ML17325B089

Monthly Operating Rept for May 1988 for DC Cook Unit 2.W/ 880603 Ltr

ML17325B089
Person / Time
Site:	Cook
Issue date:	05/31/1988
From:	Giles H, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8901180040
Download: ML17325B089 (7)

Text

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ACCESSION NBR:8901180040 DOC.DATE: 88/05/31 NOTARIZED: NO DOCKET I FACIL:50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana 6 05000316 AUTH. NAME AUTHOR AFFILIATION GILES,H.B. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele SMITH,W.G. Indiana Michigan Power Co. (formerly Indiana S Michigan Ele RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

Monthly operating rept for May 1988 for DC Cook Unit 2.W/

880603 ltr.

DISTRIBUTION CODE: IE24D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Monthly Operating Report (per Tech Specs NOTES /

RECIPIENT COPIES RECIPIENT COPIES h ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 0 PD3-1 PD 5 5 STANG,J 1 0 INTERNAL: AEOD/DOA 1 AEOD/DSP/TPAB 1 1 ARM TECH ADV NRR/DOEA/EAB NUDOCS-ABSTRACT ll 2 1

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NOTE 'ZO ALL "RIDS" RECIPIENIS'LEASE S

HELP US TO REDUCE WASTE.'OÃZACZ %HE DOCUMEtG'ONZROL DESK, RXIM Pl-37 (EXT. 20079) KO EZZMZNATE YOUR NME FMH DISTEKMXXON LISTS H)R DOCUMENIS YOU DGNIT NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 20

N.R.C. OPERATING DATA REPORT DOCKET NO. 50-316 DATE 1 JUNE 88 COMPLETED BY H.B. GILES TELEPHONE 616-465-5901 OPERATING STATUS

1. Unit Name D. C. Cook Unit 2

2. Reporting Period MAY 1988 ,'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

9. Power Level To Which Restricted.

10. Reasons For Restrictions. If If Any (Net MWe)

Any:

This Mo. Yr. to Date Cumm.

11. Hours in Reporting Period 744.0 3647.0 91295. 0

12. No. of Hrs. Reactor Was Critical 0.0 2715.5 63595.1

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator on Line 0.0 2715.1 62210.0

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Therm. Energy Gen. (MWH) 0 7410980 189566377

17. Gross Elect. Energy Gen. (MWH) 0 2419600 61896220

18. Net Elect. Energy Gen. (MWH) 0 2323265 59584665

19. Unit Service Factor 0.0 74 ' 70.0

20. Unit Availability Factor 0' 74.4 70.0

21. Unit Capacity Factor (MDC Net) 0.0 60. 1 63.3

22. Unit Capacity Factor (DER Net) 0.0 57 ' 61.7

23. Unit Forced Outage Rate ERR 0' 14.5

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

25. If Shut Down At End of startu of Report Period, Estimated Date of Startup-Estimated date is Februar of 1989.

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

Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 8901180040 880531 PDR ADOCK 05000316 R PDC

AVERAGE DAILY POWER LEVEL (MWe-Net)

DOCKET NO. 50-316 UNIT TWO DATE JUNE 88 COMPLETED BY H. B. GILES TELEPHONE 616-465-5901 MONTH MAY 1988 AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY POWER LEVEL 1 17 2 18 3 19 4 20 5 21 6 22 7 23 8 24 9 25 10 26 11 27 12 28 13 29 14 . 30

. 15 31 16

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0

( anse Pr even) 8< Collcclivc Ac<i<)n lo

((ccnrrcnce 189 880423 744.0 88C S ZZ ZZZZZZ n 4-23-88 the unit was removed from service for the steam generator replacement/refueling outage. The reporting period. ended with the reactor core unloaded. The expected ate for return to service is Feb.

1989.

) 4 I:: I'o<cc<) lleas<nl: Melhod: Exhibil C< - hlslrncli<)os S: Schc<h<)c<) A Ii<(w)p<ncnl I'alhne (Explahl) I Manwal fnt Prq)ala)1<x< of l)ala I) Mal<i)el<ance oil'es) 2'Manna) Scrawl. I!wily bhec)s fn< licensee C Rcfnclh<g .).Aw)on<ark!)<:raw<. I'.v<nll Hcp<<<I (I.I:R) I<ilc (N) ) Rl'.(I<

I) Hc),o)al<ny Reslriclion 4 Olhcl (Exp)ah'I) 0) (111 I'. Ope<alol I'<alnlni) k I)cense I'.Xan<)wallow I'.A<hl<)nlsr<alivc (1 ()i)c<alhnlal I:Ilol (I:xpian<) 'I xhlhil I Sa<nc Soo<<e

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DOCKET NO: 50-316 UNIT NAME: D.C. Cook Unit 2 COMPLETED BY: R. Cessna TELEPHONE: (616) 465-5901 DATE: June 3, 1988 PAGE: lof1 MONTHLY OPERATING ACTIVITIES - MAY 1988 HIGHLIGHTS The reporting period began with RCS in Mode 5 draining to half Loop. The RCS entered mode 6 on 05-06-88.

On 05-22-88 the reactor vessel head was removed. The control rod drives were unlatched and removed on 5-24-88. The upper internals of the reactor vessel were removed and fuel unloading began on 5-25-88. The reporting period ended with the completion of fuel unloading on 5-29-88.

Gross electrical generation for the month of May was 0 MWH.

DETAILS 05-06-88 1652 RCS enters mode 6.

05-09-88 1152 Reactor vessel head removed to repair stud k'll.

05-18-88 0228 Reactor vessel head was replaced.

05-22-88 1957 Reactor vessel head was removed for fuel unload.

05-25-88 0147 Upper internals removed.

1332 Started fuel unloading.

05-29-88 0747 fuel unloading completed.

DOCKET NO. 50-316 UNIT NAME D.C.Cook-Unit No. 2 DATE June 3, 1988 COMPLETED BY R. Cessna TELEPHONE 616 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE MAY 1988 CVCS letdown safety valve, 2-SV-51 suspected of leaking by at normal operating letdown pressure. Replaced nozzle, disc, and gaskets.

Valve tested satisfactorily.

The East Centrifugal Charging Pump outboard mechanical seal was leaking. The mechanical seal was replaced which stopped the seal leakage.

Indiana Michi Power Compa CooK Nuclear i,1 PO. Box 458 Bndgman.'l 49106 616 465 5901 iNDMMA NICHIGAN POWER U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 June 3, 1988 Gentlemen:

Pursuant to the requirements of Donald C, Cook Nuclear Plant Unit 2 Technical Specification 6.9. 1. 10, the attached Monthly Operating Report for the month of May 1988 is submitted.

Sincerely, W. G. Smith, Jr.

Plant Manager WGS/jd cc: D. H. Williams, Jr.

M. P. Alexich R. W. Jurgensen R. C. Callen C. A. Erikson D. W. Paul D. R. Hahn J. J. Markowsky E. A. Morse PNSRC File INPO Records Center ANI Nuclear Engineering Department T. R. Stephens NRC Region III B. L. Jorgensen S. L'. Hall D. A. Timberlake EPRI--Nuclear Safety Analysis Center