ML17328A925

Monthly Operating Rept for Jan 1991 for DC Cook Unit 1.W/

ML17328A925
Person / Time
Site:	Cook
Issue date:	01/31/1991
From:	Blind A, Jannise J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9102250015
Download: ML17328A925 (12)

Text

ACCELERATED DI~~BUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9102250015 DOC.DATE 91/01/31 NOTARIZED: NO DOCKET g

FACIL:50-315 Donald C.

Cook Nuclear Power Plant, Unit 1, Indiana 6

05000315 AUTH.NAME AUTHOR AFFILIATION JANNISE,J.D.

Indiana Michigan Power Co.

(formerly Indiana

& Michigan Ele BLIND,A.A.

Indiana Michigan Power Co.

(formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION R

SUBJECT:

Monthly operating rept for Jan 1991 for DC Cook Unit 1.W/

910207 ltr.

DISTRIBUTION CODE:

IE24D COPIES RECEIVED LTR ENCL SIZE:

TITLE: Monthly Operating Report (per Tech Specs)

NOTES D

RECXPIENT ID CODE/NAME PD3-1 LA COLBURN,T.

INTERNAL: AEOD/DOA IRM TECH ADV NRR/DOEA/OEAB RGN3 EXTERNAL: EGGG BRYCE,J.H NSIC COPIES LTTR ENCL 3

3 1

1 1

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1 RECIPXENT ID CODE/NAME PD3-1 PD AEOD/DSP/TPAB NRR/DL 10 RE 1

NRC PDR COPIES LTTR ENCL 1

1 1

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1 1

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, NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 16 ENCL 16 A

D D

Indiana Michigan ~

Power Company Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 616 465 5901 February 7, 1991 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555 Gentlemen:

Pursuant to the requirements of Donald C.

Cook Nuclear Plant Unit 1 Technical Specification 6.9.1.10, the attached Monthly Operating Report for the month of January 1991 is submitted.

Respectfully, A.A. Blind Plant Manager Attachment c:

NRC Region III D.R.

Hahn EPRI Nuclear Safety An R.C. Callen S.L. Hall J.G. Keppler INPO Records Center ANI Nuclear Engineering 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 J.A.

Isom W.T. Gillett E.A. Smarrella J.C. Krieger B.A. Svensson D.F. Krause E. C.

Schimme1 alysis Center Department 9102250015 910131

" PDR ADOCK 05000315 R

PDR

~

~

N.R.C.

OPERATING DATA REPORT DOCKET NO.

50-315 DATE 01-Feb-91 COMPLETED BY JD JANISSE TELEPHONE 616-465-5901 OPERATING STATUS

1. Unit Name D.

C.

Cook Unit 1

2. Reporting Period JAN.91

3. Licensed Thermal Power (MWt) 3250 4.

Name Plate Rating (Gross MWe) 1152

5. Design Electrical Rating (Net MWe) 1030 6.

Maximum Dependable Capacity (GROSS MWe) 1056 7.

Maximum Dependable Capacity (Net MWe) 1020 notes

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:

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.

744.0 218.4 0.0 118.8 0.0 168341 43350 39334 16.0 16.0 5.2 F 1 0.0 Months (Type, to Date 744.0 218.4 0.0 118.8 0.0 168'341 43350 39334 16.0 16.0 5.2 5.1 0.0 Date,and

, Cumm.

141000.0 103605.4 463.0 101747.6 321.0 295597989 96174580 92472807 73.2 73.2 65.2 63.4

7.1 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.

50-315 UNIT ONE DATE 01-Feb-91 COMPLETED BY JD JANISSE TELEPHONE 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 JAN. 91 DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31'VERAGE DAILY POWER LEVEL 0

0 0

0 0

0 0

0 0

0 185 262 325 414 453

~~

I

UNIT SHUTDOWNS AND HXKR REDUCTIONS REPORP MONTH:

January 1991 DOCKE'T NO:

UNIT NAME DATE:

COMPL'ETED BY:

TEXZZK3HE'0-315 D.C.

COOK UNIT 1 February 7, 1991 E.C. Schimmel (616) 465-5901 MEHiOD OF SHVI!TING IZCENSEE DURATION DONN EVENT SYSTEM OOMFONENT CAUSE AND COEGKCZZVE ACZION TO NO.

DATE TYPE1 HCURS XWSON2 RZACIOR3 aZPORr NO.

CODE CODE ZeZVZm REXuaaENCE 290 901020 S

623.7 (cont.)

N/A N/A ZZ ZZZZZZ

'Ihe unit was removed fmm service at ~

0031 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br /> on 901020 for cycle 11-12 refueling and maintenance outage. All refueling activities and maintenance work have been cxxpleted.

The reactor achieved initial criticality for cycle 12 on 910115 and the unit was

~leled to the system at 2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br /> on 910126. Reactor poorer was inn~ased to 324 for turbine warming prior to oversp ed testing.

Ihe total outage duration was 2376.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

291 910127 S

1.5 N/A N/A ZZ ZZZZZZ

'Ihe unit was rewed from service at 1742 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.62831e-4 months <br /> on 910127 for main turbine oveL~eed trip testing. ~ing was completed and the unit was returned to service at 1913 hours0.0221 days <br />0.531 hours <br />0.00316 weeks <br />7.278965e-4 months <br /> on 910127.

1 2

F:

Forced Reason:

S:

Scheduled A:

Equipment Failure (Explain)

B:

Maintenance or Test C:

Refueling D:

RecpQatory Restriction E:

Operator Training and Li~Examination F:

Administrative G:

Operational Erxor (Explain)

H:

Other (Explain) 3 Method:

1:

Manual 2:

Manual Scram 3:

Automatic Scxam 4:

Other (Explain) 4 5

Exhibit G Instructions Exhibit. I:

Same Source for preparation of data entry sheets for Licensee Event Report (IZR) File (NUREG 0161)

DOCKET N UNIT NAME:

COMPLETED BY:

TELEPHONE:

DATE PAGE 50-315 D.C.

Cook Unit 1 E.C.

Schimmel (616) 465-5901 February 7, 1991 1 of 3

MONTHLY OPERATING ACTIVITIES Januar 1991 HIGHLIGHTS The unit entered the reporting period with the RCS in mode 5.

RCS heatup was started on January

4. The RCS temperature was held at approximately 300 degrees Fahrenheit for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for steam generator crevice flushing.

The RCS reached no-load rated temperature and pressure on January 9.

The low-power physics testing program was started on January 9, with the reactor being critical for the first time in cycle 12 at 0826 hours0.00956 days <br />0.229 hours <br />0.00137 weeks <br />3.14293e-4 months <br /> on January 15.

The low-power physics testing was completed on January 16.

An RCS cooldown to cold shutdown was required due to a weld leak in an instrument line root valve for main steam flow transmitter MFC-120.

Mode 5 was reached on January

18. Following completion of the weld repairs, the RCS was again heated up with rated temperature and pressure conditions being reached on January 19.

The reactor was taken critical on January 23 and following turbine roll and completion of required turbine balancing the generator was paralleled to the system grid for the first time in cycle 12 at 2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br /> on January 26, 1991. Reactor power was increased to 324 RTP for turbine rotor warming prior to overspeed testing On January 27, reactor power was reduced to 7% and the generator

, removed from parallel at 1742 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.62831e-4 months <br /> to perform main turbine overspeed testing.

The generator was re-paralleled to the system grid at 1913 hours0.0221 days <br />0.531 hours <br />0.00316 weeks <br />7.278965e-4 months <br /> on January 27 and reactor power increase was commenced in accordance with the power escalation testing program.

The unit exited the reporting period at approximately 53%

RTP with power being increased to 68%.

Gross electrical generation for the month of January was 43350 MWH.

DETAILS 01/04/91 1041 1054 01/07/91 2209 2310 Commenced RCS heatup to mode 4.

The RCS is in mode 4.

Commenced RCS heatup to mode 3.

The RCS is in mode 3.

Monthly Operati ctivities January, 199 Page 2 of 3

01/14/91 2355 01/15/91 0537 0826 01/16/91 0933 0946 Commenced reactor startup.

The reactor is in mode 2.

The reactor is critical.

Commenced reactor shutdown.

The RCS is in mode 3.

1900 Commenced RCS cooldown to mode 5 to allow repair of a weld leak in an instrument, line root valve for main stem flow transmitter MFC-120.

2324 01/18/91 0130 1459 The RCS is in mode 4.

The RCS is in mode 5.

With repairs

complete, commenced an RCS heatup to mode 3.

1526 01/19/91 0228 01/23/91 2209 2345 The RCS is in mode 4.

The RCS is in mode 3.

Commenced reactor startup.

The reactor is critical.

01/24/91 0425 Commenced reactor power increase to 7.54 RTP for turbine roll.

1223 1317 1320 The reactor entered mode 1.

The reactor is at 7.5: RTP.

Rolled main turbine.

1621 Manually tripped main turbine due to high vibrations.

01/26/91 0250 0405 0515 Commenced reactor power decrease to 2% RTP while balancing the main turbine.

The reactor is in mode 2.

The reactor is at 2> RTP.

T 1

~

P e

Monthly Operati ctivities January, 199 Page 3 of 3

1554 1603 1626 Commenced reactor power increase to 74 RTP.

The reactor is in mode 1.

The reactor is at 74 RTP.

2345 The main generator is paralleled to the system grid.

Commenced unit power increase to 32~~

RTP.

01/27/91 0400 The unit is at 324 RTP.

1520 Commenced unit power reduction to 7~ RTP to perform main turbine overspeed trip testing.

1735 The unit is at 7% RTP.

1742 The main generator output breakers are opened.

Commenced turbine overspeed testing.

1913 Turbine overspeed testing is complete.

The main generator is paralleled to the system power grid.

Commenced unit power increase to 35~o RTP.

2209 01/29/91 0810 2038 01/31/91 1350 The unit is at 35~ RTP.

Commenced unit power increase to 484 RTP.

The unit is at 484 RTP.

Commenced unit power increase to 684 RTP

DOCKET NO:

UNIT NAME:

COMPLETED BY:

TELEPHONE:

DATE PAGE 50-315 D.C.

Cook Unit 1 E. C.

Schimmel (616) 465-5901 February 7,

1991 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE Januar 1991 The interlocks on the 612'containment airlock doors were not functioning, due to a broken bracket on the outer airlock door.

The bracket was re-welded and the interlocks restored to operability.

An elbow on the instrument line between

¹12 Steam Generator and instrument valve 1-MFC-120-Vl was leaking steam.

A leaking elbow in the line was re-welded to repair the leak.