ML18219D349

Letter Monthly Operating Report for March 1978

ML18219D349
Person / Time
Site:	Cook
Issue date:	04/13/1978
From:	Shaller D American Electric Power, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	Office of Nuclear Reactor Regulation
References
Download: ML18219D349 (11)

Text

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Q oq/xr/wyy REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTlON FOR INCOMING MATERIAL 50-315 REC:

NRC ORG:

SMALLER D V

IN 5 MI PWR DOCDATE: 04/13/78 DATE RCVD: 04/20/78 DGCTYPE:. LETTER

SUBJECT:

FORWARDING SUBJECT 1978.

NOTAR1 ZED:

NO COPIES RECEIVED LTR 1

ENCL 1

FACILITY"S MONTHLY OPERATING REPT FOR THE MONTH OF MARCH PLANT NAME: COOK UNIT 1

REVIEWER INITIAL:

XJM DISTRIBUTOR INITIAL:~

DISTRIBUTION QF THIS MATERIAL IS AS FOLLOWS MONTHLY OPERATING REPORT FQR GRAY BOOK PREPARATION.

(DISTRIBUTION CODE A003)

FOR ACTION:

INTERNAL:

EXTERNAL:

BR CHIEF SCHWENCER++W/2 ENCL r I

.~~~~W/ENCL MIPC FQR AC'

/2 FNCL LPDR S ST.

JOSEPH'I+4W/ENCL TIC~~~W/ENCL NS IC>>W/ENCL BNL<NATLAB)<4W/ENCL ACRS CAT B4F~W/0 'ENCL NRC PDR++W/ENCL DISTRIBUTION:

LTR 10 ENCi 10 SIZE:

1P+hP' Nyl %%%%3%%%>l %8F%%%%%%8l 3Hf0f+SHI+SHfSHfdl 5Hb%

CONTROL NBR:

781110052 THE END Nk

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INDIANA& MICHIGANPOLVER COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 April 13, 1978 Director, Office of Management Information and Program Control U.

S. Nuclear Regulatory Commission Washington, D.C.

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=I lD Gentlemen:

Pursuant to the requirements of Donald C.'Cook Nuclear Plant Unit 1

Technical Specification 6.9.1.6, the attached Monthly Operating Report for the month of March, 1978 is submitted.

Sincerely, D.

V. Shaller Plant Manager DVS:ab Attachment cc:

R.

W. Jurgensen NRC Region III K.

R. Baker R.

C. Callen R. Walsh S. J.

Mierzwa J.

E.

Dolan R. J. Vollen G.

E. Lien K.

W.

Brown J.

M. Hennigan P.

W. Steketee A.

F.

Kozlowski J.

F. Stietzel PNSRC File 78ii10052 J

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I v tl OC lV CP f'1 ll

AVEKAGEDAILYUNITPOViER LEV P

DOCK:"T.IO.

DATE CQQIPf ETED IIY H. T.

Gi 1 l.erat Te r EpH pq-E 6.1 6-465-5901 Harch 1978 DAY AVERAGE DAILYPOWER LEVEL (MÃe.>iet) 1043 C

DAY AVERAGE DAILYPpii'ER LEVEL (MWe-Net >

1045 3

7 9

13 I5 l6 1044 1043'041 1038

') 039 430 897 1043 1042 1043 1042 1042 1042 1043 I8

'19 70 2l

'23 74

)5 26 30 3I 1045 1043 1046 1043 1043 1045 1045 1044 1047 1042 1043

'l 044 1045 1045 lib'STR VCTIO)"IS Qn this format. list 'h aver ee da!ii'nit pointer Iei'el in iltVe-Yet for each day in the revvrttno month. Compute ttt'he nearest ~hole menivat t.

It)r77 )

OPERATING STATUS

'OPERATING DATAREPORT DOCI =T io.

P8 "8P ~44 78 COiIPLETED SY l~~ett TELEPHONE ~~!~901

1. Unit Name:

Donald C..Cook

.1

2. Re'portingperiod:

'hal'Ch 1978

3. Licensed Thermal Power {i41Wt):

4. Nameplate Rating, (Gross i IWe):

5. Design Elec@ical R"ting (Net MWe): MB 1080'otes

8. IfChanges Occur in Capacity Ratings (Items Numbers Throu~~!t 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 Cumulative 8

2,160 28,464. 0 2 037.4 22,660.1 2,024.9 21,994. 7 5FC5

~7 0

2,050,120 18,81 5,210 1,975,984 18,026,198

93. 7 81.5 93.7

81. 5 70.2 87.6

86. 8 65.1 6.0, 6.3

11. Hours In Reporting Period 744

12. Numoer Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line 7 8.8

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated (MWH)

19. Unit Service Factor 99.4

20. Ur.it AvailabilityFactor 99.4.

'21. Un!t Capacity Factor {Using MDC Net)

96. 0

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate

.6

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

Refueling 4/5/78 51 Days

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

26. Units In Test Status (Prio to Commercial Operation 1:

Forecast Achieved INITIALCRIT I CA LITY INITIALELEC'TRICITY COilDIERCIALOPERA TION li!I8: )

UNITSIIUTDO)UNS AND POPOVER REDUCTIONS REPORTIiIONTII MARCH, 1978 DOCKET NO.

DATE 4

coMPLpTED II@ 8...

Svensson TELEPIIONE 616 No.

I)atc L~

N

~ C/l Liccnsec Event Rcport 4 Cause 4, Corrective Action to Prcvcot Rccurrcocc 126 780307 F

4.2 N/A ZZ ZZZZZZ Reactor/Turbine trip due to:loss of power to No.

4 control group.

Power was lost due to inadvertant inter-uption of power by 'technician working on control system.

Returned to service 780307.

100/ power reached 780309 and maintained at this level for the rest of the month.

F: For<<cd S: Scheduled

(()/77)

Reason:

A-E(luipntcnt Failure (Explaitt) 0-I laitttenance nr Test C-Refueling D-Regulatory Restriction I.'-Operator Training k, Liccosc Iixaotioation F-Adtnioistrative G Operational Error (I'.xplaio)

I I.O(hcr (Explain) hlcthod:

I Manual 2.h(annal Scratn.

3-AuloolalIC Scraol.

4 Ollier (

Explain

)

Exhibit G - Instructions for Preparati(nt of Data Entry Sheets I'or Li<<ensee Event Report (LER) File (NUREG-016I)

'Exhibit I - Sante Source

UNITSHUTDOWNS AND POWER REDUCTI NS

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

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

Each signi-ficant reduction in power level (greater than 2(Y/o 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 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 start of each shutdown or signilicant 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," respectively, 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.

Self<xplanatory.

When a shutdown extends beyond the end of a report 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 duratibn of outages rounded to the nearest tenth ofan hour to facilitate summation.

The sum 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 on the report t'orm. Ifcategory H must be used. supply b riel'omments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categt>rize by number designation INole that this differs 1'rom the Edison Electric Institute (EEI) definitions ot'Forced Partial Outage" and

-Sche.

duled Partial Outage."

Fl>r these tern>>. FF:I uses J change ol'0 MW as tlie break poini. Fill larger power reactors. 30 i%1W ls t<>i> slllJll J chJnge ll> wJrlJnl cxplanali1>>l.

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 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 (iNUREG4161).

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 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 code of Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG4161).

Systems that do not ftt any existing code should be designa-ted XX. The code ZZ should be used for those events where a system is not applicable.

COMPONENT CODE. Select the most appropriate component'rom Exhibit I - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File {NUREG4161).

using the following critieria:

> 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 ftt any existing code should be de.

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

component designation is not applicable.

CAUSE 8c CORRECTIVE ACTION TO PREVENT RECUR-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

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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 outage or power reduction including an identification of the critical path activity and a report of any single release of radioactivity vr singie radiation exposure specitlcally associ

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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 Jnd reference the shutdown or power reduction lol this narfJtlve.

{9/77

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DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE 50 - 315 D.

C.

Cook - Unit No.

1 4-13-78 B. A. Svensson 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE MARCH, 1978 M-1 M-2 CSI-1 The east containment spray discharge

valve, IMO-210 wouldn't function properly.

Found a broken contactor in limitorque operator and re-placed the contactor.

No.

1 boric acid transfer pump was noisy.

Replaced pump shaft and bearings.

Leaking top flange on "N" seal water injection filter.

Installed new o-rings.

"N" waste gas compressor failure.

Replaced "N" waste gas compressor with a new compressor.

Urgent alarm on rod control system.

Replaced two phase fuses in shutdown bank "8BD".

CSI-2 Radiation monitoring system channel R-2, containment area monitor, failed low.

The connector to the detector was replaced and the channel returned to service.

CLI-3 Radiation monitoring system channels R-25 and R-26 pump failed.

The detector pump was replaced and the channel returned to service.

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Docket ~.:

Unit Name:

Date:

Completed By:

Telephone:

50-315 D.

Cook Unit 1

A ril 10, 1978 R.

S. Keith 616 465-5901 OPERATING EXPERIENCE -

MARCH 1978 Hi hli hts Unit 1 operated at 100! power for the entire month except for one trip when the unit was off line for four hours and thirteen minutes.

~Summar 3/1/78 - At beginning of the month Unit 1

was at 100/.

3/7/78 - The Reactor tripped at 1003 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.816415e-4 months <br /> due to loss of power to control group 4.

The Reactor was critical again at 1304 hours0.0151 days <br />0.362 hours <br />0.00216 weeks <br />4.96172e-4 months <br /> and the Generator was paralleled at 1416 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.38788e-4 months <br />.

Power restricted to less than 50'A until Axial flux returned to the target band.

3/9/78 Reactor was returned to 1005 power and remained there for the rest of the month.

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