ML17331B225

Monthly Operating Rept for Jan 1994 for DC Cook Nuclear Plant Unit 2

ML17331B225
Person / Time
Site:	Cook
Issue date:	01/31/1994
From:	Blind A, Janisse J, Reynnells R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9402160016
Download: ML17331B225 (7)

Text

REGULATORY XNFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSXON NBR:9402160016 DOC.DATE: 5A/I&+PL NOTARIZED-NO DOCKET FACIL:50-316 Donald C.

Cook Nuclear Power Plant, Unit 2, Indiana M

05000316 AUTH.NAME AUTHOR AFFILIATION JANISSE,J.D.

Xndiana Michigan Power Co.

(formerly Indiana

& Michigan Ele REYNNELLS,R.D.

Indiana Michigan Power Co.

(formerly Indiana

& Michigan Ele BLXND,A.A.

Indiana Michigan Power Co.

(formerly Indiana

& Michigan Ele R RECXP.NAME RECIPIENT AFFILIATION

SUBJECT:

Monthly operatin re t for Jan 1994 for DC Cook Nuclear Plant Unit 2.W/ 4020 ltr.

DISTRIBUTION CODE:

IE24D COPIES RECEIVED LTR ENCL SIZE:

TITLE: Monthly Operating Report (per Tech Specs)

NOTES:

D RECIPIENT ID CODE/NAME PD3-1 PD XNTERNAL: AEOD/DOA Nig/DO~V AB RhG FIL 01 EXTERNAL: EG&G BRYCE,J.H NSIC COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 1

1 RECIPIENT ID CODE/NAME HICKMAN,J AEOD/DSP/TPAB NRR/DRIL/RPEB RGN3 NRC PDR COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 D

D R

D NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WARM CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 11 ENCL 11 D

D

Indiana Mic

'ower Com Cook Nuclear lant One Cook Place Bridgman, MI 49106

'1 6 465 5901 R

INQlSllM MfCHl6rQN PQlRfM February 7, 1994 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555 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 January 1994 is submitted.

Respectfully,

.A. Blind Plant Manager Attachment ci NRC Region III D.R. Hahn R.C. Callen S.

Hamming J.G. Keppler INPO Records Center ANI Nuclear Engineering Department E.E. Fitzpatrick R.L.

Simms W.G. Smith, Jr.

S.J.

Brewer D.W. Paul S.H. Steinhart J.L. Leichner J.A.

Isom D.G. Turner E.A. Smarrella J.C. Krieger D.F. Krause M.E. Russo

• .'A g.

~ I 94021b001b 940131 PDR ADOCK 050003ib R,

PDR

~

~

I N.R.C.

OPERATING DATA REPORT DOCKET NO.

DATE COMPLETED BY TELEPHONE 50-316 04/Feb/94 JD Janisse 616-465-5901 OPERATING STATUS

l. Unit Name D.

C.

Cook Unit 2

2. Reporting Period JAN 94

3. Licensed Thermal Power (MWt) 3411 4.

Name Plate Rating (Gross MWe) 1133

5. Design Electrical Rating (Net MWe) 1090 6.

Maximum Dependable Capacity (GROSS MWe) 1100 7.

Maximum Dependable Capacity (Net MWe) 1060 notes 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:

11. Hours in Reporting Period 12.

No. of Hrs. Reactor Was Critical

13. Reactor Reserve Shutdown Hours

14. Hours Generator on Line

,15. Unit Reserve Shutdown Hours

16. Gross Therm.

Energy Gen.

(MWH)

17. Gross Elect.

Energy Gen.

(MWH) 18.

Net. Elect.. Energy Gen.

(MWH)

19. Unit Service Factor

20. Unit Availability Factor

21. Unit Capacity Factor (MDC Net)

22. Unit Capacity Factor (DER Net)

23. Unit Forced Outage Rate 24.

Shutdowns Scheduled over Next Six None.

This Mo.

Yr.

744.0 641.8 0.0 622.7 0.0 1746994 561510 540258 83.7 83.7 68.5 66.6 16.3 Months (Type, to Date 744.0 641. 8 0.0 622.7 0 '

1746994 561510 540258 83.7 83.7 68.5 66.6 16.3 Date,and Cumm.

141000. 0 95490 '0.0 92398.6 0 '

283861088 92169410 88766240 66.6 66 '

60.3 58.7 15.3 Duration):

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

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

Forcast INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Achieved

AVERAGE DAILY POWER LEVEL (MWe-Net)

DOCKET NO.

50-316 UNIT TWO 04/Feb/94 04/Feb/94 JD Janisse JD Janisse TELEPHONE 616-465-5901 DAY JAN 94 AVERAGE DAILY POWER LEVEL JAN 94 DAY AVERAGE DAILY POWER LEVEL 01/01/94 01/02/94 01/03/94 01/04/94 01/05/94 01/06/94 01/07/94 01/08/94 01/09/94 01/10/94 01/11/94 01/12/94 01/13/94 01/14/94 01/15/94 01/16/93 901 901 899 907 909 909 911 913 911 913 908 910 913 911 909 904 01/17/94 01'/18/94 01/19/94 01/20/94 01/21/94 01/22/94 01/23/94 01/24/94 01/25/94 01/26/94 01/27/94 01/28/94 01/29/94 01/30/94 0 1/3 1/94 906 907 938 980 891 38 0

0 0

0 205 747 787 791.

792

~

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: JANUARY 1994 UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

PAGE 1

OF 1

D. C.

COOK UNIT 2 Feb 7, 1994 R.

D. Reynnells (616) 465-'5901 DURATION NO.

DATE TYPE HOURS METHOD OF SHUTTING DOWN REASON REACTOR LICENSEE EVENT REPORT NO.

SYSTEM CODE COMPONENT CODEs CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE 233 940121 S

122.7 N/A N/A N/A Reactor shutdown commenced on 940121 to repair an unisolable leak on k21 Steam Generator Blowdown line.

The unit was off line for a total of 122.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> during this repair.

The unit exited this reporting period at 75%

RTP after the blowdown repair.

1 F:

S:

Forced Scheduled 2

Reason:

A:

Equipment Failure (Explain)

B:

Maintenance or Test C:

Refueling D:

Regulatory Restriction E:

Operator Training and License Examination F:

Administrative G:

Operational Error (Explain)

H:

Other (Explain) 3 Method:

1:

Manual 2:

Manual Scram 3:

Automatic Scram 4:

Other (Explain) 4Exhibit G Instructions for preparation of data entry sheets for Licensee Event Report (LER) File (NUREG 1061) 5Exhibit I:

Same Source

D ET NO.:

UNIT NAME:

COMPLETED BY:

TELEPHONE:

DATE'AGE:

50-316 D.C.

Cook Unit 2 R.

D. Reynnells (616) 465-5901 Feb 7, 1994 Page 1 of 2

MONTHLY OPERATING ACTIVITIES JANUARY 1994 HIGHLIGHTS The unit entered the reporting period in Mode 1 at 85.

RTP.

The unit exited this reporting period in Mode 1 at 75% RTP.

On January 21, 1994 at, 1725 hours0.02 days <br />0.479 hours <br />0.00285 weeks <br />6.563625e-4 months <br />, a reactor shutdown was commenced to repair an unisolable leak on f21 Steam Generator blowdown line.

The main generator was unloaded on January 22, 1994 at 0255 hours0.00295 days <br />0.0708 hours <br />4.21627e-4 weeks <br />9.70275e-5 months <br />.

After repair to the blowdown line, the unit was paralleled to the grid on January 27, 1994 at 0536 hours0.0062 days <br />0.149 hours <br />8.862434e-4 weeks <br />2.03948e-4 months <br />.

There were no challenges to the pressurizer safety valves or power operated relief valves.

Gross Electrical generation for the month of December was 619380 MNH.

DETAILS 01-19-94 0815 Commenced reactor power increase to meet system demands.

01-21-94 01-22-94 1228 1830 1845 1725 0255 Reactor power is at 89~~

RTP.

Commenced reactor power increase to 91.5%

RTP Reactor power is at 91.54 RTP Commenced reactor shutdown to repair an unisolable leak on f21 Steam Generator Blowdown

System, secondary side.

Unloaded Main Generator, transferred electrical auxiliaries.

01-23-, 94 01-24-94 01-25-94 1224 2057 1302 2005 1542 Commenced RCS cooldown.

The RCS is in Mode 4.

The RCS is in Mode 5.

The RCS is in Mode 4 follows;ng repair to the f21 Steam Generator Blowdown line.

Heatup to Mode 3

'continues.

The RCS is in Mode 3.

DOC NO.:

UNIT NAME:

COMPLETED BY:

TELEPHONE:

DATE PAGE:

50-316 D.C.

Cook Unit 2 R.

D. Reynnells (616) 465-5901 Feb 7, 1994 Page 2 of 2

MONTHLY OPERATING ACTIVITIES JANUARY 1994 0211 1020 1056 1606 1700 1717 The RCS is at no-load rated pressure and temperature.

Commenced reactor startup, entered Mode 2.

The reactor is critical.

The main turbine tripped at approximately 1330 rpm during turbine startup.

Commence reactor power decrease to 3~ RTP.

The reactor is in Mode 2.

2314 Following trouble shooting activities on the main

turbine, reactor power increase to 84 RTP is commenced.

2334 2355 0536 0537 1300 1912 0529 The reactor is in Mode 1.

Reactor power is stabilized at 7.7%

RTP.

The Main Turbine Generator is paralleled to the grid'ommenced reactor power increase.

Reactor power stabilized at 32:

RTP for required chemistry hold.

Commenced reactor power increase.

Reactor power stabilized at 75% RTP.