ML20097A852

Monthly Operating Rept for Jul 1984

ML20097A852
Person / Time
Site:	Cook
Issue date:	07/31/1984
From:	Gillett W, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8409130427
Download: ML20097A852 (7)

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1. Uni: Name:

Donald C. Cook 2

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AVERAGE DAILY' UNIT POWER LEVEL t

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- DOCKET NO.

50-316 i

UNIT 2

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DATE 8/2/84 COMPLETED BYW.T. Gillett

, TELEPHONE 616-465-5901 MONTH Julv. 1984 DAY AVERAGE DAILY POWER LEVEL DAY (MWE-Net)

' AVERAGE DAILY POWER LEVEL (MWe-Net) 1 17 750 2

18 946 3

19 1033 4

O 20 1028 S

21 1045 6

22 1048 7

23 1032 8

24 1037 9

25 1085 10 2s 1086 11 37 27 1078 12 282 23 1083 13 415 29 1094 14 412 30 1084-15 546 31 1067 16 656 INSTRUCTIONS On this fomat list the averace daily unit pcwer level in MWe-Net for each y in the recortina month. Ccmnor= e-

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E r NO. 50-316 UNITSilUTDOWNS AND POWER REDUCTIONS DATE 8-13-84 COMPLETEp ilY B A-svannann JULY, 1984 TELEPilONE 616/465-5901 REPORT MON 111 PAGE 1 of 1 5

E l.icensee Er E4 Cause & Conective EO 3

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Acti.m so No.

Date k

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gE 3gg Report #

in U Prevent itecmrence 6-o e

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147 840310 S

259.5 B&C 1

N.A.

ZZ ZZZZZZ The Unit was removed from service on 840310 for scheduled Cycle IV - V re-Cont'<..

fueling / maintenance outage. The out-age work has been completed and initia]

J criticality for Cycle V occurred on 840707. Low power physics testing was I

completed on 840711 and the Unit was paralleled to the System the same day.

The power ascension testing program was completed and the Unit reached 100% reactor power on 840719. The total length of the outage was 2966.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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F: Fmeed Reason:

Method:

lixhibit G -Insisuctions S. Scheduled A-Eiguipmes.: Failuse(laplain) l-Manual for Preparation of Data ll-Maintenance of Test 2 Manual Seeam.

Ensiy Sheets fm 1.icensee C itefueling 3 Ausomatic Scram.

Event Repost (1.l!R) File INllRI.G-D Regulaiosy Resisiction 4-Othes (lixplain) 01611 F-Opciator l'eaining & l.icense lixamination F-Ailminist rative 5

I!xhibit I - Same Somce G Opciational Enor Ilixplain) 19/77) 11 Other (Explain)

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UNIT SHUTDOWNS AND POWER REDUCTIONS e

INSTRUCTIONS -

This report should 'desenbe. all plant shutdowns during the -

in accordance with the table appearing on the report form.

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

If category 4 must be used. supply brief comments.

!ation of sigmftcant dips m average power levels. Each signi.

L ticant reduction in power !evel (greater than 20% reduction LICENSEE EVENT REPORT :r.

Reference the applicable 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 />) reponable _ occurrence pertaining to the outage or power

~ hould be 'noted, even though the unit may not have been reduction. Enter the first four parts (event year, sequential s

l shut down completely. For such reductions in power level.

report number, occurrence code and report type) of the tive the duration should be listed as zero.the method of reduction part designation as desenbed in item 17 of Ir:structions for

' should be listed as 4 (Other), and the Cause and Correcttve Preparation of Data Entry Sheets for Licensee Event Report Action to' Prevent Recurrence column should explain. The (LER) File (NUREG 0161). This information may not be Cause and Correenve 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 ascertain whether or describe the circumstances of the outage or power reduction.

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

NUMBER.. This column should indicate the sequential num.

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

l for that calendar year. When a shutdown or significant power 1

reduction begms in one report period and ends in another.

SYSTEM CODE. The system in which the outage or power reduction onginated sh' uld be noted by the tw'o digit code of o

an entry should be made for both report penods to be sure

.all shutdowns or signincant power reductions are reported, Exhibit C. Instructions for Preparation of Data Entry Sheets

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Until a unit has achieved its first power generation, no num.

for Licensee Event Report (LER) File (NUREG.0161).

ber should be assigned to each entry.

Systems that do not fit any existmg code should be desiana.

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 applicaole.

of each shutdown or significant power reduction. Report as year. month. and day. August 14.1977 would be reported COMPONENT CODE. Select the most appropriate component as 770814 When a shutdown or significant power reduction from Exhibit !. Instructions for Preparatton of Data Entry begms m one report penod and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG.0161).

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

or sigruncant power reductions are reported.

A. If a component failed.use the component directlyinvolved.

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 ecmponent:

i reduction. Forced shutdowns include those required to be e.g., wrong valve operated through erron hst valve as initiated by no later than the weekend following discovery component.

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

ment is requ: red 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.includ.

j completed in the absence cf the condition for which corrective ing the other components which fail, should be desenbed j

action was taken.

under the Cause and Correcttve Action to Prevent Recur.

rence column.

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

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

rounded to the nearest tenth o(an hour to facslitate summation.

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

CAUSE & CORRECTIVE ACTION TO-PREVENT RECUR.

tor was or4 line should equal the gross hours in the reportmg RENCE. Use the column in a narrative fasluon to amplify or period.

explain the circumstances of the shutdown or power reduction.

The column should include the specific cause for each shut.

d wn REASON. Cateponze by letter dengnation in accordance r signti cant p wer reduction and the immediate and l

conterrplated long term corrective acnon taken, if appropri.

with the table appearing on the report form. If category H must be used. supply brief comments.

ste. This column should also be used for a desenption of the major safety.related corrective maintenance performed durme the outsee or power reduction including an identification ot the entical path aetmty and a report of any smgle releas METHOD OF SHUTTING DOWN THE REACTOR OR

. REDUCING POWER. Categonze by number dengnation radioastmty or smgle radiation exposure speettlesily associ.

1 Note that 'this differs trom the Edis<m Electrie Institute ated with the outage which accounts for more than 10 percent I

IEEI) detinitions of " Forced Partial Outaae" =and " Sche.

of the allowable annual values.

duled Partial Outage." For these tenni. I El uses a shange of For long textual reports continue narrative on separate paper 30 MW as the break pomi. For larger power reactors.30 MW and reterense the shutdown or power redu.ttun im this is rm small 4 Shaner to wanant espianation.

narrative.

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'Dockst No.:

50-316

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Unit Nama:

D. C. Cook Unit 2' s

W Completed By:

G. J. Peak Telephone:

(616) 465-5901

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.s Date:

08/07/84 x,

Page:

1 of 1 y

s MONTHLY OPERATING ACTIVITIES - JULY 1984 Highlights:

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'The unit entered the reporting period in Mode 3 in the process of unit startup following a refueling outage.

The reactor was taken critical and low power physics testing was completed.

The unit was then loaded to 100% power where it was operating as the reporting period ended.

No major power reductions occurred during the reporting period.

Total electrical generation for the month was 446,380 MWH.

Summary:

7-6-84 All control banks and shotdown banks were completely withdrawin at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br /> and the dilution to criticality started at 2251 hours0.0261 days <br />0.625 hours <br />0.00372 weeks <br />8.565055e-4 months <br />.

7-7-84 Mode 2 was entered at 0138 hours0.0016 days <br />0.0383 hours <br />2.281746e-4 weeks <br />5.2509e-5 months <br /> and the reactor was critical at 0323 hours0.00374 days <br />0.0897 hours <br />5.340608e-4 weeks <br />1.229015e-4 months <br />.

7-9-84 The unit went back into Mode 3 at 2220 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.4471e-4 months <br /> due to problems with the rod position indication.

7-10-84 Mode 2 was entered again at 2120 hours0.0245 days <br />0.589 hours <br />0.00351 weeks <br />8.0666e-4 months <br />.

7-11-84 The reactor went critical again at 0015 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> and Mode 1 was, entered at 0621 hours0.00719 days <br />0.173 hours <br />0.00103 weeks <br />2.362905e-4 months <br />.

The main turbine was rolled at 0918 hours0.0106 days <br />0.255 hours <br />0.00152 weeks <br />3.49299e-4 months <br /> and the: main generator was paralleled at 1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br />.

7-14-84 The urbine driven auxiliary feedwater pump was inoper-

.able from 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />. or, 7 41-84 to 0010 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> on 7-15-84 due to a malfunctionir J wergency leak off valve.

7-19-84 The unit reache'd it'>

v er at 1820 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.9251e-4 months <br />.

7-24-84 The east component cooling water loop was inoperable from 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on~7-24-84 to 1427 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.429735e-4 months <br /> on 7-25-84

' t.o repair a valve in the system.

The Control Room Cable Vault Halca System remair,n inoperable as of 1707 hours0.0198 days <br />0.474 hours <br />0.00282 weeks <br />6.495135e-4 months <br /> on 4/14/83.

The backu'p CO2 System remcJns operable.

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~ DOCKET NO.

50 - 316' UNIT NAME D. C. Cook - Unit No. 2 DATE 8-13-84 COMPLETED BY B. A. Svensson

. TELEPHONE (616) 465-5901 PACE

~1 of 1 MAJOR SAFETY-RELATED MAINTENANCE JULY, 1984 M-1 Equalizing line around RH'-128E was observed to ' be leaking.

The leaking portions of. pipe were-replaced.

'M-2 The #3 Steam Generator blowdown isolation valve #DCR-330 was observed to be leaking through. The valve was disassembled, internal parts inspected and reassembled utilizing new gaskets.

M-3 Removal and inspection of _ the #21 Reactor Coolant Pump seals was' performed, replacing the #3 seal ring, all flex gaskets and o-rings.

M-4 Removal and inspection (of the #22 Reactor Coolant Pump seals was performed, replacing the #3 seal runner, #1 seal insert, ring and runner, all flex gaskets, and o-rings.

M-5 Pressurizer Power Opeiated Relief Valve, NRV-153, was observed to be leaking through. The seat ring, gaskets, plug and stem assembly were replaced. Upon reassembly the. valve was tested and returned to service.

C&I-l QTI-220, RCP #22 lower bearing temperature failed low. The RID was found open and was replaced. Proper indication was restored.

C&I-2 The RTD for loop 1 cold leg failed, causing Tavg-to fail low.

The bistables were tripped within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the spare RTD was connected, the R/E converter recalibrated and the STP was run to verify operability of the loop. The temperature indication was restored.

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maam a acman wcrac coana Donald C. Cook Nuclear Plant P.O. Bou 458, Bridgman, Mchigan 49106 August 13, 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 2 Technical Specification 6.9.1,6, the attached Monthly Operating Report for the Month of July, 1984 is submitted..

Sincerely, W

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. Hierzwa R.'F..Kroeger B. H. Bennett J. D. Huebner J. H. Hennigan A. F. Kozlowski R. F. Hering J. F. Stietzel PNSRC File 4

INPO Records Center ANI Nuclear Engineering Department 16 1

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