ML17328A888

Monthly Operating Rept for Dec 1990 for Donald C Cook Nuclear Plant

ML17328A888
Person / Time
Site:	Cook
Issue date:	12/31/1990
From:	Blind A, Schimmel E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9102080108
Download: ML17328A888 (14)

Text

ÃOHB 2 REGULATOiINFORMATION DISTRIBUTION 03TEM (RIDE)

ACCESSION NBR:9102080108 DOC.DATE: 90/12/31 NOTARIZED:

NO DOCKET FACIL:50-316 Donald C.

Cook Nuclear Power Plant, Unit 2, Xndiana 05000316 AUTH.NAME AUTHOR AFFILIATION SCHIMMEL,E.C.

Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele BLIND,A.A.

Indiana Michigan Power Co. (formerly Indiana a Michigan Ele RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

Monthly operating rept for Dec 1990 for Donald C Cook Nuclear Plant.W/900104 ltr.

DISTRIBUTION CODE'FOID COPIES RECEIVED'LTR L ENCL 2 SIZE'ITLE:

Direct Flow Distribution:

50 Docket (PDR Avail)

NOTES:

RECIPIENT ID CODE/NAME INTERNAL: NUDOCS-ABSTRACT EXTERNAL: NRC PDR COPIES LTTR ENCL 1

1 1

1 RECIPIENT ID DE/NAME REG FILE 01 COPIES LTTR ENCL 1

1 1

1 TOTAL NUMBER OF COPXES REQUIRED:

LTTR 4

ENCL 4

Indiana Michigan Power Company Cook Nuclear Plant One Cook Place Bridgrnan, Ml 49106 616 465 5901 January 4,

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 December 1990 is submitted.

Respectfully, 8 &e A.A. Blind Plant Manager Attachment c:

NRC Region III D.R.

Hahn EPRI Nuclear Safety Analysis Center R.C. Callen S.L. Hall J.G. Keppler INPO Records Center ANI Nuclear Engineering Department D.H.'illiams, 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 E. C.

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OPERATING DATA REPORT DOCKET NO.

50-316 DATE 03-Jan-91 COMPLETED BY WT GILLETT TELEPHONE 616-465-5901 OPERATING STATUS

1. Unit Name D.

C.

Cook Unit 2

2. Reporting Period DEC,90

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 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 744.0 8760.0 621.0 4958.9 0.0 0.0 582.3

'856.4 0.0 0.0 1887935 15289163 621030 4990730 599299 4813309 78.3 55.4 78.3 55.4 76.0 51.8 73.2 50.0 21.7 10.8 Months (Type, Date,and Cumm.

113952.0 75134 F 9 0.0 73585.9 0.0 226167053 73786840 71058967 65.9 65.9 60.1 58.5 13.6 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 NOTE:

The NRC Report for December 1990, lines 12, 14, 19 and 20 for the Year to Date and Cumm.

columns has been corrected for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> error made in November 1990.

AVERAGE DAILY POWER LEVEL (MWe-Net)

DOCKET NO.

50-316 UNIT TWO DATE 03-Jan-91 COMPLETED BY WT GILLETT TELEPHONE 616-465-5901 DAY 1

2 3

4 5

6 7

8 9

10 11 12'3 14 15 16 MONTH AVERAGE DAILY POWER LEVEL 1091 1090 1092 1095 1093 1091 1'094 1091 1088 1085 1093 152 0

226 547 0

DEC,90 DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 AVERAGE DAILY POWER LEVEL 0

0 0

418 979 923 1031 1033 1088 1098 1097 1093 1095 1094 1094

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UNIT SHIJXKNNS AND H3HER REIXJGTIONS REEORT MDNIH:

December 1990 DOCKEZ NO UNIT NAME:

DATE:

OGMPL'EHB BY:

TEIEEKNE:

PAGE 1 OF 2 50-316 D.C.

COOK UNZl' January 4, 1990 E.C. Sctdzanel (616) 465-5901 MEIHOD OF SHVITING LZCENSEE IX3HATION KNN EVENT SYSTEM KMKNEÃZ CAUSE AND KBRECXXVE ACTION I0 NO.

DATE TYPE BXRS REASON REACIOR REEORP NO.

CODE CDDE PREVENT RECUHRENCE 210 12/12/90 F

54.1 90-012-00

%he unit tripped fram 100% RIP at 0318 hours0.00368 days <br />0.0883 hours <br />5.257936e-4 weeks <br />1.20999e-4 months <br /> on 901212, due to the mal of the west main feedwater pump bearing wear detection device. lhe thrust bearing wear detector was repaired.

%he unit was returned to service at 0925 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br /> on 901214.

211 12/15/90 F

107.6 A

90-013WO A reactor shutdown per Technical Specification 3.8.2. 3 action statanent was initiated at 1245 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.737225e-4 months <br /> on 901215 due to 2-AB battery being inoperable.

During the shutdown a unit trip from 38% RIP occurred due to an AMSAC system initiation.

(continued on next page) 1 2

F:

Forced Reason:

S:

Scheduled A:

Equipment Failure (Explain)

B:

Maintenance or Test C:

Refueling D:

Regulatory Restriction E:

Operator Training and License Ihazdnation F:

Administrative G:

Operational Error (Explain)

H:

Other (Explain) 3 Method:

1:

Manual 2:

Manual Scram 3:

Automatic Scram 4:

Other (Explain) 4 5

Exhibit G Instructions Exhibit I:

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

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UNIT SHUl'DOWNS AND PONER REIXJCZIONS REFORZ K51H:

Decen9mr 1990 DOQKT NO:

UNIT NAME:

DATE:

CG51PUHKD BY:

TEXZZ%iONE'AGE 2 OP 2 50-316 D.C.

COOK UNIT 2 January 4, 1990 E.C. Schimmel (616) 465-5901 M IHOD OF SHVITING IZCEZSKZ IXJRATIQN IXNN EVENT TYPE HOURS RFASON REACIOR REEOIK M.

SYSTEH COMK5ENI'AUSE AND CORRECTIVE ACZIQN TO CODE CODE BLENT RECGKKNCE 211 12/12/90 (continued)

She 2-AS ba~ was declared inoperable due to a greater than allowable dern -ue in an individual ~

cell voltage. 'Ihe battery was ~red to operable condition by electrically removing the cell fram the battery.

Investigation of the AMSAC system revealed that the feedmter lcm f le trip was set to an incorrect setpoint.

9he AMSAC system was recalibrated to the correct setpoint and declared operable.

Cbe unit was returned to service at 0237 hours0.00274 days <br />0.0658 hours <br />3.918651e-4 weeks <br />9.01785e-5 months <br /> on 901220.

1 2

F:

Forced Reason:

S:

Scheduled A:

Equipment Failure (Explain)

B:

Maintenance or Test C:

Refueling D:

Regulatory Restriction E:

Operator Training and Lice'xamination F:

Administrative G:

Operational Error (Explain)

H:

Other (Explain) 3 Method:

1:

Manual 2:

Manual Scram 3:

Autamatic Scram 4:

Other (Explain) 4 5

Exhibit G Instructions Exhibit I:

Same Source for preparation of data entry sheets for Licensee Event Report (IZR) Pile (NURHG 0161)

DOCKET NO:

UNIT NAME:

COMPLETED BY:

TELEPHONE:

DATE'AGE 50-316 D.C.

Cook Unit 2 E. C. Schimmel (616) 465-5901 January 4,

1991 1 of 3

MONTHLY OPERATING ACTIVITIES December 1990 HIGHLIGHTS The unit entered the reporting period at 100% Rated Thermal Power.

The unit tripped at 0318 hours0.00368 days <br />0.0883 hours <br />5.257936e-4 weeks <br />1.20999e-4 months <br /> on December 12, 1990 due to low feedwater flow coincident with low level on steam generator loop 4.

The low feedwater flow condition was caused by a trip of the west main feedpump turbine due to a false initiation of the feedpump turbine thrust bearing wear detection device.

The unit was returned to service at 0925 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br /> on December 14, 1990.

100%

Rated Thermal Power was reached at 0825 hours0.00955 days <br />0.229 hours <br />0.00136 weeks <br />3.139125e-4 months <br /> on December 15, 1990 '

forced unit shutdown commenced beginning 1245 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.737225e-4 months <br /> on December 15, 1990 due to the AB train battery being inoperable.

The reactor tripped during the shutdown due to an incorrect AMSAC system initiation. The unit was brought to Mode 5, cold shutdown.

The reactor was returned critical At 0525 hours0.00608 days <br />0.146 hours <br />8.680556e-4 weeks <br />1.997625e-4 months <br /> on December 18, 1990.

The reactor was shutdown at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on December 18, 1990 to allow repair of the containment sump system.

The unit remained in mode 3 for containment sump system repairs.

The main generator was paralleled to the grid at 0237 hours0.00274 days <br />0.0658 hours <br />3.918651e-4 weeks <br />9.01785e-5 months <br /> on December 20, 1990.

The unit reached 1004 Rated Thermal Power at 0133 hours0.00154 days <br />0.0369 hours <br />2.199074e-4 weeks <br />5.06065e-5 months <br /> on December 25(

1990.

Gross electrical generation for the month of July was 621030 MWH.

DETAILS 12/12/90 0318 The reactor tripped due to low feedwater flow coincident with low level on steam generator

¹4.

12/13/90 1111 1147 12/14/90 0607 0925 12/15/90 0825 1245 1501 Commenced reactor startup.

The reactor is critical.

The unit is in Mode 1.

The main generator is paralleled to the system grid'he unit is at 100% Rated Thermal Power.

Commenced unit shutdown due to the AB battery being inoperable.

The reactor tripped at approximately 38% Rated Thermal Powe& due to an incorrect AMSAC system initiation.

Monthly Operating Activities - December 1990 page 2 of 3 12/15/90 1912 12/16/90 0014 0600 12/17/90 0330 0748 12/18/90 0430 0525 Commenced RCS cooldown to Mode 5.

The RCS entered Mode 4.

The RCS entered Mode 5.

Commenced RCS heatup to Mode 3.

The RCS is in mode 3.

Commenced reactor startup.

The reactor is critical.

1426 1530 Commencea reactor shutdown to allow repair of containment sump system.

The RCS entered Mode 3.

12/19/90 1851 1934 2144 12/20/90 0237 0245 1110 1230 12/21/90 0412 2115 2155 Commenced reactor startup.

The reactor is critical.

The reactor entered Mode l.

The main generator is paralleled to the system grid.

Commenced unit power increase to 484 Rated Thermal Power.

The unit is holding at 48% Rated Thermal Power for calorimetrics testing and quadrant power tilt ratio stabilization.

Commenced unit power increase to 954 Rated Thermal Power'.

The unit is it 95% Rated Thermal Power.

Commenced unit power reduction due to a misaligned control rod.

The misaligned control rod is within specification.

Stopped unit power reduction at 764 Rated Thermal Power.

Monthly Operating Activities December 1990 page 3 of 3

12/22/90 0420 12/22/90 1735 12/24/90 1600 12/25/90 0133 Commenced unit power increase to 95% Rated Thermal Power.

The unit is at 954 Rated Thermal Power.

Placed moisture separator reheaters in service.

The unit is at 1004 Rated Thermal Power.

DOCKET NO'NIT NAME:

COMPLETED BY:

TELEPHONE:

DATE:

PAGE:

50-316 D.C.

Cook Unit. 2 E.C.

Schimmel (616) 465-5901 January 4,

1990 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE December 1990 There were no major safety-related maintenance items during the month of December.

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