e-4 months due to a failed bearing.

Repairs were made and the Motor Generator Set was returned to service at 2210 hours0.0256 days 0.614 hours 0.00365 weeks 8.40905e-4 months , 9/15/80.

The 150'ind Direction Instrument was declared inoperable at 1331 hours0.0154 days 0.37 hours 0.0022 weeks 5.064455e-4 months .

Repairs were made and this was returned to service at 1110 hours0.0128 days 0.308 hours 0.00184 weeks 4.22355e-4 months 9/14/80.

This instrument is common to both Units.

9/10/80 Unit loading was increased from 971 to 98K power over a 2.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ramp starting at 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months .

I k

t PI

D t No.:

t Name:

Completed By:

Telephone:

Date:

Page:

50-315 D.

C.

Cook Unit Pl R. S. Lease (616) 465-5901 October 14, 1980 20f3 Summary (cont. )

9/ll/80 345KV Generator Breaker K-1 was open for a 1.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period while Reserve Power Transformer 0'5 was test energized.

9/13/80 9/14/80 Unit loading was reduced to 55Ã power over a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ramp, starting at 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months .

This was to remove the West Main Feed Pump from service to repair oil leaks in the Lubricating Oil Tank.

The liest Main Feed Pump was returned to service at 2315 hours0.0268 days 0.643 hours 0.00383 weeks 8.808575e-4 months .

Unit loading was held at the 55Ã level due to reduced system demands.

Unit power was increased to 93K power over a

7.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months ramp starting at 0550 hours0.00637 days 0.153 hours 9.093915e-4 weeks 2.09275e-4 months .

9/15/80 -- Power was returned to 98Ã over a

5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ramp starting at 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months .

9/19/80 Containment Recirculiation Fan CEg-1 was inoper-able for a 11.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period while, a second breaker was installed in its power circuit.

The Unit was unloaded to the 6X power level over a 2.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months ramp starting at 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months .

The Turbine Generator was removed from service at 2214 hours0.0256 days 0.615 hours 0.00366 weeks 8.42427e-4 months .

The reason for the outage was to repair a suspected leak in the sensing line for No.

12 Steam Generator Narrow Range Level Channel No. 3.

The leak was located at a socket weld elbow downstream of the root valve.

9/20/80 9/21/80 To improve working'onditions within the Contain-ment, the Reactor was made subcritical at 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months and the Reactor Plant was cooled down to 370oF and depressurized to 1600 psig by 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months .

All Reactor Coolant Pumps were placed in service at 1900 hours0.022 days 0.528 hours 0.00314 weeks 7.2295e-4 months and the Reactor Coolant System was returned to normal operating temperature and pressure by 2237 hours0.0259 days 0.621 hours 0.0037 weeks 8.511785e-4 months .

Reactor was returned to criticality at 0029 hours3.356481e-4 days 0.00806 hours 4.794974e-5 weeks 1.10345e-5 months .

Main Turbine was rolled at 0155 hours0.00179 days 0.0431 hours 2.562831e-4 weeks 5.89775e-5 months and the Unit paralleled to the system at 0233 hours0.0027 days 0.0647 hours 3.852513e-4 weeks 8.86565e-5 months .

The Unit was loaded to 944 power by 2020 hours0.0234 days 0.561 hours 0.00334 weeks 7.6861e-4 months .

The Unit was returned to 97Ã power over a 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ramp starting at 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months .

D t No.:

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-315 D.

C.

Cook Unit ¹1 R. S.

Lease (616) 465-5901 October 14, 1980 3of3 Summary (cont.)

9/23/80 The Unit was loaded to 994 power over a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ramp starting at 1015 hours0.0117 days 0.282 hours 0.00168 weeks 3.862075e-4 months .

The West Essential Service Water pump was inoper-able for a 15.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period, while adjustments were made to the pump.

East Safeguard Fan 1-HV-AES-2 was removed from service at 1415 hours0.0164 days 0.393 hours 0.00234 weeks 5.384075e-4 months to run a Performance check on its charcoal filter.

This fan was returned to operable status at 1415 hours0.0164 days 0.393 hours 0.00234 weeks 5.384075e-4 months 9/25/80.

9/27/80 Power was reduced to 95% for testing of the Hain Turbine Control Valves.

The Control Valve testing was not accomplished due to the Turbine Control System becoming unstable when setup in the testing Mode.

Total time below 99K power was 2.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months .

9/30/80 Vent Stack Radiation Monitors R-25 and R-26 were inoperable for a 9.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period f'r replacement of the sample pump.

,AB Emergency Diesel Generator was inoperable five times during the reporting period for a total time of 37.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months , while adjustments were made to the engine.

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50 315 D.

C.

Cook - Unit No.

1 10-14-80 B. A. Svensson 6

6 465-5901 1 of 1

MAJOR SAFETY-RELATED MAINTENANCE SEPTEMBER, 1980 A weld leak developed at the root valve for instrument IPI-220, west containment spray pump discharge pressure indication.

The pipe nipple was cracked next to the weld.

The nipple was cut off and replaced.

Applicable NDE was performed.

A leak was suspected in the sensing line for No.

2 steam generator level instrument.

The unit was removed from service and investi-gation revealed a pinhole leak in a socket weld downstream of the root valve for instrument BLP-122.

The leak was repaired by welding and applicable NDE was completed.

i

ML17319A648

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