Text

Monthly Operating Rept for Aug 1986
	ML20207D791
Person / Time
Site:	Cook
Issue date:	08/31/1986
From:	Kirchoff W, Will Smith, Svensson B; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8612310200
	Download: ML20207D791 (9)
	v • d • e

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

50-315 DATE 9/4/86 COMPLETED BY CLIMER TELEPHONE 616-465-5901 OPERATING STATUS

1. Unit Name

.D.

C. Cook Unit 1

2. Reporting Period <-

AUG 86 l notes

3. Licensed Thermal Power (MWt) 3250 l 4.

Name Plate Rating (Gross MWe) 1152 l l

S. 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 5031.0 102263.0

12. No. of Hrs. Reactor Was Critical 728.8 4629.3 72918.7

13. Reactor Reserve Shutdown Hours 0.0 0.0 463.0

14. Hours Generator on Line 700.7 4565.4 71418.0 lb. Unit Reserve Shutdown Hours 0.0 0.0 321.0

16. Gross Therm. Energy Gen. (MWH) 1986925 13147916 208143599

17. Gross Elect. Energy Gen. (MWH) 617740 4230340 68207880

18. Net Elect. Energy Gen. (MWH) 592326 4065608 65612765 4

19. Unit Service Factor 94.2 78.3 71.2

20. Unit Availability Factor 94.2 78.3 71.2

21. Unit Capacity Factor (MDC Net) 78.1 68.4 64.1

22. Unit Capacity Factor (DER Net) 77.3 67.7 61.8

23. Unit Forced Outage Rate 5.8 21.7 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 Cor.imercial Operation):

Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1

8612310200 860831 ADOCK05000g5 j

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AVERAGE DAILY POWER LEVEL (MWe-Net)

DOCKET NO.

50-315 UNIT ONE DATE 9/4/86 COMPLETED BY CLIMER TELEPHONE 616-465-5901 MONTH AUG 86 AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY POWER LEVEL 1

1 17 863

-2 28 18 889-3 505 19 910 4

874 20 906 5

873 21 901 6-873 22 894 7

872 23 884 8

855 24 877 9

543 25 874 10 793 26 870 11 869 27 874

'12 866 28 872 13 869 29 876

~14 871 30 884 lb 867 31 884 16 861 O

i 50-315 IMM:KE1 NO.

llNITS38tlillOWNS ANilPI)WER Hlittik llHNS Unit'NAhlE D.C. Cook - UgJt 1 DATE 9-5-86 HI: PORT Aff)NHI August, 1986 COMPI ETEllitY B.A. Sve_nsson TER.l:l'IBONE 616/465-5901 PAGE 1 of 3 p '1, s.

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3 86-017-00 ZZ ZZZZZZ The reporting period began with (Cont'd.)

unit startup in progress with the reactor in Mode 2 at 2% RTP.

The unit had tripped on 860722 due to an operational error. During a containment inspection a leak was discovered on pressurizer spray valve, NRV-164, which required re-pairs prior to returning the unit to service. On 860801 at 1844 hours0.0213 days 0.512 hours 0.00305 weeks 7.01642e-4 months , the generator was paralleled to the grid and a power increase started. Total length of the out -

age was 245.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

254 860801 F

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3 86-015-00 ZZ ZZZZZZ During the power increase with re-actor power at 24 percent, a tur-bine/ reactor trip occurred due to a high-high level in No. 2 steam gen-erator. The feed water control was i

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IJNil'SlHillMlWNS ANilPOWI:n Hl:l>lkTIONS UNIT NAhlE D.C. Cook - Unit 1 DATE 9-5-86 COkiPI ETEn ley B. A. Svensson Ill PORT hlpN nt August, 1986 616/465-5901 TEl.EPlH)NE PAGE 2 of 3 p

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still in manual and the high-high 254 level was a result of a feed water (Cont', l. )

system transient that the operators were unable to mitigate. A trip recovery commenced with the generator paralleled to the grid at 0921 hours0.0107 days 0.256 hours 0.00152 weeks 3.504405e-4 months on 860802.

255 860802 F

11.1 F.

3 86-018-00 ZZ ZZZZZZ During the power increase with re-actor power at 14 percent a reactor trip occurred, caused by steam flow /

feed water flow mismatch coincident with a low level in No. 4 steam gen-erator. The trip again occurred while the feedwater control was in manual and the operators were not able to control the level during a feed water system transient. The primary contributor to the transient could not be determined, but during

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i 50-315 IMK'EET NO.

LINIT SittiIllOWNS AND POWER HliDtN'llONS D.C. Cook - Unit 1 UNIT NAhlE DATE 9-5-86 COhiPI ETED gy B.A. Svensson REPORT &lpN111 August, 1986 TER.ErilONE 616/465-5901 PAGE 3 of 3 w

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taken to minimize the possibility for the initiation of the feedwater transients. The ge.nerator was par-alleled to the grid at 2056 hours0.0238 days 0.571 hours 0.0034 weeks 7.82308e-4 months on 860802 and 90% power was reached at 2118 hours0.0245 days 0.588 hours 0.0035 weeks 8.05899e-4 months on 860803.

256 860808 S

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4 N/A ZZ ZZZZZZ Reactor power was reduced to 54% to permit removing the east main feed pump turbine from service to inves-j tigate a vibration problem. The exact cause of the vibration could not be determined. The east main feed pump was returned to service and reactor power was returned to the 90% administrative power limit i

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Dockst No. -

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

W. H. Kirchoff Telephone:

(616) 465-5901

.Date:

September 4, 1986 Page:

1 of-2 MONTHLY OPERATING ACTIVITIES - AUGUST, 1986 HIGHLIGHTS:

The reporting period began with the reactor in Mode 2 at 2% rated thermal power.

On August 1, 1986 the main generator was paralleled to the grid at 1844 hours0.0213 days 0.512 hours 0.00305 weeks 7.01642e-4 months .

The unit tripped from 24% power during power escalation due to a high-high level in No. 2 steam generator.

The reactor was returned to criticality and the unit paralleled to the grid at 0921 hours0.0107 days 0.256 hours 0.00152 weeks 3.504405e-4 months an August 2, 1986.

With the reactor at 14% power a trip was again experienced.

The cause was a steam flow / feed flow mismatch coincident with a low level in No. 4 steam generator.

The reactor was again returned to criticality and the unit paralleled to the grid at 2056 hours0.0238 days 0.571 hours 0.0034 weeks 7.82308e-4 months .

90% reactor power was reached at 2118 hours0.0245 days 0.588 hours 0.0035 weeks 8.05899e-4 months on August 3.

On August 8, 1986 reactor power was reduced to 54% to investigate a vibration problem on the east main feed pump turbine.

Reactor power wac returned to 90% on August 10, 1986.

The reporting period ended with the reactor at 90% of rated thermal power.

Gross electrical generation for the month of August was 617740 MWH.

SUMMARY

8-1-86 At 1724, the reactor entered Mode 1.

At 1844, the Unit was paralleled to the grid.

At 1952, the reactor tripped from 24% power due to a turbine trip.

The turbine trip was due to #2 S/G level Hi-Hi, that occurred while feedwater control was still in manual.

L Dockst'NO.:

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

W.

H. Kirchoff Telephone:

(616) 465-5901 Date:

September 4, 1986-Page:

2 of 2

SUMMARY

(Cont.)

8-2-86 At 04'15, the reactor was taken critical.

At 0619, the reactor entered Mode 1.

At 0921, the Unit was paralleled to the grid.

At 0949, the reactor tr!pped from 14% power due to 64 S/G level low coincident with feed flow / steam flow mismatch, this occurred while feedwater control was-still in manual.

At-1642, the reactor was taken critical.

At 1936, the reactor entered Mode 1.

At 2056, the Unit was paralleled to the grid.

At 2220, holding reactor power at 28.5% for Chemistry.

8-3-86 At 0615, a reactor power increase was begun at 6%/hr reaching and holding at 48.5% for Chemistry at 0950.

At 1220, a reactor power increase was begun at 6%/hr to 90% power, reaching 90% at 2118.

8-5-86 At 0045, the TDAFP was declared inoperable due to the trip and throttle valve would unlatch and then would not closed.

At 1725, the TDAFP was declared operable.

8-8-86 At 1635, a reactor power reduction to 54% was begun for troubleshooting the east main feed pump vibration problem.

8-9-86 At 0650, holding reactor power at 54%.

At 1842, commenced reactor power increase to 90%.

At 2355, holding reactor power at 78.5% for Chemistry.

8-10-86 At 1300, a reactor power increase was begun at 6%/hr.

to 90% power, reaching 90% at 1555.

8-11-86 At 0417, CD Diesel was declared inoperable due to an incomplete start.

At 1747, CD Diesel was declared operable after replac-ing D.G.

incomplete start agastat relay.

s._

s DOCKET NO.

50 - 315

. UNIT NAME D. C. Cook'- UniE No. 1 DATE 9-5-86 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE AUGUST, 1986 C&I-l' CCR-440, component cooling water from main steam penetration cooling coils would not open. Found ASCO solenoid valve defec-tive. ASCO solenoid valve was replaced and correct valve operation was verified.

'f,^

gn.

INDMNA & MICHIGAN ELECTRLC_COMPAN1 ge, Donaki C. Cook Nuclear Plant P.O. Box 458. Bridgman, Mehgan 49106 September 5, 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 att ched Monthly Operating Report for the Month of August, 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 B. 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 j

ANI Nuclear Engineering Department f,T i

i I

ML20207D791

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