ML20066D454

Monthly Operating Rept for Sept 1982

ML20066D454
Person / Time
Site:	Cooper
Issue date:	10/06/1982
From:	Ballinger P NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20066D448	List: ML20066D446 ML20066D454
References
NUDOCS 8211110346
Download: ML20066D454 (4)

Text

. 6 OPERATING DATA REPORT DOCKET NO. 050-298 DATE 10-6-82 COMPLETED BY P. L. Ballinger TELEPHONE 40Z-625-3311 OPERATING STATUS Cooper Nuclear Station Notes

1. Unit Name:

2. Reporting Period:

September 1982

3. Licensed Thennal Power (MWt): 2381

4. Nameplate Rating (Gross MWe): 836

5. Design Electrical Rating (Net MWe): 778

6. Maximum Dependable Capacity (Gross MWe): 787 754

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report.Give Reasons:

9. Power Level To Which Restricted.lf Any (Net MWe):

10. Reasons For Restrictions.If Any:

This Month Yr to.Date Cumulative

11. Hours in Reporting Period 720.0 6.551.0 72,336.0

12. Number Of Hours Resetor Was Critical 705.4 5,306.0 59,192.4 0.0 0.0 >

0.0

13. Reactor Reserve Shutdown Hours

14. Hours Generator On.Line 696.5 5,246.7 58,204.2

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1,511,832.0 11,380,032.0 115,068,510.0

17. Gross Electrical Energy Generated (MWH) 503,570.0 _, 3,772,701.0 36,253,488.0 486,715.0 3,651,395.0 34,948,773.0

18. Net Electrical Energy Generated (MWH)

19. Unit Seavice Factor 96.7 80.1 80.5

20. Unit Availability Factor 96.7 80.1 80.5

21. Unit Capacity Factor (Using MDC Net) 88.5 73.0 63.2 62.1 l

22. Unit Capacity Factor (Using DER Net) 86.9 71.6

23. Unit Forced Outage Rate 3.3 3.1 3.9

24. Shutdowns Schedul-d Over Next 6 Months (Type. Date,and Duration of Each1:

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

26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY cl COMMERCIAL OPERATION C'211110346 821006 PDR ADOCK 05000298 toc 7, R FDR

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-298 Cooper Nuclear Station UNIT DATE October 6, 1982 COMPLETED BY P. L. Ballinger t

TELEPHONE 402-825-3811

~

MONTH September DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 764 37 728 2 758 13 729 3 759 39 714 .

4 304 20 728 3 130 728 21 6 493 22 728 7 534 ,3 729 8 639 24 730 9 731 25 743 10 720 700 26 1I 717 ----

27 731 12 698 ;g 751 13 713 29 773 14 705 30 729 694 ___

15 3, 16 725 INSTRUCTIONS On this format. list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77)

+ - t DOCKET NO. 050-298 UNIT SIIUIDOWNS AND POWER REDUCTIONS UNIT N AME Cooper Nuclear Station DATE october 6 1982 P. L. Ballinger COMPLETED BY REPORT MONTil s a m- amk a r TELEPHONE 402-825-3811

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• • Cause & Corrective

, [] E 3j $Y5 Licensee ,E g, g, No. Date i 3g jj$ Event p mU g3 o Action to Prevent Recurrence H

$ 5 3 e @ =g Report e u

o O

NA NA An electronic component in the "A" 82-8 820904 F 23.5 A 3 NA feedwater pump controller shorted out causing the "A" W loop flow to reduce to nearly zero flow. The reactor water level decreased to the trip leve L and the reactor scrammed. The failed component in the W pump controller was replaced and the plant was re-turned to operation.

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' 3 4 1 2 F: Forced Reason: Methtxt: Exhibit G -Instructions A. Equipment Failure (Explain) 1-Manual for Preparation of Data S: Scheduled 2-Manual Scram. Entry Sheets for Licensee n-Meintenance or Test C-Refueling 3 Automatic Scram. Event Report ILER) Fde t N1IRIT;-

D Regulatory Restriction 4-Other (Explain) 0161) l E-Operator Training & License Examination -

F Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source l')/77 ) Il-Other (Explaini -

l

e - g*

Attachment B OPERATIONS NARRATIVE Cooper Nuclear Station September 1982 The plant operated the month of September with only one unscheduled shutdown. On September 4, 1982, an electronic component in the "A" feedwater pump control system failed causing the "A" FW loop flow to drop to nearly zero flow. Reactor water level decreased to the trip level and the reactor scrammed. Although the "B" FW automatically increased its flow to compensate for the loss of the "A" FW loop flow, it was insufficient to prevent the reactor scram. The failed component in the FW control system was replaced and the plant was returned to operation.

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