LIC-90-0632, Monthly Operating Rept for Jul 1990 for Fort Calhoun Station Unit 1

Monthly Operating Rept for Jul 1990 for Fort Calhoun Station Unit 1

ML20058P138
Person / Time
Site:	Fort Calhoun
Issue date:	07/31/1990
From:	Gates W, Stice D OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-90-0632, LIC-90-632, NUDOCS 9008160097
Download: ML20058P138 (8)

Text

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Omaha Public Power District 444 South 16th Street Mall Omaha. Nebraska 68102-2247 :

402/636-2000 August-13, 1990

-LIC-90-0632.

V. S. Nuclear Regulatory Commission Attn: Document Control Desk  :

Mail Station Pl-137 Washington, DC 20555

Reference:

Docket No. 50-285 l

Gentlemen:

SUBJECT:

July Monthly Operating Report (MOR)

Please find enclosed the July 1990 Monthly Operating Report for the Fort Calhoun Station Unit No. I as required by Technical Specification Section 5.9.1.

If you should have any questions, please contact me.

' Sincerely, W. G. Gates Division Ma ger ,

Nuclear Operations '

WGG/sel Enclosures  ;

c: LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, NRC' Regional Administrator, Region IV R. P. Mullikin, NRC Senior Resident. Inspector D. K. Sentell,. Combustion Engineering R. J. Simon, Westinghouse

' Office of Management & Program Analysis (2)

Nuclear Safety Analysis Center INP0 Records Center gj[

American. Nuclear Insurers pI 900816o097hhhk

.[DR =ADOCK o gg PDC Employment Eq Opcatunity / g' i

, L AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285' UNIT -Fort Calhoun Station DATE August 13, 1990-COMPLETED BY D. L. Stice TELEPHONE- (402)636-2474

.l MONTH July 1990 DAY . AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL; (MWe-Net) (MWe-Net) l

1. 468 17- 472' l

-2 467' 181 472 3 467- 19- 471 j

~4 467 ' 20 ' . 471 1 5 468 21' 473 6 469 22- 473-7 471 23. 474  :;

8 -469 "

24' 475 9 470 25 474 10 470%, 26- 475  ;

11' 471 27 -473' o 12 474 28 473 I 13 476 .29 472 i 14 476 30 472 15 475 31 472 16 473 l

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.

f s - )

4 OPERATING DATA REPORT I

DOCKET N0. 50-285 UNIT Fort Calhoun Station l DATE August 13, I F '

COMPLETED BY D. L. Stice ,

I 1 TELEPHONE (402)636-2474 OPERATING STATUS' W

1. Unit Name: ' Fort Calhoun' Station Notes l r

2. Reporting Period: July 1990 ,

3. Licensed Thermal Power (MWt): 1500

4. NameplateRating(GrossMWe): 502-

5. Design Electrical Rating (Net MWe): -478

6. 502 ,

7. Maximum. Dependable Capacity-((Gross '

478MWe):

Maximum Dependable' Capacity- Net MWe)(:'If changes occur in Capacity Ratings

8. ' '

Give Reasons:- <

1 N/A-L. 9. PowerLeveltoWhichRestricted,IfAny(NetMWe): N/A i L 10. Reasons for Restrictions;'If Any: N/A v

This Month' .Yr-to-DateL Cumulative 11.. Hours in Reporting Piriod 744.0 5,087.0 147,697.0 t

12. Number of Hours-Reactor was Critical 744.0 2,755.6 113,921.9 ~

13. Reactor Reserve Shutdown. Hours 0.0- 0.0- 1,309.5

14. Hours Generator _0n-Line _

744.0 -2,600.7 112,606.1

15. Unit Reserve Shutdown Hours 0.0 . 0.0 0.0 t

16. Gross Thermal Energy. Generated (MWH)' 1,112,248.1- 3,602,976.6 147,218,087.8 -i

17. Gross Electrical Energy Generated-(MWH) 368,010.0; 1,177,148.0 48,387,256.2 1

18. Net Electrical Energy Generated (MWH)_

350,967.2 1,119,091.2 46,186,644.0

19. Unit Service Factor 100.0- 51.1- 76.2

20. Unit. Availability Factor 100.0 51.1 76.2 21 '. UnitCapacityFactor-(UsingMDCNet) ,

98.7 46.0- 67.9

.22.- Unit Capacity Factor (Using DER Net) 98.7 46.0 66.3 -!

23. Unit Forced Outage Rate 0.0 0.0- 2.9 1 24. ShutdownsScheduledOverNext6 Months (Type,Dateiand--Durs' n of-Each):

NONE '

l

25. If. Shut Down at End of Report Period, Estimated Date of Startup:, N/A

26. UnitsInTestStatus(PriortoCommercialOperation): Forcast Achieved INITIAL CRITICALITY

' INITIAL ELECTRICITY N/A COMERCIAL OPERATION

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DOCKET NO. 50-285- ..

UNIT NAfE Fort Calhoun Station DATE August 13, 1990 UNIT SHUTDOWHS AND POWER REPUCTIC*:S C0pFLETED BY D. L. Stice TELEPHONE (402) 636-2474 REPORT MONTH July 1990 5 ~

E E Ucensee g g' g cause a m No. Date .

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g 5 jjg g Event dg y

Acton to e iI a e

g4=j ae,-t e 9

3 8

~ There were no unit shutdowns or power reductions during the month of -July, 1990.

I 4 2 3 1

Methoet Exfedt G - Instructions F-Forced Reasort 14denual for Preparation of Data.

S-Scheduled A-Eqidpment Fagure (Explain) 2-4denomi Scram Entry Shoots for Uconese B-Meintenance er Test 3-Automette Scram Event Report A fee INUREG-01811 C-RefueEng D-Regulatory Restriction 4-Other Stadeir$

~

5 E-Operator Training a Ucense Exandnation Exfedt 1 - Some Source F-Administattwe G-Operational Error .

H-Other (Explain)

-. - - . . - - - - - - . - - - - - - - - - - .L

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~ Refueling-Information Fort Calhoun'- Unit No.-1 Report for the month ending July 1990~

. 1. Scheduled date for next refueling shutdown. Seotember 1991

2. Scheduled date for restart following refueling. November 1991

3. L Will refueling-or resumption of operation thereafter require a technical specification change or other? license amendment? Yes

a. If answer is'yes, what, in general, will q these'be?; i Incorporate ' specific

- requirements - resul_ ting 1 from reload, safety >

. analysis..  ;

i

b. If answer is no,.has the reload fuel design and -  !

core-configuration'been reviewed by.your P1 ant- * '

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 .

i it' scheduled? N/A

4. Scheduled date(s) for submitting proposed 11icensing action and support information.

June 1991 L

5. Important licensing considerations associated I with refueling, e.g., new or different' fuel design or supplier; unreviewed design or performance' analysis' methods, significant changes in. fuel design, new operating ,

i procedures. New fuel supplier ,

New LOCA'Analvsis'

6. The number of fuel assemblies: a) in the core 133 ' Assemblies b) in the spent fuel pool- 477 Assemblies c) spent. fuel pool storage-d capacity- 729 Assemblies d) planned spent fuel pool Planned to be increased storage capacity with higher density spent  !

fuel racks.

b'

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1994* '

Capability of full core offload of 133 assemblies lost.

~ Prepared by E ~- Mb Date 8'?-9d I

e OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 ,

- July .1990

' Monthly Operating Report I. OPERATIONS

SUMMARY

l L Fort Calhoun Station operated at a nominal 100% power for the month of July 1990. The Institute of Nuclear Power Operations (INP0) annual evaluation- '

exit and the corporate evaluation were held in July. The NRC Systematic l Assessment-of Licensee Performance (SALP) briefing was held on July-26, 1990.

Full flow testing of-the-motor driven and turbine driven auxiliary-feedwater pumps using a' recirculation line was. conducted for the first time '

to verify the baseline pump curves. The turbine driven pump-speed control ,

. loop and back-pressure trip were also_ verified.  :

-Pre-operational testing for'the new diesel engine-driven auxiliary '

feedwater pumt has been completed. Flow testing of the.pum) was'in progress at tie end of the month. The engine-driven pump s1ould be operable in August 1990 barring any unforeseen. circumstances.

Investigation of emergency diesel generator (DG) cooling problems continued -

in July with DG room temperature profiles being generated during DG operation. The water / antifreeze coolant mixture for DG-2 was' replaced with

~

L water and a corrosion inhibitor, as was done with DG-1 in June, to aid in heat transfer capability. An electrical load capacity curve for the DGs with respect to ambient air temperature has been issued. ,

The following NRC inspections took p1~ ace in July:

IR.90-32 Residents' Monthly Inspection (06/17/90 thru 07/28/90)

.IR 90-35 Residents' Monthly. Inspection-(from 07/29/90 to present).

The following LERs were submitted: Date Submitted 90-018 Error in Axial Shape Index Calibration Procedure July 12, 1990 l,90-019 Automatic Start of Diesel Generators Due to July 23, 1990

Main Turbine Trip A. SAFETY VALVES OR PORV CHALLENGES OR FAILURES hHICH OCCURRED None I

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'[ ;

-Monthly Operating Report July,1990.

Page Two B. RESULTS OF LEAK RATE TESTS The results of_ the Reactor Coolant System-(RCS) Leak Rate-Tests for q the month of' July indicate a continuation of the very low RCS leakage i

. trend following the' 1990 refueling and maintenance outage. lia known . '

leakage to the Reactor Coolant Drain Tank and the Pressurizer Quench  !

-Tank varied throughout the month from 0.0 to-0.051 gpm. The f.otal

-leak rate,-wk.ch is the sum of both the known and unknown leak rates, i peaked on July 21,1990 with 0.188 gpm calculated. The highest  !

unknown leakage was determined on July 24, 1990 as 0.164 gpm _ 1 Reactor power remained essentially constant at 100% for the' month.. 'j C. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY

-COMMISSION AUTHORIZATION PURSUANT T0 10CFR50.59 Amendment No. Descriotion; 4

No. 132 The amendment made changes to pages 5 - 1, ' 5 - 5, -.' 5 - 8, .

and 5-19a of the Technical Specifications _to ~  ;

incorporate title changes as a result of a.  ;

reorganization and also a partial relocation of i the Emergency Planning Department. In addition, a i title was changed in Amendmant 115 but was'omitted  :

from page 5-19a, so this change was'also included.  !

D. SIGNIFICANT SAFETY RE. LATED MAINTENANCE FOR THE MONTH OF JULY 199'O Significant safety-related maintenance activities completed.in the month of July 1990 are outlined below:

)

During the performance of ST-ESF-2 F.4 the " Auto-Start" light on. ,

sequencer S2-2 for Charging Pump CH-13 did.not come on after its timer timed out. The breaker for CH-1B did close,~however. Work ,

performed verified ~ continuity in the " Auto Start" light circuit. ..The failure was due to dirty -contacts. Post Maintenance Testing (PMT) _

was performed in accordance with OP-ST-ESF-0023, S2-2 Automatic Load i Sequencer Test.

The Qualified Safety Parameter Display System (QsPDS),' Channel A,' had' i excessive system failure alarms. The fiber optic modems were tested,  !

removed and adjusted for zero errors..The failure was due-to the modem'on the Emergency Response Facility Computer: System end being out of adjustment. PMT was performed by monitoring for proper operation'of the system over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

,1 i

4 Monthly Operating Report July-1990-

- Page Three.

+

The 125 volt direct' current Battery Charger 2 developed problems with thr, low voltage sensing relay cart. - Repairs _ required installation of i

-a new low voltage sensing relay card. The cause of. failure was unknown. Post Maintenance = Testing was performed in accordance with' applicable sections of EH RR-EE-0811, Maintenance of Battery Charger

1. 2, (EE-8B) Alarm Cards.

Terry L. Patterson; ,

Manager-Fort Calhoun Station -

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