ML20136B712

Monthly Operating Rept for Aug 1985

ML20136B712
Person / Time
Site:	Cook
Issue date:	08/31/1985
From:	Climer, Will Smith, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8511200270
Download: ML20136B712 (11)

Text

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s g N.R.'C." OPERATING DATA REPORT a

DOCKET NO.

50-316

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DATE 9/4/85 sp*.-4T

• COMPLETED BY ClIMER y

TELEPHONE 616-465-5901 OPERATING STATUS 1.

Unit Name D.

C.

Cook Unit 2

2. Reporting Period AUG 85 notes

3. Licensed Thermal Power (MWt) 3411 4.

Name Plate Rating (Gross MWe) 1133 :

5.

Design Electrical Rating (Net MWe) 1100 !

6. Maximum Dependable Capacity (GROSS MWe) 1100

7. Maximum Dependable Capacity (Net MWe) 1060 -----------------------

8. If Changes Occur in Capacity Ratings (Items no. 3 through 7) Since Last Report Give Reasons __________________________________________

Power Level To Which Restricted. If Any (Net M ________-__________

__________________________---_______-______-__We) 9.

10. Reasons For Restrictions. If Any ________________________________

________________-___________-_______________________________Cumm.

This Mo.

Yr. to Date

11. Hours in Reporting Period 744.0 5831.0 67199.0

12. No. of Hrs. Reactor Was Critical 98.4 4507.6 47587.6

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator on Line 56.0 4447.3 46445.9

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Therm. Energy Gen. (MWH) 6067S 14637312 147715373

17. Gross Elect. Energy Gen. (MWH) 130GO 4771520 48556950

18. Net Elect. Energy Gen. (MWH) 11170 4604162 46821896

19. Unit Service Factor 7.6 76.3 71.8

20. Unit Availability Factor 7.6 76.3 71.8

21. Unit Capacity Factor (MDC Net) 1.4 74.5 68.3

22. Unit Capacity Factor (DER Net) 1.4 71.9 66.9

23. Unit Forced Outage Rate 92.4 22.9 13.8

24. Shutdowns Scheduled over Next Six Months (Type,Date,and Duration):

25. If Shut Down At End of Report Period, Estimated Date of Startup:

Mode 2 expected 9/15/85

26. Units in Test Status (Prior to Commercial Operation):

Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 8511200270 850831 PDR ADOCM 05000316

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AVERASE DAILY POWER LEVEL (MWe-Net)

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DOCKET NO.

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. UNIT TWO DATE 9/4/85 COMPLETED BY CLIMER TELEPHONE 616-465-5901 MONTH AUG 85 i

AVERAGE DAILY AVERAGE DAILY

' DAY POWER LEVEL DAY POWER LEVEL 1-0 17 0

2 42 18 0

1 3

0 19 0

4 0

20 0

2 5

0 21 0

6 0

22 187 7

0 23 214 i

'8 0

24 23 9

0 25 0

10' O

26 0

11 0

27 0

12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 0

7 16 O.

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i 50-316 DOCKET NO.

IlNIT SiltilDOWNS AND POWER ltEDilCTIONS UNIT NAME D.C. Cook - Unit 2-DAHE 9-7-85 B. A. Svensson COMPT.ETED BY HLPORT MONTil August, 1985 TELEPilONE 616/465-5901 PAGE 1 of 2 Fe t

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• id u t-6 162 850715' F

35.9 A

1 N.A.

CC HTEXCH The Unit was removed from service at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on 850715 due to an in-crease in the steam generator primary to secondary leak rate. The Unit was returned to service at 1152 hours0.0133 days <br />0.32 hours <br />0.0019 weeks <br />4.38336e-4 months <br /> on 850802. Total length of the outage was 422.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />.

163 850802 F

464.2 A

1 N.A.

C'C HTEXCH During power ascension from the pre-vious outage with reactor power at 31%, it was determined that steam gen-erator primary to secondary leakage existed in steam generator #23 and it was decided to remove the Unit from service. Based on eddy current test-ing results, 35 tubes were mechani-cally plugged. The Unit was re-turned to service at 0211 on 850822.

(Unit 2 Continued On Next Page)

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12: 12uccJ Reasons:

Metiumi:

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lintiy Slicens few liensee C.Nc(ucting 3 Autunutic Stsaan.

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UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should desenbe all plant shutdowr.s dunng te in accordance with the taole appearms on the report form.

report penod. 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 levels. Each signi.

ficant reduction in power level (greater than 20", reduction LICENSEE EVENT REPORT ar.

Reference the apptteable in average daily power level for the preceding 24 hnurs) reportaole occurrence pertaming to the outage or power should be noted, even though is unit may not have been reduction. Enter the first four parts (event year, sequennal l

shut down completely. For such reducuens in power level, report number, occurrence code and report types of the tive the duration should be IIsted as zero. the method of reduccon part designation as desenbed in item 17 of Instrucucns for should be listed as 4 (Other), and the Cause and Correcuve Preparanon of Data Entry Sheets for L:censee Event Report Action to Prevent Recurrence column should explam. The (LER) File (NUREG 0161). This information may not be Cause and Correcuve Acton to Prevent Recurrence column immediately evident for all suJs shutdowns. of course, stace should be used to provide any needed explanation to fully further invesugation may be requ: red to ascertam whether or desenbe the circumstances of the outage or power reduction.

not a reportable occunence was involved.) If the outade or power reductton will not result in a reportaole occurrence.

NUMBER. This column should indicate the sequennal num.

the postttve indication of this !ack cf correlation should be ber assigned to each shutdown or sigmacant reducuanin power noted as not applicable (N/A).

for that calendar year. When a shutdown or ugnificant power SYSTEM CODE The system in wiuch the outage or power reduction begms m one report penod and ends m another.

reduction ongmated sh' uld be noted oy the tw"o digit code of o

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

Ex:ubit G. Instruccons for PreParauon of Data Eat'Y Sheets Unt:1 a umt.as achieved its first power generation, no num.

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

S ber should be asugned to each antry.

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

ted XX. The code Z2 should be used for those events where DATE. Esis column should indicate the date of the start a system ts not appiicaele.

of each shutdown or signi!! cant power reduccon. Report as year. mont. and day. Aagust 14.1977 would be reported COMPONENT CODE. Select me most appropnate ;omportent as ~C814. When a shutdown or ugruilcant power reduccon from Exhibit I. Instrucuons for Preparanon of Data Entr) bepts in one report pened and ends in another. an entry should Sheets for Liernsee Event Report (LER) Ftle (NCREG 016i L be made for both report penods to be sure all shutdowns usms the following critiona:

or samfcant power reductons are reported.

I TYPE. Use -F' or -S" to indicate either " Forced" or " Sche-culed." respectively, for each snutdown or sigmficant power B.

If not a :ornponent fadure, use the related component.

reducuon. Forced snutdowns include those required to be -

e.g. wrong valve operated through errott list valve as imusted by ne later utan the weekend following discovery component.

of an off. normal condition. It is recogmzed that sorne judg.

1 ment is reqtated in categorizmg shutdowns la thas way. In C.

If a chain of fadures occurs, the first component to mai.

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

completed in the absence of the conditiort for which correcuve mg the other components which fail should be desenbed i

acuon was taken.

under the Cause and Correcuve Acuan to Prevent Recur.

rence column.

DURATION. Selfexplanacory. When a shutdown extends beyond the end or a report penod. count only the ume to the Components that do not ilt any exasung code should be de.

end of trie report pened and pick up the ensumg down uma signated XXXXXX. The code Z2222Z should be used for in the feilowmg report penods. Report durstson of outaps events where a component deugnation is not applicable.

ruunded to the nearest :enth of an hour to fac:litate summanon.

The sum of the tetal outage hours plus the hourt the pnera.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

for was on line should equal the gross hours in the repcrtmg RENCE. Use the column in a narranve fastuon to smplify or penod.

explaan the circumstances of the shutdown or power reducuan.

The column should in:!ude the spectile cat.se for each shut.

• n r ugm cant Pown reducuon and the anmediate ams REASON. CateP$ rue by letter deu4nanon in accorcance

• tth the taale appeartsty un the report form. If category H eontemoisted long term :orrecuve scuon taken. !f appropn.

must he used, suociy bnet eumments.

ate. This column should also be used for a desenption of the mator safety related correcttve maintenance performed durma METHOD OF SHUTTING DOWN THE REACTOR OR

' h' * "' * "' E * * ' "d "*" " i" *I"#i"' *" *d '""'I** 'I""

• I REDUCING POWER. Categonze ey nurneer dessnanun

'O' """'ai path aennty and a report of any smgie release.3r radioaettvity or imple radiauon exposure spe6ttkady assost.

3%:e that this differs from the Edissm Ele:ttte Insuture sted with the eutage which accounts for more tnan 10 cersent I EEI) detimtions of -Forced Parnal Ourage'* and " Sche.

di th* 2130*2018 2nnual values.

Juled Part:41 Outer. For (Sese tenni. eel uses 4 shange or For tung textual reports ontmue narrative -an seoarate ; aper 10 MW as the break pumi. For larger po*er reactors.30 MW and referen.e the shutdown or power redu.uun tio tm.

s nu imall 4.hange to wanant espiattalion.

narrative.

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e 50-316 DOCKET NO.

llNIT SilU fpOWNS ANil N)WER Mailuk DONS UNIT NAME D.C. Cook - Unit 2 IDAIE 9-7-85 COMel ETED NY B. A. Svensson MI PORT MONDI August, 1985 TEl.ErilONE 616/465-5901 PAGE 2 of 2 r.

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6 164 850824' F

187.1 A

1 N.A.

CC HTEXCH With reactor power at 30% and hold-ing for a steam generator boric acid soak, the primary to secondary leak rate determinations,again showed a steadily increasing leak rate. The decision was made to remove the Unit from service for steam generator re-pairs. Visual examinations with the steam generators flooded identified one leaking tube in each of steam generators #22 and #24. Eddy current testing of all four steam generators is presently in progress. The esti-mated return to service date is September 28, 1985.

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UNIT 5HUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS Tins report should descnbe all plant shutdowns during te in accordance with the table appearms on the report form.

4 report penod. In addition. it should be the scurce of explan.

If category 4 must be used. supply crief comrnents.

4 anon of sismricant dips m average power levels. Each signi.

Scant reducuan in power Iewi (greater than 209 reduction LICENSEE EVENT REPORT w.

Reference the applicable in average dady power level for the preceding 24 hnurs) reportaole occurrence pertaming to the outage or power should be noted, even though the uma may not have been reduction. Enter the erst four parts (event year sequent:al shut downs completely!. For such reductions in power level, report numeer. occurrence code and report type > of the tive the duration should be listed as zero, the method of reducuort.

part designation as desenhed in item 17 of Instrucuons for should be listed as 4 (Other), and the Cause and Correcuw Preparanon of Data Entry Sheets for Licensee Event Report Aetion to Prevent Recurrence column should explain. The (LER) F:le (NUREC4161). This infmanon may not be Cause and Correenve Acuan to Prewn Recurrence column immediately evident for all such shutdowns, of :ourse, since should be used to provide any needed explanation to fuily further invesugation may be required to ascertam whether ur descnoe the circumstances of the outage or power reduction.

not a mponable occmace was involved.) If the outage or power reduction wtll not result m a reportable occurrer:ce.

NUMBER. This column should indicate the sequential num.

the posmve indicanon of this lack of correlation should be her assiped to each shutnown or sigmricant reduction in power noted as not applicable (N/A).

for that calendar year. When a shutdown or significant powet SYSTEM CODE The system in whzch the outage or power reduction begms in one report penod and ends in another.

reduction ongmated sh"ould be noted by the tw'o digit eode of i

an entry should be made for botn report penods to be sure all shutdowns or ugnu1 cant power reducuons are reported.

Exhtbit G. Instrucuons for Preparanon or Data Entry Sheets 1

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

for Licensee Event Report (1.ER) File (NUREG4161).

j ber should be assiped to each entry.

Systerns that do not tit sny eximag code should be dengna.

ted XX. The code ZZ should be used for those events where 1

DATE. This column should aidicate the date of the start a system is not appticaole.

I of each snutdown or sigmncant power reducuon. Report i

as year. month. and day. August 14.1977 would be reported COMPONENT CODE Select W most aopropnate.amponent as ~~C814. When a shutdown or uptficant power reduccon from Exhibit ! Instrucuons tU Preparanort of Data E:ttry j

begms m one report penod and ends m another, an entry should Sheets for Licensee Event Report (LER) File (NCREG416L).

be made for both report penods to be sure all shutdowns ussig the followmg entiona:

l or ugmricant power reductions are reported.

i A. If a component faded.use the component directlyinvolved.

2 TYPE. Use "F" or "$" to indicate e:ther " Forced" or " Sche.

duled." respectively, for each shutdown or sigmScant power S.

If not a comoonent fadure, use the related component:

reducuan. Forced shutdowns include those required to b*

q wrong valw operated through errott list vsive as initiated by no later than the weekend following discovery component.

of an off. normal condition. It is E

--J=a that some judg-ment is required in categoriams shutdowns in this way. In C. If a cham of fadures occurs. the first component to mai.

pneral a forced shutdown is one that would not have been function shou!d be !!sted. The secuence of events. metud.

j completed in the absence of the condition for which corrective

- ing the other components which fail, should be desenbed ac.non was taan, under the Cause and Correcove Acuan to Prewn Recur.

tence column.

j DURATION. Seif expianatory. When a shutdown extends beyond the end of a report penod, count only the tune to the e,,,

,g g, g, gg and of the report pened and pick up the ensuing down nme signated XXXXXX. The code ZZZZZZ snould be used for in the followmg resort periods. Report duramon of outaps ewnts where a component desapanon is not spplicable.

rounded to the nearest tenth of an hout to facditate summation.

The sum of the total cutage hours plus the hours the pners.

CAUSE & CORRICTIVE ACTION TO PREVENT RICUR.

tor was on line should ecual the gross hours in the reportmg RENCE Um h column in a num fm to ampiify w i

i pencd.

expiaan the circumstances of the shutdown or power rsoucuon.

The column should include the specid: cause for each shut.

REASON. Categonae by !stter deugnanon m accordance wn or upidsant poww mducum an the tmmedlau and with the taole appearms on the report form. If :stegory H

"""*" N '"

8'"" #'"' # *PM P"*

2 i

must be used.supeiy bnet eumments.

Ate. This e umn shoidd also be used for a desenption of the maior safety.related correcuve maintenance performed durma l

METHOD OF SHUTTING DOWN THE REACTOR OR the outspe or power reduction including an toentul:stion of 1

RRDUCING POWER. Categonae ey number despauon

'"' 4""'21 path acuvuy ami a spon of any s.npe misase of rad!oactivity or sm#e radiation exposure meettleatly asso6t.

4 INote that this differs trom the Edisim E!e;tne Institute 2ted with the outsp *hich accounts for rnore than to :erwent IE!!i derinsuons of "Fareed Partial Outap at:d "Scae.

of the allowaoie sasual values.

Juled Partial Outapt." For these tenni. FEl uses 4 hange of For long textual reports sontmue narrative on separate ; spee "0 MW as the tresk pmnt. For larpr puwer reastors.30 MW

.nd referen.e the shutdown or power redu. tion roi imi a too small 4 hany to warrant nplananoa.

narrative.

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Docket No.:

50-316 Unit Namas D.C. Cook Unit 2 Completed By:

D. A. Bruck Telephone:

(616) 465-5901 Date:

September 6, 1985 Page:

1 of 3 MONTHLY OPERATING ACTIVITIES - AUGUST, 1985 HIGHLIGHTS:

The reporting period began with the reactor coolant system in Mode 3, preparing for startup.

The reactor was taken critical on 8-01-85 and the Unit was paralleled on 8-02-85.

Power reached 31% when a controlled shutdown was begun because of primary-to-secondary leakage.

Mode 5, Cold Shutdown was reached on 8-03-85.

Steam Generator tube repairs were completed and the reactor coolant system heatup started on 8-18-85, reaching Mode 3 on 8-19-85.

The reactor was critical on 8-21-85 and the Unit was paralleled on 8-22-85.

Power reached 30% on 8-22-85 and was held for flux mapping.

On 8-23-85, a controlled shutdown was begun because of primary-to-secondary leakage reaching Mode 5 on 8-25-85.

The reporting period ended with reactor coolant system in Mode 5.

Gross electrical generation for the month of July was 13,080 MWH.

SUMMARY

8-01-85 At 1455, the reactor was taken critical.

8-02-85 At 0715, the reactor entered Mode 1.

At 1152, the Unit was paralleled.

At 1655, with the Unit at 31% power, a controlled shutdown was begun due to primary-to-secondary leakage.

At 1801, the Unit was removed from service.

8-03-85 At 0234, the reactor coolant system entered Mode 4.

8-04-85 At 0112, the reactor coolant system entered Mode 5.

8-06-85 At 0638, the reactor coolant system was at half loop.

8-09-85 At 1817, the Control Room Cable Vault Halon System was declared operable.

8-16-85 At 1944, the #3 Steam Generator Auxiliary Feedwater Valve, FMO-232, failed to auto open on a Steam Genera-tor Lo-Lo signal and was declared inoperable.

DockDt No.:

50-316 l.'

Unit Ntm2 D.C. Cook Unit 2 Completed'By:

D. A. Bruck l

Telephone:

(616) 465-5901 l

Date:

September 6, 1985 Page:

2 of 3 l

8-18-85 At 1320, FMO-232 was declared operable.

8-19-85 At 0023, the reactor coolant system entered Mode 4.

r At 0717, the reactor coolant systen entered Mode 3.

At 1135, an inadvertant Engineered Safeguard Features actuation (containment ventilation isolation) occurred due to an alarm on the lower containment radiation monitor ERS-2301.

The alarm which caused the actuation l

was due to the reactor coolant system heatup.

f l

8-20-85 At 1512, the Control Room received a report of smoke coming from the reactor trip breakers.

The reactor trip breakers were opened and breaker

'A' declared j

inoperable (discovered a smoking-coil in breaker ' A').

At 2250, an inadvertant reactor trip occurred during surveillance testing on source range instrument N-31.

8-21-85 At 0515, reactor trip breaker

'A' declared operable.

At 0839, the reactor was taken critical.

At 1401, the reactor entered Mode 1.

l 8-22-85 At 0211, the Unit was paralleled.

At 0244, with the reactor at 20% power, a 3%/hr power increase was started.

At 0306, reactor power was held at 23%.

At 0310, an inadvertant Engineered Safeguard Features actuation occurred due to upper containment area l

radiation monitor VRS-2101.

The high alarm which caused the actuation was due to the power increase.

At 0515, a reactor power increase at 3%/hr to 30% power was started.

l l

At 0629, an inadvertant Engineered Safeguard Features actuation occurred due to upper containment area l

radiation monitor VRS-2201.

The high alarm which caused the actuation was due to the power increase.

i At 0700, a reactor power hold at 29% was started for l

flux mapping.

At 0828, an inadvertant Engineered Safeguard Features actuation occurred due to lower containment radiation monitor ERS-2305.

The high alarm which caused the i

actuation was due to the power increase.

l

Docket No.:

50-316 Unit Namn D.C. Cook Unit 2 Completed By:

D. A. Bruck Telephone:

(616) 465-5901 Date:

September 6, 1985 Page:

3 of 3 8-24-85 At 0205, a controlled shutdown was begun due to primary-to-secondary leakage.

J.

At 0540, the reactor entered Mode 2.

P At 0450, the Unit was removed from service.

At 1455, the reactor coolant system entered Mode 4.

8-25-85 At 0708, the reactor coolant system entered Mode 5.

8-27-85 At 0242, the reactor coolant system was at half loop.

8-28-85 At 0624, the East Residual Heat Removal loop was declared inoperable due to a leak at valve RH-128E.

8-30-85 1At 2140, the East Residual Heat Removal loop was declared operable.

t

t DOCKET NO.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 9-7-85 COMPLETED BY B. A. Svensson MAJOR SAFETY-RELATED MAINTENANCE AUGUST, 1985 M-1 NRV-151, pressurizer power' operated relief valve was reported to be leaking by.

Valve was disassembled, seats inspected and lapped, tested for operability, and returned to service.

M-2 NRV-153, pressurizer power operated relief valve was reported to be leaking by.

Valve was disassembled, inspected, seat ring re-placed, and seats lapped. Teuted for operability and returned to service.

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ystem l$$$$b &JEH!GAN.E1ECTRIC_C0MPANY.

Donald C. Cook Nuckar Plant P.O. Box 453. Brusgman, Mchgan 49106 September 7, 1985 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, 1985 is submitted.

Sincerely,

f-- ~

e(pv-W. G. Smith, Jr.

Plant Manager WGS:ab Attachments ec:

J. E. Dolan M. P. Alexich R. W. Jurgensen NRC Region III B. L. Jorgensen R. O. Bruggee l

R. C. Callen l

S. J. Mierzwa l

F. S. VanPelt, Jr.

l P. D. Rennix D. R. Hahn i

Z.

Cordero l

J. J. Markowsky

[

S.-R.

Khalil J. F. Stietzel PNSRC File INPO Records Center l

ANI Nuclear Engineering Department i

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