ML17317A810

Monthly Oper Rept for Nov 1978

ML17317A810
Person / Time
Site:	Cook
Issue date:	12/04/1978
From:	Gillett W INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17317A809	List: ML17317A808 ML17317A810
References
NUDOCS 7812200174
Download: ML17317A810 (9)

Text

AVERAGE DAlLYUNITPOWER LEVEL DOCK:-7 NO.

50 315 UNIT COMPLETED BY W. T. Gillette T">>LEPHONE 616-465-5901 November 1978 DAY AVERAGE DAlLYPOWER LEVEL (MWe->Ver) 1042 1043 1029 1042 1041 1040 DAY AVERAGE DAlLYPOWER LEVEL (MWe.Net) 1032

~

1033 1036 1032 1034 1035 1035 10 13.

15 16.

1028 1028 1026 1043 1041 1039 1040 1035 1033 24 l5 27 ZS

'>9 30 31 1031 1032 1035 1036

'034 971 892 INSTRUCTIONS On this format. list:h average daily unit p>><<'er level'tn MWe-Net ior each cay in the repucttnc ~n>>nth. C>>minute tu'he nearest u:hole rnepwat t.

OPERATIiiG DATAREPORT DOCKET NO.

D~Yz ~>2--

TELEPHONE ~6~4-901 OPERATING ST%.TUS

1. Unit Name:

MnMd C. CCok 1

2. Reporting Period:

3. Licensed Thermal Power (MWt):

4.. Nameplate Rating (Gross MWe):

5. Design Electrica R"ting (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

7. Nfaximum Dependable Capacity (Net MWe):

3 250 1 089 1 080 1

44 Notes

8. IfChanges Occur In Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

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

10. Reasons For Restrictions. IfAny:

This Month Yr.-to.Date

',016 6 009.2 5 879.7 18 100 430 2 306 615 5,753,551

73. 3

68. 8

68. 1 3.9 ll. Hours In Reporting Period 720

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours 0

16. Gross Thermal Energy Generated (MWH)

18. Net Electrical Energy Generated PilWH)

19. Unit Service Factor 100

20. Urit AvailabilityFactor 100

21. Unit C pacity Factor (Using MDC Net) 98.5

22. Unit Capacity Factor (Using DER Net)

~D. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type. Date. and Duration of Each):

Cumuhtive 34,320 25,849.5 321 69 656 623 22,735 510 21 803 765 7

78. 3

68. 5

64. 3

25. IfShut Down At End Of Report Period. Estimated Date of Startup:

~

26. Units ln Test Status(Prior to Commercial Operation):

Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY CORDIERCIAL OPERATION

UNITSIIUTI)OWNS ANI)POlVER I(EI)UCTIONS I

REPORThlON'fll November, 1978 It I)OCKETNO.

I)ATF 12-14-78 COh(PLETE() gy B.A. Svensson TELEPIIONE 61 6 - 465-5901 Nt).

l)alc rl>>

~ttr)J n>>J 4

~ M g Ln:cllsec Evenl Rcporl rr CN V 0 Vl~'6 0

0 a

I) D Q

O Cause &. Corrc<<live Aclion lo Pfcvcol Rccufrcu).I.

139 781129 S

0 B

N/A ZZ ZZZZZZ Reactor power reduced to 70%%d to perform N. I.S. Incore/Excore cross calibration.

Power returned to 99%%d 781130.

I I': For<<ed S: ScIIcrluICII Reason:

. A-Erluipn)cnl Failure (I:xplain) ll.hlalnlclrance or Tcsl C-R f lclinl, I) Rcgulaloly Rcslrl<<lion E.Operalor 'I'raining & Lic<<usc Exanlinalion

'-Adn)in(st ral ivc G.Opcralional Lnu)r (I)xplaiu)

II.OII)cr(fxplain) h(el(Iud:

I-hlanual 2 hlanual Sclanl.

3-Aulonlalic Scraln.

'I-Olllcr(Explain)

I:xhlbit G - lnslruclions for Preparali)n) I)fl)ala Entry Sllccls for l.i<<cnsec Evcnl Rcporl (I.l!R) File (NURI:G~

OI6I )

t Lxllil)ilI Sanlc S)uuec

UiiITSHUTDOWNS AND POWER REDU NS INSTRUCTIONS This report should describe all plant shutdowns during the report period.

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

Each signi ~

ficant reduction in power level (greater than 2¹ reduction in average daiiy 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 compieteiyi.

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 fuuy 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 io be sure Jl shutdowns or signittcant power reductions are reported.

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

DATE.

This column should indicate the date oi the start oi each shutdown or signirtcant 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 sianificant power reducuons are reported.

TYPE.

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

duled." respectively, ior each shutdown or significant power reduction.

Forced shutdowns indude 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.

Seifwxplanatoty.

When a shutdown extends beyond the end oi a report period. count only the time to the end oi the report period and pic'p the ensuing down time in the following report periods.

Report duration of outages rounded to the nearest tenth oi 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 vn the report form. Ifcategory H must be used. supply brief comments.

IIETHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by number designation INote that this difiers irom the Edison Electric Institute tEEI) deiinitions ot'Forced Partial Outage-and

-Sche.

duled Partial Outage."

F<ir iilese tenn>. EFI uses a change of

0 MW as the break point.

Fi>r larger power reactors.30 MW is tiii>>mali a change to warrant explanation.

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 iirst 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 Reoort (LER) File (NUREG416!).

This information may not be immediately evident for all such shutdowns, of course, since further investiaation may be required to asc rtain whether or not a reportabie occurrence was involved.) If th>> 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).

SYSTE'ii CODE.

The system in which the outage or power reduction originated should be noted by the two digit code of Exhibit G

~ Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG416l).

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.

COi'iIPONENT CODE.

Select the most appropriate component from Exhibit I - Instructions for Preparation of Data Entq Sheets for Licensee Event Report (LER) File {NUREGOI61).

using the followingcriti ria:

A. Ifa component failed, use the component direcriy 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 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 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 k, CORRECTIVE ACTION TO PREVENT 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 specittc cause for each shut-down or signiticant 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 outaae or power reduction including an identification of the critical path activity and a report of any single release of radioactivity or single radiation exposure spe<<iiicaily asso<<i-ated with the outage which accounts for more than 10 oercent oi the allowable annual values.

For long textual reports continue narrative on separate paper and reference the shutdown or power reduction foi th>>

narrative.

Docket No.:

Unit Name: ~

Completed By:

Telephone:

Date:

50-315 D.

C.

Cook Unit 81 R.

S. Keith (616) 465-5901 December 13, 1978 OPERATING EXPERIENCE -- NOVEMBER, 1978 Hi hli hts The Unit was on line throughout the entire month.

505 of the Cycle III expected life was passed.

Summar ll/01/78 The Unit entered this reporting period operating at

'005 power producing 1070 megawatts electrical gross generation.

11/04/78--

11/07/78 Radiation Monitor R-25 was inoperable from '0625 to'500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> because of failure of the slow speed paper drive motor.

"AB" Emergency Diesel Generator was inoperable from 1140 to 1555 hours0.018 days <br />0.432 hours <br />0.00257 weeks <br />5.916775e-4 months <br /> because of a faulty voltage r egu-lator card.

The card was damaged when it caught on the pocket of the technician working in the area.

Both windspeed and direction recorders were out of service from 1.130 to 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> when a cable to the tower was damaged during construction/excavation activities.

11/09/78 11/10/78 Reactor Coolant System leak rate test shows the system leakage is running between 0;8 and 0.9 gpm.

A portion of this leakage has been identified as coming from a leaking pressurizer safety valve.

The average rate of leakage from the pressurizer safety valve is 0.6 gpm.

II "CD" Emergency Diesel.Generator was inoperable from 0718 to 1509 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.741745e-4 months <br /> for installation of design change RFC-DC-12-919.

0

~

0 11/11/78 -- Containment equalization fan CEg-1 was inoperable from 1329 to 1915 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.286575e-4 months <br />.

11/17/78--

CEg-2 fan was inoperable from 0809 to 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />.

Emergency Power Breaker 1-EP was open from 1055 to 1252 hours0.0145 days <br />0.348 hours <br />0.00207 weeks <br />4.76386e-4 months <br /> to tie in the power supply to test the Unit tl spare main transformer.

Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-315 D.

C.

Cook Unit ¹1 R.

S. Keith (616) 465-5901 December 13, 1978 (2) 11/29/78 -- At 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> started reducing power to 705 to perform (cont)

Incore/Excore. Cross Calibration.

ll/30/78 Incore/Excore Cross Calibration was completed and the Unit returned to 99K power producing 1070 megawatts electrical gross generation.,

Reactor Coolant System leak rate is 1.033 gpm with 0.818 gpm attributed to a leaking pressurizer safety valve.

DOCKET 'NO.

'0 - 315 UNIT NAME D.

C.

COOK - UNIT NO.

1 DATE 12-14-78 CONPLETEO BY

~B.

. Svensson

.TELEPHONE 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE NOVEMBER, 1978 M-1 M-2 M-3 South waste gas compressor moisture separator makeup valve, RRV-385 was not maintaining proper level.

Valve diaphragm was replaced and proper operation verified Middle boric acid storage tank recirculation bypass

valve, CS-429M, would not operate.

Replaced valve bonnet.

No.

2 boric acid transfer pump did not develop required discharge pres-sure.

The impeller was replaced and pump retested satisfactorily.