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Monthly Operating Rept for Jul 1983
	ML20024F070
Person / Time
Site:	Cook
Issue date:	08/02/1983
From:	Might A, Will Smith; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8309080182
	Download: ML20024F070 (7)
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X, INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 (616) 465-5901 August 12, 1983 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 1 Technical Specification 6.9.1.6, the attached Monthly Operating Report for the Month of July, 1983 is submitted.

Sincerely, 2

(,(./$ uK/1 W. G. Smith, Jr.

Plant Manager WGS:ab Attachments cc:

R. S. Hunter 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 H. L. Sobel J. D. Huebner J. H. Hennigan A. F. Kozlowski R. F. Hering J. F. Stietzel PNSRC File INPO Records Center 8309080182 830802 Q

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C?IRAT:NC DATA RI? ORT 1

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50-315 DCC:C ' NO.

DA7z 8-2-83 Coat?L..50 EY A. Minht TII.I?.Scy; ( 616 )46s-5901 c?rnTrNG s ATUs DONALD C. COOK 1

No::s

1. Uni: N c:::

JULY, 1983

2. Reportis;?: dad:

3250

3. L:censedTh :==I?swer(StW:!:

1152

4. N =eu!:i: ?..:i.;(Cro:s ?,1W:):

1030

5. Desi;= I!e=:i=1 R::in;(Ne: 51We):

1056

6. 5'- d :== Dependsh1: C p::i:f (Cross 51We):

1020

7. 'daxi=== De~ d 'I: e---W (Net 31We):

S. If C. a;es 0 = in Cap 2=i:7 R::i:;s (1::=s Numba:3 Th:oc;h 7) Sis : L:s:Repor:. Give R sons:

Reasons stated at bottom of nace.

9. Power Leve! To Which R:r::i= d.If Any (Ne': 3:W:):

10. R== sons Foe R..::i::fo::.If Asy:

'D:is 5tonth Yr.<o. Data Cu. : !::ive

11. Hou:s != Repor.!a; ?=ied 744 sinR7 75.215 362 4619.3 56,500.9

12. Nu::.her af Hou:s R==:rw:s Cd:i=1

13. Re==:r R:sene Shu:dovm H:::s 0

0 463

14. Hour: Ce===:ce ca Lie, 360.2 4610.8 55.323.7

15. U..!: R: serve S~nutdown Ho::=

0 0

321 943.698 14.242.117 161.544.677

16. Cross The=:1 In:::y C4===ted (3twM)

17. Orcss Ee=n=!I:cr;y Gen:=::d G.IWH) 301,630 _

4,669,410 53.105.260 288,837 4,501,984 51,095,485

13. Net E :=i=1I:=;y Cen==::d C.;WH) 48.4 90.6 75.7

19. Unit Senic:.::ctor 48.4 90.6 75.7 l

23. Uni: As:IIshi!!:v.:c:or

1. Uni: C:: sci:y 5=::=r (Usi=; >!rC Net) 38.1 86.8 68.6

. Unit Caescity. :::or (Usin; DI?..% n 37.7.

85.9 65.6 0

1.1 7.9 l

23. Uni: Fore d Cu::ge Rat

24. Shutdowr.s Scheduf d Over Nec 6 Stor.:i:s (Type. D:te.::.d Du=:fon a(.:cht:

I

'5. If Sh : Down A: End Of Repor: P::iod.Esti==:ed D:te of Sc:r::p:

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.25; Units la Tes: S;::us IPnor to C:==ercist Ope =: font:

Fore =s:

Ac.ieved i

INIT:A L CRIT *CA LITY

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INmAL I:.I TR:C: Y CO:4:.:I?.C:A:. 0?InA T:0N

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ITEM 4 THROUGH 7 CHANGED BY AEPSC ENGINEERING AS OF JUNE 11,1983 DUE TO CHANGING THE CONTROL VALVES TO FULL ARC ADMISSION. THIS CHANGE IS INCLUDED g,_,

l IN THE YEAR-T0-DATE AND THE CUMULATIVE COLUMN FOR ITEMS 21 AND 22.

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AVERAGE DALLY UNIT POWER LEVEL i

j DOCKET NO.

50-315 UNIT 1

DATE 8'-2-83 COMPLETED BY A. Might TELEPHONE (616)465-5901' MONTH JULY, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1 918 17 2

905 is 3

901 19 4

887 20 5

873 21

^

6 879 22

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7 876 23

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8 876 24 9

869 l

25 10 870 l

25 11 866 27 s

12 863 28 13 550 29

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14 444 30 15 453 31 16 INSTRUCTIONS On this format list the average daily unit power level in MWe-Net for each day in the reporting month.

Ccmoute to the nearest whols mecawatt.

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IMM KEI NO. 50-315 tlNITSinflDOWNS AND POWEH HElstfr' lint <S UNil' N AhlE D.C. Cook - Unit 1 D A'I E 8-12-83 COhlet.li~l ED itY B.A. Svensson H l.P O H I alO N~Ill JULY, 1983

'llil.LPilONE 616/465-5901 SHEET 1 of 1 I

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3gg Repuso u un u o'

Psevene Itcciusenie e-a u

o 203 830713 F

0 A

4 N.A.

CH PUMPXX Reactor power rapidly reduced from 86% to 49%.to remove the west main feed pump from service due to appar-ent pump bearing failures. Inspec-tion revealed that both journal bear-ings and the thrust bearing shoes were wiped. The cause of the failure was found to be two broken 3/4" pipe nipples in the bearing oil supply system.

204 830716 S

383.8 B&C 1

N.A.

ZZ ZZZZZZ The unit was removed from service at 0010 on 830716 for scheduled Cycle 7-8 refueling and maintenance outage. The unit remained out of service at the end of the month.

1 2

3 4

1: l'oc ceil Reason:

kleilual:

1:xloint G - Insinua tions S. Stlicif ulcal A l'iguspines. 1 ailuie (1.xplain)

I klanual itu Psep.naan..: of Dan.:

11 Alaintenance or Test 2-klanual Sa am.

1 nasy Slicens foi J i cnsee l Antonnese & sam.

I:vens Hepo 6 (I l'H l 1 sic lNiiHI G-C Hefueling 18 llegulaluay Hesisii. lion l Onlics 11: aplain)

(1861l I Opcs.itos Isaining & license I.xamination IC Ailmuusisallye 5

talolai 1 - Same Somic G Opesational I.isne lliplanin l'8/ /ll 11 Othcs (lapi.iin)

UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should desence 2!! ;! ant shutdowns aunng te a ::=r:ance with de t2cle acces:::g on the report form.

report perted. In addition. tt snould be the sour:e of exolan.

If estegory a must be used. suppiy bnef :cmments.

atton of sigmneant dips m sverage power leveis. Each nant.

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LICENSEE EVENT REPORT :. Reference the apphenole fi:2nt reduenon in power level (greater esa 20^ reduction m 2venge dady power leve! for the preceding 24 houn) rgon2ste ennence pensam;.o m autage or po.e:

recu:non. Enter th: '.rtt :our ;2:ts t event ;.est. sequent =

2ould be noted, even dough is umt may not have been shut down completely. For such reducnons in power level.

repon number, o;;urrence ; ode 2nd report type) of tne uve l

tne duration should be !!sted as :ero, the medod of redu:non part deugnation as desenbed in Item 1, or, Instruenons ::t should be listed as a (Oder). 2nd de Cause and Corre:nve

? roaranon of Data Entry Sheets for Licensee Event Report Acuan to Prevent Recurrence ;oluma should exp!2m. The tLER) File (NUREC Olm Tms mformanon may not :e Cause 2nd Corre:nve Action to Prevent Recur:ence column smediate!y evident for 211 such shutdowns, of coune, smce should be used to provide any needed explanation to fully rurther mvest:gstion may be required to :scertam whether er desence the ::rcumstances of the outage or power reducuan, not 2 reponsole ocanence uss involved.) If tne outage or power reduct: ort will not result in 2 reportable oc:urrence.

NUMBER. TNs column should indinte the sequent:21 num.

the positive mdt: anon of this :2ck of orreistron should te ter assigned to each shutdown or sigmAcant reducuan m power noted as not applicable (N/A).

for mat e21endar year. When 2 shutdown or ngmScant power SYSTEM CODE. The system in wh:2 $e autare or cower reduction begins in one report pened 2nd ends m another.

redu:non ortgmated should be noted.sy the two digit eode or.

an entry should be made for born report penods to be sure crnoit G. Instrueuons for Preparanon of Data entry 2nects L.1 snutdowns or stamdcant power redu nons are reported.

1 for Licensee Event Report (L.R) r_de (NL. REG 0161).

e nn! 2 unit 2s semeved its.n.rtt ;cwer jeneration, no num-i.

ber should be :ssigned to each entry.

Systems that do not fit sny existmg : ode shoulc :e dengna-ted XX. The oce ZZ should be used for mose events where DATE. This column shoc!d indicate de date ol ie start a system is not applimole.

of each shutdown or signid: ant power reduct:on. Report

.s year. mcnth. 2nd day. August 14.1977 would be reported COMPONENT CODE. Seis:t ce most 2;prcprute ;omponent as 770814 When 2 shutdown or sigmncant power reducnon from Exhibit I. Instru:nons for P epstanon of Data Entry bepas in one report pened 2nd ends m another. 2n entry should Sheets for Licensee Event Report (LER) File (NUREG 01oli.

be made for both report peneds to be sure all shutdowns usmg the followmg :nnena:

or npun:2nt power redu:nons are reported.

TYPE. Use "F" or "S" to indicate either "For:ed" or " Sche.

duled." respe:nve!y, for each shutdown or significant power B.

If not 2 omponent fadure. use de reitted ecmoonent:

reducnon. Forced shutdowns include those required to be e.g.. wrong valve operated througn :::en list valve as mitiated by nc later than the weekend following discovery component.

of an of' normal condinon. It is recogmzed that some judg.

ment ts required i.n estegonzmg shutdowns in tais way. In C. If a chain of failures occurs, the first =mponent to mai.

general. 2 for:ed situtdown is one that would not have been function should be listed. The secuence of events.mciuc.

compicted in the absen:e of the :endition for which corrective ing de other cmponents whi:h tail. should be desenbed acnon was taxen.

under the Cause sad Corre:nve Acton to Prevent Re ur.

rence coiumn.

DURATION. Sel.f. explanatory. When a shutdown extends Comeonents that do not St any ex:stmg : ode snould be Je.

beyond the end of s report pened. count only the tmte to the ugnated XXXXXX. The code ZZZZZ2 should be used for end at the re; ort penod and pick up the ensums down nme events where 2 component designanon ts not appii:2cle.

m me foi!owmg report penods. Report duration of outages rounded to the nearest tenth of an hour to facditate sur trnation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

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

RENCE. Use de clumn in 2 astranve fashion :o ampitiy or tor was on line should equal the gross hours m the report:ng exp sin the circumstances of the shutcown orpower recucuen.

penod.

The column should include the spec:ile :2use for each shut.

REASON. Cateeunze bs,etter desanstrun m accordance 2m power reducnon sad the immeciate anc Jawn or siamS contemolated long term corre:nve act:en taken, if appropn.

with the table aepearmg on tne report form. If :stegory H ste. Trus column snocid also :e used for a desenption of tne must be used, suppty bnet eurnments.

maior safety.re!sted correettve mamtenance performed dunna the outsae or power reducnon inc!uding sn :dentidcation of METHOD OF SHUTTISG DOWN THE REACTOR OR REDUCING POWER. Categonze ey numner desansuun

'h'.*"""*I E** ** * *F **" * E " 3' *^Y ""*" * **** #'

raotosetmty or smpe radiation exocsure speettteady asses:.

3%te that this differs trom the Edison E!e:tric Insutute sted with the outage which accounts for more tn;m 10 percent (EEll denruttons of " Forced Parnal Outage" and "Sete.

Olde allo *20!* 2nnual v21ues.

auled Partial Outau." For these temis. tEl uses 4 hange at For long textual reports continue narrative on secarste ; soer O MW as the creak ;mmt. For !arpr puwer resetors.30 MW

.nJ referen e the shutdown or power redu uun M un.

s rm small a.hange to warunt espiananon.

narrative.

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Docket No.:

50-315 Unit Name:

D. C. Cook Unit 1 Completed By:

C.

E. Murphy Telephone:

(616) 465-5901 Date:

8/8/83 Page:

1 of 2 L

MONTHLY OPERATING ACTIVITIES - JULY 1983 Highlights:

The Unit entered the reporting period operating at 90% power.

This extended run on this core was so that Unit 2 could be brought back on the Grid from a Steam Generator Tube Plugging outage.

The Unit power was allowed to drift down to 86% until 0650 hours0.00752 days 0.181 hours 0.00107 weeks 2.47325e-4 months on July 13, 1983 when indications of high vibration-on the West Main Feedpump Turbine was received in the Control Room.

A power reduction was started immediately and the pump was manually tripped from service at 0703 hours0.00814 days 0.195 hours 0.00116 weeks 2.674915e-4 months .

Reactor power was leveled out at 49% and the Unit operated at that power level until 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months on July 15, 1983, at which time a power reduction to "0" power was started.

The Unit was' removed from the Grid at 0010 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months on July 16, 1983.

This~ reporting period ends with the Unit in Mode 5, RCS at loop, and making preparations for the seventh refueling.

The gross electrical generation for the month was 301,63b MWH.

Summary:

7/5/83 The Ice Condenser Recorder (SG-07) was inoperable for a 10.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period when all points failed low.

7/7/83 CMO-415 Component Cooling Water (CCW) Miscellaneous Header Isolation Valve was inoperable for a 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months period.

The valve would not completely close from the Control Room.

CRV-445 CCW from the Spent Fuel Pit Cooling Valve was inoperable for a 32.75 hour8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months period.

The valve would not completely close from the Control Room.

7/11/83 East CCW Pump was inoperable for a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months period due to the Bonnet blowing off the Seal Water Valve.

7/12/83 R-26 Unit Vent Stack Monitor was inoperable for a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months period due to a bad detector.

HV-CEQ-1 Fan was inoperable for a-23.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period. - Fan breaker tripped while doing Surveillance.

7/13/83 0650 hours0.00752 days 0.181 hours 0.00107 weeks 2.47325e-4 months received High Vibrations indications on the West Main Feedpump.

0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months began power reduction to 50%.

0703 hours0.00814 days 0.195 hours 0.00116 weeks 2.674915e-4 months manually tripped the West Main Feedpump.

0710 hours0.00822 days 0.197 hours 0.00117 weeks 2.70155e-4 months Reactor power at 49%.

7/15/83 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months started removing Unit from service.

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Docket No.:

50-315 Unit Name:

D. C. Cook Unit 1 Completed By:

C. E. Murphy Telephone:

(616) 465-5901 Date:

8/8/83 Page:

2 of 2 7/16/83 0007-hours entered Mode 2.

0010 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months removed Turbine / Generator from service.

0158 hours0.00183 days 0.0439 hours 2.612434e-4 weeks 6.0119e-5 months . entered Mode 3.

0730 hours0.00845 days 0.203 hours 0.00121 weeks 2.77765e-4 months entered Mode 4.

1457 hours0.0169 days 0.405 hours 0.00241 weeks 5.543885e-4 months entered. Mode 5.

7/20/83 Reactor Coolant System at loop at 1950 hours0.0226 days 0.542 hours 0.00322 weeks 7.41975e-4 months .

.The. Control Room Cable Vault Halon System rema ns inoperable as of i

System remains operable.

1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months on 4/5/83.

The Backup CO2 4

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s DOCKET NO.

50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 8-12-83 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE JULY, 1983

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The suction isolation valve for the boric acid transfer pump, J

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CS-406, was not operating properly. The diaphragm was found separated from the valve stem. Replaced the diaphragi.

M-2 The circuit breaker for containment equalization fan, HV-CEQ-1, was tripping fer no apparent reason. Replaced the circuit breaker and completed a test run on the faa.

M-3 The isolation valve in the line from the boric acid blender to the outlet of the volume' control tank, CS-392,' was leaking due to a diaphragm failure. Replaced the valve bonnet assembly.

M-4 A socket weld on the branch connection for IFI-331, the West RHR Heat Exchanger flow instrument was leaking, Ground out the weld and revelded. Had the necessar? NDE performed.

N M-5 The #3 RCP seal water containmen; isolation check valve, CS-442-3, failed to meet the acceptance crateria of the Type C Leak Rate Test. Disassembled the valve. lapped the seat and disc and re-assembled the valve. Had the valve retested.

C&I-l Containment isolation valve, CRV 445,' component cooling water outlet from the spent fuel pit heat exchanger would not close com-pletely with flow at 7000 gpm. The asco air operator for CRV-445 was rebuilt to correct the valve operation.

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ML20024F070

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