ML17328A320

Monthly Operating Rept for June 1990 for Donald C Cook Nuclear Power Plant,Unit 2

ML17328A320
Person / Time
Site:	Cook
Issue date:	06/30/1990
From:	Blind A, Gillett W INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9007170182
Download: ML17328A320 (7)

Text

ACCELERATED DISTRIBUTION DEMONST TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9007170182 DOC.DATE: 90/06/30 NOTARIZED: NO DOCKET FACIL:50-316 Donald C.

Cook Nuclear Power Plant, Unit 2, Indiana 6

05000316 AUTH.NAME AUTHOR AFFILIATION GILLETT,W.T.

Indiana Michigan Power Co. (formerly Indiana

& Michigan Ele BLIND,A.A.

Indiana Michigan Power Co.

(formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

Monthly operating rept for June 1990 for Donald C Cook Nuclear Power Plant, Unit 2.N/900705 ltr.

DISTRIBUTION CODE:

IE24D COPIES RECEIVED:LTR L ENCL SIZE:

TITLE: Monthly Operating Report (per Tech Speck)

NOTES D

S RECIPIENT ID CODE/NAME PD3-1 LA GIITTER,J.

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

3 1

1 1

1 2

2 1

1 1

1 3

3 1

1 RECIPIENT ID CODE/NAME PD3-1 PD AEOD/DSP/TPAB NRR D gg/

B10 G FILE LPDR NSIC COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 1

1 A

D D

S R

I D

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 19 ENCL 19 D

D

Indiana Michigan Power Company Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 616 465 5901 July 5, 1990 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 2 Technical Specification 6.9.1.10, the attached Monthly Operating Report for the month of June 1990 is submitted.

Respectfully, 8 6ltr~

A.A. Blind Plant Manager Attachment.

c B.A. Svensson NRC Region III D.R. Hahn EPRI Nuclear Safety Analysis Center R.C. Callen S.L. Hall 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 B.L. Jorgensen W.T. Gillett E.A. Smarrella J.C. Krieger E.C.

Schimme1 J.G.

Keppler 9007i70i82 900630 PDR ADOCK 050003l6 R

PDC

t N.R.C.

TING DATA REPORT DOCKET NO.

50-316 DATE 02-Jul-90 COMPLETED BY WT GILLETT TELEPHONE 616-465-5901 D.

C.

Cook Unit JUNE OPERATING STATUS

1. Unit Name

2. Reporting Period

3. Licensed Thermal Power (MWt) 4.

Name Plate Rating (Gross MWe)

5. Design Electrical Rating (Net MWe) 6.

Maximum Dependable Capacity (GROSS MWe) 7.

Maximum Dependable Capacity (Net MWe) 2 90 3411 1133 1100 1100 1060 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. to Date 720.0 4343.0 630.3 3788.5 0.0 0.0 623.6 3770.2 0.0 0.0 1767222 12062932 547550 3940250 525116 3802660 86.6 86.8 86.6 86.8 68.8 82.6 66.3 79.6 10.7 10.1 Months (Type, Date,and Cumm.

109535.0 73964.5 0.0 72499.7 0.0 222940822 72736360 70048318 67.7 67.7 61.7 60.0 13.6 Duration):

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

Se tember 12 1990

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

Forcast INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Achieved

AVERAGEOILY POWER LEVEL (MWe-Net)~

DOCKET NO.

50-316 UNIT TWO DATE 02-Jul-90 COMPLETED BY WT GILLETT TELEPHONE 616-465-5901 DAY MONTH AVERAGE DAILY POWER LEVEL JUNE 90 DAY AVERAGE DAILY POWER LEVEL 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 902 897 896 891 889 884 882 888 886 881 489 0

0 54 609 925 17 18 19 20 21 22 23 24 25 26 27.-

28 29 30 31 924 925 930 928 914 916 917 829 745 726 744 744 661 4

0

UNZZ SHUIDXKS AND POWER RHXJCZIONS REPORT MONIH:

June 1990 DOCKEZ NO:

UNIT NAME DATE COMPLEAT) BY:

TEIZPHONE 50-316 D.C.

COOK UNIT 2 July 5, 1990 E.C. Schimmel (616) 465-5901 MEKSOD OF SHUZTING LICENSEE DURATION DOWN EVENT NO.

DATE TYPE HOURS REASON2 REACIOR3 REPORT NO.

SYSZM COMPONEFZ CAUSE AND CDRRECZIVE ACZION TO CODE CODE PEKVEWZ RECORRENCE 208 900611 F

74.8 A

3 90-004-00 The unit tripped fram 86< paver at 1417 hours0.0164 days <br />0.394 hours <br />0.00234 weeks <br />5.391685e-4 months <br /> on 900611 due to a paver range neutron flux high negative rate signal.

Although the cause of the trip is nat conclusively hxm, it is believed a drop of two or more rods caused the reactor to trip on a high negative rate signal.

After extensive checks of the rod control system failed to uncover evidence of failure, all contxol rods were exercised using a special procedure.

All contxol rods performed normally during the special procaTure.

'Ihe unit was returned to service at 1704 hours0.0197 days <br />0.473 hours <br />0.00282 weeks <br />6.48372e-4 months <br /> on 900614.

209 900630 S

21. 6 N/A zz zzzzzz Ihe unit was removed fram service at 0225 hours0.0026 days <br />0.0625 hours <br />3.720238e-4 weeks <br />8.56125e-5 months <br /> on 900630 for the cycle 7-8 refueling outage.

In addition to refueling, surveillance testing, maintenance and design change installation will he performed

'ihe.~

estimated return to sevrice date is 900912.

1 2

F:

Forced Reason:

S:

Scheduled A:

Hpxipment Failure (Explain)

B:

Maintenance or Test C:

Refueling D:

RepQatory Restriction E:

Operator Training and License Ihandnation F:

Mrnini.txative G:

Operational Error (Explain)

H:

Other (Explain) 3 Method 1:

Rural 2:

Manual Scram 3:

Autcaaatic Scram 4

Other (Explain) 4 5

Exhibit G Instructions Exhibit I:

Same Saurce for preparation of data ent~ sheets for Licensee Event Report (LER) File (NUEKG 0161)

DOCKET NO:

UNIT NAME:

COMPLETED BY:

TELEPHONE:

DATE:

PAGE 50-316 D.C.

Cook Unit 2 E.C.

Schimmel (616) 465-5901 July 5, 1990 1 of 1 MONTHLY OPERATING ACTIVITIES June 1990 HIGHLIGHTS The unit entered the reporting period at 85.5% Rated Thermal Power.

On June 11, 1990, at 1417 hours0.0164 days <br />0.394 hours <br />0.00234 weeks <br />5.391685e-4 months <br />, the unit tripped due to a power range neutron flux high negative rate signal.

The unit was restarted and paralleled to the grid at 1704 hours0.0197 days <br />0.473 hours <br />0.00282 weeks <br />6.48372e-4 months <br /> on June 14, 1990.

Reactor power was increased to 904 RTP at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on June 15, 1990.

A power decrease to 75% Rated Thermal Power was initiated starting 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on June 26, 1990, for cycle extension to the beginning of the refueling outage.

A unit shutdown commenced at 1808 hours0.0209 days <br />0.502 hours <br />0.00299 weeks <br />6.87944e-4 months <br /> on June 29, 1990, for the Cycle 7-8 refueling outage.

The unit was removed from service at 0225 hours0.0026 days <br />0.0625 hours <br />3.720238e-4 weeks <br />8.56125e-5 months <br /> on June 30, 1990.

A cooldown was commenced with the reactor coolant system reaching Mode 4, Hot Shutdown, at 1226 hours0.0142 days <br />0.341 hours <br />0.00203 weeks <br />4.66493e-4 months <br /> on June 30, 1990.

Gross electrical generation for the month of June was 547550 MWH.

DETAILS 06/11/90 1417 06/14/90 0928 1027 1704 06/15/90 2000 06/23/90 2300 06/25/90 0542 06/29/90 1808 06/30/90 0225 0231 0310 1226 Reactor trip due to high negative rate.

Commenced reactor start up.

Reactor is critical.

Paralleled the generator to the grid and commenced unit power increase to 90% RTP.

Unit is at 90< RTP.

Unit is at 904 RTP.

Unit is at. 754 RTP.

Commenced unit power reduction to 04 RTP.

Tripped the main turbine generator.

Unit is in Mode 3.

Opened the reactor trip breakers.

The unit is in Mode.

4

DOCKET NO:

UNIT NAME:

COMPLETED BY:

TELEPHONE:

DATE PAGE:

50-316 D.C. Cook Unit 2 E.C.

Schimmel (616) 465-5901 July 5, 1990 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE June 1990 Replaced the discharge head on the diesel driven fire pump.