ML20069L898

Monthly Operating Rept for May 1994 for Fort Calhoun Station Unit 1

ML20069L898
Person / Time
Site:	Fort Calhoun
Issue date:	05/31/1994
From:	Gates W, Howman M OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-94--0106, LIC-94--106, NUDOCS 9406200341
Download: ML20069L898 (8)

Text

__

h[

4 e

Omaha Public Power District 444 South 16th Street Mall Omaha. Nebraska 68102-2247 402/636-2000 June 14, 1994 LIC-94-0106 V. S. Buclear Regulatory Commission i

ATTN: Document Control Desk Mail Station Pl-137 Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

May 1994 Monthly Operating Report (MOR)

Enclosed is the May 1994 MOR for Fort Calhoun Station (FCS) Unit flo.1 as required by FCS Technical Specification 5.9.1.

If you should have any questions, please contact me.

Sincerely,

/&

. $Zh W. G. Gates Vice President WGG/mah Enclosures c:

LeBoeuf, Lamb, Greene & MacRae L. J. Callan, NRC Regional Administrator, Region IV S. D. Bloom, NRC Project Manager R. P. Mullikin, NRC Senior Resident Inspector R. T. Pearce, Combustion Engineering R. J. Simon, Westinghouse Office of Management & Program Analysis (2)

INPO Records Center 9406200341 94o53; PDR ADOCK 05000295

[hh k

PDR

\\

j c5-5124 0* '

...c unployment w:th E pl opportun!!y L L \\s v s' L}

l

LIC-94-0106 i

Inclosure Page 1 OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 J

MAY 1994 Monthly Operating Report 1.

OPERATIONS

SUMMARY

During the month of May, the station operated at a nominal 100% power level. The spent fuel pool reracking project continued.

The condensate cooler was cleaned and returned to service.

Technical Specification (TS) 2.19 on fire protection has been removed from the TSs.

Fire protection requirements are now contained within Standing Orders G-102, " Fire Protection Program Plan" and G-103, " Fire Protection Operability Criteria and Surveillance Requirements."

New setpoints were put into the Power Operated Relief Valve (PORV)/ Low l

Temperature Overpressure Protection (LTOP) circuitry to allow plant operation through 20 Effective Full Power Years (EFPY) of operation.

On May 16, Reactor Protection System (RPS) Channel A Thermal Margin / Low Pressure (TM/LP) and Axial Power Distribution (APD) trip units failed to the tripped condition.

A 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Limiting Condition for Operation er Technical Specification 2.15(1) and trip units for (LCO) was entered Channel A hi h power, TM/LP, and APD were bypassed.

The problem was traced to a cose connection in the APD calculator and was repaired.

The affected trip units were declared operable and the LC0 was exited the same day.

On May 26, a Swagelock outlet fitting from the secondary system hydrazine tote was found to be not fully engaged and leaking.

Access to the area was controlled and the spill was cleaned up by Hazardous Material personnel. A notification was made to the State of Nebraska with a follow-up 4-hour notification made to the NRC due to the spill of hazardous material, The following NRC inspections were completed during this reporting period:

l HR No.

Description 94-12 Monthly Resident Inspection 94-15 Engineering / Safety Assessment & Quality Verification /SALP Cycle Closecut Team Inspection i

LIC-94'-0106 Enclosure Page 2 The following Licensee Event Reports were submitted during this reporting period:

LER No.

Description 94-004 Inoperability of Halon Gas Fire Suppression System Due to Inoperable Fire Damper 94-005 Failure to Appropriately Address Out-of-Tolerance Test Results for Snubbers.

2.

SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED l

l During the month of May, no PORV or primary safety valve challenges or failures occurred.

3.

RESULTS OF LEAK RATE TESTS RCS leak rate was steady throughout the month of May.

The leak rate was a nominal 0.10 gpm, with no degrading trends noted.

The only changes observed were due to normal plant trans:ents.

4.

CHANGES TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION 1

AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No.

Description NONE 5.

SIGNIFICANT SAFETY RELATED MAINTENANCE Replaced closing springs with those of a more reliable design on e

Breakers lA4-12/ Raw Water Pump AC-100, lA4-1/ Diesel Generator #2 Feed to Bus lA4, and 1A4-15/ Feeder for Lighting Transformer TIC-4A.

Installed a new size orifice plate to reduce system vibration on Component Cooling Water Heat Exchanger AC-18.

Installed the rebuilt Raw Water Pump AC-10D and replaced the lugs on the Raw Water Pump Motor AC-10D-M.

Replaced the failed multiplier / divider module on Nuclear Instrumentation and Reactor Protective System Channel A (AI-31A).

Installed the rebuilt Backwash Control Valve HCV-2805B for Raw Water i

Strainer AC-128.

Replaced a failed solenoid on Component Cooling Water Outlet Valve HCV-403D for Containment Cooling coil VA-8B.

Installed and filled a Furmanite containment box on the leaking Swagelock fitting upstream of Main Steam Warmup Line Isolation Valve MS-367 for Auxiliary Feedwater Pump FW-10.

i i

LIC-94'-0106 E'ncl osure Page 3 Replaced the CR-120A relays with those of a more reliable design in e

Sequencer 52-1 circuits 3, 4, 5, and 6 and Sequencer 52-2 circuits 3, 4, 5, and 6.

6.

OPERATING DATA REPORT Attachment I 7.

AVERAGE DAILY UNIT POWER LEVEL Attachment II 8.

UNIT SHUTDOWNS AND POWER REDUCTIONS Attachment III 9.

REFUELING INFORMATION, FORT CALHOUN STATION UNIT NO. 1 4

Attachment IV

ATTACHMENT I OPERATING DATA REPORT DOCKET NO.

_5 0__2 8 5 _ _ _._ _ _ _. _. _ __ _

UNIT FORT CALHOUN STATION DATE

~JDsE

_f~d{f~9V4-~

COMPLETED BY M._A._H_OWMAN OPERATING STATUS TELEPHONE 402-533-6939

l. Unit Name:

FORT CALHOUN STATION

2. Reporting Period: __

MAY 1994 NOTES i

3. Licensed Thermal Power (MWt): 1500_

j

4. Nameplate Rating (Gross MWe):

502 1

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...........

744.0 3623.0 181297.0

12. Number of Hours Reactor was Critical 744.0 3589.2 141280.9

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

.0

.0 1309.5

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

744.0 3574.1 139637TT l

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

~ - ~

.0

. 0'

.0

16. Gross Thermal Energy Generated (MWH) 1113428.5 5238740.2 184524539.8 l

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

373638.0 1772530.0 608K0554.2~

18. Net Elec. Energy Generated (MWH).... ~ '356578.f

~16919D9.6

~5806T9 7 2T$ ~

~

~

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

100.0 98.7 77.0

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

100.0 98.7 77.0

~

21. Unit Capacity Factor (using MDC Net) 100.3

' ' ~ 97.7~

~~

6F.~4~

22. Unit Capacity Factor (using DER Net) 100.3 97.7 67.7

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

.0 1.3 4.F

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 ir. test status (prior to comm. oper.):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A

~

COMMERCIAL OPERATION

..~

ATTACHMENT II l

AVERAGE DAILY UNIT POWER LEVEL l

l DOCKET NO.

50-285 i

UNIT FORT CALHOUN STATION DATE JDNE

_ _0 6 lW4 u

COMPLETED BY M.

A.

HOWMAN TELEPHONE 402-533-6939 MONTH MAY 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 485 17 478_

t l

2 485 18 477 l

~-

l 3

485 19 476 j

4 484 20 477 i

5 483 21 477 l

6 483 22 477 l

7 484 23 476 8

485 24 473 25 473 9

484 10 483 26 474 11 482 27 476 12 481 28 476 13 480 29 476 14 481 30 475 15 480 31 472 16 479 INSTRUCTIONS l

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.

I i

ATTACHMENT III DOCKET NO. 50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Fort Calhoun St.

DATE June 6, 1994 COMPLETED BY M. A. Howman TELEPHONE (402) 533-6939 REPORT MONTH MaY 1994 No.

Date Type' Duration Reawn Method of Licensee System Component Cause & Corrective 2

(Hours)

Shutting Event Code' Code' Action to Down Reactor $

Report #

Prevent Recurrence None During May 1994, the plant operated at a nominal 100% power.

k I

t 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-Other (Explain)

Exhibit H - Same Source (9/77)

Attachment IV Refueling Information Fort Calhoun - Unit No. 1 Report for the month ending May 31. 1994

1. Scheduled date for next refueling shutdown.

March 11. 1995

2. Scheduled date for restart following refueling.

April 29. 1995

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

No

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

N/A

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

No

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

Prior to April 1995

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

No submittal planned

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.

6. The number of fuel assemblies:

a) in the core 133 Assemblies b) in the spent 570 Assemblies fuel pool c) spent fuel pool storage capacity 729 Assemblies d) planned spent fuel pool storage capacity 1083 Assemblies

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

1995 Outaae*

Capability of full core offload of 133 assemblies lost.

Reracking began in March and is scheduled for completion in August 1994.

• • OPPD is utilizing the CASM0-3/ SIMULATE-3 codes for reactor physics related analyses for Cycle 16.

Prepared by M hU Date

/A - -