ML17325B209

Monthly Operating Rept for Mar 1989 for DC Cook Nuclear Plant

ML17325B209
Person / Time
Site:	Cook
Issue date:	03/31/1989
From:	Giles H, Will Smith, Stevens T INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8906130242
Download: ML17325B209 (13)

Text

gq cKLZRATED DlsTKBUTION DKMONSTRA,Tlat SYSTEM REGULATO INFORMATION DISTRIBUTION'STEM (RIDE)

ACCESSION NBR:8906130242 DOC.DATE: 89/04/07 NOTAR1ZED:

NO DOCKET FACIL:50-316 Donald C.

Cook Nuclear Power Plant, Unit 2, Indiana a

05000316 AUTH.NAME AUTHOR AFFILIATION GILES,H.

Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele SMITH,W.G.

Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

Monthly operating rept for Mar 1989 for DC Cook Nuclear Plant.W/890407 ltr.

DISTRIBUTION CODE:

IE24D COPIES RECEIVED:LTR i ENCL /

SIZE:

TITLE: Monthly Operating Report (per Tech Specs)

NOTES:

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Indiana Michigan Power Company Cook Nuclear Plant One Cook Place Bridesman, Ml 49106 616 465 5901

à MWSlNSl NfCMGQN PSALM U.S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, D.C.

20555 April 7, 1989 Gentlemen:

Pursuant to the requirements of Donald C.

Cook Nuclear Plant Unit 2 Technical Specification 6.9.1.10, the attached Mogthly Operating Rey~t for the month of Wkevasy 1989 is submitted.

War4 h Sincerely, W. G. Smith, Jr.

Plant Manager WGS/jd cc:

B. A. Svensson NRC Region III D. R.

Hahn EPRI Nuclear Safety Analysis Center R.

C. Cal]'en S. L. Hal'1 INPO Records Center ANI Nuclear Engineering Department D. H. Williams, Jr.

M. P. Alexich J.

F. Kurgan J. J. Markowsky D. A. Timberlake D.

W. Paul T. 0. Argenta S.

H. Steinhart B. L. Jorgensen J.

R. Sampson D. S. Climer E. A. Smarrella Dolly Krieger T. R. Stephens

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8906130242 89OXRf

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N.R.C.

OPERATING DATA REPORT DOCKET NO.

50-316 DATE 03-Apr-89 COMPLETED BY H. Giles TELEPHONE 616-465-5901 OPERATING STATUS

1. Unit Name D.

C.

Cook Unit 2

2. Reporting Period MAR 89

,'notes 3.

Licensed Thermal Power (MWt) 3411 4.

Name Plate Rating (Gross MWe) 1133

5. Design Elect,rical Rating (Net MWe) 1100 ii 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 Le~el 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 This Mo.

Yr. to Date 744.0 2160.0 395.4 395.4 0.0 0.0 345.7 345.7 0.0 0.0 775260 775260 245880 245880 233812 233812 46.5 16.0 46.5 16.0 29.6 10.2

28. 6.

9.8 0.8 0

~ 8 Months (Type, Date,and Cumm.

98592.0 63990.5 0.0 62555.7 0.0 190341637 62142100 59818477 65.0 65.0 58.6 57.1 14.5 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 UNIT DATE COMPLETED TELEPHONE 50-316 TWO Oa-Apr-89 BY H. Giles 616-465-5901 DAY 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 MONTH AVERAGE DAILY POWER LEVEL MAR 89 DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 AVERAGE DAILY POWER LEVEL 121 298 398 459 461 456 454 160 498 933 1096 11OO 1105 1110 1092

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'190 880423 89-324 S

395.5 2.8 B&C N/A N/A zz zz zzzzzz zzzzzz The unit was removed from service on 880423 for cycle 6"7, refueling and steam generator repair pro)ect.

Startup testing and low power physics testing were completed on March 17, 1989 with the unit heing paralleled to the system on 1129 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.295845e-4 months <br /> the same day.

Reacto power reached 48io RTP on March 19, 1989.

The total length of the SG RP outage was 7880.4

'ours.

The unit was removed from service at 0955 hours0.0111 days <br />0.265 hours <br />0.00158 weeks <br />3.633775e-4 months <br /> to repair letdown isolation valve 2-QRV-112 with the reactor remaining critical.

Following repaiis and main turbine overspeed testing the unit was paralleled at 1240 hours0.0144 days <br />0.344 hours <br />0.00205 weeks <br />4.7182e-4 months <br />.

the same day.

The reactor reached 100% RTP on March 28> 1989.

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DOCKET NO:

UNIT NAME'OMPLETED BY:

TELEPHONE:

DATE:

PAGE:

50-316 D.C.

Cook Unit 2 T.

R. Stephens (616) 465-5901 April 7, 1989 1of3 MONTHLY OPERATING ACTIVITIES -

MARCH 1989 HIGHLIGHTS The unit entered the reporting period in Mode 4 with the reactor coolant system (RCS) being cooled down to repair leak on control rod drive mechanism housing for control rod located at P-6.

Following repairs, the RCS was returned to Mode 3 and no load rated temperature and pressure.

Cool down and depressurization was again initiated on March 10, 1989 to permit repairs of No.

1 steam generator stop valve three-way test valve, MMO-210.

The RCS was again returned to Mode 3 and NO load rated temperature and pressure on March 14, 1989.

Initial criticality for Cycle-11 was achieved at 1238 hours0.0143 days <br />0.344 hours <br />0.00205 weeks <br />4.71059e-4 months <br /> on March 15, 1989.

Following completion of low power physis testing the unit was paralleled to the system at 1129 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.295845e-4 months <br /> on March 17, 1989.

Reactor thermal power reached 48K on March 19, 1989 at 1220 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.6421e-4 months <br />.

This power level was maintained until 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on march 23, 1989 when a power reduction was commenced to perform repairs on letdown isolation valve, 2-HARV-112.

The unit was removed from parallel at 0955 hours0.0111 days <br />0.265 hours <br />0.00158 weeks <br />3.633775e-4 months <br /> on March 24, 1989.

Following repairs to 2-HARV-112 and turbine oyerspeed testing the unit was paralled to the system at 1240 hours0.0144 days <br />0.344 hours <br />0.00205 weeks <br />4.7182e-4 months <br /> on the same day.

Reactor power was gradually increased with 100K RTP being reached on March 28, 1989.

The reporting period ended with a reactor power reduction, for condenser

cleaning, being initiated at 2155 hours0.0249 days <br />0.599 hours <br />0.00356 weeks <br />8.199775e-4 months <br /> on March 31, 1989.

DETAILS 3-1-89 3-2-89 3-4-89 1934 Started RCS cooldown and depressurization.

0402 RCS entered Mode 5.

0125 Started RCS heatup and pressure increase in preparation to start-up.

0850 RCS entered Mode 4.

1930 RCS entered Mode 3.

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3-10-89 1630 Began RCS cooldown and depressurization to repair 2-MN0-210.

1738 Spurious RTP trip signal received on low-low level on 821 SG.

2043 RCS entered Mode 4.

3-13-89 1100 Started RCS heatup in preparation for reactor start-up.

1704 RCS entered Mode 3.

3-14-89 0530 RCS at full temp and pressure.

3-15-89 0803 Commenced reactor start-up.

1017 Reactor entered Node 2.

1238 Rx critical.

First time in Cycle 11.

3-17-89 0325 Reactor entered Node 1.

1129 Unit paralleled to system.

3-19-89 0545 Started power increase to 48$.

1220 RTP at 48K.

3-20-89 0630 HARV-112, letdown isolation valve failed closed.

3-23-89 2100 Started power reduction to repair letdown isolation valve HARV-112, and perform turbine overspeed test.

3-24-89 0940 RTP at 85.

0955 Removed generator from parallel by opening Al and A2 breakers.

1012 Performed 1'10$ and 112$ overspeed test.

1240 Unit paralleled to system.

1435 Started power increase at 6X/hr to 48K then 2X/hr to 68K power.

3-25-89 1945 RTP power at 68% for Chemistry hold.

3-26-89 0027 Increasing RTP to 90K.

1045 RTP power at 90%.

1700 Increasing RTP to 994.

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3-27-89 0005 RTP power at 99K.

3-28-89 1620 Increasing power to 100K RTP.

1826 RTP at 100%.

3-31-89 2155 Started power reduction to 90%.

Reactor power being reduced for condenser c1eaning.

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50-316 D.C.Cook-Unit No.

2 A ri 7,

1989 T.

R. Ste hens 616 465-5 01 1o 1

MAJOR SAFETY-RELATED MAINTENANCE MARCH 1989 2-M-1 Replaced the governor valve stem and the mechanical overspeed tappet assembly on the turbine driven Aux. feedpump.

2-M-2 Aligned 2-MMO-210 for proper flow path.

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