LIC-93-0142, Monthly Operating Rept for Apr 1993 for Fcs,Unit 1

Monthly Operating Rept for Apr 1993 for Fcs,Unit 1

ML20044D052
Person / Time
Site:	Fort Calhoun
Issue date:	04/30/1993
From:	Edwards M, Gates W OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-93-0142, LIC-93-142, NUDOCS 9305170172
Download: ML20044D052 (8)

Text

'

1 Omaha Public Power District 444 South 16th Street Mall Omaha, Nebraska 68102-2247 402/636-2000 May 14, 1993 LIC-93-0142 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station Pl-137 Washington, DC 20555

REFERENCE:

Docket No. 50-285 Gentlemen:

SUBJECT:

April 1993 Monthly Operating Report (MOR)

Enclosed is the April 1993 MOR for Fort Calhoun Station (FCS) Unit No. I as required by FCS Technical Specification Section 5.9.1.

If you should have any questions, please contact me.

Sincerely, Wh kW W. G. Gates Vice President WGG/mle Enclosures c:

LeBoeuf, Lamb, Leiby & MacRae J. L. Milhoan, NRC Regional Administrator, Region IV j

S. D. Bloom, NRC Project Manager R. P. Mullikin, NRC Senior Resident Inspector R. T. Pearce, Combustion Engineering i

R. J. Simon, Westinghouse i

Office of Management & Program Analysis (2)

INPO Records Center l

/f 9305170172 930430 i

PDR ADOCK 05000285

,-r 1

R PDR j

I Errveggo,wtav ese

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 April 1993 Monthly Operating Report i

1. OPERATIONS

SUMMARY

l Fort Calhoun Station (FCS) operated at approximately 77% power until the unit t

was taken off-line on April 24, 1993 at 0244 hours0.00282 days <br />0.0678 hours <br />4.034392e-4 weeks <br />9.2842e-5 months <br /> for a scheduled one-week maintenance outage. The purpose of the outage was to im plant reliability and thermal performance for the peak summer season.proveDuring the outage, the plant was maintained in het shutdown.

On April 24 and 25, work on 161KV Circuit 1587 (components located in the switchyard) was conducted. After work on Circuit 1587 was completed,161KV power was supplied to FCS through Transformer T1A4 while Transformer TIA3 was out-of-service. The oil in Transformer TIA3 was changed and Transformer TIA3 and its fire protection deluge piping were tested. On April 29, Transformer TlA3 was returned to service and the 161KV system was restored to its normal lineup.

During the outage, the condensers were cleaned, six containment area radiation monitors were replaced, three safety injection tanks were drained and refilled (to increase the boron concentration),

and a turbine electrohydraulic control system circuit card was replaced.

FCS returned to reactor critical status at 2025 hours0.0234 days <br />0.563 hours <br />0.00335 weeks <br />7.705125e-4 months <br /> on April 30, 1993 and the turbine-generator was synchronized to the grid at 0429 hours0.00497 days <br />0.119 hours <br />7.093254e-4 weeks <br />1.632345e-4 months <br /> on May 1, 1993.

The following NRC inspection was completed during this reporting period:

IER No. Descriotion 93-04 Residents' Routine Inspection No LERs were submitted during this reporting period.

2. SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED None

3. RESULTS OF LEAK RATE TESTS In early April, possibly due to the repacking of Charging Pump CH-1A, the reactor coolant system (RCS) leak rate increased to approximately 0.300 gpm over several days before returning to a nominal rate between 0.100 gpm and 0.200 gpm.

The leak rate stabilized at the nominal rate through the remainder of April 1993.

t

l

~

Monthly Operating Report April 1993 Page Two

4. CHANGES. TESTS AND EXPERIMENTS RE0VIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUAN7 TO 10CFR50.59 Amendment No1 Descriotion None i

5. SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF APRIL 1993 Adjusted lift on Raw Water Pumps AC-10A, AC-10B and AC-100 Replaced Raw Water Pump AC-10D Installed new packing and adjusting rings, plungers, front cap gaskets and steam chest "0" rings on Charging Pump CH-1A Replaced Schrader valve assembly on Suction Accumulator CH-268 for Charging Pump CH-1B Repaired the fresh air supply damper alarm circuit (YCV-871G) for Diesel e

Generator No. 1 Replaced the 52/HH switch for Breaker IA4-12, (feeder for Raw Water Pump AC-10D)

Repaired interlocks on containment Personnel Air Lock AE-2 Outage Activities

[

Replaced the 52/HH ; witch for Breaker IA3-1, the 161KV normal feed to Bus 1A3 Repaired a loose terminal and calibrated reactor coolant Temperature Indicator D/TI-Il2H Replaced the control switch for Boric Acid Storage Pumps CH-4A and CH-4B Installed 28 new EGS Corporation power supplies (120 VAC to 52.5 VDC)

Replaced 13 General Electric CR120A relays Performed circuit analysis testing on the control element drive mechanism (CEDM) clutch coils Checked the power supply output voltage and the AC ripple for the 48 trip units and 12 matrix power supplies on Reactor Protective System Power Supply Assembly Al-31 A-AW8 Sampled Containment Air Cool / Filter Unit "A" Carbon Filter to verify filter efficiency Repaired the control switch on outlet Isolation Valve HCV-258 for Boric Acid e

Storage Tank CH-llB Repaired noise problem on wide range channel "D" (NT-004) e

6. OPERATING DATA REPORT Attachment I

7. AVERAGE DAILY UNIT POWER LEVEL Attachment II t

4 i

Mon'thly Operating Report P

April 1993 Page Three

8. UNIT SHUTDOWNS AND POWER REDUCTIONS Attachment III

9. REFUEllNG INFORMATION. FORT CALHOUN STATION UNIT NO. 1 Attachment IV t

i i

I i

l l

t t

8 f

r

}

9 t

ATTACHMENT I OPERATING DATA REPORT DOCKET 'X1 50-2E5 UNIT FORT CALHOUN STATION DATE

_MAY 04,1993 COMPLETED BY M.

L.

EDWARDS

)

OPERATING STATUS TELEPHONE (402) 636-2451

l. Unit Name:

FORT CALHOUN STATION

2. Reporting Period:

APRIL 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) sinc? last report, give reasons:

N/A

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

10. Reascn. for restrictions, if any:

N/A THIS MONTH YR-TO-DATE CUMULATIVE

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

719.0 2879.0 171793.0

12. Number of Hours Reactor was Critical 558.5 2718!$~

fill 28. s-

~~

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

.0

.0 1309.5 14, Hours Generator On-line.............

554.7 2714.7 131777.9

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

.0~

.0

.0

16. Gross Thermal Energy Generated (MWH) 633532.0 3754275.9 173319751.9

17. Gross Elec. Energy Generated (MWH)..

209656.0 1265788.0_

57106588.2~~

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

199384.6 1207172.5 54478059.4

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

77.1 94.3 76.7

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

77.1 94.3 76.7

21. Unit Capacity Factor (using MDC Net) 58.0 87.7 68.9 '

22. Unit Capacity Factor (using DER Net) 58.0 87.7 67.1,

23. Unit Forced Outage Rate.............

.0

.0 4.3

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

18 _1993 AND_LA.ST REFUELING OUTAGE SCHEDULED TO BEGIN ON SEPTEMBER 2

APPROXIMATELY_5_6 DAY.S.

25. If shut down at end of report period, estimated date of startup: 05/01493

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

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION

.~

l ATTACHMENT II AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-285 UNIT FORT CALHOUN STATION DATE

_MAY

_ 04,1993 COMPLETED BY M.

L. EDWARDS i

TELEPHONE (402) 636-2451 k

MONTH APRIL 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 360 17 364 2

361 18 364 362 3

360 19 i

4 360 20 363 5

361 21 363 22 363 6

362 7

362 23 349 8

363 24 0

25 0

9 363 10 362 26 0

11 362 27 0

12 363 28 0

13 364 29 0

14 364 30 0

31 N/A 15 364 16 364 t

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.

l

'i l

ATTACHMENT III DOCKET NO. 50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Fort Calhoun DATE Nay 10. 1993 COMPLETED BY M. L. Edwards TELEPHONE (402) 636-2451 REPORT MONTH ADril 1993 No.

Date Type' Durstion Reesen Method of Ucensee System Component Cause A Corrective (Hours)

Shutting Event Code' Code' Action to Down Reactor' Report #

Prevent Recurrence 2

04/24/93 S

164.3 H

I N/A N/A N/A Or April 24. For' Calboun Station began a one-week maintenance outage to imprvve plant reliability and thermal performance for the peak summer season.

1 2

3 4

F: Foned Reason:

Method:

Exhibit r) - Instructions 5: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram.

Entry Sheets for Ucennee C-Refbeling 3-Automatic Scram.

Event Report (LER) File (NUREG4161)

D-Regulatory Restriction 4Oher (Explain)

E-Operator Training & Ucen.e Examination F-Administrative 5

O@ rational Error (Explain)

Exhibit 1 - Same Soune Hoher (Explain)

(9'77)

]

Attachment IV i

Refueling Information Fort Calhoun - Unit No.1 Report for the month ending April 1993

1. Scheduled dated for next refueling shutdown.

September 1993

2. Scheuuled date for restart following refueling.

November 1993

3. Will refueling or resumption of operations f

thereafter require a technical specification change or other license amendment?

Yes i

a. If answer is yes, what, in general, will i

these be?

Incorporate specific i

requirements resulting i

from reload safety analysis.

b. If answer is no, has the reload fuel design I

and core configuration been reviewed by

[

your Plant Safety Review Committee to determine whether any unreviewed safety i

questions are associated with the core reload.

N/A t

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 analysis methods, significant changes in fuel design, new operating procedures.

None Planned 4

6. The number of fuel assemblies:

a) in the core

_]33 Assemblies b) in the spent 529 Assembli_es fuel pool 4

c) spent fuel pool storage capacity-729 Assemblies d) planned spent Planned to be fuel pool increased with high storage capacity density spent-fuel racks.

7. The ~harged to the spent fuel pool assuming the.Jected date of the last refueling that can be disc present licensed capacity.

1995*

I o

Capability of full core offload of 133 assemblies lost. Reracking to be performed between the 1993 and 1995 Refueling Outages.

Prepared by b Date 5~ ~ t -u

!