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Monthly Operating Rept for Sept 1984
	ML20108B205
Person / Time
Site:	Cook
Issue date:	09/30/1984
From:	Climer D, Will Smith, Svensson B; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8411160002
	Download: ML20108B205 (7)
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4 AVERAGE DAILY UNIT POWER LEVEL 00CXET NO. 50-315

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UNIT

~1 DATE 10/2/84 COMPLETED BY D. Climer TE!.EPHONE (616) 465-5901 MONTH september 1984 OAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL '

(MWE-Net).

(Mwe-Net) 1 495 17 1018 2

sos la 1018 3

635 19 1018 4

937 20 1016 5

1010 21 1015 6

1011 22 1016 7

1008 23 1015 6

8 1012 24 1014

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9 1011 25 1013 10 1012 25 1016 11 init 27 1018 12 1011 4

i 23 1019 13 1010 29 1018 14 1010 30 1018 i

15 1019 31, 16 i

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On this femat list the average daily unit pcwer icvel in MWe-Net for each i

day in the recortina month. Cemnute tn *ba i

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DOCKETNO.

50-315 UNITSIIUTDOWNS AND POWER REDUCTIONS UNII NAME D.C. Cook - Unit 1 DATE October 4. 1984 September, 1984 COMPl.ETED BY R_A_ Svonannn 616/465-5901 REPORT AIONIli TELLrilONE e.

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Hil TURBIN The power reduction which started on 840831 to repair the east main feed Cont'd pump turbine inboard bearing con-tinued until 840902 when the east MFPr was returned to service.

100%

reactor power was reached on 840904.

There were no other Unit shutdowns or significant power reductions dur-ing the month.

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F: Fosced Reas.m Meths=l:

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Event Rep.as (I FRll etc INURI'G-D Rcgulas. sy Resiskaum 4 Ottice iEmi anil 01611 d

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UNIT SHUTDOWNS AND POWER REDUCTIOFS LNSTRUCTIONS This report should desenbe all plant shutdowns during the

n accordance with the table appearing on the report form.

report penod. In addinon. It should be the source of explan.

If category 4 must be used. supply bnef comments.

atton of signincant dips m average power levels. Each signi.

ficant reduction in power level (5reater thm00% reduction LICENSEE EVENT REPORT :. Reference the applicable m average daily power level for the precedirq 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) reportable occurrence pertaining to the outage er power reduction. Enter the Srst four parts (event yearcsequennal should be noted, even though the unit mayj; sot have been shut down completely!. For such reducuor.s in power level, rep rt number occurrence code and report type) of the 6ve the duration should be 2sted as zero, the method of reduction part designation as desenbed in Item 17 of Instrucuens for should be listed as 4 4ther), snd the Cause and Correcuve. Prepration of Data Entry Sheets for Licensee Event Report Acuan to Prevent Rbutrence column should explain. The (LERP File (NUREG.0161). This information may not be Cause and Correenvc kion to Prevent Recurn ace column immediately evident for all such shutdowns, of course, sm,ce,

should be used to provide any needed explanation to fully further investigation may be required to ascertam whether or desenbe the circumstances of the outage or power reduction.

not a reportable occurrence was involved.) If the outage or power reduction wtll not result in a reportable occurrence.

NU51BER. This column should indicate the sequenttal num.

the positive indication of this lack of correlation should be ber assigned to each shardown or sigmncant reducuonin power noted as not applicable (N/A).

for that calendar year. When a shutdown or sigmResnt power SYSTEM CCDE. The system in which the outage or power reduction begins m one report pened and ends m 2nother.

an entry should be made for both report penods to be sure reduction onginated should be noted by the two digit eode of all shutdowns or sient6 cant power reducuons are reported.

Exhibit G. Instructions for Preparation of Data Entry Sheets Until a unit has acltieved its first power generatien. no num-fm Licmsu Evmt Report (LER) File (NUREG.0161).

ber should be assigned to each entry.

Systems that d.not 6t any existing code should be designa-ted XX. The code ZZ should be used for those events where DATE. This column should indicate the date of the start a system is not applicable.

of each shutdown or sigm5 cant power redaction. Report as year. month, and day. August 14.1977 would be reported COMPOSENT CODE. Select the most appropnate component as 770S14. When a shutdown or sigmficant power reducucn from Exhtbit [. Instrucuens for Preparauon of Data Entry begms m one report penod and ends :n another, an entry should Sheets for Licensee Event Report (LER) File (NUREG.0161).

be made for both report periods to be sure all shutdowns using the following critiena:

or sigmficant power reductions are reported.

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

duled." respect.vely, for each shutdown or signific>nt power B.

If not a component failure, use the related component:

reducuon. Forced shutdowns include those required to be e.g.. wrong valve operated througn error list valve as mitiated by no later than the weekend following discovery component.

of an off. normal condition. It is recognized that some Judg.

ment is required in categonzmg shutdowns in this way. In C.

If a chain of failures occurs. the first component to mai.

general, a forced shutdown is one that would not have been function should be listed. The sequence of events. includ.

completed in the absence of the condition for which corrective ing the other components which fail. should be desenbed action was taken.

under the Cause and Corrective Acuan to Prevent Recur.

rence column.

DURATION. Self explanatcry. When a shutdown extends beyond the end of a report dnod, count only the time to the Components that do not nt any existing code should be de-signated XXXXXX. The code 777777 should be used for and of the report pened and pick up the ensamg dom time in the foi!owing report penods. Report duration of outages events where a component designation is not applicaole.

rounded to the nearest tenth of an hour to fae:litate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR. i The sum of the total outage hours plus the hours (he genera.

RENCE. Use the column in a narrative fastuon to ampitfy or tot was on line should equal the gross nours in the reportmg penod.

explain the circumstances of the shutdown or power reduction.

The column should include the specific cause for each shut.

I* * * * * *" d REASON. Categonze by :etter designation in accordance with the table appeant:g on tne report form. If category H contemplated long term correcuve action taken, if appropn.

ate. This column should also be used for a desenotion of the must be used. supply bnei comments.

maior safety-related corrective maintenance performed dunna METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identification ot}

REDUCING POWER., Categonze ey number designation the entreal path acuv ty and a report of any smgle re! ease et radiosenvity or smgle radiation exposure spectrically assoct.

% e that this differs nom the Edison Electne Insuture sted with the outage which accounts for more than 10 percent (EEll de6mtions of " Forced Partia.50utage" and " Sche.

of the allowsole annual values.

duled Partial Outag." For these term 3. eel uses a shange ut For long textual reports continue narrative on separate p:.per,

.t0 MW as the break pomt. For larpe. power reactors. 30 NtW and referense the shutdown or power redusnon im ini, ts too small a change to wanant explananon.

narrative.

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Dockst No.:

50-315 Unit Nr. mas D.C. Cook Unit 1

/

Completed By:

G. J. Peak Telephone:

(616) 465-5901 Date:

10/04/84 Page:

1 of 2 MONTHLY OPERATING ACTIVITIES - SEPTEMBER, 1984 HIGHLIGHTS:

The unit entered the reporting period in Mode 1 with the reactor at 57% power due to the East Main Feed Pump being out of service.

The East Main Feed Pump was returned to service and the unit was subsequently loaded to 100% power where it was operating when the reporting period came to an end.

No other major power reductions occurred during the reporting period.

Total electrical generation for the month was 721,400 MWH.

SUMMARY

9-02-84 The East Main Feed Pump was returned to service at 2053 hours0.0238 days 0.57 hours 0.00339 weeks 7.811665e-4 months and a power increase to 100% began.

9-04-84 The unit reached 100% power at 0940 hours0.0109 days 0.261 hours 0.00155 weeks 3.5767e-4 months .

9-05-84 Engineering safety features ventilation unit HV-AES-2 was inoperable from 0618 hours0.00715 days 0.172 hours 0.00102 weeks 2.35149e-4 months on 9-05-84 to 1446 hours0.0167 days 0.402 hours 0.00239 weeks 5.50203e-4 months on 9-10-84 for repair of the dampers and door frame.

9-20-84 The Spray Additive Tank was inoperable for a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months period for maintenance.

The Control Room Cable Vault Halon System remains inoperable as of 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months on 4-05-83.

The backup CO System for the Control 2

Room Cable Vault remains operable.

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DOCKET NO.

50 - 315 UNIT NAME D. C. Cook - Unit No. 1 I'

DATE 10-5-84 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE 4

SEPTEMBER, 1984 i

M-1 IM0-51,. BIT Discharge.to Loop #1 600V ground was found to be caused by a pinched motor lead in the limitorque operator' switch compartment.

M-2 U-l CD diesel starting air compressor discharge check valve i

1-CD-l'was leaking by.

The valve was disassembled and the l

seat lapped and blued to restore seating.

C&I-l Bistable LB-519A/B in the steam generator mismatch protection circuit was replaced due to repeated setpoint drift.

It was recalibrated and the surveillance test was performed to verify operability.

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e, ya, - INDIANA & MICHIGAN ELECTRIC COMNMY Donald C. Cook Nuclear Plant P.O. Son 458 Bridgman, Mehgan 49106 October 5,.1984 Director, Office Of. Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. '20555 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 September, 1984 is submitted.

Sincerely, bY W. G. Smith, r.

Plant Manager WGS:ab Attachments cc:

J. E. Dolan M. P. Alexich R. W. Jurgensen NRC Region III E. R. Swanson R. O. Bruggee (NSAC)

R. C. Callen S. J. Mierzwa R. F. Kroeger B. H. Bennett J. D. Huebner J. H. Hennigan Z.

Cordero R. F. Hering J. F. Stietzel PNSRC File INPO Records Center ANI Nuclear Engineering Department

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ML20108B205

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SUMMARY

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