ML20090H992

Monthly Operating Rept for June 1984

ML20090H992
Person / Time
Site:	Cook
Issue date:	06/30/1984
From:	Gillett W, Might A, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8407270336
Download: ML20090H992 (6)

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AVERAGE DAILY UNIT F0WER LEVEL DOCKET NO.

50-316 UNIT 2

DATE 7/2/84 COMPLETED BY A. Might TELEPHONE (616) 465-5901 MONTH June 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY FOWER LEVEL (MWE-Net),

(MWe-Net) 1 17 2

18 3

19 4

20 5

~21 6

22 7

23 8

24

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'9 25 10 25 11 27 12 28 13 29 14 30 15 31 16 INSTRUCTIONS On this; fonnat itst the averace daily unit pcwer level in MWe-Net for each day in the recortino month.

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50-316 DOCKETNO.

UNITSilUTl) OWNS AND POWER REDUCTIONS UNIT NAME D.C. Cook-Unit 2 DATE 7-3-84 COMPLETEllilY B.A. Svensson_

REPORT MONTil JUNE, 1984 TELEPilONE 616/465-5901 PAGE 1 of 1 Cause & Conective jg

'h E 4 1.icensee h

N. i.

Date E.

M2 3s5 livent G?

93 A'8 8"" 8" 5

itepose u NO EO Prevent itecussence O:n y

tc c 2 Mg u

6 147 840310 S

720 B&C 1

N.A.

ZZ ZZZZZZ The Unit was removed from service on 840310 for scheduled Cycle IV-V re _

Cont',1 fueling / maintenance outage. The re ~

fueling and all outage work is essen-tially completed. Steam' generator crevice flushing has been completed and reactor coolant system heatup is presently in progress.

I 2

3 4

Mettmd:

Exinbit G Insiincimus 17: Forced Reason:

S: Sdicilnical A-Equipmen Failme(Explain) 1 Manual fin l'acpasation of Dara 11 Mainienanc.: or Test 2 Manual Scram.

lintiy Sheets foi licensee C.Refncling

.l Automatic Sct.un.

livent Repoit 11fiti File INilRI G-D Itegulatoiy itestoiction 4-Ot her ( Explain) 0161) li-Operatos Tsaiaing & license lixaminalion 5

1 Ailminist ative INhtbit 1 - Same Souice G Ope:ational Leios flixplaio) 19/77)

Il Olher (thplain)

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IINIT SHUTDOWNS AND POWER REDUCTIONS V ' INSTRUCTIONS This report should descrie all plant shutdowns during the in accordance with the table appearmg on the report form.

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

If category 4 must be used. supply brief comments.

anon of sigmficant dips in average power leveis. Each sirni.

Scant reduction m power level (greater than 20% reduction LICENSEE EVENT REPORT :. Reference the applicable m averaae 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 />) reportaole occur ence pertammg to the outage or power should be noted, even though the urut may not have been reduction. Enter the tirst four parts (event year. sequential l

shut down completely. For such reducuens in power level, report number, occurrence code and report type) of the tive the duration should be listed as zero, the method of reducuan part designation as desenbed in item 17 of Instrucuons for should be listed as 4 tother). 2nd the Cause and Correcuve Preparation of Data Entry Sheets for Licensee Event Report Act:en to Prevent Recurrence column should explain. The (LER) File (NUREG.0161). This information may not be Cause 2nd Correcuve Action to Prevent Recurrence colu'nn immediately evident for all such shutdowns, of course, smee should be used to provide any needed explanation to fully turther 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 will not result in a reportable occurrence.

NUMBER. This column should indicate the sequentir.1 num-the positive indication of this lack of correlanon should be ber as:igned to each shutdown or signtiieant reduction m power noted as not applicable (N/A).

for that calendar year. When a shutdown or sigmScant power SYSTEM CODE. The system in which the outage or power reduction begins m one report perod and ends m another.

.m entry should be mtde for both report penods to be sure reduenon ortgmated should.oc noted my the two digit code at.

all shutdowns or sigmdcant power reducuons are reported.

Exhibit G Instn2cuons for Preparation at Data Entry Sheets Untti a unit has achieved its first power generation, no num-f r Licensee Ennt Repon (LER) File (NCREG.0161).

ber should be assigned to each entry.

Systems that do not 6t any existmg code should be denps.

ted XX. The code 22 should be used for those events where DATE. This column should mdicate the date of the start a system is not applicable.

of each shutdown or sigm0 cant power reducuon. Report as year. month and day. August 14.1977 would be reported COMPOSENT CODE. Select the most apprepnate omponent as 70814. When a shutdown or sigmficant pcwer reducuen from Exhibit I instrucuons for Preparanon of Data Entr>

begms m orie report penod and ends m another, an entry should Sheets for Licensee Event Report (LER) File (SUREG.0161L be made for both report periods to be sure all shutdowns usmg the following entieda:

or sign.ficant power reductions are reponed.

TYPE. Use "F" er "S" to indicate either " Forced" or " Sche-du!ed." respecuvely, for each shutdown or significant power B.

If not a component failure, use the related ecmponent:

reduenon Forced shutdowns include those required to be e.g., wrong valve opera:ed through error: list valve as tnatiated by no later than the weekend following discovery component.

of an off cormal condition. It is recogntzed that some judg-ment is requ: red m catesonzmg shutdawns in tfus way. In C.

If a cham of fatlures 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. mclud.

completed in the abscrice of the condition for which correcuve ing the other components which fail, should be desented 3ction was taken.

under the Cause and Corrective Acuon to Prevent Recur.

rence column.

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

end of the report pennd and pick up the ensumg down time signated XXXXXX. The code ZZZZZZ should be used for m the fullewmg report penods. Report duranon of outages evems where a component designation is not applicable.

rounded to the nearest tenth of 2n hour to facilitate summation.

The sum of the tural outage hours plus the hours the genera-CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-tot was on line shoutc equat the gross hours in the reporting RENCE. Use the column in a narrative fashion to ampiify or penod.

explam the circumstances of the shutdown or power reduction.

The column should include the spectile cause for each shut.

REASON. Categonze by :etter deugnanon m accordance down or significan: power reduction and the immediate and with the table appeanng un tne report form. If category H contemplated long term correcuve acuen taken. if appropri-must he used. suspiy bnet comments.

ate. This column should also be used for a desenption of the m:.or safety.related corrective mamtenance performed dunna METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an idenufication of REDUCING power. Categorize ev number designation the enucal path acuwty and a report of any smale release et, radioactmty or smgle radianon exposure speemeady assoet.

INme that this differs trom the Edtson Eleetne Insutute ated with the outage which accounts for more than 10 cereent IEEl) derimtions of " Forced Partiel Outage" and " Sche.

of the allowsole annual values.

Juled Partial Out g For enese term >. H'l uses 4 shange or For long textual reports contmue narrattve on separ:te paper JO \\lW as the brea pwnt. For larger ;m*er reactors. 30 MW and reterence the shurdown or power redusttuu tW tm3 is n.o > mall a change to wariant evianauoo.

narrauve.

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Docket No.:

50-316 Unit Name:

D. C. Cook Unit 2 Completed By:

G. J.

Peak Telephone:

(616) 465-5901 Date:

07/05/84 Page:

1 of 1 MONTHLY ODERATING ACTIVITIES - JUNE 1984 Highlights:

The Unit entered the reporting period in Mode 5 with the Reactor Coolant System at the half loop elevation following the fourth refueling of the Reactor.

The Reactor Coolant System was filled and vented and as the repor+.ing period came to an end the Unit was in Mode 3 at operating temperature.

The containment integrated leak rate test was successfully completed during the reporting period.

Summary:

6/9/84 The East Residual Heat Removal Pump was inoperable for a 15 hour1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> period to repair a discharge sample valve.

6/11/84 The West Residual Heat Removal Loop was inoperable from 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> on 6/11/84-to 1410 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.36505e-4 months <br /> on 6/13/84 due to repairs being made on the Component Cooling Water System.

6/26/84 Mode 4 was entered at 1915 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.286575e-4 months <br />.

7/1/84 Mode 3 was entered at 0438 hours0.00507 days <br />0.122 hours <br />7.242063e-4 weeks <br />1.66659e-4 months <br />.

The Control Room Cable Vault Halon System remains 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 backup-CO System remains operable.

2 C

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DOCKET NO.

50 - 316 UNIT NAME

.D. C. Cook - Unit No. 2 DATE 7-3-84 COMPLETED BY B. A, Svensson TELEPHONE (616) 465-5901 PAGE 1 of 2 MAJOR SAFETY-RETATED MAINTENANCE JUNE, 1984 M-1 Equalizing line for RH-127E developed a weld leak at the flange joint. The tubing was refitted and welded eltm-inating the defective portion.

M-2 A weld leak was observed on the CCW line to #21 Reactor Coolant Pump lower motor bearing. The cracked weld was ground out and rewelded.

M-3 The lower oil reservoir on #21 Reactor Coolant Pump 'totor developed a leak between the copper tubing and reservoir plate. The leaking joint was cleaned and resoldered.

M-4 Check Valve #RHR-141 was found to be leaking through. The valve was disassembled, lapped and checked for proper seating surface contact. Upon reassembly, leak rate testing was performed satisfactoril'.

y M-5 The AB Emergency Diesel Generator tripped due to low lube oil pressure. Inspection of the lube oil foot valve revealed a damaged gasket, which caused low oil pressure. A new gas-ket was installed.

M-6 The outer and inner 612' personnel alrlock door compression seals were replaced using EPDM type seals and the 650 and 612 inner and outer personnel airlock door window gaskets were replaced using EPDM type gaskets.

M-7 The boron injection tank outlet valves, ICM-250 and ICM-251, were observed to be leaking through. Upon disassembly, the seating surfaces were lapped until a proper contact pattern was obtained.

M-8 ECR-31, Containment Air Monitor isolation was observed to be leaking through excessively. After disassembly and upon reassembly; the plug, seat,' cage, and gaskets were replaced.

M-9 Containment Air Monitor isolation valve, ECR-35, was obsetved to be leaking through excessively. Machining of seating sur-faces was performed to obtain-proper surface contact. The valve was also repacked.

M-10 CM0-416, Component Cooling Water to miscellaneous services required excessive force to operate. The 16" centerline valve was replaced with a new Pratt velve. Functional testing was performed satisfactorily and the valve was returned to service-

C 45, DOCKET NO.

50 - 316

~ ' '

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

=DATE 7-3-84 COMPLETED BY B. A. Svensson TELEPHONE

_(616) 465-5901 PAGE

- 2 of 2 MAJOR SAFETY-RELATED MAINTENANCE JUNE, 1984 M-ll RH-114E, Sample Isolation Valve was observed to be leaking through. The valve bonnet was removed, and the seating surfaces lapped until a proper seating contr.ct pattern was obtained. RH-114E was then reassembled and returned to service.

M-12 ICM-305, Containment Sump tc 2E RHR pump was found to be

' leaking through excessively. Upon disassembly, the seating surfaces were lapped until a proper contact pattern was obtained. The valve was then reassembled and leak rate tested.

M-13 The Containment Air Monitor Isolation valve, #ECR-31, was observed to be leaking through excessively. The valve was disassembled, and seating surfaces were lapped to obtain proper seating surface concact. ECR-31 was then reassembled and leak rate tested.

M-14 During B&C Leak Rate Testing, CPN-4 was observed to have a leak. Upon inspection, one hole was found in the bellows and was repaired by welding.

M-15 Upon inspection of the #23 Reactor Coolant Pump seals, the following parts were replaced: #1 insert, #2 seal and in-sert, #3 seal and runner, all 0-rings, and seal water Flex-gaskets. The pump was_then aligned and coupled.

M-16 The RhR discharge safety valve, #SV-104E, was found to be leaking through. The valve was rebuilt replacing the disc, pin, nozzle and gaskets. Upon reassembly, SV-104E was set at' 600 lbs., tested and reinstalled into the system..

C&I-l On 2CD diesel the fuel rack trip cylinder shuttle valve was blowing air'out of-the exhaust port..The diaphragm on the shuttle valve was found to have a hole in.it.

The valve was replaced; r.

l_____________._.____.____._._____.__._._____._.___._.__i

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Lsy,a.,,, - IN0MNA & MICHIGAN ELECTRIC COMMMY Donald C. Cook Nuclear Plant P.O. Box 458, Bridgman, Mchigan 49106 July 3,.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 June, 1984 is submitted.

Sincerely, TAI'l W. G. Smith, Jr.

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 A.- F. Kozlowski R. F. Hering

.J.

F. Stietzel

'PNSRC File INFO Records Center ANI Nuclear Engineering Department 1

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