ML20084E222

Monthly Operating Rept for Mar 1984

ML20084E222
Person / Time
Site:	Cook
Issue date:	03/31/1984
From:	Gillett W, Will Smith, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
References
NUDOCS 8405020191
Download: ML20084E222 (8)

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,,,., CPI.*:a"*NC DATA P.I?CP.'r 56-315 DCC:*

NO.

DATI 4/3/84 CCS ?!.I I': "y W. T. n11tott TI: I?HCsI 61 r,- a rs s - s 901 cri.s.~'N." '~LT:s No"8

1. Uni Nacts:

Dnnild c. Cook 2

March 1984

2. Repen.r.; ?t:fod.:

3411 3.1.ks sed nt:.:I ?swer (S Wt!:

1133

4. N =rplats Pu:..;(Csou atWe):

1100

!. Desi;:t I:ed=17 :da2 (Net S!We):

11on

4. S!* :.:::: Depe.d.:hte Q;:=rt (Crou $1We):

10 ri n

7. Sf axi=: ::: Ce; -t:ht C,::= / (Net StWe):

8. !!C2::tts 0:=r !n Cap =:7 P.ub:;s (1st~s Ne.har 3 nroc;h 7) Stas t ut R ; ort. Ciie Rausast

9. Power t.sve! To W'.hh Rest.".=ed. t Any (Net StWe):

10. Reuens ?or 7.. d: doc.t.lf.L1yr

%!*Sionth Yr. 4 o.Ca ta Cu=uhttve

11. Hours In ?. ;ortin; Ptricd 711 7 104

• 'u wo l' Nc.her Cf Hours Re::: r %u C.1d=1 2 2 0. r,

1. 6 y. g 19 a99

13. Res::ar Reusve Shutdowit Scu.rs 220.I 1, ri 2 H in,42H,1

14. Hour: Cetnist Cn.t.he

~

15. UrJ Reurve Shutdown Hou:s

16. Cross The..:1 Intr;y Cennted (St%H)

"5,405,164 123,u/H,152 733 977 i

17. Cron I: ace.=1 Zmer;7 Canentri eflW3) 244,500 1.793,100 40.019,740

13. Net I::=r.=1Ir r;y Genentic C.th'd) 2 II' ' 2 3 ')

_ Ie71Ie f' O f'

_ IHrSH4r977 2 9.

74.5 73.4

19. Urut Servies 7: star 29*"

74*3 73.4

• 0. UcJ Avsfabit::y F:stor 30 Y 74.3 70 1

!. Unit C : cr/ Tsat:r(U In; StCC Net)

?A 9 72.I hH.9

12. Ur.!: Cescf y F star (Uslag ll17..'!atl 0

I*9 13*4 i

l lJ. Unit For:rd Cutzte hie 1

4. :hatdowm ferenfad Cver Neu 6 Montas(7.vse.0tte.snt hr: con o(Ischit 1

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J. If Dur Down At End Cf P.trart Period. Estimated Oate o(Itamst -

.25. Unitila Test SutdIPnst to Ctmmen!al Csentisnit Foreent

.Asafesed IN17:A:.CT.:7::.4UT*/

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iNiitAt.I'.1:7?.:::7t Co'.ts IT.c:A '. :Ptr. 67:CN

• Corrected arror in the February report.

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0405020191 840331 i

PDM ADOCK 03000316 le I

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AVERAGE DAfLY UN87 POWER LEVEL 00CXET NO.

50-316 l

l UtlIT 2

DATE 4/1/n4 COMPT.ETED SY W. T.

ciilett l

TELE. HONE 616-465-5901 MONTH M,

-n 1ona DAY AVERAGE CAILY PCWER LEVEL DAY AVERAGE OAILY POWER LE'lEL l

(MWE-fiet ) ~

(MWe-ifet) l 1

1101 17 2

1101 la 3

1996 19 4

1099 l

20 l

5 1099 21 l

6 1099 22 7

1007 23 8

1099 24

~

9 1023 25 10 36 26 11 27 12 23 13 29 14 30 l

15 31 16 l

!!isiRUCit0NS On this fornat list tho avorsgo daily unit pcwor lovel in MWe-Not for each day in the recortino month.

Ccmouta en tha aa ~ *

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50-316

.1 3MKIE T NO.

Reset SIstilleOWNS ANga FOWLM ItEletM7 Mas D.C. Cook - Unit 2 l

LINRI NAME 4-6-84 IDAIE COMytETEg3 gy B.A. Svensson af FOR I MONf H K m, 1934 616/465-5901 IERLF900NE

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t eucawe p,,

raine A Cuese6sive y

s'8 A6:s.m ses W.

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r Psevras Rci;ussen.e f9 E

j;f, Rep.es s e

d 147 840310 S

523.9 B&C 1

N.A.

ZZ 77777Z The Unit was re=oved from service at 0403 hours0.00466 days <br />0.112 hours <br />6.66336e-4 weeks <br />1.533415e-4 months <br /> on 840310 for scheduled Cycle IV-V refueling / maintenance out-age.

In addition to the refueling major maintenance work includes steam generator eddy current testing and tube plugging, R.C.P. motor modifica-tions, main turbine condenser re-tubing and Appendix "R" design changes The Unit is scheduled to return to service on June 9, 1984.

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II Othes iEse44ent

r UNIT SilCTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should deser e all plant shutdowns during the m accoraanet with the table apesarms on the report form.

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

If catepr> 4 must be used. suppis 3rtef comments.

atton of signideant dips trt aserage power levels. Ea:n signi.

tieant reduction m power level (greater than 203 redu:tiort LICENSEE EVENT REPORT A Referen:e the appliesble m average daily power level for the preceding 24 hnurs) reportaole ae:urrence pertammg :o the outage or power

.huuld be noted, esen though tha urus may not have been

.eductio n.

Enter the drst four pa::: (event year. sequential sttut down completelvl For such reda:nens m power level, report number, occurrence code and report type) of the rive the duration should be !!sted as zero, the method of reduetton part designation as des r: bed in It:m l' of Instructions for should be listed as.t (Other), and the Cause and Corrective Preparation of Data Entry Sheets for L..ensee Event Report Aetten to Pment Recurrence eolumn should explam. The (LER) F:le (NCREG 0161). Th2s aiformanon may not be Cause and Corre:tive Action to Prevent Recurrence column tmmediatety evident for all su.h shaidowns, of course, smee should be und to provide any needed explanation to fully turther mvestgation may be required to ascertam *hether ur descnbe the etrcumstances of the outage or power reduction.

not a reportable occurrence was involyd.) If the outage or power reduct:on *d] not result in.: reportable occurrence.

NUMBER. Tha :olumn should md!cate the sequential num.

the p s tive indication of this lack of correlation should be bet assigned to each shutdown or signadeant reduettu.s m power noted as not applicable IN/A),

for that esiendar year. When a snutdown or signtocaat power SYSTEM CODE. The system in *ht:h the outage or power reduction beg:ns m one report pened and ands m 2nother.

reduettort crymated sho' uld be nottd oy the tw'o digit eode of an entry sitould be made for both report ;enods to be sure all shutdowns or signideant power reductions are reported.

Extubit G. Instruettons for Preparanon of Data Entry Sheets Until a unit has a:hteved its 8tst power generation, no num.

for Licensee ivent Report iLER) Ftte tNUREG41el) bet shouid be assigned to ea:h entry.

Systems that do not tit any existir; code snould be deugna.

ted XX. The code ZZ should be ustd for those events where DATE. Thts eclumn should.ndiests the date of the start a system is not applicable.

of eseh shutdown or syntdcant power reduction. Report as year. menth. and 123 Aupst 14.19'* would be reported COMPOSENT CODE. Sele:t the most apprapnate.omponent as ~~CS!4. When a shutaown or utnifl:4nt power reduction from Eshibit I. Instructions for Presatattun of Dati Entr>

begms m one report pened and ends m another an entry should Sheets for Lt ensee Event Report (LER) Fde(NUREG 0161L te made for born report penods to be sure all shutdowns usms the following critierta:

or ugruncant power redu;tions are reported.

TYPE. L se "F" or "S" to.ndicate either " Forced" or " Sche.

duled." respectnely, for each shutdown or ugnincant power B.

If not a component fadure, use the re!ated eomponent.

reduction. Forced shutdowns mciude those required to be e g.. wrong valve operated through error: 111t valve as

.nitiated by no later than the weekend followmg discovery component.

of an off. normal conditton. It la recognued that some judg.

ment is required m categonung shutdowns in this way. In C.

If a cham of fadures occurs, the first component to mal.

general. a forced shutdown is one that would not have been function should be IIsted. The sequence o(events mciud.

completed m the abserice of the :endition for which corrective ing the other components which fail, should be des:ribed action ws: taxen.

under the Cause and Corrective Action to Prevent Recur.

tence column.

DURATION. Self explanatory. When a shutdown extends beyond the end at a report penod,eount only the time to the Components that do not At any existing code shou!J be je.

signated XXXXXX. The code Z2222.7 should be used for end of the report pertod and pic4 up the ensums down time in the foilowmg report penods. Report duration of outages events where a component designation is not applicaele.

ruunded to the neatest tenth of an h )ur to fact!Atate summation.

The sum o( tne tetal outage hours plus the hours the genera.

CAUSE & CORRECTIVE ACfl0N TO PREVENT RECUR.

for was on line should equal the gross hours m the reporting RENCE. Use the column in a narrative fas.Wn to ampitfy or pe nod.

explam the ettcumstances of the shutdown or power reduetton.

l The solumn should include the sceelde :ause for each shut.

down or signideant pnwer reduction and the immediate 2.id REASON Cate8orue 5 etter deutnation in anordance

• ith the table appeantig on tne report form. If :ategory H sontemplated long term sorrective action taxen, if approprt.

ate. This colur9n should also be uxd for a description of the must be used, supply briel.umments.

, gfg,g,g g

, gg METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction mch.dtng an ident:6 cation of, REDUCING POWER. Categorue ey numrier deugnation

'h' '""'3I Eh "tivity and a repat af an) ungle release at radioactivuy or smgle radianon exonsure speett),aily assoet.

1%e that this datters from the EJison Ele. irte in:Utug, ated with the outage which accounts n e more than 10 percent

1. EEh defintrions of "For6ed Partal Outate" and " Sche, of the allowsole annual velues.

Ju4ed Pantal Outm." For thesir terms. HI uses 4 hann ut For long testual r iorts sontmue n.. itve an tecarate raper

.'0 MW as the brea pont. For larpt rower rmturn. 30 MW

.nd referen.e the shutdown or paer reJu.tioa toi um

.s Isai small J.hange til *4rldnt m1plJnanoH.

11JrrJtive.

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Docket No.:

50-316 Unit Nams:

D. C. Cook Unit 2 Completed By:

G.

J.

Peak Telephone:

(616) 465-5901 Date:

4/4/84 Page 1 of 1 MONTHLY OPERATING ACTIVITIES - MARCH 1984 Highlights:

The Unit entered the reporting period in Mode 1 with the reactor at 100% of rated thermal power.

The coastdown to the start of the refueling outage began on March 6, 1984, as Tavg was allowed to sag in order to keep power at 100%.

The generator output breakers were opened at 0403 hours0.00466 days <br />0.112 hours <br />6.66336e-4 weeks <br />1.533415e-4 months <br /> on March 10, 1984, and the fourth refueling outage officially began.

No other significant power reductions had occured prior to the start of the refueling outage.

As the reporting period came to an end, refueling tool checkouts were in progress in preparation for the upcoming refueling of the reactor.

Total electrical generation for the month was 244,500 MWH.

Summary:

3/5/84 The East Containment Spray pump was inoperable from 0505 hours0.00584 days <br />0.14 hours <br />8.349868e-4 weeks <br />1.921525e-4 months <br /> on 3/5/84 to 0759 hours0.00878 days <br />0.211 hours <br />0.00125 weeks <br />2.887995e-4 months <br /> on 3/6/84 to repair a weld crack on the discharge pressure sensing line.

l 3/6/84 The South Safety Injection pump was inoperable for about i

nine hours to repair a leak on valve ICM-265 (Pump Discharge Containment Isolation Valve).

i 3/9/84 The power reduction to remove the Unit from service for the refueling outage started at 2125 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.085625e-4 months <br /> and stopped at 48% at 2236 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.50798e-4 months <br /> to perform a number of miscellaneous tests on the West Main Feed Pump.

3/10/84 Power was further reduced to 25% at 0117 hours0.00135 days <br />0.0325 hours <br />1.934524e-4 weeks <br />4.45185e-5 months <br /> for a chemistry hold prior to removing the Unit from service.

The generator output breakers were opened at 0403 hours0.00466 days <br />0.112 hours <br />6.66336e-4 weeks <br />1.533415e-4 months <br />.

The turbine was tripped at 0412 hours0.00477 days <br />0.114 hours <br />6.812169e-4 weeks <br />1.56766e-4 months <br />.

The reactor trip breakers were opened at 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br />.

Mode 4 was entered at 1431 hours0.0166 days <br />0.398 hours <br />0.00237 weeks <br />5.444955e-4 months <br />.

3/11/84 Mode 5 was entered at 0936 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.56148e-4 months <br />.

3/12/84 The Reactor Coolant System Degassing was complete at 0020 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

3/14/84 The peroxide cleaning of the Reactor Coolant System was complete at 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />.

3/15/84 The Reactor Coolant System was drained to the half loop level at 1425 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.422125e-4 months <br />.

Docket No.:

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

G. J.

Peak Telephone:

(616) 465-5901 Date:

4/4/84 Page:

1 of 1 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

DOCKET NO.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DAT."

4-6-84 COMPuETED BY B. A. Svensson TELEPIIONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE MARCil. 1984 M-1 A weld leak was observed at the instrument tap socket for IPI-210 on the Unit 2 east containment spray pump. The 1" nipple and instrument isolation valve were replaced. QC performed an inspection and the line was returned to ser-vice.

M-2 The breaker for 2CD emergency diesel generator jacket water heater would not remain in the on position. The breaker was replaced. Testing was performed and the heater was re-turned to service.

!!-1 The "W" containment spray heat exchanger inlet valve, 2-CTS-121W, was reported to be leaking. The internals were in-spected, the disc was lapped and blued and the valve re-1 assembled with new gaskets and packing.

!!-4 During a 24-hour surveillance run of the AB diesel generator, Icakage was observed on the #6 rear bank fuel injector line.

The fuel line and injector were replaced.

M-5 Weld Icaks were observed on the residual heat removat piping between Ril-123 and Ril-124. A section of pipe and Ril-123 were replaced.

C&I-1 Delta T/Tavg Protection Set I overtemperature reactor trip /

turbine runback bistables, TB-411C/D, were observed to have drifted during performance of monthly surveillance test STP.104. The dual bistable was replaced and recalibrated.

A subsequent check showed no calibration drif t.

C&I-2 Delta T/Tavg Protection Set IV overtemperature reactor trip /

turbine runback bistables, TB-441C/D were found to have drifted during performance of STP.107. The dual bistable was recalibrated per IMP.197. When ratested b) STP.107, no subsequent calibration drif t was noted.

CLI-3 Battery charger 2-AB-2 tripped its AC input circuit breaker when the charger was placed in service. An SCR had shorted, blowing a protective fuse. After replacement of these parts, the charger was returned to service.

/

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Y.c.".

INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 48A, Bridgman, Mkhlgan 49106 (616) 465-8901 I

April 6, 1984 Director, Office of Management Information and Program Control U. S. Nucicar 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 March, 1984 is submitted.

Sincerely, L.

<e i

M W. G. Smith, Jr.

Plant Manager WCStab i

l Attaciunents cc:

J. E. Dolan i

M. P. Alexich R. W. Jurgensen NRC Region III E. R. Swanson R. O. Bruggee (NSAC)

R. C. Callen S. J. !!ierzwa R. F. Kroeger B. 11. Dennett J. D. Iluebner J. H. Hennigan A. F. Kozlowski R. F. llering J. F. Stietzel PNSRC File INPO Records Center 4'S N