ML20134M428

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Monthly Operating Rept for Jan 1997 for Fort Calhoun Station Unit 1
ML20134M428
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 01/31/1997
From: Edwards M
OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20134M424 List:
References
NUDOCS 9702200239
Download: ML20134M428 (6)
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LIC-97-0021 Page 1 OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 JANUARY 1997 Monthly Operating Report 1.

OPERATIONS

SUMMARY

The Fort Calhoun Station (FCS) was at 30% of rated power on January 1, 1997 following the steam leak repairs on the orifice downstream of MOV-CV that occurred on December 31, 1996. At 2338 hours0.0271 days <br />0.649 hours <br />0.00387 weeks <br />8.89609e-4 months <br /> on January 1, 1997, FCS began to increase power after clearing a hold for Steam Generator chemistry. The Station reached 100% of rated power at 2053 hours0.0238 days <br />0.57 hours <br />0.00339 weeks <br />7.811665e-4 months <br /> on January 2,1997 and continued to operate at a nominal 100%

power level for the remainder of the rc.onth,.

As a result of the Millstone Unit 2 Licensee Event Report (LER), which reported a problem with the failure to account for steamline pressure drops in the calculation of the Main Steam Safety Valve (MSSV) setpoints, OPPD investigated if similar issues existed at FCS. Although it was determined on January 22, 1997 that MSSV chatter is not an issue at FCS, it was concluded that the number and location of inoperable MSSVs allowed by FCS Technical Specifications could have placed the plant outside of its design basis.

OPPD is performing the necessary analyses to update the design basis of the plant and is providing additional guidance to the operating staff to ensure that the revised design basis is maintained.

See LER 97-001 for additional details.

2.

SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED During the month of January 1997, no power operated relief valve (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. January daily leak rates were constant at approximately 0.1 to 0.2 gpm.

9702200239 970214 PDR ADOCK 05000205 R

PDR

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'LIC-9'7-0021 Page 2 4.

CHANGES. TESTS AND EXPERIMENTS RE0VIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No.

Description None 5.

SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF JANUARY 1997 i

Adjusted level indication on Diesel Generator No. 2 (DG-2) fuel oil day tank Replaced battery pack and calibrated DG-2 Fuel Oil Rotary Meter FE-2122 Replaced battery pack and calibrated DG-1 Fuel Oil Flow Indicator i

FE-2123 Replaced Solenoid Valve HCV-474-20 per ECN 95-369 Replaced Breaker MCC-3A2-F02 per ECN 96-356 Replaced transmitter on Radiation Monitor RM-062 Replaced Raw Water Pump AC-10B Discharge Check Valve RW-121 Troubleshot, removed, and replaced the compressor for Control Room Air Conditioning Unit VA-46A Replaced racking mechanism parts on Breaker Unit 184A-5 (Screen Wash Pump CW-3B; Feed to Local Contactor)

Replaced GE CR120 relay on 94B/PE-5A (control relay for HCV-2899A/B/C/0) 6.

OPERATING DATA REPORT Attachment I 7.

AVERAGE DAILY l' NIT POWER LEVEL i

Attachment II 8.

UNIT SHUTDOWNS AND POWER REDUCTIONS Attachment III 9.

REFUELING INFORMATION. FORT CALHOUN STATION UNIT NO. 1 Attachment IV

_ _ _ _. ~ _. _ _ _ _

ATTACHMENT I OPERATING DATA REPORT DOCKET NO.

50-285 UNIT FORT CALHOUN SfXTION l

DATE FEBRUARY _ 10,1997 J

COMPLETED BY M. L.

EDWARDS i

OPERATING STATUS TELEPHONE 402-533-6929

1. Unit Name:

FORT CALHOUN STATION

2. Reporting Period:

JANUARY 1997 NOTES

]

3. Licensed Thermal Power (MWt): 1500_
4. Nameplate Rating (Gross MWe):

502

5. Design Elec. Rating (Net MWe):

478_

j

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

502 1

l

7. Max. Dep. Capacity (Net MWe):

478

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

l N/A l

9. Power Level to which restricted, if any (Net MWe): N/A j
10. Reasons for restrictions, if any:

1 l

N/A THIS MONTH YR-TO-DATE CUMULATIVE

11. Hours in Reporting Period...........

744.0 744.0 204722.0

12. Number of Hours Reactor was Critical 744.0 744.0~-

161435.6

13. Reactor Reserve Shutdown Hours......

.0

.0 1309.5 y

14. Hours Generator On-line.............

744.0

_744.0 159611.8

15. Unit Reserve Shutdown Hours.........

.0

.0

.0

16. Gross Thermal Energy Generated (MWH) 1081758.8 1081758.8 213586T38.8 l
17. Gross Elec. Energy Generated (MWH)..

368158.0 368158.0 70586391.1

18. Net Elec. Energy Generated (MWH)....

~i513s1.9 351391.9 67317513.2 l

19. Unit Service Factor.................

100.0 100.0 78.0 l

20. Unit Availability Factor............

100.0 100.0 78.0 l

21. Unit Capacity Factor (using MDC Net) 98.8 98.8 71.0 l
22. Unit Capacity Factor (using DER Net) 98.8 98.8 69.5
23. Unit Forced Outage Rate.............

.0

.0 4.0 l

L

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

N/A l

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

(-

26. Units in test status (prior to comm. oper.):

Forecast Achieved i

INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION

. -. _ _ - ~ -. -.

i ATTACHMENT II

. AVERAGE DAILY UNIT POWER LEVEL f

i DOCKET NO.

50-285 UNIT FORT CALHOUN STATION DATE FEBRUARY 10,1997 COMPLETED BY M.

L.

EDWARDS TELEPHONE 402-533-6929 MONTH JANUARY 1997 1

1 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL-(MWe-Net)

(MWe-Net) 1 106 17 488 l

l 2

367 18 489 I

i 3

487 19 489 4

488 20 489 5

489 21 489 6

489 22 489 7

489 23 489 8

489 24 489 4

9 489 25 488 i

j 10 489 26 488 11 489 27 489 12 489 28 488 13 488 29 489 14 488 30 489 15 488 31 489 3

16 488

' INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each j

day in the reporting month.

Compute to the nearest whole megawatt.

i

.._...._.m__.___.._

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ATTACHMENT III DOCKET N0. 50-285 UNIT-SHUTDOWNS AND POWER REDUCTIONS UNIT.NAME Fort Calhoun St.

DATE February 10. 1997-COMPLETED BY M. L. Edwards TELEPHONE (402) 533-6929 i

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REPORT MONTH January 1997 l

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- Exhibit -F - Instructions

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S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data l

B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File (NUREG-0161) f D-Regulatory Restriction 4-Other (Explain) i E-Operator Training & License Examination F-Administrative 5

l H-Other (Explain)

Exhibit H - Same Source

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l Attachment IV Refueling Information Fort Calhoun Station Unit No. 1 Report for the month ending: January 31. 1997 1.

Scheduled date for next refueling shutdown.

March 21, 1998 ll 2.

Scheduled date for restart following refueling.

May 2, 1998

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3.

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

a.

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

l b.

If answer is no, has the reload fuel No l

design and core configuration been l

reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload?

1 c.

If no such review has taken place, when Prior to May 2,1998 is it scheduled?

4.

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

l 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.

l 6.

The number of fuel assemblies-l a) in the core 133 Assemblies l

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 assuming the present licensed capacity.

l Date:

2//oN 7 4, M Prepared by:

i I

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