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Monthly Operating Rept for Nov 1990 for DC Cook Unit 2.W/
	ML20065R731
Person / Time
Site:	Cook
Issue date:	11/30/1990
From:	Blind A, Gillett W; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9012190153
	Download: ML20065R731 (7)
	v • d • e

1 Indinna lechigan Power Cornpny o

Cook Nuclear hant one Cook I':a:e litidgmAn. MI 491D6 61(,4f4 $901 Y

sesed INDIANA MICHIGAN POWER December 6, 1990 U.S. Nuclear Regulatory Commission ATTN Document Control Desk Washington, D.C.

20555 Gentlement 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 November 1990 is submitted.

Respectfully, kY A.A. Blind Plant Manager Attachment l

os NRC Region III l

D.R. Hahn EPRI - Nuclear Gafety Analysis Center R.C.

Callen S.L. Hall J.G.

Keppler 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.O. Argenta S.H.

Steinhart I

J.A.

Isom W.T. Gillett E.A.

Smarrella-J.C.

Krieger B.A. Svensson E.C.

Schimmel

-9012190153 901130

.PDH ADOCK 05000316 t

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N.R.C. OPERATING DATA REPORT l

I DOCKET No.90-316 DATE 03-Dec-90 COMPLETED BY WT GILLETT TELEPHONE 616-465-5901 OPERATING STATUS

1. Unit Name D. C. Cook Unit 2

3. Reporting Period NOV.90 notes

3. Licensed Thermal Power (MWt) 3411

4. Name Plate Rating (Gross MWe) 1133

9. Design Electrical Rating (Het MWe) 1100

6. Maximum Dependable Capacity (GROSS MWe) 1100

7. Maximum Dependable Capacity (Net MWe) 1060

8. If Changes Occur in Capacity Ratings (Items no. 3 ' hrough 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 720.0 8016.0 113200.0

12. No. of Hrs. Reactor Was Critical 573.4 4361.9 74537.9

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator on Line 527.9 4298.1 73027.6

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Therm. Energy Gen. (MWH) 1338296 13401228 224279118

17. Gross Elect. Energy Gen. (MWH) 429450 4369700 73165810

18. Het Elect. Energy Gen. (MWH) 411350 4214010 70459668

19. Unit Service Factor 73.3 53.6 65.9

20. Unit Availability Factor 73.3 51.6 65.9

21. Unit capacity Factor (MDC Net) 53.9 49.6 59.9

22. Unit Capacity Factor (DER Net) 51.9 47.8 58.4

23. Unit Forced Outage Rate 0.0 9.0 13.5

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

+

AVERAGE DAILY POWER LEVEL (MWe-Net)

DOCKET NO.

50-316 UNIT TWO DATE 03-Dec-90 i

COMPLETED BY WT GILLETT TELEPHONE 616-465-5901 MONTH NOV.90 AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL D'Y POWER LEVEL 1

0 17 673 2

0 18 743 1

3 0

19 929 4

0 20 946 5

0 21 1073 6

0 22 1033 7

0 23 1078 8

0 24 1083 9

0 25 1086 10 229 26 1086 11 274 27 1085 12 412 28 1085 13 431 29 1087 30 1079 14 442 15 623 16 664

.t

-,v_--

i' DLGET NO:

50-316

+

j IMIT SHUIDOWS AND KMER PEDUCnCNS UNIT NAME:

D.C. COOK iRIT 2 DIGE:

Dh~ 6 1990

[

1 REImr ENIH: ' November 1990 CCMPIEIED B7:

F.C. Schimmel

}

TFmHONE:

(616).465-5901.

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l-saamm ucEssEE i

o@xrim com Evmr SysIm Otmanmr causE AND cmRectrvE ACrlm 70 t

I-no.

mTE rnr1 2

3 5

mWS FSSm REACIm REImr NO.

00m' 00m MEVENT RDWRRmCE i

l 2he unit w::s removed frw service ' t a

i j

O225 hours on 900630 for cycle 7-8 i

refueling outage. The r=B= ling and i

maint===ce activities have been j

mleted. The raha. was critical for

(

j the first tima in cycle 8 cn 901109, i

and the unit parallelled at 0006 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months j

on 901110. 100% power was Ivar+wwi at

' i 0315 hours0.00365 days 0.0875 hours 5.208333e-4 weeks 1.198575e-4 months at 901121. 'Ihere were no j

shutdowns or significant power rvvtrtions during the rest cf the 3

month.

4 i

1

.r j

1 2

3 4

5 F: Forced Reason:

Method:

Exhibit G - Instructi<ms Ekhibit I: Same Source jl; S: Scheduled A: Fq2i,rmant Failure (Explain) 1: Manual for preparatimt of data B: Maintermax or Test 2: Manual Scramt entry simi,=G for Licensee 1-C: ReDp1ing 3:

Autr== tic Scram Event Report (IIR) File D: Begulatory Bestrir+iert 4: Other ( h lain)

(NUREG 0161)

E: Opeaai.ur Training and License Examination

].

F: artninistrative '

i G: Operational Error (Explain).

i...

H:- Other (Explain) f' m.

..Tg y

m

-Q

l DOCKET Hot 30-316 I

UNIT NAME:

D.C. Cook Unit 2 1

COMPLETED BY:

E.C. Schimmel TELEPHONE:

(616) 465-5901 l

DATE:

December 6, 1990 PAGEt 1 of 1 MONTHLY OPERATING ACTIVITIES - Novembgr 1990 HIGHLIGHTS 4

4 The unit entered the reporting period in mode 3. The unit entered mode 2 at 2342 hours0.0271 days 0.651 hours 0.00387 weeks 8.91131e-4 months on November 7, 1990. Reactor criticality was achieved at 0235 hours0.00272 days 0.0653 hours 3.885582e-4 weeks 8.94175e-5 months on November 8, 1200. The unit entered mode 4

1 at 1735 hours0.0201 days 0.482 hours 0.00287 weeks 6.601675e-4 months on November 9, 1990. The uni' was paralled to the power grid at 0006 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months on November 10, 1990. W.i' Dower was increased to 48% Rated Thermal Power starting 0028 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months on November 10,1990. Unit power was increased to 62% Rated Thermal l

Power starting 1915 hours0.0222 days 0.532 hours 0.00317 weeks 7.286575e-4 months on November 14, 1990. Unit power was increased to 90% ?.ated Thermal Power starting 1237 hours0.0143 days 0.344 hours 0.00205 weeks 4.706785e-4 months on i

November 18, 1990. Unit power was increased to 100% Rated Thermal Power starting 1530 hours0.0177 days 0.425 hours 0.00253 weeks 5.82165e-4 months on November 20, 1990. The unit exited the reporting period at 100% Rated Thermal Power.

Gross electrical generation for the month of July was 429450 MWH.

DETAILS 11/07/90 2009 Commenced dilution of the Reactor Coolant System Boron concentration.

d 2342 The unit is in mode 7.

11/08/90 0235 First reactor criticality in cycle r

0512 Low power physics testing is '

11/09/90 0755 Commenced unit power increase to 2% Rated Thermal Power.

0947 The unit is at 2% Rated Thermal Power to allow for establishing main condenser vacuum.

1539 Commenced unit power increase to 4% Rated Thermal Power.

1550 The unit is at 4% Rated Thermal Power.

1701 Commenced unit power increase to 8% Rated Thermal power.

l 1735 The unit is in mode 1.

11/10/90 0006 The main generator is parallelled to the power grid for the first time in cycle 8.

0028 Commenced unit power increase to 48% Rated Thermal Power.

l l

11/12/90 0508 The unit is at.\\8% Rated Thermal Power.

l 11/14/90 1915 Commenced unit power increase to 62% Rated 1

Thermal Power.

]

11/15/90 0445 The unit is at 62% Rated Thermal Power.

j 11/15/90 0823 Commenced unit power increase to 68% Rated Thermal Power.

1117 The unit is at 68% Rated Thermal Power.

11/10/90 1237 Commt.nced unit power increase to 90% Rated Theraal Power.

11/19/90 0023 The anit is at 90% Rated Thermal Power.

1530 Commanced unit power increase to 100%.Rit'ad Thermal Power.

e 1625 Unit powe.- is held at 91% due to the Quadra7t-Power Tilt Ratio approaching its technical 1

specification limit.

11/20/90 1423 Resumed unit power increase to 100% Rated Thermal Power.

11/21/90 0315-The unit is at 100% Rated Taarmal Power.

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- ~. - -.. - -. - - - - - - ~ ~ - - - - - --

-'-i

l DOCKET Not 50-316 UNIT NAME:

D.C. Cook Unit 2 COMPLETED BY:

E.C. Schimmel TELEPHONE:

(616) 465-5901 DATE:

December 6, 1990 PAGE:

1 of 1 BA@ R SAFETY-RELATED MAINTENANCE - November 1991 2-M-1 Pressurizer safety valve 2-SV-45-C was leaking by. The leaking valve was removed from service and replaced with a new valve.

2-M-2 Pressurizer safety valve 2-SV-45-A was leaking by. The leaking valve was removed from service and replaced with a new valve.

2-M-3 The East Component Cooling Water Heat Exchanger service water outlet shutoff valve would not fully close. The defective valve was removed from service and replaced with a new valve.

2-M-4 The Regenerative Heat Exchanger charging header inlet drain to Reactor Coolant Drain Tank shutoff valve, 2-CS-323, was leaking by. The leaking valve was removed from service and replaced with a new valve.

I

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ML20065R731

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