ML20034H264
| ML20034H264 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 02/28/1993 |
| From: | Edwards M OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20034H263 | List:
|
| References | |
| NUDOCS 9303160295 | |
| Download: ML20034H264 (8) | |
Text
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U. S. Nuclear Regulatory Commission LIC-93-0090 1
F ENCLOSURE 1 FEBRUARY 1993 MOR E
9303160295 930312 PDR ADOCK 05000285 R
OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 February 1993 Monthly Operating Report 1.
OPERATIONS
SUMMARY
During most of February 1993, Fort Calhoun Station operated at a nominal 100% power level. Late in the month, power was decreased to approximately 98% to maintain the peak linear heat rate (PLHR) at less than 90% of the maximum allowed value of 14.4 kw/ft.
This was performed because a reduction to less than 80% power would be required by Technical Specification 2.10.4(1)(b)(i) if the Emergency Response Facility Computer was lost and the PLHR was above 90% of the maximum allowed value.
No NRC inspections were completed during this reporting period.
The following LERs were submitted during this reporting period:
LER No.
Description 91-007 R1 480V Circuit Breaker Coordination Outside Design Basis92-031 R1 Inoperability of Fire Suppression Water System 93-001 Failure to Satisfy Surveillance Requirement for Boric Acid Tank Level Check 93-002 Inappropriate Steam Generator low Signal Block Reset Value 93-003 Failure to Satisfy Inservice Testing Requirement for Raw Water Pump 2.
SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED There were no safety valve or PORV challenges or failures during this reporting period.
3.
RESVLTS OF LEAK RATE TESTS The total leak rate averaged less than 0.250 gpm for the month of February. On February 9, the total leak rate increased to 0.282 gpm; then on February 10, it increased again to 0.550 gpm. The increase was due to a failure of the packing in Charging Pump CH-1A. The packing was replaced and the leak rate returned to normal.
Currently, the leak rate remains steady.
The leak rate has increased somewhat during the cycle, but the increase is equivalent to that i
experienced during previous cycles.
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Monthly Operating Report February 1993 Page Two 4.
CHANGES. TES"S AND EXPERIMEN"S REQUIRING NUCLEAR REGULATORY COMMISSIOR AUTHORIZATIOb PURSUANT TO 100 :R50.59
)
Amendment No.
Description i
None
)
5.
SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH 0F FEBRUARY 1993-Removed Diesel Generator No. 2 from service and completed the following maintenance:
repaired primary starting air pressure gauge; changed various hoses and fittings on starting air, Jacket water and fuel oil systems; replaced radiator fan bearings and oil seals; installed a 5.6 Ku resistor in static excitor; and replaced a jacket water thermowell.
Replaced Solenoid Valve HCV-480-20 (4A.co ponent cooling water inlet valve to Shutdown Cooling Heat Exchanger AC-Replaced the 52/STA switch on spare Breaker IA3-14.
Replaced damaged outdoor lighting transformer Breaker IB3C-3 with a new breaker.
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6.
OPERATING DATA REPORT Attachment I 7.
AVERAGE DAILY UNIT POWER LEVEL j
Attachment II 8.
UNIT SHUTDOWNS AND POWER REDUCTIONS Attachment III 9.
REFUELING INFORMATION, FORT CALHOUN STATION UNIT NO. I Attachment IV
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ATTACHMENT I OPERATING DATA REPORT DOCKET NO.
50-285 UNIT FORT CALHOUN STATION DATE MARCH 08 1993-COMPLETED BY M.
L.
EDWARDS OPERATING STATUS TELEPHONE (402) 636-2451
- 1. Unit Name:
FORT CALHOUN STATION
- 2. Reporting Period:
FE55UARY 1993 NOTES
- 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 8.
If changes occur in Capacity Ratings (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, if any:
N/A THIS MONTH YR-TO-DATE CUMULATIVE
- 11. Hours in Reporting Period...........
672.0 1416.0 170330.0'
- 12. Number of Hours Reactor was Critical 672.0 1416.0 132026.3
- 13. Reactor Reserve Shutdown Hours......
.D
.0 1309.5
- 14. Hours Generator On-line.............
672.0 1416.0 13047YT2~'
- 15. Unit Reserve Shutdown Hours.........
.6
.0
.0
- 16. Gross Thermal Energy Generated (MWH) 1002476.2 2114478.0 171379954.0
- 17. Gross Elec. Energy Generated (MWH)..
340276.0 718406.0 56559206.2
- 18. Net Elec. Energy Generated (MWH)....
325149.4 686Y58.l_
539572fiTb]
- 19. Unit Service Factor.................
100.0 100.0 76.6
- 20. Unit Availability Factor............
100.0 100.0_
76761,
- 21. Unit Capacity Factor (using MDC Net) 101.2 101.4 68.8
- 22. Unit Capacity Factor (using DER Net) 101.2 101.4 677d'
- 23. Unit Forced Outage Rate.............
.0
.0 4.3 l
- 24. Shutdowns scheduled over next 6 months (type, date, and duration of each):
.ON_ APRIL 24, 1993; THE PLANT WILL_BEGIN A MID-CYCLE MAINTENANCE _ OUTAGE SCHEDULED TO LAST APPROXIMATELY ONE WEEK.
- 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 CORMERCIAL OPERATION i
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ATTACHMENT II AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
_50-285 UNIT FORT CALHOUN STATION' DATE MARCH _
08,1993 COMPLETED BY M. L.
EDWARDS TELEPHONE (402) 636-2451 MONTH FEBRUARY 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 485 17 485 2
485 18 485 3
485 19 485 4
485 20 485 5
485 21 486-6 485 22 485 7
485 23 485 8
485 24 482 9
485 25 477 10 485 26 478 11 485 27 478 12 485 28 478 13 485 29 N/A 14 485 30 N/A 15 485 31 N/A 16 485 INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each.
4 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 8. 1993 COMPLETED BY M. L. Edwards TELEPHONE (402) 636-2451-REPORT MONTH February 1993 j
No.
Date Type' Duration Reason 2 Method of Ucensee System Component Cause & Corrective (Hours)
Shutting Event Code
- Code' Action to Down Reactor' Report #
Prevers Recurrence None During most of February 1993, the plant operated at a nominal 100%
power level. late in the mornh, power was slightly reduced to maintain the peak linear heat rate at less than 90% of the masimum allowed value.
I 2
3 4
F: Forred Reason:
Method:
Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data
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PrMaintenance or Test 2-Manual Scram.
Entry Sheets for Ucensee C-Refueling 3-Automatic Scram.
Event Report (1.ER) File (NUREG-016!)
D-Regulatory Restriction.
4Oher (Explain)
E-Operator Trsining & License Examination F-Administrative 5
GQrational Error (Explain)
Exhibit 1 - Same Source Hoher (Explain)
(9/77)
- - - "' ~-"
hm m_m_
Attachment IV Refueling Information Fort Calhoun - Unit No. 1 Report for the month ending February 1993
- 1. Scheduled dated for next refueling shutdown.
September 1993
- 2. Scheduled date for restart following refueling.
November 1993
- 3. Will refueling or resumption of operations thereafter require a technical specification change or other license amendment?
_Y3s l
- a. If answer is yes, what, in general, will these be?
l Incorporate specific requirements resulting from reload safety analysis.
I
- b. If answer is no, has the reload fuel design and core configuration been reviewed by l
your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload.
N/A
- c. If no such review has taken place, when is it scheduled?
N/A
- 4. Scheduled date(s) for submitting proposed licensing action and support information.
June 1993
- 5. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance i
analysis methods, significant changes in fuel i
design, new operating procedures.
None Planned j
- 6. The number of fuel assemblies:
a) in the core 133 Assembl es b) fuel pool in the spent 529 Assembl' es c) spent fuel pool storage capacity 729 Assemblies d) planned spent Planned to be fuel pool increased with high j
storage capacity density spent fuel I
racks.
- 7. The arojected date of the last refueling that can be disciarged to the spent fuel pool assuming the present licensed capacity.
1995*
Capability of full core offload of 133 assemblies lost. Reracking to be performed between o
the 1993 and 1995 Refueling Outages.
Prepared by /K
, dAC-Date
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U. S. Nuclear Regulatory Commission LIC-93-0090 i
ENCLOSURE 2
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Revised Operating Data Reports for Period of November 1991 - January 1993 I
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