LIC-94-0139, Monthly Operating Rept for June 1994 for FCS Unit 1

Monthly Operating Rept for June 1994 for FCS Unit 1

ML20070K013
Person / Time
Site:	Fort Calhoun
Issue date:	06/30/1994
From:	Gates W, Howman M OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-94-0139, LIC-94-139, NUDOCS 9407260072
Download: ML20070K013 (7)

Text

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4 Bibbienfanse drarmausr 6 Omaha Public Power District 444 South 16th Street Mall Omaha, Nebraska 68102-2247 402/636-2000 July 15, 1994 LIC-94-0139 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station Pl-137 Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

June 1994 Monthly Operating Report (MOR)

Enclosed is the June 1994 MOR for Fort Calhoun Station (FCS) Unit No. I as required by FCS Technical Specification 5.9.1.

If you should have any questions, please contact me.

Sincerely,

/$V b 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)

INP0 Records Center 94o7260072 940630 7

PDR APOCK 05000285 PDR R

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4 LIC-94-0139 Enclosure

- Page 1 OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 JUNE 1994 Monthly Operating Report 1.

OPERATIONS

SUMMARY

During the month of June, the station operated at a nominal 100% power level.

The spent fuel pool reracking project continued.

The west Raw Water header successfully passed a 10-year hydrostatic test on June 2.

A temporary modification (TM) was made to Main Steam Valve MS-118 on June 27.

This valve is a root isolation valve for pressure transmitter that could not be(a Furmanite box) was installed to seal a packing leak PT-941. The TM isolated; the valve could not be replaced on line.

The following NRC inspection was completed during this reporting period:

IER No.

Description 94-16 Monthly Resident inspection The following Licensee Event Report was submitted during this reporting period:

LER No.

Description 94-006 Failure to Place Charcoal Filter (VA-66) in Service Prior to Moving Irradiated Fuel 2.

SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED During the month of June, no PORV or primary safety valve challenges or failures occurred.

3.

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

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

The only changes observed were due to normal plant transients.

4.

CHAtGES, TESTS AND EXPERIMENTS REQUIRING NVCLEAR REGULATORY COMMISSION AUlFORIZATION PURSVANT TO 10CFRSO.59 Amendment No.

Description NONE I

LIC-94-0139 Enclosure Page 2 5.

SIGNIFICANT SAFETY RELATED MAINTENANCE Installed a larger size orifice plate to reduce system vibration on e

Component Cooling Water Heat Exchangers AC-1A and AC-lC.

Installed new internal discharge check valves and replaced primary packing on Charging Pump CH-lC.

Replaced leaking packing and installed new plungers on Charging Pump CH-18.

Suction and discharge valves were also replaced.

Replaced a failed solenoid coil on Boric Acid Make-Up Inlet Valve e

FCV-269-20.

Replaced the closing spring on Breaker lA3-9/ Raw Water Pump AC-10A with one of a more reliable design.

Replaced 74/FW-10 Relay on Auxiliary Feedwater Pump FW-10.

e 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. FART CALHOUN STATION UNIT NO. 1 Attachment IV

ATTACHMENT I OPERATING DATA REPORT DOCKET NO.

50-285 UNIT FORT CALHOUN STATION DATE

~ JULY

_07,1934 COMPLETED BY M.

A.

HOWMAN OPERATING STATUS TELEPHONE 402-533-6939

l. Unit Name:

FORT CALHOUN STATION

2. Reporting Period:

JOSE'f554

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:

s 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...........

720.0 4343.0 182017.0 ~

12. Number of Hours Reactor was Critical 7'20.0 4369.f

~ ~ 14 2 6 6'.'9

~~

0

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

~~~ 6

.0 13U9.5~

7 720.0 4294.1

~ 14'6357.3'

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

~ ~ ~ ~ ~ ~ ~.0

.0

~

~~0

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

~

16. Gross Thermal Energy Generated (MWH) lle77276.'6 163160ld_.~8 1(56DisiO[. 4 j 17.. Gross Elec. Energy Generated (MWH)..

355708.0 2128238.0 61216262.2

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

_ 33_9069.8 2030979.4, 58404042.3_

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

~ ldU.0 98.9~

~

77.1 100.0 98.9

20. Uni Availaoility Factor............

77.1 21 Unit Capacity Factor (using MDC Net) 98.5 97.8 69.5 Capaci~.y Factor (using DER Net) 98.5 97.8 67.8

22. Ur

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

. 0_

l.l_

. i- ~l.jf~

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 DOCKET NO.

5_0__285_ _

UNIT FORT CALHOUN STATION DATE JULY 07,1994 COMPLETED BY M. A.

HOWMAN TELEPHONE 402-533-6~939 MONTH JUNE 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 473 17 469 2

476 18 469 3

477 19 468 20 467 4

476 5

476 21 466 6

474 22 465 23 467 7

472 8

472 24 469 9

475 25 469 26 468 10 477 11 475 27 468 12 474 28 468 13 472 29 469 14 470 30 469 15 469 31 N/A 16 469 INSTRUCTIONS On_this form, list the average daily unit power level in MWe-Net for each day in the reporting.nonth.

Compute to the nearest whole megawatt.

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

DATE July 7. 1994 COMPLETED BY M. A. Howman TELEPHONE (402) 533-6939 REPORT MONTH June 1994 No.

Date Type' Duration Reasan' Method of Licensee System Component Cause & Corrective (ILasrs)

Shutting Event Code' Code' Action to Dos n R.eactor' Report #

Prevent Recurrence None During June 1994, the plant operated at a norninal 100% power.

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

l H-Other (Explain)

Exhibit H - Same Source (9/77) t

i Attachment IV Refueling Information Fort Calhoun - Unit flo.1 Report for the month ending June 30. 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 Emendment?

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 i

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/NN Date 7./7 /94-p 1

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