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Monthly Operating Rept for Aug 1984
	ML20093H222
Person / Time
Site:	Cook
Issue date:	08/31/1984
From:	Gillett W; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
References
	NUDOCS 8410160207
	Download: ML20093H222 (7)
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p AVERAGE DAILY UNIT POWER LEVEL T

00CXET NO.

50-316 i

UNIT 2

DATE 9/4/84 COMPLETED BY A.'Might TELEPHONE (616 ) 465-5901 1-M0flTH August'1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net).

(Mwe_ net) 1 1058 17 1033 i

2 1048 18 1037 3

1070 19 1065 4

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-1042 10 1038 2s 1047 11 1085 27 1051 12 1091 23 1049 13 1084 29 1041 14 1071 30 1040 15 1046 31 1037 16 1039 INSTRUCTIONS On this format list the aversoe daily unit pcwer level in MWe-Net for each day in the recortino month.

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DO' KET NO. 50-316 UNITSilUTilOWNS ANI) POWER REDUCTIONS UNIT N AME D.C. Cook - Unit 2 DATE 9-13-84 COMPLETEI) BY B.A. Svensson AUGUST, 1984 REPORT MON HI TELEPilONE 616/465-5901 E

Cause & Canacciive

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M Nep HI #f Prevelli Ree:Hiestcc d

148 840805 F

50.8 A

3 84-020-00 EF INSTRU A reactor trip occurred from 100% pow-er due to a failure of vital instru-i I

ment, CRID II, Inverter. The inver-ter failure was due. to a blown fuse.

The blown fuse, the silicon control-led rectifiers and diodes were re-placed. The Unit was returned to service on 840807 and 100% reactor i

power was restored on 840808.

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2 3

4 F: Fenced Reason:

Method:

Exhibii G Insisuctions S: Scheduled A Equipmen Faihue(Explain)

I-Manual for Psepasation of Data H Maintenance of Test 2 Manual Scram.

linisy Stieces foi Licensee C. Refueling 3-Automatic Scs.am-Evens Repost II.ER) File (NIIREG-4 D Regul.isory Resisiciion 4-Othes (lixpl.ain) 016II I: Operator Daining & license fixa nination F Administrative 5

G-Operational Ensus tlixpl.nni INhibis 1 Same Somce-19/77)

II Other (Explaini I

e UNIT SHUTDOWNS AND POWER REDUCTIONS 3

INSTRUCTIONS This report should desenbe all plant shutdowns dunng the

n accordance with the table appearmg on the report form.

report period. In addition. it should be the source of explan.

If category 4 must be used. supply brief comments.

anon of significant dips in average power levels. Each signi.

ficant reducuon in power level (greater than 20", redtetion LICENSEE EVENT REPORT =. Reference the applicable in average daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) reportable occurrence pertammg to the outage or power should be noted, even thouzh the unit may not have been reduction. Enter the first four parts (event year. sequennal shut down completely. For'such reductions in power level, report number occurrence code and report type) of the tive l

i the duration should be listed as zero, the method of reduction part designation as described in item 17 of Instrucuons for snou!d be listed as 4 (Other) and the Cause and Correcuve Preparation of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG.0161). T1us information may not be Cause and Correcuve Action to Prevent Recurrence column immediately evident for all such shutdowns, of course, smee should be used to provide any needed explanation to fully further investigation may be required to ascertam whether or describe the circumstances of the outage cr power reduction.

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

NUhtBER. This column should indicate the sequential num.

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

for that calendar year. When a shutdown or significant power SYSTE31 CODE. The system in which the outage or power reduction begms in one report period and ends m another, reduction ongmated sh' uld be noted by the two digit code of o

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an entry should be made for both report penods to be sure all shutdowns or sigmilcant power reductions are reported.

Exiubit G. Instructions for Preparation of Data Entry Sheets Until a unit has achieud its first power generation, no num.

f r Licensee Event Report (LER) File (NUREG4161).

ber should be assigned to each entry.

Systems that do not fit any existing code should be deslana.

ted XX. The code ZZ should be used for those eventswhere DATE. This column should indicate the date of the start a system is not applicable.

of each shutdown or significant power reducuon. Report as year. month. and day. Auaust 14.1977 would be reported C05tPONENT CODE. Select the most appropriate component as 770814 When a shutdown or significant power reduccon from Exhibit i. Instructions for Preparation of Data Entr3 begms m one report pened and ends in r.nother, an entry should Sheets for Licensee Event Report (LER) File (NUREG4161).

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

or s:gnificant power reductions are reported.

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

duled." respectively, for each shutdown or significant power B.

If not a component failure, use the related component:

reduction. Forced shutdowns include t! ose required to be e.g.

wrong valve operated through error: list valve as initiated by no later than the weekend following discovery component.

4 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 mal-general, a forced shutdown is one that would not have been function should be listed. The sequence of events.inclub 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 Action to Prevent Recur.

rence column.

DURATION. Self. explanatory. When a shutdown extends beyond the end or a report penod. count only the time to the Components that do not fit any existing code should be de.

signated XXXXXX. The code 777777 should be used for end of the report penod and pick up the ensuing down tune m the following report penods. Report duration of outages events where a component designation is not applicable.

rounded to the nearest tenth of an hour to facilitate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

The sum of the total outage hours plus the hours the genera.

RENCE. Use the column in a narrative fashion to ampitfy or tor was on line should equal the gross hours in the reportmg explam the circumstances of the shutdown orpower reduction.

penod.

The column should include the scecitic cause for each shut.

REASON. Categorize by letter dengnation in acordance down or significant power reduction and the immediate and with the table appearm(on the report form. If category H contemplated long term correenve action taken, if appropn.

must be used. supply bnet eumments.

ste. This column should also be used for a desenptton of the r safety.related corrective maintenance performed dunne

'stETHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identification ot RELUCING POWER. Categonze by number cesignation W mg and a vn d av sp,62se a me a radioactivity or smgle radiation exposure speettiestly associ.

I INote that this differs from the Edison Electric Institute ated with the outage which accounts for more than 10 percent IEEI) definitions of " Forced Partial Outage" and " Sche, of the allowsole annual vslues.

duled Partial Ourag." For these termi. eel uses a shange ut Fur long textual reports continue narrative on separate paper

0 alW as the break pomt. For larger puwer reactors.30 5tW and referense the shutdown or power redu. tion fm t his is im small J Shange to wariant o planation.

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Dockst No.:

50-316 Unit Namma D.C. Cook Unit.2 Completod By:

G. J. Peak Telephone:

(616) 465-5901 Date:

09/07/84 Page:

1 of 1 MONTHLY' OPERATING ACTIVITIES - AUGUST, 1984 HIGHLIGHTS:

The unit entered the reporting-period in Mode 1 at 100% of rated thermal power.

The unit tripped on 8-5-84 due to the failure of Crid II.

Crid II was repaired and the unit was returned to service and subsequently loaded to 100% power.

No major power reductions occurred during'the reporting period.

Total electrical generation for the month was 748,680 MWH.

SUMMARY

8-05-84 The unit tripped at 1414 hours0.0164 days 0.393 hours 0.00234 weeks 5.38027e-4 months due to the failure of Crid II.

8-06-84 Crid II was declared operable at 0615 hours0.00712 days 0.171 hours 0.00102 weeks 2.340075e-4 months .

8-07-84 The reactor was critical at 1220 hours0.0141 days 0.339 hours 0.00202 weeks 4.6421e-4 months and mode 1 was entered at 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months .

The main turnbine was rolled at 1510 hours0.0175 days 0.419 hours 0.0025 weeks 5.74555e-4 months .and the main generator was paralleled at 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months .

8-08-84 Power reached 100% at 0935 hours0.0108 days 0.26 hours 0.00155 weeks 3.557675e-4 months .

8-10-84 Engineering safety features ventilation unit HV-AES-2 was inoperable for a five hour period for coupling work.

8-29-84 AB diesel generator was inoperable for a nine hour period for maintenance.

8-30-84 AB diesel generator was inoperable from 0553 hours0.0064 days 0.154 hours 9.143518e-4 weeks 2.104165e-4 months on 8-30-84 to 1819 hours0.0211 days 0.505 hours 0.00301 weeks 6.921295e-4 months on 8-31-84 to repair a broken bolt on the generator.

The Control Room Cable Vault Halon System remains inoperable as of 1707 hours0.0198 days 0.474 hours 0.00282 weeks 6.495135e-4 months on 4-14-83.

The backup CO System remains operable.

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t DOCKET NO.

50 - 316 UNIT NAME D. C. Cook.- Unit No. 2

'DATE 9-13-84 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE AUGUST, 1984 M-1 Repaired 2CD diesel starting air compressor discharge check valve, DG-104C. Valve was stuck open. Lapped seat and re-installed internals.

C&I-l CR1D II, power inverter failed. After replacement of a blown 150A fuse, the inverter operated for 5 minutes when the fuse again blew. All switching diodes and silicon controlled rec-i tifiers were replaced. The inverter then operated satisfactorily for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months on a load box, af ter which it was returned to service.

6 C&I-2 Steam flow channel II, FI-513 read 0.65 x 10 lb/hr with no steam flow. Ifultiplier module FY-513B was replaced and the flow chan-nel was recalibrated to correct the problem.

I-l C&I-3 CD-2 battery charger oscillated about 270 volts when on equalize l

charge. Replaced C-1 on the gate filter and a defective firing

[

board #4. Adjusted the float setting to 260.5 vde and equalize to 277 vdc. The current limit (PS) was set at 110 amps.

C&I-4 Replaced and calibrated Dynalco Tachometer on 2AB diesel gen-erator.

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- lWDMnt & MICH&4N ELECTRIC CONNM DoneW C. Cm Nuclear Plant P.O. Seu 458, Snegman, Mchegan 49106 -

September 13, 1984 1

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 2 Technical Specification 6.9.1.6, the attached Monthly Operating Report for the Month of August, 1984 is submitted.

Sincerely, h

W. G. Smith, Jr.

Plant Manager

[

WGS:ab Attachments cc:

J. E. Dolan M. P. Alexich i

R. W. Jurgensen NRC Region III E. R. Swanson R. O. Bruggee (NSAC)

R. C. Callen S. J. Micrzwa l

R. F. Kroeger B. II. Bennett j

J. D. Iluebner J.11. llennigan l

Z.

Cordero R. F. liering i

J. F. Stietzel PNSRC File INPO Records Center ANI Nuclear Engineering Department 1

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ML20093H222

Text

SUMMARY

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