ML20215D877

Monthly Operating Rept for Jul 1986

ML20215D877
Person / Time
Site:	Cook
Issue date:	07/31/1986
From:	Climer, Will Smith, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8610140340
Download: ML20215D877 (9)

Text

.

vg AVERAGE DAILY POWER LEVEL (MWe-Net)

DOCKET NO.

50-315 UNIT ONE DATE 8/5/86 COMPLETED BY CLIMER.

TELEPHONE-616-465-5901 MONTH JULY 86 AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY POWER LEVEL 1

'O 17 919 2

0 18 959 3

0 19 899 4

0 20 872 5

0 21 896 6

0 22 453 7

29 23 0

8 196 24 0

9 252 25 0

10 127 26 0

11 217 27 0

12 534 28 0

13 875 29 0

14 879 30 0

-15 879 31 0

16 881 8610140340 860731 PDR ADOCK 05000315 R

PDR IE2'I Ih

• t N.R.C. OPERATING DATA REPORT DOCKET NO.

50-315 DATE 8/5/86 COMPLETED BY CLIMER TELEPHONE 616-465-5901 OPERATING STATUS

1. Unit Name D. C. Cook Unit 1

2. Reporting Period JULY 86 l notes l

3. Licensed Thermal Power (MWt) 3250 l l

4. Name Plate Rating (Gross MWe) 1152 l l

5. Design' Electrical Rating (Net MWe) 1030 l l

6. Maximum Dependable Capacity (GROSS MWe) 1056 l l

7. Maximum Dependable Capacity (Net MWe) 1020 -----------------------

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 5087.0 101519.0

12. No. of Hrs. Reactor Was Critical 373.2 3900.5 72189.9

13. Reactor Reserve Shutdown Hours 0.0 0.0 463.0

14. Hours Generator on Line 337.4 3864.7 70717.3

15. Unit Reserve Shutdown Hours 0.0 0.0 321.0

16. Gross Therm. Energy Gen. (MWH) 819019 11160990 206156673

17. Gross Elect. Energy Cen. (MWH) 248760 3612600 67590140

18. Net Elect. Energy Gen. (MWH) 236794 3473282 65020439

19. Unit Service Factor 45.3 76.0 71.0

20. Unit Availability Factor 45.3 76.0 71.0

21. Unit Capacity Factor (MDC Net) 31.2 66.9 64.0

22. Unit Capacity Factor (DER Net) 30.9 66.3 61.7

23. Unit Forced Outage Rate 54.7 24.0 8.9

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

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

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

Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e IK)CKET No. 50-315 iINITSilllllMlWNS ANilPOWiiR NElliMTIONS UNII~NAME D.C. Cook-Unit 1 IDAIE 8-7-86 COMFI ETEn hY B.A. Svensson HLPOR'I MON HO July, 1986 TEl.EFIBONE 616/465-5901 PAGE 1 of 2

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3 86-012-0 HA INSTRU The outage which began on 860528 fol-lowing a turbine trip from 90% RTP has been completed. The Unit was returned to service at 1937 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.370285e-4 months <br /> on 860707 and was held at 25% for tur-bine' rotor warming in preparation for turbine overspeed testing.

251 860707 S

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1 N/A ZZ ZZZZZZ The turbine generator was removed from parallel at 0307 hours0.00355 days <br />0.0853 hours <br />5.076058e-4 weeks <br />1.168135e-4 months <br /> for tur-bine overspeed testing. Tne Unit was returned to service at 0405 hours0.00469 days <br />0.113 hours <br />6.696429e-4 weeks <br />1.541025e-4 months <br /> the same day.

252 860710 F

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1 86-007-1 ZZ ZZZZZZ The Unit was removed from service when it was determined that a non-compliance existed on two Technical Specification required surveillance tests. The testing was completed and the Unit returned to service on 860711.

90% reactor power was I

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3 Later ZZ ZZZZZZ A turbine / reactor trip occurred while performing a routine calibra-tion of the turbine generator stator cooling water low pressure trip.

The trip occurred due to inadequate blocking of the trip circuit.

During a containment inspection following the trip, a leak was dis-covered at a body-to-bonnet joint on pressurizer spray valve, NRV-164.

To effect repairs, the RCS had to be brought to cold shutdown and de-pressurized. The Unit remained out of service at the end of the month with the reactor critical at 2%

RTP.

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i Dockst No.s.

50-315 Unit Namas D.C. Cook Unit 1 Completed By:

D. A.

Bruck Telephone:

.(616) 465-5901 Date:

August 8, 1986 Page:

1 of-3 MONTHLY OPERATING ACTIVITIES - JULY, 1986 HIGHLIGHTS:

The reporting period-began with the reactor coolant system in cold shutdown,-Mode 5.

The unit was returned to. service on July

'7, 1986,.following-an approximate six weeks maintenance outage.

-The unit was removed from service briefly on July 8, 1986 to perform' turbine overspeed testing.

The unit was again. removed from service on July 10th to perform delinquent technical

-specification required surveillance testing and returned to service again on July 11,=1986.

A unit trip from 90% power occurred on July 22, 1986 while performing a routine calibration of the turbine generator stator cooling water low pressure trip instrumentation.- The unit remained out of service to the end of the month for repairs to pressurizer spray valve, NRV-164 and an oil leak on a reactor-coolant pump.

The reporting period ended with the reactor at 2%

power and holding.

Gross electrical generation for the month of July was 248,760 mwh.-

SUMMARY

07-04-86 At 1208, the reactor coolant system entered Mode 4.

07-05-86 At 0415, the reactor coolant system entered Mode 3.

07-07-86 At 0325, the reactor entered Mode 2.

At 0409, all control banks were inserted and the reactor entered Mode 3 because criticality was not achieved by 228 steps on bank D.

At 0642, after a reactor coolant system dilution, the reactor achieved criticality At 1130, the reactor entered Mode 1.

At 1937, the generator was paralleled to the grid.

At 2100,.with reactor power at 20%, a power increase at 3%/hr to 25%, was started.

1 Docket No.: '50-315 Unit Names D.C. Cook Unit 1 Completed By:

D. A. Bruck Telephone:

(616) 465-5901 Date:. August-8, 1986 Page:

2 of 3

SUMMARY

-(Cont.)

07-08-86.

At 0209, a power reduction was begun for turbine overspeed testing.

At 0307, the generator was removed from parallel.

At 0405, turbine overspeed testing was complete and the generator paralleled to the grid.

At 1643, a reactor power increase to 35% at 3%/hr has begun, reaching 34.5% at 2040.

07-10-86 At 1120, a reactor power decrease required by. Tech Spec's (3.0.3) was started due to a missed time response surveillance on steam generator Hi Hi relays and power range nuclear instruments.

At 1322, the main turbine was tripped with the reactor at 8% power.

07-11-86 At 0258, a reactor power increase began when the required surveillance tests were completed.

At 0321, the reactor entered Mode 1.

At 0428, the generator was paralleled to the grid.

At 0810, the power increase was stopped at 28%.

At 1438, a reactor power increase to 48% was begun reaching 48% at 2115.

07-12-86 At 1018, a reactor power increase to 80% at 3%/hr was begun.

07-13-86 At 0416, the reactor reached 90% power.

07-17-86 At 1035, a reactor power increase was begun at 5 2%/hr to 95% then 5 1%/hr to 100%, reaching 99.5%

at 2015.

07-19-86 At 1020, a reactor power decrease to 90% began, reaching 90% at 1210.

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1 Dockot No.:

50-315 Unit Namas D.C. Cook Unit 1 Completed By:

D. A. Bruck Telephone:

(616) 465-5901 Date: -August 8, 1986 Page:

3 of 3

SUMMARY

(Cont.) 22-86 At 1307, the reactor tripped due to a turbine trip.

The turbine trip occurred due to inadequate blocking of the stator cooling water low pressure trip during a routine calibration.

At 2145, a reactor coolant system cooldown was initiated to permit repairs of a body-to-bonnet leak on pressurizer spray valve, NRV-164.

07-23-86 At 0225, the reactor coolant system entered Mode 4.

At 1109, the reactor coolant system entered Mode 5.

07-26-86 At 0150, the reactor coolant system entered Mode 4.

At 0647, the East Essential Service Water pump failed due to a broken shaft.

07-27-86 At 0246, the reactor coolant system was returned to Mode 5 to repair a. reactor coolant pump oil leak.

07-30-86 At 1022, the reactor coolant system re-entered Mode 4.

At 2117, the reactor coolant system entered Mode 3.

07-31-86 At 1715, the reactor achieved criticality.

At 1804, reactor power was held at 2% which was the-condition of the unit as the end of the month.

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'd-DOCKET NO.

50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 8-7-86 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE JULY, 1986 M-1 Motor operated ESW crosstie valve to Unit 2, WM0-705,' on the discharge.from the West ESW Pump was extremely difficult to operate locally and would not operate from the Control Room.

The valve was replaced and the limit switches were adjusted.

The valve tested satisfactorily.

C&I-l FPI-244, west motor driven auxiliary feed pump discharge pres-sure' read erratically with constant flow.

Pressure transducer was found to be deformed and leaking.. Re-placed defective transducer, electronic circuit board and re-calibrated transmitter.

C&I-2 The ASCO solenoid valve for RRV-103, the PRT vent valve was blowing air.

Rebuilt ASCO solenoid valve and verified proper.

operation.

C&I-3 The west auxiliary feed water pump discharge pressure transmitter.

bourdon tube was found ruptured and transmitter full of water.

The bourdon tube, electronic circuit board, zero potentiometer and span potentiometer were replaced and the transmitter recal-ibrated and returned to service.

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..cmcu accroccamer Donald C. Cook Nuclear Plant P.O. Bon 458. Bndgman, Mchgan 49106

. August 8, 1986 Director, Office Of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Gentlemen:

Pursuant to the requirements of Donald C. Cook Nuclear plant Unit 1 Technical Specification 6.9.1.6, the attached Monthly Operating Report for the Month of July, 1986 is submitted.

Sincerely, W. G. 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 C. A. Erikson D. W. Paul D. R. Hahn Z.

Cordero J. J. Markowsky E. A. Morse PNSRC File INPO Records Center ANI Nuclear Engineering Department-7 Y-o