ML20129F777

Monthly Operating Rept for Mar 1985

ML20129F777
Person / Time
Site:	Cook
Issue date:	03/31/1985
From:	Climer, Will Smith, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8506070037
Download: ML20129F777 (8)

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1: N.R.C. OPERATING DATA REPORT DOCKET NO. 50-316' i DATE 4/2/85 COMPLETED BY CLIMER TELEPHONE 616-465-5901 OPERATING STATUS 1.-Unit Name D. C. Cook' Unit 2 -----------------------

2. Reporting Period Mar 1985 inotes .:

3. Licensed Thermal Power (MWt) 3411  ! i

4. Name Plate Rating (Gross MWe) 1133  :  :

5. Design Electrical Rating (Net MWe) 1100 6 .. Maximum' Dependable Capacity (GROSS MWe) 1100 i  !

- 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. If Any (Net MWe) ___ ._

10. Reasons For: Restrictions. If Any: __

This Mo. Yr. to Date Cumm.

- 11. Hours in' Reporting Period 744.0 2160.0 63528.0

12. No.-of Hrs. Reactor-Was Critical 744.0 1869.0 44949.0 1 13.-Reactor' Reserve-Shutdown Hours 0.0 0.0 0.0

14. Hours Generator on Line' 744.0 1850.5 43849.1

15. Unit Reserve Shutdown Hours 0.0- 0.0 0.0

16. Gross-Therm. Energy Gen. (MWH) 2461488 6094080 139172141-

17. Gross Elect. Energy Gen. (MWH) 815840 2018110 45803540

18. . Net. Elect. Energy Gen. (MWH) 787771 1948364 44166098

19. Unit Service Factor 100.0 85.7 71.9

20. Uni t . Avail abili ty Factor 100.0 85.7 71.9

21. Unit Capacity Factor (MDC Net) 99.9 85.1 68.4

22. Unit Capacity Factor (DER Net) 96.3 82.0- 66.9 23.' Unit Forced Outage Rate 0.0 11.7 .

~ 12. 6,

- 24.'Shutduans Scheduled over Next-Six Months (Type,Date,and Duration):

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

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

l Forcast Achieved INITIAL CRITICALITY INITIAL. ELECTRICITY

. COMMERCIAL OPERATION i

l e506070037 eso331 /

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AVERAGE DAILY POWER LEVEL (MWe-Net)

DOCKET NO. 50-316 UNIT TWO DATE 4/2/85 COMPLETED BY CLIMER TELEPHONE 616-465-5901 MONTH Mar 1985 AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY POWER LEVEL 1 1097 -17 1094 2 1096 18

• 1093 3 1099 19 1080 4 1098 20 1092 5 1085 21 1094 6 1096 22 1093 7 1098 23 1087 8 1098 24 1092

. 9 1090 25 1091 10 1099 26 1080 11 1097 27 1090 12 1086 28 1093 13 1094 29 1093 14 1095 30 471 15 1094 31 668 16 1093 l

i DOCKET NO. 50-316 . .

UNIT SituTI) OWNS AND POWER REDUCIlONS UNIT NAME D.C. Cook Unit 2-

1) ATE 4-5-65 8

March, 1985 COMPT ETED BY B.A. Svensson

+

NEPORT MON 11f TEl.EPilONE 616/465-5901 1, -

% .3 Eit:CnSec h9, 4 Canst & CsHsective a oU N.. . Da.e e n , E-ist u MV Ac ..ne ...

Pievent Rcensscnce M

$$ $ M Repent #

6 160 850330, F 0 A 4 N.A. CH VALVEX Reactor power was reduced to 9% to permit isolation of the normal feed-water to No. 4 Steam Generator and to transfer to the auxiliary feed-water supply. This action was re-quired due to a severe packing leak 1

on the No. 4 Steam Generator feed-water regulating valve. The repack-ing was successfully completed and reactor power was returned to 100%

on 850331.

i 1 2 3 4 1: l'aH ced Reason: Methud: Exhibit G . instancliinis S: Sthedulcal A-Equipmer.t I;ailme (Explain) 1 Manual fo Psepasatism ol' Data la Maintenance ni Test 241 annat Scsam. Enisy 3Incess lin IJeensee C Refueling 3- Anto.aatic St sam. liven Repuso ll.liR)17ile INilRI.G-4 Othes IEmplain)

D Regulatoiy Restoiction 01611

IM)pesatos Isaining & 1icense I:xamination

' 5 I Asinunisesative ,

G Openanimal I inus IExpl.nni lixinbit I - Same Somee j p8/1'li 11 Othes IEsplaini J

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UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should desenbe 211 plant shutdowns during de m accordance with the taole appestmg on the report form.

report penod. In addiuon. it should be the source of explan. If category 4 must be used. supply brief comments.

anon of sigmficant dips :n average power levels. Each signi.

ficant reducnon in power level (yester than 20% reduction LICENSEE EVENT REPORT =. Reference the applicable m sverage 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 />) reportable occurrence pertsmmg to the outage or power should be noted. even though e umt may not have been reducton. Enter the erst four parts (event year. sequenusi shut down completelyl . For such reductions in power level. report numcer. occurrence ecde 2nd report type) of the Sve tne durst2on should be !isted as :ero. the method of reducuan part designation as descnbed in item 17 of Instruccons for should be listed as 4 (Other). 2nd the Cause and Correenve Preparanon of Data Entry Sheets for L:censee Event Report Action to Prevent Recurrence column should explcin. The (LER) File (NUREG.0161). This information may not be Cause and Correenve Acuan to Prevent Recurrence column immediately evident for all such shutdowns of course. since should be 2 sed to provide any rieeded explanation to fully further mvesugation may be required to ascertam whether ur describe the circumstances of the outsge or power reduction. not a reportable occurrence was involved.) If the outage or power reduction will not result in 2 reportable occurrence.

NUMBER. This column shculd indicate the sequential num. the posittve indication of thts lack of correistion should be ber assigned to each shutdown or sigruncant reductionin power noted as not applicable (N/A).

for that c:lendar year. When 2 shutdown or signiScant power SYSTEM CODE. The system in whica the outage or power reduction begins in one recort pened and ends m another. -

sn entry should be made for both report genods to be sure reducti n Ortsmated should be noted oy the two digit ecde or.

11 shutdowns or stamde:nt power reducuans are reported. ExMit G . Insanons for Prepar:non or Data Entry inuu Unt:1 a urut has sch'ieved its Erst power generstion, no num. f r Licensa Ennt Repan RER) Fde NREG@61L ber should be assigned to each entry. Systems that do not tit any existing code should be designa.

ted XX. The code ZZ should be used for tnose events where DATE. This column should indicate de date of the start a systert is not appticsole.

of each shutdown or ugmncant power reduenon. Report as yest. month. 2nd day. August 14.1977 would be report.d COMPONENT CODE. Select the most appropnate component as 770S!;. When a shutdown or ugnincant power reduction (ccm Exhstt i . Instruenons for Preparat:en of Data Entr) begmsin one report per:od sac ends m anoter, an entry should Sheets for Licensee Event Report (LER) File (NUREG.0161).

be made for both report penods to be sure all shutdowns usmg the followmg critiena:

or ugmncant power reduccons are reportes.

TYPE. Use "F" or "S" to indicate etter " Forced" or " Sche.

Juled." respectively. for each shutdown or signincant power S. If not a component fadure. use the related cornponent:

reducnon. Forced shutdowns include those required to be e.g., wrong valve operated through erron list valve as

nstisted by no later than the weekend following discovery component.

of an off. normal condition. It is recognized that some judg.

ment is required in categonz:ng shutdowns in this way. In C. If a : ham of failures occurs the Hrst component to mai.

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

completed in the absence of the condiuon for which corrective ing the other components wh:ch fail. should be descnbed acuan was taken. under the Cause and Correenve Acuan to Prevent Recur.

rence column.

DURATION. Se!f. explanatory. When a shutdown extends beyond de end of 2 report penod. count only the time to the Components that do not St any emstmg code should be de.

signated X CCCC(. The code 777777 should be used for l end of the report penod and pict up the ensumg down time in the following reeott penods. Report duranon of outages events where 2 component designation ts not spoiicsole.

rounded to the nearest tenth of an hour to facitate summanon.

The sum of the total cut 26e heurs plus tne hours the genera. CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

! RENCE. Use the column m a narranve fashion to ampiify or tor was on 'ine should equal the Jross hours in the reportmg 1 penod. explam the circumstances of the dutdown orpower recuenon.

The column should include the spec 2Sc cause for each shut.

l down or sigmdcant power reducnon and tne immediate anc REASON. Categortze by etter deugration m accordance with the table acecanny un the report form. If category H ontemolated tung term correenve acnon taken, if sppropn.

l must be used, suecay bnet eumments. ste. T*rus column should also be used for a desenption of the maior safety.related correenve maintenance performed dunna METHOD OF SHUTTING DOWN THE REACTOR OR de outage or pm moucnon inM.g m dennde:tbn

' REDUCING power. Categonze tw numner designauen 'O' # "'*I E* * " 'I *"d * " E " #',*"Y "" N' " N *** #' q r:diosenytty or im#e radtation exposure spectrie:dy cssue:.

INote that this difrers from the Ecison Electne Insatute sted with the out:ge which accounts for more tnan 10 :er.ent TEED dennitions of "Foreed Parual Outage" sne -Sene. di the 211owaaie unual values.

Juleu P:rtral Cut 2p." For these temu. hEl uses a hange at For :ong textual *eoorts continue carrattve on se:zr:re ;.soer

.0 MW as the break ;vmt. For targer power reacturs.30 MW and re:eren e tiie shutdown or power redu uun foi int,

, :s too imail a .har:ge tu wanarts evi:. nation. narrattve.

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. , Dockst No.: 50-316

- - Unit Namn D.C. Cook Unit 2 Completed By: D. A. Brucx }

Telephone: (616) 465-5901 Date: April 3, 1985 Page: 1 of 2 MONTHLY OPERATING ACTIVITIES - MARCH, 1985 HIGHLIGHTS:

The reporting period began and ended with the Unit in Mode 1 at 100% rated thermal power. One major power reduction occurred to repair a packing leak on feedwater regulating valve, 2-FRV-240.

Total electrical generation for the month was 815,840 MWH.

SUMMARY

3-05-85 At 0601, a power decrease tc 97% was started for C&I Surveillance Testing. Power reached 97% at 0707.

At 1345, a power increase to 100% was started, reaching 100% at 1430.

3-12-85 At 0603, a power decrease to 97% was started for C&I Surveillance Testing. Power reached 97% at 0633.

At 1420, a power increase to 100% was started, reaching 100% at 1457.

3-19-85 At 0605, a power decrease at 97% was started for C&I Surveillance Testing. Power reached 97% at 0643.

At 1615, a power increase to 100% was started, .-, aching 100% at 1720.

3-26-85 At 0607, a power decrease at 97% was started for C&I Surveillance Testing. Power reached 97% at 0700.

- AT 1730 a power increase to 100% was started, reaching 100% at 1859.

3-30-85 At 0915, a power decrease to 9% began to repair feedwater regulating valve, 2-FRV-240.

At 1852, a power increase to 100% began.

- - Docket No.: 50-316 Unit Nans: D.C. Cook Unit 2 Completed By: D. A. Bruck .

Telephone: (616) 465-5901 Date: April 3, 1985 Page: 2 of 2 3-31-85 At 0255, the power increase was stopped a 48% due to guadrant power tilt calculated at 1.037.

At 0355, because of a trailer fire inside the protected zone, an Unusal Event was declared.

At 0405, the fire was out and the Un'usal event terminated.

At 1015, the power increase resumed, reaching 100% at i 2134.

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 2 System remain operable.

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DOCKET NO. 50 - 316_

UNIT NAME D. C. C ook - Unit No. 2 DATE 4-5-85 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 IIAJOR SAFETY-RELATED MAINTENANCE MARCH, 1985 There are no significant safety-related maintenance items to report.

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- van IMDMMA &_MICMB_ALERCERLC COMPAN1 Donald C. Cook Nuciner Plant P.O. Son 458, Bridgman, Mohigan 49106 April 5, 1985 Director, Office Of Management Information and Program Control U. S. Nuclear Regulatory Commissicn 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, 1985 is submitted.

Sincerely,

(/W W. G.

V Smith, Jr.

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 R. F. Kroeger B. H. Bennett P. D. Rennix J. H. Hennigan Z. Cordero J. J. Markowsky J. F. Stietzel PNSRC File INPO Records Center ANI Nuclear Engineering Department l' ,\

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