ML20236W232
| ML20236W232 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/31/1987 |
| From: | Hirsch, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC |
| References | |
| NUDOCS 8712070339 | |
| Download: ML20236W232 (10) | |
Text
..
a N.R.C.
OPERATING DATA REPORT DOCKET NO.
50-315 DATE 11/1/87 COMPLETED BY HIRSCH TELEPHONE 616-465-5901 OPERATING STATUS 1.
Unit Name D.
C.
Cook Unit 1 2.
Reporting Period OCT 87 notes
- 3. Licensed Thermal Power (MWt) 3250 l l
4.
Name Plate Rating (Gross MWe) 1152 :
I 5.
Design Electrical Rating (Net MWe) 1030 l I
6.
Maximum Dependable Capacity (GROSS MWe) 1056 I 7.
Maximum Dependable Capacity (Net MWe) 1020 ----------------- -----
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:________________________________
i This Mo.
Yr. to Date Cumm.
- 11. Hours in Reporting Period 745.0 7296.0 112488.0
- 12. No. of Hrs. Reactor Was Critical 627.9 4536.6 80362.4
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 463.0
- 14. Hours Generator on Line 568.5 4454.8 78773.4
- 15. Unit Reserve Shutdown Hours 0.0 0.0 321.0
- 16. Gross Therm. Energy Gen. (MWH) 1326293 12149878 228782386
- 17. Gross Elect. Energy Gen. (MWH) 411610 3877070 74772940
- 18. Net Elect. Energy Gen. (MWH) 391403 3714971 71912202
- 19. Unit Service Factor 76.3 61.1 71.2
- 20. Unit Availability Factor 76.3 61.1 71.2
- 21. Unit Capacity Factor (MDC Net) 51.5 49.9 63.8
- 22. Unit Capacity Factor (DER Net) 51.0 49.4 61.6
- 23. Unit Forced Outage Rate 3.3 7.9 8.5
- 24. Shutdowns Scheduled over Next Six Months (Type,Date,and Duration):
JL3_ day _.suteJ llante_outane_is..icheda]rd_tJLtentit.on_Anr.il_L_lSE8 ________
- 25. If Shut Down At End of Report Period, Estimated Date of Startup:
Unite ~in~Te$t 5tAtuE~lPhi~E~to CommeEcIAi~UpeEAtI~n5I~~~~~~~~~~~~
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'50-315 i
UNIT ONE DATE 11/1/87 COMPLETED BY HIRSCH TELEPHONE 616-465-5901 MOtiTH OCT 87 AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY POWER LEVEL 1
0 17 499 2
0 18 707 3
0 19 909 4
0 20 916 5
0 21 621 6
76 22 901 7
e 22 23 915 8
244 24 917 9
400 25 917 10 400 26 915 11 395 27 917 12 456 28 909 13 183 29 913 14 362 30 913 15 489 31 916 16 498 l
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DOCKET NO:' 50-315 i
UNIT NAME:
D. C. Cook Unit 1 l
COMPLETED BY:
J. L.-St. Amand i
TELEPHONE:.(616)465-5901 DATE: November 6, 1987 PAGE:
1 of.3 I
MONTHLY OPERATING ACTIVITIES - OCTOBER 1987 I
HIGHLIGHTS:
The. reporting period began with the unit in Mode 3, cooling down to repair a weld leak on the #134 reactor coolant pump seal injection line. The leak
'l was repaired, and RCS heatup continued.
Criticality was achieved, and the turbine-generator paralleled to facilitate turbine heat-soaking prior to~ ov speed testing. The unit was removed from service on 10-7-87 and turbine overspeed testing was begun.
The unit was, returned to service early on 10-8-87.
Following four hours of 4
operation the unit was.once again removed from service to comolete turbine
.?
overspeed testing.
At 0655 on'10-8-87, the generator was again paralleled to the. system and power increased to 48%, where it was held for condenser cleaning.
Following cleaning, power was again increased to 69%.
On 10-13-87, a reactor ~ trip occurred when failure of the shaft-driven control oil pump on the east feedpump caused a feedwater transient resulting in low level in steam generator #11, coincident with steamflow--feedflow-mismatch.
The following day, the unit was returned to service utilizing the west feedpump, and power increased to 54%. Upon the return to service of the east feedpump on 10-18-87, power was increased to 90%.
On 10-21-87 Power was reduced to 54% to permit cleaning storm induced debris from the feedpump condensers.
The A-north and B-south condensers were also cleaned.
Power was increased to 90% on 10-22-87, where it remained throughout the remainder of the reporting period.
Gross Electrical Generation for the month of September was 411,610 MWH.
SUMMARY
t 10-1-87 1545 The reporting period began with the unit in Mode 3.
RCS cooldown was begun to repair a weld leak on the #13 reactor coolant pump seal injection line.
I I
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l 10-2 1630 Began heatup of reactor coolant system following. weld repair.
~ '
10-4-87 1842 The reactor achieved criticality; low power physics testing continues.
'10-6-87 1358 The unit was in Mode 1.
1443 Rolled main turbine.
1543 Paralleled unit, increasing power to 33% for. turbine temperature soak prior to overspeed testing.
10-7-87 0221 Started power decrease to <10% for overspeed testing.
0426 Generator isolated from system (K & K1 breakers opened).
0430 Began overspeed testing.
10-8-87 01g0 Paralleled to system.
0558 Off system for continued overspeed testing.
0655 Paralleled to system, overspeed testing complete.
0848 Power stabilized at 34%.
1245 Began power increase.
1936 Power held at 48%.
10-12-87 0048 Began increasing power.
0545 Power increase halted at 58%, due to report of smoke from beneath insulation on the east feedpump.
0610 East feedpump was removed from service 0646 Started power reduction of approximately 2% to decrease load on west feedpump.
2047 Began power increase, both feedpumps in service.
10-13-87 0505 Power was steady at 69%.
0818 A reactor trip occurred when the east main feedwater pump's A.C. control oil pump was turned off as required by procedure, and the shaft driven pump failed to hold pressure. The decrease in pressure caused the east feedpump discharge valve to close, resulting in a low level in steam generator #11 concurrently with steam flow--feed flow mismatch.
2305 Reactor taken critical.
~
,a 10-14-87 0125 Entered Mode 1.
0330 Unit paralleled to system.
Power at 24%.
L 1330 Power stabilized at 54%; east feedpump out of service.
L 10-18-87 0324 East feedpump returned, power ascension started.
10-19 0230-Power at 90%.
10-21-87 0241 Power reduction started to allow feedpump condenser cleaning.
0830 Power at 55%; feedpump condensers cleared of storm induced debris.
1849 Power ascension commenced.
10-22-87 0530 Power stable at 90%.
10-23-87 16$0 The west essential service water pump was declared inoperable due to failure of the strainer change-over mechanism.
10-25-87 0200 Changed from eastern daylight time to eastern standard time.
10-26-87 1512 The west essential service water pump was returned to operable status._
The reporting period ended with the Unit in Mode 1 at 90% power.
l l
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~-'
DOCKET N0.
50-315
-UNIT NAME D.-C. Cook - Unit No. l' DATE November 6, 1987 COMPLETED BY J. L. St. Amand TELEPHONE (616) 465-5901 PAGE 1 of 2 MAJOR SAFETY-RELATED MAINTENANCE OCTOBER, 1987 M-1 1-WMO-753 (Essential Service Water to Turbine Driven Auxiliary feed Pump Shutoff Valve) required excessive force to operate. The valve was replaced.
The new valve tested satisfactorily.
M-2 1-SV-IA-4 (Steam Generator OME-3-4 Safety Valve #1A) failed Trevi-Test. The valve internals were cleaned and the spindle was replaced. The valve tested satisfactorily.
M-3 1-SV-28-1-(Steam Generator 0ME-3-1 Safety Valve #28) was leaking by.
The valve was repaired and it tested satisfactorily.
M-4 1-SV-1A-l'(Steam Generator 0ME-3-1 Safety Valve #1A) was leaking by.
The' valve was repaired and it tested satisfactorily.
M-5 1-SV-1B-2 (Steam Generator OME-3-2 Safety Valve #1B) was leaking by.
The valve was repaired and it tested satisfactorily.
M-6 1-SV-3-2 (Steam Generator 0ME-3-2 Safety Valve #3) was leaking by.
The valve was repaired and it tested satisfactorily.
I M-7 1-SV-1B-3 (Steam Generator 0ME-3-3 Safety Valve #1B) was leaking by.
The valve was repaired and it tested satisfactorily.
i M-8 1-ESW-101W (West Essential Service Water Pump Discharge Strainer OME-34W Outlet Check Valve) had a badly deteriorated clapper hinge.
The valve internals were replaced. The valve now works properly.
M-9 1-IM0-53 (Boron Injection to Reactor Coolant Loop #3 Shutoff Valve) experienced breaker trips on two successive open attempts. The i
valve operator was rebuilt and it tested satisfactorily.
_ _____o
- f..
4.
-M 1-11PHC2 (Pressurizer Group C1 Back-up Heater 480 VAC Motor Control
. Center PHC-1. Supply Breaker) tripped on pressurizer' level with control switch in the.close position. Replaced control device on breaker 1-11PHC2.
The breaker. now functions properly.
M-11 1-11PHA3'(Pressurizer Group-A2 Back-up Heater 480 VAC Motor Control Center PHA-2 Supply Breaker) tripped on low pressurizer level with
.the control switch in the close position. Replaced control device on breaker 1-11PHA3. The breaker now functions properly.
I&C-1
' The analog rod position indicator for H-4 was found pegged low. The signal conditioner module was found to be defective, requiring.
replacement, and recalibration.
I&C-2 The intermediate range source detector, N-35, was determined to be operating incorrectly. The indication was connected to a spare detector, recalibrates, and performance tested prior to returning'to i
service.
I&C-3 The s, tart-up feedwater flow indicator for steam generator #12 was found failed.
The amplifier board was replaced, and the new board was calibrated and verified to work properly.
1 t
I t
___________w
indiana Ochigan Power Company.
Cook Nuclear Plant P.O. Box 458 8nagman MI 43106 -
616 465 5901
('
fNDfANA l~
AlfC NfG A N H
POWER l
Director, Office Of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D..C.
20555 November 6, 1987 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 October,1987 is submitted.
Sincere'ly, tA.P h 9 Q-W. G. Smith,' Tr.
Plant Manager WGS/jd cc:
J. E. Dolan M. P. Alexich R. W. Jurgensen R. C. Callen C. A. Erikson D. W. Paul D. R. Hahn J. J. Markowsky E. A. Morse PNSRC File INP0 Records Center ANI Nuclear Engineering' Department T. R. Stephens NRC Region III B. L. Jorgensen S. L. Hall D. A. Timberlake EPRI--Nuclear Safety Analysis Center f
js,
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