Text

Monthly Operating Rept for Nov 1985
	ML20137S417
Person / Time
Site:	Cook
Issue date:	11/30/1985
From:	Will Smith, Svensson B; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	; NRC OFFICE OF ADMINISTRATION (ADM)
References
	NUDOCS 8602180044
	Download: ML20137S417 (10)
	v • d • e

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50-316 IINir SillillHlWNS AND POW 1.H HlilltfrilONS D.C. Cook - Unit' 2.

ifNil NAME IIA IE 12-6-85 COMPI ETEll kY B.A. Svensson Ill POR'l Hf)N ill November, 1985 616/465-5901 1El.1' PHONE PAGE 1 of 2 "t.

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165 851029 F

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3 85-035-00 ZZ ZZZZZZ The Unit tripped on 851029 at which Cont'd time reactor trip breaker "A" failed to open. The reactor trip breaker problem was thoroughly in-vestigated, corrective action taken and the results reported to the NRC in our letter, AEP:NRC:0962, to Mr. James G. Keppler, dated, November 6, 1985. The Unit was returned to service at 1008 hours0.0117 days 0.28 hours 0.00167 weeks 3.83544e-4 months on 851108 and reactor power increased to 80% on 851109. An administrative power limit of 80% is being maintained to minimize steam generator tube degra-dation.

166 851113 F

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3 85-037-00 ZZ ZZZZZZ A reactor trip occurred at 1458 hours0.0169 days 0.405 hours 0.00241 weeks 5.54769e-4 months on 851113 due to a steam flow /

feedwater flow mismatch coincident with low level in steam generator #2.

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166 The mismatch signal was as a result Cont'd of removing steam generator #2 pres-sure transmitter from service and placing the associated bistables in a tripped condition. Removing the pressure transmitter from service

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resulted in a decrease in the steam flow signal due to loss of the pres-sure compensation. The control sys-tem " sensing" the steam flow decreasi reacted by closing the feedwater regulating valve which resulted in an actual low steam generator level, thus completing the coincidence cir-cuit for the reactor trip signal.

To prevent recurrence, appropriate procedures will be revised. The Unit was returned to service at 1058 hours0.0122 days 0.294 hours 0.00175 weeks 4.02569e-4 months on 851_114 and reactor power increased to 80% on 851115.

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Docket No.:

50-316 Unit Name:

D.C. Cook Unit 2 Completed By:

D.

A.

Bruck Telephone:

(616) 465-5901 Date:

December 9, 1985 Page:

1 of 2 MONTHLY OPERATING ACTIVITIES - NOVEMBER, 1985 HIGHLIGHTS:

The reporting period began with the reactor coolant system in Mode 3 and 538*F temperature.

On 11-07-85, the reactor was taken critical and on 11-08-85, at 1008 hours0.0117 days 0.28 hours 0.00167 weeks 3.83544e-4 months the main generator was paralleled to the grid.

On 11-09-85, reactor power was increased to 80%.

(An administrative limit of 80% has been imposed in an effort to minimize steam generator tube degradation).

I On 11-13-85, at 1458, the reactor tripped from 80% power due to steam flow / feed flow mis-match coincident with low steam generator level.

On 11-14-85, the reactor was taken critical and the generator was paralleled to the grid at 1058 hours0.0122 days 0.294 hours 0.00175 weeks 4.02569e-4 months .

Reactor power was in-creased to 80% on 11-15-85.

The reactor remained at 80% for the rest of the reporting period.

Gross electrical generation for the month of November is 436,050 MWH.

SUMMARY

11-07-85 At 2239, the reactor became critical.

11-08-85 At 0613, the reactor entered Mode 1.

At 1008, the main generator was paralleled to the grid.

At 1055, a reactor power increase to 30% was begun.

At 2000, Chemistry ~was meet and a power increase to 50%

began at 2015.

11-09-85 At 0310, a reactor power increase to 80% was begun.

At 1315, the power increase was stopped at 79%.

11-10-85 At 0156, an inadvertant Engineered Safety Features actuation occurred due to a high alarm on containment radiation monitor ERS-2401.

11-13-85 At 1458, the reactor tripped on steam generator number 2 steam flow / feed flow mis-match coincident with low steam generator level.

Docket No.:

50-316 Unit Name:

D.C. Cook. Unit 2 Completed By:

D.

A.

Bruck Telephone:

(616) 465-5901 l

Date:

December 9, 1985 j

Page:

2 of 2 i

j 11-14-85 At 0514, cnc reactor became critical.

I At 0804, the reactor entered Mode ~1.

At 1058, the generator was paralleled to the grid.

I At 1220, the reactor power increase was stopped at approximately:30% for Chemistry.

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At 1615, a reactor power increase to 50% was begun.

i At 2045, the power increase was stopped at 49%.

11-15-85 At 0736, a reactor power increase to 80% begun.

At 1300, the power increase was stopped at 80.5%.

1 11-17-85 At 0043, an Engineered Safety Features actuation j

occurred due to high alarm on containment area monitor i

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DOCKET NO.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 12-6-85 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE

-NOVEMBER, 1985 C&I-l Tcold wide range RTD loop 2 (NTR-220) was reading 15* higher than the other 3 loops.

The RTD was replaced and loop 2' now reads the same as the other 3 loops.

C&I-2 Containment isolation valves, VCR-10 and 20, on the glycol system closed when controls were in " auto" position. HFA relay H3X1-GET was found bcrned out.

The relay was replaced and correct opera-tion of the valves in " auto" was verified.

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2 50-316 DOCKET No.

ljNIISilillDOWNS ANDl' Owl:H HliDlM'TIONS D.C. Cook, Unit 2 U Nef N AblE 18 ATE 11/8/85 CObit*l.ETEn lay B.A. Svensson October, 1985 l

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CC HTEXCH The Unit was removed from service on 850824 for steam generator tube leak repairs and to perform required desigi changes. The Unit was returned to service on 851023 at 1712 hours0.0198 days 0.476 hours 0.00283 weeks 6.51416e-4 months EDT.

165 851029 F

58.0 A

3 85-035-0 ZZ ZZZZZZ During power ascension from the pre-vious outage, a reactor trip occurred from 79% power. The trip was trig-gered by a spurious indicated low-flow condiiton in R.C. Loop 2 due to a momentary drop in the output volt-age from vital instrument bus, CRID II.

The voltage drop is believed to have been caused by a component fail-ure in radiation monitor, ERS-2300.

Following the reactor trip it was discovered that reactor trip breaker "A" failed to open. The trip was accomplished through reactor trip i

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50-316 r.

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llNil'SilllHIOWNS AND POWLH RElHM'TIONS UNil NAblE D.C. Cook. Unit 2 IIATE 11/8/85 COnaPLETEDay B.A. Svensson Hl: PORT &lONTil October, 1985 TELEPHONE 616/465-5901 PAGE 2 of 2 "t.

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The Unit remained shut 165 ( ::ontinued) down at the end of the month (RCS in kode 3) pending resolution of the reactor trip breaker problem.

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IN0 LANA & MICHIGALELECIRfC COMPANY ys t.,

Donald C. Cook Nuclear Plant P.O. Box 458. Bru$gman, MN:hgan 49106 December 6,.1985 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 2 Technical Specification 6.9.1.6, the attached Monthly Operating Report for the Month of November, 1985 is submitted.

Also attached please find a copy of the Unit shutdown and power re-duction form for the month of October, 1985, which has been updated to show the Licensee Event Report Number for Outage No. 165.

Sincerely, gt4h &'W 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 F. S. VanPelt, Jr.

P. D. Rennix D. R. Hahn Z.

Cordero J. J. Markowsky J. F. Stietzel PNSRC File gf

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INPO Records Center ANI Nuclear Engineering Department r 'j I

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N.R.C.

OPERATING DATA REPORT DOCKET NO.

50-316 DATE 12/3/85 COMPLETED BY CLIMER TELEPHONE 616-465-5901 OPERATING STATUS 1.

Unit Name D.

C.

Cook Unit 2 2.

Reporting Period NOV 85 : 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. 'I f Changes Occur in Capacity Ratings (Items no. 3 through 7) Since Last Report Give Reasons

.. - -.. - _ = _ -

_=

Net MWe)

Power Level To Which Restricted. If Any (

9.

10. Reasons For Restrictions. If Any:________________________-___---_

_ =---------------

Yr. to Date Cumm.

This No.

11. Hours in Reporting Period 720.0 8116.0 69384.0

12. No. of Hrs. Reactor Was Critical 539.2 5204.8 48284.8

13. Reactor Reserve Shutdown Hours O.O O.O O.O

14. Hours Generator on Line 521.9 5111.0 47109.6

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Therm. Energy Gen. (MWH) 1372641-161732O2 149251263

17. Gross Elect. Energy Gen. (MWH) 436050 5249820 49035250

18. Net Elect. Energy Gen. (MWH) 416770 5058301 47276035

19. Unit Service Factor 72.5 63.0 70.4

20. Unit Availability Factor 72.5 63.0 70.4

21. Unit Capacity Factor (MDC Net) 54.6 58.8 66.7

22. Unit Capacity Factor (DER Net) 52.6 56.7 65.3

23. Unit Forced Outage Rate 27.5 35.7 16.0

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

REFUELING OUTAGE SCHEDULED TO START 3/1/85, EXPECTED DURATION 90 DA'

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

J AVERAGE DAILY POWER LEVEL (MWe-Net)

DOCKET NO.

50-316 UNIT TWO DATE 12/3/85 COMPLETED BY CLIMER TELEPHONE 616-465-5901 MONTH NOV 85 AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY POWER LEVEL 1

0 17 841 2

0 18 852 3

0 19 846 4

0 20 845 5

0 21 850 6

0 22 850

-7 0

23 851 8

131 24

-853 9

677 25 852 10 813 26 848 11 828 27 851 12 837 28 855 13 519 29 854 14 165 30 851 15 657 31 0

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ML20137S417

Text

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