ML20207S217

Monthly Operating Rept for Feb 1987

ML20207S217
Person / Time
Site:	Fort Calhoun
Issue date:	02/28/1987
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-87-156, NUDOCS 8703190142
Download: ML20207S217 (8)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun Station DATE March 11, 1987 COMPLETED BY T. P. Matthews .

TELEPHONE 402-536-4733 MONTH February. 1987 DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Neti I 488.9 37 489.4 2 488.7 ,g 4g9 3 488.5 3 19 489.6 4 488.4 20 489.6 5 488.5 21 489.6 .

400*O 6 22 489.5 7 ARR 7 23 489.4 8 488.5 24 489.3 9 488.3 489.4 25 to 488.0 26 489.4 11 490.2 27 489.9 12 488.3 490.2 28

,3 489.1 14 488.8 39 15 489.5 3, 16 A89 a INSTRUCTIONS On this format.itst the average daily unit power Icvel in MWe. Net for each darin the reporting month. Compute to j the nearest whole megawatt.

(9/77 )

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8703190142 870228 5 DR ADOCK 0500

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OPERATING DATA REPORT DOCKET NO. 50-285 DATE March 11, 1987 COMPLETED BY T. P. Matthews.

TELEPIIONE an? R E d733 OPERATING STATUS Fort Calhoun Station Notes

1. Unit Nam'e:

2. Reporting Period: February, 1987 1500

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe): 502

5. Design Electrical Rating (Net MWe): 478

6. Maximum Dependable Capacity (Gross MWe): Gn?

7. Maximum Dependable Capacity (Net MWe): 47A

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

N/A

9. Power Level To Which Restricted,If Any (Net MWe): N/A

10. Reasons For Restrictions. lf Any: None This Month Yr.-to-Date Cumulative i1. Hours in Reporting Period 672.0 1.416.0 117,722.0

12. Number Of Hours Reactor Was Critical 672.0 1,416.0 91,647.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5

14. Hours Generator On-Line 672.0 1.416.0 90,803.1

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1,003,666.7 2,082,703.2 117,133,205.1 .

17. Gross Electrical Energy Generated (MWH) 343.21810 , 711,068.0 38,477,794.2

18. Net Electrical Energy Generated (MWH) 328,670.5 680,402.5 36,763,863.4

19. Unit Service Factor 100.0 100.0 77.1

20. Unit Availability Factor 100.0 100.0 77.1

21. Unit Capacity Factor (Using MDC Net) 102.3 100.5 67.6

22. Unit Capacity Factor (Using DER Net) 102.3 100.5 65.6

23. Unit Forced Outage Rate 0.0 0.0 3.3

24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Eacht:

The 1987 ' Refueling Shutdown commenced on March 7,1987 with startup tentatively scheduled for May 26, 1987.

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

26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

DOCKET NO. 50-285 -

UNITSHUTDOWNS AND POWER REDUC 110NS UNIT NAME Fort Ca houn Station DATE March 1 L, 1987 REPORT MONTit February, 1987 COMPLETED 8Y T.P. Matthews TELEPHONE 402-536-4733 1

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, .! ? "h jY5 Licensee ,Ev.

$"',8 Cause & Corrective No. Date o- 3g s ,5 g 5 Event gg o. Action to H

$E $ j5g Report a mU fU Prevent Recurrence 6

There were no unit shutdowns or power reductions during the month

! of February, 1987.

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l 2 3 4 y F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-

. D-Regulatory Restriction 4 Other (Explain) 0161) l E-Operator Training & License Examination F Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source (9/77) Il-Other (Explain)

. Refueling Information Fort Calhoun - Unit No. 1 Report for the month ending February 1987 .

1. Scheduled date for next refueling shutdown. March 1987

2. Scheduled date for restart following refueling. May. 1987

3. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes

a. If answer is yes, what, in general, will these be?

Fuel supplier change from ENC to CE and possible Technical Specification change.

b. If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to deter-mine whether any unreviewed safety questions are associated with the core reload.

c. If no such review has taken place, when is it scheduled?

4. Scheduled date(s) for submitting proposed licensing action and support information. January, 1987

5. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

New fuel supplier (Combustion Engineering) but the new fuel will be essentially the same as that supplied by Combustion Engineering for Cycle 5.

6. The number of fuel assemblies: a) in the core 133 assemblies l

b) in the spent fuel pool 349 "

c) spent fuel pool storage capacity 729 "

d) planned spent fuel pool May be increased "

storage capacity via fuel ein "

consolidation

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1996 Prepared by Date February 25, 1987

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 February, 1987 Monthly Operations Report I. OPERATIONS

SUMMARY

fort Calhoun Station operated at 100% power throughout February,1987.

Receipt and inspection of new fuel and CEA's were completed. Preparation and planning for the 1987 refueling and maintenance outage continued.

Temporary staffing increased during February to support the outage.

Overhaul of circulating water pump CW-lC was started in February. One shipment of waste was sent offsite containing two solidified concentrate liners and 16 drums of other waste. Two additional waste concentrate liners were solidified in February.

Training continued for Equipment Operator Nuclear-Turbine Building and the four member SR0 upgrade class. In addition, refresher training continued for nonlicensed operators. Simulator training in Windsor, Connecticut, at the Combustion Engineering PWR training facility was completed during February.

No safety valves or PORV challenges or failures occurred.

A. PERFORMANCE CHARACTERISTICS None B. CHANGES IN OPERATING METHODS None C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-LI0H-1 Lithium Hydroxide Moisture Carryover Test.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only involved conducting a steam generator moisture carryover test to determine the actual steam quality of the steam leaving the steam generators.

Monthly Operations Report February, 1987 Page Two D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)

System Acceptance Committee Packages for February, 1987:

Packaae Descriotion/ Analysis EEAR FC-85-202 Service Air Connection Near Railroad Siding.

This modification provided for service air to Corridor 26 and the railroad siding area. This modification does not have an adverse effect on the safety analysis.

EEAR FC-86-089 AFW-15 Removal .

This modification provided for the removal of support AFW-15 from Room 81. This modification does not have and adverse effect on the safety analysis.

E. RESULTS OF LEAK RATE TESTS The biannual containment PAL door leak rate test was completed during the month of February per ST-CONT-2. The total leakage for the PAL door was found and left at 0 sccm.

The "B" and "C" leak rate total of 8,543 sccm has not been affected, and is well below the allowed leakage of .6 La as specified in 10 CFR 50 Appendix J.

The next scheduled "B" and "C" leak rate tests are to be completed during the 1987 refueling outage.

F. CHANGES IN PLANT OPERATING STAFF None.

G. TRAINING Training continued for Equipment Operator Nuclear-Turbine Building and the four member SR0 upgrade class. In addition, refresher training continued for nonlicensed operators. Simulator training at the Combustion Engineering PWR training facility in Windsor, l Connecticut, was completed during February. ,

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Monthly Operations Report February,_1987 Page Three H .' ' CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 None s

II. MAINTENANCE (Significant Safety Related)

None W. Y W. Gary Gates Manager-Fort Calhoun Station l

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Omaha Public Power District 1623 Harney Omaha. Nebraska 68102-2247 402/536 4000 March 13, 1987 LIC-87-156 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285

SUBJECT:

February Monthly Operating Report Gentlemen:

Pursuant to Technical Specification Section 5.9.1, and 10 CFR Part 50.4(b)(1),

please find enclosed one copy of the February,1987 Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

Sincerely, W

R. L. Andrews Division Manager Nuclear Production RLA/me Enclosures cc: NRC Regional Office Office of Management & Program Analysis (2)

R. M. Caruso - Combustion Engineering R. J. Simon - Westinghouse Nuclear Safety Analysis Center INP0 Records Center American Nuclear Insurers NRC File (FCS) d f

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