ML20246A954

Monthly Operating Rept for Jul 1989 for Fort Calhoun Station Unit 1

ML20246A954
Person / Time
Site:	Fort Calhoun
Issue date:	07/31/1989
From:	Cook G, Morris K OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-89-785, NUDOCS 8908230195
Download: ML20246A954 (23)

Text

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j Omaha Public Power District 1623 Hamey Omaha. Nebraska 68102-2247 402/536 4000 August 14,-1989 LIC-89-785 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station PI-137 Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

July Monthly Operating Report Pursuant to Technical Specification Section 5.9.1, and 10 CFR Part 50.4(b)(1),

please find enclosed one copy of the July 1989 Monthly Operating Report for the Fort Calhoun Station Unit No.1.

Sincerely,

/

. Morris Division Manager Nuclear Operations KJM/pje i

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R. D. Martin, NRC Regional Administrator P. H. Harrell, NRC Senior Resident Inspector Office of Management & Program Analysis (2)

R. M. Caruso - Combustion Engineering R. J. Simon - Westinghouse Nuclear Safety Analysis Center INP0 Records Center

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.A AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-285 L

UNIT Fort Calhoun Station DATE August 11, 1989 COMPLETED BY G. M. Cook TELEPHONE (402)636-2490

MONTH,

_ July 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 457 17 457

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456 18 456 3

454 19 457 4.

452 20 457 5

451 21 456 6

450 22 455 7

449 23 455 8

448 24 454 9

449 25 453 10 449 26 453 11 449 27 452 12 447 28 449 13 448 29 449 14 450 30 449 11 5 453 31 448 16 456 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.

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OPERATING DATA REPORT DOCKET NO.

50-285 UNIT Fort Calhoun Station DATE August 11, 1989 COMPLETED BY G. M. Cook TELEPHONE (402)636-2490 OPERATING STATUS 1.

Unit Name: Fort Calhoun Station Notes 2.

Reporting Period:

July 1989 3.

Licensed Thermal Power (MWt):

1500 4.

Nameplate Rating (Gross MWe):

502 5.

Design Electrical Rating (Net MWe): 478 6.

Maximum Dependable Capacity (Gross MWe):

502 MaximumDependableCapacity(NetMWe)(:ItemNumbers3through7)SinceLastRepo 7.

478 If changes occur in Capacity Ratings 8.

Give Reasons:

N/A 9.

PowerLeveltoWhichRestricted,IfAny(NetMWe):

N/A

10. Reasons for Restrictions, If Any:

N/A This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744.0 5,087.0 138,937.0

12. Number of Hours Reactor was Critical 744.0 4,244.8 107,594.6

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5

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14. Hours Generator On-Line 744.0 4,027.3 106,442.6

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. GrossThermalEnergyGenerated(MWH) 1,112,612.1 5,628,053.8 138,517,047.7

17. Gross Electrical Energy Generated (MWH) 353,482.0 1,819,644.0 45,563,772.2

18. Net Electrical Energy Generated (MWH) 336,384.6 1,730,469.9 43,501,974.7

19. Unit Service Factor 100.0 79.2 76.6

20. Unit Availability Factor 100.0 79.2 76.6

21. UnitCapacityFactor(UsingMDCNet) 94.6 71.2 67.7

22. Unit Capacity Factor (Using DER Net) 94.6 71.2 66.0

23. Unit Forced Outage Rate 0.0 4.1 2.9

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:

N/A

26. Units In Test Status (Prior to Commercial Operation): Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION l

D

Rsfueling Information

-Fort Calhoun - Unit No. 1 Report for the month ending July 1989

.l 1.

Scheduled date for next refueling shutdown.

February 1990 2.

Scheduled date for restart following refueling.

May 1990

. 3.

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 these be?

- Incorporate specific requirements resulting from reload safety analysis b.

If answer is.no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to deter-mine whether any unreviewed safety questions are associated with the core reload.

c.

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

4.

Scheduleddate(s)forsubmittingproposedlicensing action and support information.

January 1990 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 6.

Tha number of fuel assemblies: a in the core 133 assemblies b in the spent fuel pool 437 c spent fuel pool storage capacity 729 d) planned spent fuel pool May be increased

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storage capacity via fuel Din consolidation or dry cask storage 7.

The )rojected date of the last refueling that can be disclarged to the spent fuel pool assuming the present 3

licensed capacity.

1994*

• Full core offload of 133 assemblies lost.

Prepared by M 4 Date Auctist 9,1989 l

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OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 July 1989 Monthly Operations Report I.

OPERATIONS

SUMMARY

Fort Calhoun Station operated at a nominal 100% power throughout the month of July, 1989.

Work on;the Control Room filter modification to meet GDC 19 habitability requirements for operators continues. The modification replaces the present single' charcoal filter with dual higher efficiency filters.

The water plant outage for system repair continues. The reverse osmosis demineralized unit had to be moved when its weight contributed to the cracking of the under ground fire protection water main.

Repair of the fire main is complete.

Charging pump CH-1A experienced low flow problems. The problem was corrected by replacing all valves and valve seats in the pump. A low discharge pressure problem was corrected by fixing a leak on the discharge accumulator and recharging it.

An emergency diesel generator experienced above normal coolant temperatures during a test run. The cause was first thought to be the coolant temperature control valve being mounted vertically as opposed to the normal horizontal. The vertical mounting could permit air to be trapped in the upper part of the valve and give false conditions to temperature sensors.

Further testing showed this to have little or no effect. The diesel exhaust lines are now un-insulated. The heat which the-lines are adding to the room may be causing the rise in coolant temperature. The rise in ambient room temperature contributes to potential derating of the diesel. Corrections to the problems include

.possible re-insulation of the exhaust lines, installing a vent line off the temperature control valves and reanalysis of the temperature effects.

Operations personnel are now instructed to declare Diesel Generator #2 inoperable due to diesel generator derating whenever ambient temperature increases above 97'F.

Diesel Generator #1 must be declared inoperable if ambient temperatures increase above 110'F.

Both diesels will remain in full automatic and will not be physically removed from service even if declared inoperable.

Safety Analysis for Operability (SAO)89-012 was issued in anticipation of river water temperature exceeding 85' but did not have to be put into effect. SA0 89-12 demonstrates that the heat removal capability of the raw water-system is sufficient to remove the minimum heat load from the

-component cooling water system as stated in the USAR when the Missouri River water temperature exceeds 85'F.

During July 1989 the river temperature came very-close to 85*F but did not exceed it.

SA0 89-12 shows that river temperature up to 92*F may be permissible.

U - -__ ____ -____ -____-

= l

. Monthly Operations Report Page Two July 1989 Special Procedures SP-RW-3 and SP-RW-4 were performed to obtain baseline data on Raw Water pumps for future In Service Inspection (ISI) testing.

During the testing one of the Raw Water / Component cooling water heat exchangers (AC-1B) was found to be partially plugged. The heat exchanger was air sparged to reduce fouling and increase flow through the heat exchanger. An engineering evaluation was performed to ensure the operability of the Raw Water syste..: with the current pump and heat exchanger flows.

A new program was initiated to ensure timely completion of all surveillance tests (ST).

Each day the Shift Technical Advisor will receive ST's completed within the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and ensure those required were performed.

If the ST is not completed within its required time interval, the STA brings it to the attention of the Shift Supervisor for appropriate action.

The SALP ratings for the last period were issued.

Fort Calhoun Station was rated 2 in all categories.

The annual emergency response exercise was held July 19, 1989.

The fol!owing NRC inspections took place in July:

IR 89-28 Resident Inspector's Monthly Inspection IR 89-29 Emergency Plan Annual Exercise Evaluation IR 89-30 NRC Bulletin 87-02 Closeout and 10 CFR Part 21 Inspection IR 89-31 Security Inspection The following LER's were submitted.

Date Submitted 89-015 Plant Emergency Lighting Outside Design Basis July 13,1989 89-016 Aux. Feedwater Pump FW-10 Outside Design Basis July 17, 1989 89-017 Raw Water System Outside Its Design Basis July 31, 1989 An enforcement conference was held on July 28, 1989 in Arlington, Texas.

j The subject of the conference was auxiliary feedwater pump FW-10 inoperability and Inspection Report 89-27.

No safety valves or PORV challenges or failures occurred.

A.

PERFORMANCE CHARACTERISTICS None B.

CHANGES IN OPERATING METHODS None

]

Monthly Operations Report Page Three C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL System Acceptance Committee Packages for July 1989:

Packaae Description /Analysjl MR-FC-88-104 Moisture Separator Erosion Repair This modification provided for repair of eroded areas in the moisture separators, and application of an erosion resistant cladding to these areas.

This modification does not have an adverse effect on the safety analysis.

E.

RESULTS OF LEAK RATE TESTS During the month of July the total Reactor Coolant System leak rate generally remained at its nominal value of approximately 0.3 gpm.

ST-RLT-3(F.1) showed the normal day to day variations in leak rate, however.

The highest total in leak rate during the month occurred on July 14, with a recorded value of.512 gpm. Work on the charging pump packings again reduced the RCS leal: rate to its nominal value.

F.

CHANGES IN PLANT OPERATING STAFF None G.

TRAINING During the month of July, simulator testing commenced at Westinghouse j

Corporation in Pittsburgh, PA. Testing of the simulator handler and j

hardware is progressing in parallel with the completion of the 1

prerequisites.

To support the testing phase, license operators are i

arriving in Pittsburgh for two week shifts. The Supervisor -

j Simulator Services has now relocated to Pittsburgh for the duration

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to coordinate testing.

l l

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Monthly. Operations Report j

Page Four E

l Fifteen engineers successfully completed the first System Engineer training course..The STA class branched off from the System-Engineers program. After completing their common courses, the three STA' candidates are now' studying material ' specific to their_ job.

All five licensed operator candidates passed the NRC Generic fundamentals examination. Results received.were'a high grade of 98%,

a_ low grade of 88%, with an average of 92%. The SR0 class of three students have completed their OJT,,and are preparing for their._.

upcoming NRC exam in October.

Five individuals completed the eight week Equipment Operator Nuclear - Turbine (EONT) program. A seven week Auxiliary Operator Nuclear (AON) program started for three individuals.

H.

CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 None

-II.

MAINTENANCE (Significant Safety Related)

See attached printout.-

G. R. Peterson Manager-Fort Calhoun Station

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