ML20236W001
| ML20236W001 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/31/1987 |
| From: | Hirsch, Will Smith, St Amand J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC |
| References | |
| NUDOCS 8712070216 | |
| Download: ML20236W001 (8) | |
Text
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4 N.R.C. OPERATING DATA REPORT DOCKET NO.
50-316 DATE 11/1/87
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COMPLETED BY HIRSCH TELEPHONE 616-465-5901 OPERATING STATUS
- 1. Unit Name D. C. Cook Unit 2
- 2. Reporting Period OCT 87 inotes
- 3. Licensed Thermal Power (MWt) 3411 l l
- 4. Name Plate Bating (Gross MWe) 1133 l l
- 5. Design Electrical Rating (Net MWe) 1100 l l
- 6. Maximum Dependable Capacity (GROSS MWe) 1100 l l
- 7. Maximum Dependable Capacity (Net MWe) 1060 -----------------------
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.
l
- 11. Hours in Reporting Period 745.0 7296.0 86184.0 l
- 12. No. of Hrs. Reactor Was Critical 502.5 4819.1 59408.4
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator on Line 493.7 4787.6 58030.9
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Therm. Energy Gen. (MWH) 1258092 12495379 178186583
- 17. Gross Elect. Energy Gen. (MWH) 399260 3964820 58182860
- 18. Net Elect. Energy Gen. (MWH) 380860 3787064 56021900
- 19. Unit Service Factor 66.3 65.6 69.3
- 20. Unit Availability Factor 66.3 65.6 69.3
- 21. Unit Capacity Factor (MDC Net) 48.2 49.0 63.1
- 22. Unit Capacity Factor.(DER Net) 46.5 47.2 61.6
- 23. Unit Forced Outage Rate 0.0 22.9 15.4
- 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 i
l 871200216B{hSb316 1
ADOCK PDR gDR Q
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DOCKET NO.
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0 17 634 2
0 18 845 3
0 19 843 4
0 20 839 5
0 21 841 6
0 22 848 7
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0 24 843 9
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DOCKET.N0:
50-316 UNIT NAME:
D.C. Cook Unit 2 COMPLETED BY:
J. L. St. Amand TELEPHONE:
(616) 465-5901 DATE:. November 6, 1987 PAGE:
1 of 2 MONTHLY OPERATING ACTIVITIES - OCTOBER 1987 HIGHLIGHTS i-The unit entered the reperting period in Mode 5 with the RCS drained to half-loop level.
Heat-up of the RCS was delayed due to both non-essential service water pumps being out of service.
On October 2,1987, a safety injection signal was initiated during repairs to the solid state protection system. No actuation occurred.
In an unrelated event, a_ reactor trip / turbine trip signal was generated during the power range surveillance. Both events were attributed to personnel error.
The reactor was taken critical on 10-10-87, and the turbine rolled. A reactor-
. trip' from turbine trip occurred when the turbine was at approximately 1500 RPM. No cause could be identified.
The unit was restarted, and the generator paralleled to the system on 10-11-87.
Power was increased to 80%, and held until 10-17-87, when a reduction began to allow condenser cleaning.
Power was reduced to 55%.
Following cleaning, the power was increased to 80%.
On 10-27-87, due to excessive leakage through the pressurizer spray valves, power was reduced to 20% to allow entry and investigation. The problems were identified and resolved, regaining normal pressurizer pressure control.
The unit was returned to 80% power on 10-29-87, where it remained through the end of the reporting period, i
Gross Electrical Generation for the month of September was 399,260 MWH.
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1
SUMMARY
j i
10-01-87 0000 The unit entered the reporting period in Mode 5 with the 1
RCS drained to half-loop level.
j 10-2-87 1658 A train "A' safety injection signal was initiated when the solid state protection system (SSPS) was being returned to
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service following a repair.
No injection occurred.
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Immediate corrective action was taken, j
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10-3-87 1350 Began reactor coolant system fill and vent process, followed by RCS heatup.
i i
10-8-87 2328 A reactor trip / turbine trip signal was generated due to a personnel error during the nuclear instrumentation power range surveillance.
10-10-87 0152 The reactor was taken critical.
l-1213 A reactor trip from turbine trip occurred with the. turbine at approximately 1500 RPM.
No cause could be identified for the reactor trip.
10-11-87 0535 The reactor was taken critical.
1118 The generator was paralleled to the system.
10-13-87 0145 Power increase was halted at the 80% administrative power limit.
10-17-87 0100 '
A' power reduction was begun to allow condenser cleaning.
Power was reduced to 55%, and both feedpump condensers were cleaned, along with main condenser halves "A"-South and "B"-North.
2045' Reactor power was returned to 80%.
10-27-87 1900 A power reduction was started to allow resolution of the pressurizer spray valve leakage.
10-28-87 0510 The reactor power decrease halted at 20%.
1210 Troubleshooting showed the valve positioner to be malfunc-tioning, so the control air to NRV-163 was isolated.
NRV-164 was returned to service, by unisolating the 85 psi control air, establishing normal pressurizer pressure control.
l 1302 Power increase started.
10-29-87 0628 Power stabilized at 80%.
The reporting period ended with the unit in mode 1 at 80% power.
l
I DOCKET N0.
50-316 UNIT NAME D.C. Cook-Unit No. 2 DATE November 6, 1987 COMPLETED SY J. L. St. Amand TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE OCTOBER, 1987 M-1 2-VCR-20 (Ice Condenser Refrigeration Glycol Return Header Train 'A' containment Isolation Valve) would not open. The diaphragm was replaced. The valve now functions properly.
I&C-1 During restoration of the solid state protection system, the "A"-train undervoltage board was found to be defective, failing to initiate an undervoltage trip. The board was replaced and surveil-lance tested before returning to operability.
I&C-2 A steam generator level alarm bistable (2LB-517 A/B) was found to be defective during calibration. The bistable was replaced, recali-brated, and surveillance tested before returning to service.
ladiana Cichigan J;#
Power Company.
Cook Nucleaf Plant P0. Box 458 -
Bndgman. MI 49106 616 465 5901 DNDCANA AIDCNfGAN l
powra 1
Director, Office Of Management Information and Program Control V. S. Nuclear Regulatory Commission Washington, D. C.
20555 November 6,1987 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 October,1987 is submitted.
Sincerely, bW. G. Smith r.
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
//
- 5. L. Hall
/
D. A. Timberlake
<d @
EPRI--Nuclear Safety Analysis Center M
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