ML20132G183

Monthly Operating Rept for Jul 1985

ML20132G183
Person / Time
Site:	Cook
Issue date:	07/31/1985
From:	Climer, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8510010493
Download: ML20132G183 (11)

Text

9 m

N.R.C.

OPERATING DATA REPORT.

DOCKET NO.

50-316 DATE 8/1/85 COMPLETED BY CLIMER TELEPHONE 616-465-5901 OPERATING STATUS 1.

Unit Name D.

C. Cook Unit 2 JUL 85 inotes 2.

Reporting Period

3. Licensed Thermal Power (MWt) 3411 4.

Name Plate Rating (Gross MWe) 1133 :

5. Design Electrical Rating (Net MWe) 1100 1

6. Maximum Dependable Capacity (GROSS MWe) 1100 1

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

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

9. Power Level To Which Restricted. I.f Any (Net MWe)

10. Reasons For Restrictions. If Any:________________________________

____________________________________This Mo.

Yr. to Date Cumm.

11. Hours in Reporting Period 744.0 5087.0 66455.0

12. No. of Hrs. Reactor Was Critical 357.2

'4409.2 47489.2

13. Reactor Reserve Shutdown Hcurs 0.0 0.0 0.0

14. Hours Generator on Line 357.0 4390.5 46389.1

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Therm. Energy Gen. (MWH) 1049002 14576673 147654734

17. Gross Elect. Energy Gen. (MWH) 318510 4758440 48543870 4

1

18. Net Elect. Energy Gen. (MWH) 305215 4592984 46810718

19. Unit Service Factor 48.0 86.3 72.6

20. Unit Availability Factor 48.0 86.3 2.6

21. Unit Capacity Factor (MDC Net) 38.7 85.2 69.1

22. Unit Capacity Factor (DER Net)-

37.3 82.1 67.7

23. Unit Forced Outage Rate 52.0 12.6 12.7

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

__1985._a_e f u e_lin3_Ou_t a3e _e s e ima t e_d_ s t a r t_ d a t e_ la t_e__Ngemb_e r_19_85cEs t ima_t e d_ _ _

duration 100 dags.

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~ ~ 3te oi~5t3EtupI~

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Ii 5 hut Down At 5nd'~oi~RepoE$~PeEI~odI~E~sti~ mated

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D 25.

i STARTUP IN PROGRESS-8/1/85

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

Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION i

S 8510010493 850731' PDR ADOCK 05000316 Rf R

PDR f

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AVERAGE DAILY POWER LEVEL (MWe-Net)

DOCKET NO.

50-316 UNIT TWO DATE 8/1/85 COMPLETED BY CLIMER TELEPHONE 616-465-5901 MONTH JUL 85 AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL D AY -

POWER LEVEL 1

1051 17 0

2 1031 18 0

3 712 19 0

4 388 20 0

5 383 21 0

6 426 22 0

7 968 23 0

8 993 24 0

9 990 25 0

10 1013 26 0

11 1013 27 0

12 1011 28 0

13 1007 29 0

14 1002 30 0

15 729 31 0

16 0

N i

50-316 2.

IMM.KE'I NO IINIISilulilOWNS ANilPOWl:H HlitallCIBONS IJNil NAME D.C. Cook Unit 2 IDA IE 8-9-85 B.A. Svensson July' 1985 COMPl.ETEp itY HI POH I MONill

'I El.I'PilONE 616/465-5901 PAGE 1 of 2 B

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161 850703' F

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N.A.

RB INSTRU Reactor power was reduced to 47%

due to an indicated misaligned group of rods in Control Bank D.

The mis-alignment was found to be caused by rod control problems. While at the reduced power, the main feed pump turbine condensers were checked for condenser tube leaks. Reactor power was returned to 100% on 850708.

162 850715 F

387.0 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 e'..e calculated steam gen-erator primary to secondary leak rate.

One leaking tube was identi-fled and eddy current testing iden-tified one tube with 94% degradation.

Both tubes were mechanically plugged.

At the end of the reporting period the reactor coolant system was in 1

2 3

4 1:: l'in ce.1 Heason:

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UNIT!HUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS N report should descr2e 211 plant shutdowns dunng me m 2::ordan:e with the tacle appearms on the report form.

report penod. In addiuon. it should be the sour:e of explan.

If:stegory 4 must be used. supply bneicomments.

anon of signdcant dips m average power lewis. Each ngni.

ficant reduenon ut power level (greater than M'Tr reduction LICENSEE EVENT REPORT z.

Reference the app 12 cable m average daily power level for the preceding 24 hnurs)

Mponacle ocence putaming to the outage or power should be noted, even though de unit may not have been mduction. Enter the first tour ; arts (event year. sequennai l

shut down completely. For su:n reducuens in power lew!,

report numcer. ce:urrence code and report type) of the tive tne duranon should be !isted as tero. the method of reducuon part designation as des:nbed in !!em 17 of Instrucuons for snould be listed as 4 (Other), and the Cause and Correcuve Preparanon of Data Entry Sheets for Licensee Event Report Acuan to Prevent Re:ur e.sce column should explain. The (LER) File (NUREG.0161). N information may not be Cause and Correcuve Acuon to Prevent Recutance column immediately evident for all suds shutdowns, of course, since should be used to provice any needed explananon to fully further mvesugation may be reqmted to ascertam whetner ur descnbe the circumstances of the outage or power reducuen.

not a reportable oc:u rence was myolved.) If the outage or power reducuon wt!! not result in a reportsele oc:urrence.

NUMBER. N :olumn should indi:ste the sequennal num.

the positive mdiestion of this lack of correlation should be ber assagneo to each shutdown or sigmricant reducuan in power noud as not applicable (N/A).

for that saiencar year. When a shutdown or ngmilcant power SYSTEM CODE The system in whi:h the outage or oower reduetton beg:ns m one report pened and ends m another.

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an entry should be made for both report penods to bs sure all st:utdowns or ng:ud ant power reducuons are reported.

Extubit G. Instrucuans for Preparanon of Data Entry Sheets Unti a umt has ach:eved its first power generation, no num.

for Lzcansee Ewn: Resort (LER) File $UREG.0161).

ber snou;d be asugned to eaen entry.

Systems that do not fit any ex:stmg code should be deugna, ted XX. The : ode ZZ should be used for those events where DATE. This celu=n should edicate the date of te start a system is not appdc:31e.

of esca shutdown or ngntil: ant pcwer reduccon. Report as year. month. and day. August 14.19t' would be reported COMPO.NENT CODE. Seis:t the most appropnate component as ~~CS14. When a shutdown or ugmficant power reducuan from Exhibit ! - Instruccons for Preparanon of Data Entr>

begms m one report eer:od and ends m another, an entry should Sheets for Licensee Ewnt Report (LER) File (NCREC4161).

be made for both report penods to be sure all shutdowns usmg the fonowmg cnuena-or ngmd: ant power reductions are reported.

TYPE. Use -F' or -S" to ;ndicate either " Forced" or " Sche.

duled." respe:nwiy for each snarcown or ugn:dcant power B.

If not a component fadure. use the retated. component:

refuenon. Forced shardowns meiude tnose reqmrod to be e.g., wrong valw operated througn errort list valw as

mrtatec by no later than the weeitend followmg discovery

omponent.

of an off. normal condicon. It is recosmzed that some judg.

meet :s requared :n categonzmg shutdowns in t!us way. In C. If a mam of failures occurs. tne first component to mai.

general a forced snutdown is one that would not have been function should be listed. The secuence of events mciud.

completec in tne absence of de condicon for which correcuve ing the other components wiu:h fad. should be desenbed scuen was taken.

under 'he Cause and Cormenw Acuan to Prevent Recur.

rence column.

DURATION. Self. explanatory. When a shutdewn extends beyond the end or a report penod. count only the uma to the Components that do not ilt any existmg : ode should be de.

signated XXXXXX. The code ZZ2222 should be used for end at the report penod and pick up the ensumg down ume

,,, g.2 component designation is not appitcable.

m me foilowts:s moort senoes. Report duranon of outages rounded to tne nearest tenth of an hour to facdtrate summat2on.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

The sum of the total outage hours ;tus the hours the geners' RENCE. Use the :clumn in a carrsute fashaon to ampitfy or tor was on line should equal the gross hours in the reportmg l

p nod.

expla:n the etrcumstances of the shutdown or power reducuan.

Die column should include the spectile :st.se for each shut.

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REASON. Cateponze by !etter deugnattua in xcorcance down or ugmticant power reducuon ud the irimediate anc l

with the racle acoeurutg on tt:e report form. If :stegory H ontemotated long term correcuve acuan taken. :(appropn.

must be used. sunory enet eumments' ste. Uus column should also be used for a desertption of the maior safety.related correcuve mamtenance performed dunn METHOD OF SHUTTING DOWN THE REACTOR OR - the outage or power reducuen me!udmg an ident:11 cation of REDUCING POWER. Categortze t'y numr'er densnauen the muesi path xum) anc a apon of any unpe misase et radioacuvtry or unge radianon exposure speettiestly ttsce:.

Inose that this differs trom the Edison Eleutne Insuture ated with rne outage wruch accounts for more than 10 :erwent iEEI) detinitions of -Forced Pamal Oursee~ and "Sene.

of th' 211owsole 2nnual values.

uled Pantal Ourage.~ For these tenus. FE! uses 4 shange of For tons textual resorts sontmue narrative on seo: rate ;. aper

.tO MW as the areak pnt. For taryer pu er reactors.30 MW and referen.e the shutdown or power redu tion fu ini.

s v.u > mail a nange to wanant opfanation.

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50-316 DOCKETNO.

IlNir SilllllHlWNS AND P(Hvtu Htplu IlONS UNII NAblE D.C. Cook Unit 2 DATE 8-9-85 COMPLETED by B.A. Svensson HI PON'l klONill July, 1985 616/465-5901

'IEl LPilONE PAGE l of 2 "t

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d 162 (Continued)

Mode 3, Hot Standby, at rated pres-sure and temperature and preparations for reactor startup in progress.

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limlabit G lusisutti.uis S. Seleeifule.1 A l' pnpener.1 1:ailius (1.nplain)

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1:nisy Sliccis fos liensee C Hsfueling

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a UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS Th:s recort should descr$e all plant shutdowns dunng de

n accordance with the taole appeanns on the report form.

report penod. In addition,it shodd be the source of expian.

If category 4 must be used. supply bneicomrnents.

anon of ngmne:nt dips :n asersge power leveis. Each upi.

ficant reducnon m power level (grester than Fe reductica LICENSEE EVE.NT REPORT =. Reference the applic:ble m average daily power level for the preceding 24 houn) reportsele occurrence pertammg to the outage or power should be noted, even dough de umt may not have been mduction. Enter the f.nt four pans (event year. sequent:al shut down comp!stely. For such reducuens in power level, report number. occurrence ude and report type) of the dve l

the durst:on should be listed as zero, the method of reducuan part designation as desenbed in Item I7 or, Instruenons for should be 'isted as 4 (Oder), and de Cause and Correenve Prep 2rauon of Data Entry Sheets for L:censee Event Recort Acnon to Prevent Recurrence column should expism. The (LER) File (NUREG.0161). This mformation may not be Cause and Correcuve Acton to Prevent Recurrence column immediately evident for all sudt shutdowns, of course, smce snould be used to provtce any needed explanation to fully turther :nvesugauon may be requ: led to ascertsm whether er descnbe tne c:rcumstances of the cutage or power reduction.

not 2 reportaole occurrence was involved.) If the outage or power reducnon wt!! not result :n a reportaofe occurrence.

NUMBER. Th:s column should indimte the sequennal num.

the p sit ye meicanon of this !ack of correlation should ce ber asuped to each shutdown or sigmdcant reducuan m power noted as not applicsole (N/A).

for ti.at calendar year. When a shutdown or ngmtlesnt power SYSTEM CODE. The system M whna the out:ge or power reducton begms m one report pened and ends m another.

an entry snould be made :or born report penocs to be sure reduction ong:nated could be noted by the two dig:t code of Enu.mit G. Instruenons for Preparanon or. Data Entry Sheets

11 snuscowns or na:u6 cant power reduenons are reported.

Untd a.amt h:s a:h':evec :ts F.nt ;ower generuton, no nu:n-f r Ltcensee mt ep n R) Ne MREM 61b ber snould be assiped to each entry.

Systems that do not tit any ex:stmg code should be denpa.

ted XX. The code ZZ should ee used for dose events where DATE. This column should.ndicate the d:te of me start a system is not appticaole, ot* esca shutdown or ugmScant power recuenon. Report as year. month. and :sy. Aurast 14.197 would be reported COMPONENT CODE. Sciect the most aoprepnate camponent as ""'CS14 When a shutdown or ngmEc:st power reduenan from Exh: bit I. Instruenons fer Preparanon of Data Entr) beg:ns m ene report pened sad ends m another. 2n entry should Sheets for Licensee Event Report (LER) F:!e(NCREG41611.

be " tace for both report penods to be sure all shutdowns usmg the followmg cntienar or up: Scant power reduenons are reponed.

A. If a comconent fuled.use the ecmponent directly mvcived.

TYPE. Lse "F" or "S" to mdicate either " Forced" or "Sene.

du!ed.*' resoccuvely, for esch snutcown or signincant power B.

If not a component fat!ure, use the re:ated component:

redue:;on. Forced shutdowns mciuce tnose required to be e.g.. wrong valve operated through errert list valve as uunated by no later dan de weekend followmg discovery comoonent.

of 2n off.riormal condinon. It is recogm:ed that some judg.

ment :s required in categott=ng shutdowns in th:s way. In C.

If a cham of failures occurs. the Ant component :o mai.

general. a forced shutdown is one that would not have been funcuen should be listed. The sequence of events. meiud.

completed m the absence of de =ncluon for wrach correcuve mg the other components wh:ca fail. snould be desenbed acnon wu taken.

under the Cause and Correcuve Acnon to Prevent Recur.

rence column.

DURATION. Seif. explanatory. When a shutdown extends Commonents that so not rit any exisung code snould be de-beyond de end at 2 report penod, courit only the tune to the ugnated XXXXXX. The code 7P77 snould be used for end or the report penod and pick up the ensumg down ame l

m tne foilowmg reocrt cenods. Report duranon of outages events where a component designanon is not applicaole.

rounced to the nestest tenth uian nour te faclitate summanon.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

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

RENCE. Use the column m a narranve futuan to ampufy or ter was on !me snould cousi the gross hours a the reportmg explain the c::cumstances of de shutdown orpower reducuan.

F'O d-l The column could melude the specde cause for esch snut.

[

down or sipidesnt power reducnon and the immeciate anc REASON. Categorize by :etter deupatton in accordance with tne r2ote aopearmg on the re; ort form. If category H eentemoiated long term correenve acnon taken. if appropn.

ste. Tius column should also be used for a desenpuon of the must be used.succiy : met eumments.

maior safety < elated correenve mamtenance performed dunna METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduenon me:uding an Idenutication ot; REDUCING POWER. Categonee ey numner designauon

• ^' *""si path acavny 2no a repon or any unge reiesse at radioacuvtty or 6mgfe rsdist:on exocsure soeetrie:tly asce:.

I IN<ue that this difrers trom the Edistm E!e:tnc Inst:tute Jted with the outsge wiuch accounts for more than 10 cer.ent iEED der.aons of " Forced P2ntal Outage" anc "Scae.

Jl de 211swacic annual vslues.

culed P2ntal Outage - rbr these temti. f El uses 4 stange at For lung textual reports eentmue astrative on secar:te pseer 10 MW as the creak ;mmt. For targer puwer reactors.30 MW

.nd reteren.e tite shutcown or power reou avn for tm>

s rm imail a.nange to wariant oplanation.

narranve y-

--~.s-

Docket No.:

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

A.

S. Puplis Telephone:

(616) 465-5901 Date:

August 12, 1985 F,

Page:

1 of 3 I

MONTHLY OPERATING ACTIVITIES - JULY, 1985 HIGHLIGHTS:

~

The reporting period began with the Unit at 100% power.

One major power reduction to 47% occurred due to a control rod misalignment problem.

The Unit was removed trom service on July 15, 1985 due to an increase in the calculated steam generator primary to secondary leak rated.

At the end of the reporting period the reactor coolant system was Mode 3, Hot Standby, at rated pressure and temperature.

Gross electrical generation for the month'of July was 318,510 MWH.

SUMMARY

7-02-85 At 0850, a power decrease to 98% was started to perform surveillance testing.

Power reached 98%.at 0858.

At 1452, a power increase to 100% was started.

Reactor power reached 100% at 1510.

7-03-85

.At 1100, a power decrease to less than 50% was started due to indicated misaligned-group of rods in Control

~ Bank D.

At 1208, Control Bank D Rods:

D4, D12, M12, and M4, indicated greater than 12 steps below the group demand.

At 1405, the West Main Feed Pump was removed from service to check tor tube leaks in the feed pump turbine condenser.

At 1412, reactor power was at 47% to satisfy Technical Specification 3.1.3.1.

7-06-85 At 1937,.a reactor power increase was started to 98%

power based upon an allowable limit of 100.6%.

7-07-85 At 0447, the powerLincrease was stopped at 98% due to allowable power-limit considerations.

7-08-85 At 1203, reactor power was increas'ed to 100%, which was reached at 1244.

I

Docket No.:.

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

'A.

S. Puplis Telephone:

(616) 465-5901 Date:

August 12, 1985 Page:

2 of 3 7-09-85 At 0600, a power decrease to'98% to perform surveil-lance testing was started.

Power. reached 98% at 0632.

At 1514, as a result of surveillance testing being completed started increasing reactor power to 100%,

which was reached at 1618.

7-14-85 At 0227, No. 4 Boric Acid Transfer Pump was declared Inoperable due to pump casing leaks.

The No. 3 Boric Acid Pump is operable.

The No. 4 pump '.tas declared operable at 0515 on 7-21-85.

At 0338, Boric Acid Storage Tank flowpath_was inopera-ble from 0227 to 0238 due to taking No. 4 Boric Acid Transfer Pump out of service.

The No. 3 pump was on recirculation back to the Middle Boric Acid Storage Tank.

At 2000, started decreasing reactor power for Moderator Temperature Coefficient (MTC) Testing.

7-15-85 At 0400, the Unit was at 95% power for MTC testing.

At 1640, the primary to secon'dary leak rate was.219 gpm.

At 1741, a reactor shutdown was commenced because of-the primary-to-secondary leak.

At 2030, plant auxiliaries were transferred to reserve supply.

At 2100, the Unit entered Mode 2.

At 2136, the reactor trip breaker ~were opened, and Mode 3 was entered.

7-16-84 At 0335, the Unit entered Mode 4.

At 2050, the Unit entered Mode 5.

7-19-85

-At 0840, degassing of the Reactor Coolant System had been completed.

7-23-85 At 0130, the Reactor Coolant System was at half loop.

I~-

Docket No.:

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

A. S. Puplis l

Telephone:

(616) 465-5901 Date:

August 12, 1985 Page:

3 of 3 7-27-85 At 0650, while in. Mode 5, after " bumping" the second reactor coolant pump for the first time pressurizer pressure increased to the lower limit of the power operated rslief valve setpoint, causing the. relief valve to lift.

AT 2240, started bubble tormation in pressurizer.

7-30-85

~At 1700, the Unit entered Mode 4.

7-31-85 At 0427, the Unit entered Mode _3.

The Control Room Cable Vault Halon System remains inoperable as of 1707 on 4-14-83.

The backup CO System for the Control Room Cable Vault was inoperable for per$onnel entry at the end of the reporting period.

i

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DOCKET NO.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 8-9-85 COMPLETED BY B. A. Svensson EUOR SAFETY-RELATED MAINTENANCE JULY, 1985 M-1 No. 4 boric acid transfer pump was removed from service for repairs of a mechanical seal leak.

Impeller, shaft, bearings and mechanical seal were replaced.

Pump was tested for operability.

vstem_LNOMNL6_ MICHIGAN ELECMIC COMPANY Donald C. Cook Nuclear Piant P O. Bom 458. Brusgman, Mctugan 49106 August 9, 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 July, 1985 is submitted.

Sincerely, 1

g4-ll-

. SmitET-3.

Plant Manager WGS:ab Attachments cc:

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

{

S. J. Mierzwa F. S. VanPelt, Jr.

P. D. Rennix D. R. Hahn l

Z.'

Cordero j

J. J. Markowsky-j S. R. Khalil j

J. F. Stietzel PNSRC File j'

INFO Records Center ANI Nuclear Engineering Department

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