ML20136G591

Monthly Operating Rept for Feb 1997 for Fort Calhoun Station

ML20136G591
Person / Time
Site:	Fort Calhoun
Issue date:	02/28/1997
From:	Edwards M, Tills J OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-97-0034, LIC-97-34, NUDOCS 9703180110
Download: ML20136G591 (7)

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Omaha Public PowerDistrict 444 South 16th Street Mall Omaha NE68102-2247 March 14, 1997 LIC-97-0034 U. S. Nuclear Regulatory Commission Attn: Document Control Desk

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Mail Station P1-137 Washington, D.C. 20555 d

Reference:

Docket No. 50-285 4

SUBJECT:

February 1997 Monthly Operating Report (MOR) i Enclosed please find the February MOR for Fort Calhoun Station (FCS)

Unit No.1 as required by FCS Technical Specification 5.9.1.

If you should have any questions, please contact me.

Sincerely, 3 \

J. W. Tills  !

Manager - Nuclear Licensing l

JWT/mle I Enclosures I

c: Winston & Strawn I t J. E. Dyer, Acting NRC Regional Administrator, Region IV L. R. Wharton, NRC Project Manager ,

W. C. Walker, NRC Senior Resident Inspector R. J. Simon, Westinghouse gJ, Agt /

INP0 Records Center 9703180110 970228 E PDR ADOCK 0S000205 lllE$5Ellllllllllll R PDR_.

45.5124 Employment with EqualOpportunny

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t LIC-97-0034 Enclosure Page-1 OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 February 1997 -

Monthly Operating Report

1. OPERATIONS

SUMMARY

During the month of February 1997, the Fort Calhoun Station (FCS) operated at a nominal 100% power level. Normal plant maintenance, surveillance, equipment rotation activities and scheduled on-line modifications were performed and  !

there were no major equipment failures, plant transients or reportable events ,

during the month, b

On . Wednesday, February 26, 1997, Component Cooling Water Heater Exchanger AC-1D, was removed from service for scheduled cleaning and coating. This placed Fort Calhoun Station in a 14 day Limiting Condition for Operation (LCO). Heat Exchanger AC-ID was returned to service on March 7, 1997.

2. SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED During the month of February 1997, no power operated relief valves (PORV) or '

primary system safety valve challenges or failures occurred.

3. RESULTS OF LEAK RATE TESTS The reactor coolant system (RCS) leak rate was steady throughout the month continuing the trend of minimal RCS leakage following the 1996 refueling outage. February daily leak rates were approximately 0.1 to 0.2 gpm.

4. CHANGES. TESTS AND EXPERIMENTS RE0VIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No. Description 180 This amendment revises the Technical Specifications to add a LC0 and Surveillance Test for safety related inverters and deletes the LCO for nonsafety related instrument buses.

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i LIC-97-0034.

Enclosure l

} Page 2 i 5. SIGNIFICANT SAFETY RELATED MAINTENANCE F0F. THE MONTH OF February 1997 Adjusted lift clearance on AC-100-M (Raw Water Pump C Motor)-

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Repacked CH-1B (Charging Pump)

Replaced EE-4N (Inverter "A" Bypass Transformer) 4 Replaced electrolyte withdrawal tubes on EE-8A and EE-8B (125 VDC Station Batteries No.1 & 2)  ;

i Fabricated and installed a new coupling and manual operator on HCV-491A (Component Cooling Water Heat Exchanger AC-10, Inlet Valve)

Replaced two (2) General Electric CR120A relays in the Auxiliary . ~!-

BuildingHVACsystemandone(1)intheContainmentHVACsystem

6. OPERATING DATA REPORT Attachment I

7. . AVERAGE DAILY UNIT POWER LEVEL Attachment II S. UNIT SHUTDOWNS AND POWER REDUCTIONS Attachment III

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9. REFUELING INFORMATION. FORT CALHOUN STATION UNIT N0. 1 Attachment IV i

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. ATTACHMENT I a ,

OPERATING DATA REPORT ,

DOCKET NO. 50-285 UNIT YUfT CALHOUN STATION DATE MARCH 06 1997 COMPLETED BY - M. L. EDWARDS OPERATING STATUS TELEPHONE (402) 533-6929

l. Unit Name: FORT CALHOUN STATION  !

2. Reporting Period: FEBRUARY 1997- NOTES l l

3. Licensed Thermal Power (MWt): 1500 ,

4. Nameplate Rating (Gross MWe): 502_

5. Design Elec. Rating (Net MWe): 478

6. Max. Dep. Capacity (Gross MWe): 502

7. Max. Dep. Capacity (Net MWe): 478 l I

8. If changes occur in Capacity Ratings (3 through 7) since'last report, I give reasons:

N/A l l

9. Power Level to which restricted, if any (Net MWe): N/A

10. Reasons for restrictions, if any: i N/A ,

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THIS MONTH YR-TO-DATE CUMULATIVE I

__________ __________ __________ l

11. Hours in Reporting Period........... 672.0 1416.0 205394.0

12. Number of Hours Reactor was Critical 672.0--- 1416.0 162107.6

13. Reactor Reserve Shutdown Hours...... .0 .0 1309.5

14. Hours Generator On-line............. 672.0 1416.0 160283.8 15' Unit Reserve Shutdown Hours......... .0 .0 .0

16. Gross Thermal. Energy Generated (MWH) 1006966.3 2088725.1 214592605.1

17. Gross Elec. Energy Generated (MWH).. 343746.0 711904.0 70530137.l' ,

18. Net Elec. Energy Generated (MWH).... 328269.3 T7Ff61.2 67665782T~5

19. Unit Service Factor................. 100.0 100.0 78.0

20. Unit Availability Factor............ 100.0 100.0 78.0

21. Unit Capacity Factor (using MDC Net) 102.2___ 100.4 71.1

22. Unit Capacity Factor (using DER Net) 102.2 100.4 69.6

23. Unit Forced Outage Rate............. .0 .0 4.0

24. Shutdowns scheduled over next 6 months (type, date, and duration of each):

NONE

25. If shut down at end of report period, estimated date of startup:

26. Units in test status (prior-to comm. oper.): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION ,

ATTACHMENT II AVERAGE DAILY UNIT POWER LEVEL l

DOCKET NO. 50-285 UNIT FORT CALHOUN STATION DATE ~ MARCH 06,1997 COMPLETED BY M. L. EDWARDS  !

TELEPHONE (402) 533-f929 l MONTH FEBRUARY 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL I (MWe-Net) (MWe-Net) I 1 489 17 489 2 489 18 489 3 489 19 488 4 488 20 488 5 488 21 488 i 6 488 ,_ _

22 488 7 488 23 488 8 489 24 488 9 489 25 488 10 489 26 488 l 11 488 27 488 12 488 28 489 13 489 29 N/A 14 488 30 N/A 15 489 16 489 INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

ATTACHMENT III DOCKET NO. 50-285 .

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Fort Calhoun St.

DATE March 6. 1997 COMPLETED BY M. L. Edwards TELEPHONE (402) 533-6929 REPORT MONTH February 1997

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. TDate5 'Typ~e9

'  :. Duration). ) Reason *U . Method.[of? i: Licensee 2 [$ystem' l Component' lCause &iCorrective'.:i f(Hours)b iShutting) .lEventf (Cods *D (Code 5

.  ? Actiori to l i-Downl~  ; Report).Noi - Prevent- Recurrence.:

- ReactoW None 1 2 3 4 F: Forced Reason: Method: Exhibit F - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File (NUREG-0161)

D-Regulatory Restriction 4-Other (Explain)

E-Operator Training & License Examination F-Administrative 5 H-0ther (Explain) Exhibit M - Same Source (9/77)

Attachment IV Refueling Information Fort Calhoun Station Unit No. 1 Report for the month ending: February 28, 1997

1. Scheduled date for next refueling shutdown. March 21, 1998 l

2. Scheduled date for restart following refueling. May 2, 1998 ll

3. Will refueling or resumption of operations No thereafter require a technical specification change or other license amendment?

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a. If answer is yes, what, in general, will N/A l these be? l

b. If answer is no, has the reload fuel No design and core configuration been reviewed by your Plant Safety Review

, Committee to determine whether any unreviewed safety questions are associated with the core reload?

c. If no such review has taken place, when PrioYtoMay2,1998 is it scheduled?  ;

4. Scheduled date(s) for submitting proposed No submittal required licensing action and support information.

5. Important licensing considerations associated None 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.

6. The number of fuel assemblies:

a) in the core 133 Assemblies b) in the spent fuel pool 662 Assemblies c) spent fuel pool storage capacity 1083 Assemblies

7. The projected date of the last refueling that l can be discharged to the spent fuel pool 2007 Outage I assuming the present licensed capacity. 4 Prepared by: 7 Date: 3hM7 u ' '

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