ML20247F698

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Monthly Operating Rept for Apr 1989 for Fort Calhoun Station Unit 1
ML20247F698
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 04/30/1989
From: Morris K, Stanley B
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-89-502, NUDOCS 8905300143
Download: ML20247F698 (17)
v • d • e


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l Omaha Public Power District {

1623 Harney Omaha, Nebraska 68102 2247 l 402/536 4000 j May 18, 1989 LIC-89-502 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station PI-137 Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

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

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

Sincerely,

/ 719 O J. Morris Division Manager Nuclear Operations KJM/jak c: P. H. Harrell, NRC Senior Resident Inspector Office of Management & Program Analysis (2)

R. M. Caruso - Combustion Engineering R. J. Simon - Westinghouse Nucles,' Safety Analysis Center INP0 Records Center American Nuclear Insurers 8905300143 890430 PDR ADOCK 05000285 R PDC

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT -Fort Calhoun Station DATE May 11. 1989 COMPLETED BY B. E. Stanlev TELEPHONE 402-636-2456 MONTH April 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 469 17 _ 46?,

2 450 18 469 3 469 19 468 4 469 20 468 5 469 21 467 6 469 22 465 ,__

7 469 23 464 8 469 24 463 9 469 25 462 10 470 26 461 11 470 27 460 12 470 28 280 13 469 29 0 14 469 30 0 15 469 16 469 INSTRUCTIONS On this format, 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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e OPERATING DATA REPORT DOCKET N0. 50-285 UNIT Fort Calhoun Station DATE May 11. 1989 COMPLETED BY B. E. Stanley TELEPHONE 402-636-2456 OPERATING STATUS

1. Unit Name: Fort Calhoun Station Notes
2. Reporting Period: April 1989
3. Licensed Thermal Power (MWt): 1500
4. Nameplate Rating (Gross MWe): 502
5. DesignElectricalRating(NetMWe): 478
6. MaximumDependableCapacity(GrossMWe): 502
7. Maximum Dependable Capacity (Net MWe): 478
8. If changes occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, 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 719.0 2.879.0 136,729.0
12. Number of Hours Reactor Was Critical 719.0 2,197.5 105.547.3
13. Reactor Reserve Shutdown Hours 0.0 0.0 1.309.5
14. Hours Generator On-Line 671.0 2.094.2 104.509.5
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. GrossThermalEnergyGenerated(MWH) 992.388.6 2.857.212.3 135.746,206.2
17. Gross Electrical Energy Generated (MWH) 323,370.0 931.380.0 44.675,508.2
18. NetElectricalEnergyGenerated(MWH) 309.003.2 885.972.6 42.657.477.4
19. Unit Service Factor 93.3 72.7 76.4
20. Unit Availability Factor 93.3 72.7 76.4 2:. UnitCapacityFactor(UsingMDCNet) 89.9 64.4 67.5
22. Unit Capacity Factor (Using DER Net) 89.9 64.a 65.8
23. Unit Forced Outage Rate 0.0 0.0 2.8
24. ShutdownsScheduledOverNext6 Months (Type,Date,andDurationofEach):

None

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 COMMERCIAL OPERATION

Refusling.Information Fort Calhoun - Unit No. 1 Report for the month ending April 1989

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 resiewed 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. Scheduled date(s) for submitting proposed licensing action and support information. January 1990
5. Imoortant licensing considerations associated with re. fueling, 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. The 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 storage capacity via fuel oin consolidation or dry cask storage
7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1994*

1

  • Full core offload of 133 assemblies lost.

Prepared by C Date May 11,1989

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0MARA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 April 1989 Monthly Operations Report I. OPERATIONS

SUMMARY

Fort Calhoun Station operated at a nominal 100% power for the majority of the  !

month of April. A power reduction to a nominal 95% was performed on April

17. This power reduction was performed to allow the isolation and repair of a steam leak on an extraction line to a feedwater heater. Power was returned to a nominal 100% on April 17. A power reduction was performed on April 28 to allow turbine overspeed tests, auxiliary feedwater pump full flow tests and miscellaneous maintenance items. This power reduction continued through the end of April.

Major operational items included the slow dilution of "C" safety injection tank. Drain and fill operations were performed on the tank several times during the month of April to maintain the boron concentration in the tank above the Technical Specification limit. A special procedure was performed to pump a boric acid solution into the tank. A turbine overspeed test was ,

performed. A full flow test was performed on the motor driven and steam driven auxiliary feedwater pumps. A 161 kV offsite power source maintenance outage was performed to upgrade dampeners on the line. A 345 kV offsite power source maintenance outage was performed to repair the main station transformer. Control rod sequencing problems occurred during the power reduction to 95% power. Diesel Generator DG-1 was declared inoperable due to fuel oil transfer pump problems. DG-1 was removed from service for maintenance on the fuel oil transfer system. Motor driven auxiliary feedwater pump FW-6 was declared inoperable after failing a surveillance test. It was subsequently determined that FW-6 was operable and the surveillance test needed to be revised. Raw water pump strainer AC-12A was declared inoperable due to low flow. The backwash valve liner was replaced and strainer AC-12A was returned to service. Raw water pump cell A was returned to service after completion of work performed on Circulating Water Pump CW-1A. This work included replacement of an expansion joint, inspection of the pump, and rebuilding the pump motor. Raw water pump cell B was removed from service to perform maintenance on Circulating Water Pump CW-18. This work included replacement of an expansion joint, and rebuilding the pump motor. ,

i Two operators, John Borger and Pat Cronin, obtained Reactor Operator licenses. NRC written walkthrough, and simulator requal exams were administered. Annual licensed operator simulator training at Combustion .

Engineering continued. '

IhP0 performed a plant evaluation during the first two weeks of April.

During the month of April, OPPD Fort Calhoun Station was inspected by Mr.

Dennis Kelley and Mr. Jim Nicholaus who performed the final portion of the Maintenance Team Inspection. The regular monthly inspection was conducted by Mr. Phil Harrell and Mr. Terry Reis. Messrs. Murphy and McKernon followed up on their previous inspection activities related to returning the station to  !

power operation. A team of inspectors from the NRC performed an assessment of the OPPD Safety Enhancement Program during the week of April 17 through 21.

The SALP period ended for Fort Calhoun on April 30, 1989.

c .

Monthly Operations Report

< April 1989 Page Two Three Licensee Event Reports were issued during April. LER 89-007 concerned identified stresses above code limits ~at the point where new feedwater regulating valves had been installed. LER 89-008 concerned discovery in March 1989 of the failure in January 1989 to complete ST-FP-2 F.2 within the required interval. LER 89-009 concerned the non-seismic installation of the inversion switch for RM-061.

No safety valves or PORV challenges or failures occurred.

A. PERFORMANCE CHARACTERISTICS None B. CHANGES IN OPERATING METHODS None C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL SP-EEQ-1 EEQ Associated Equipment Identification Check 4

This procedure did.not constitute an unreviewed safety question as defined by 10 CFR 50.59 because no test or experiment is performed on any equipment. -The procedure only verifies equipnant covered by the EEQ program contains the appropriate designation. The results of the examination were acceptable.

SP-EEQ-1 EEQ Associated Equipment Identification Check This procedure did not constitute an unreviewed safety question as defined by 10 CFR.50.59 because no test or experiment is performed on any equipment. The procedure only verifies equipment covered by the EEQ program contains the appropriate designation. The results of the examination were acceptable.

1

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Monthly Operations Report j April 1989 Page Three 1 D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL System Acceptan te Committee Packages for April 1989: (Continued)

Packaae Description /.ualvsis MR-FC-88-61 Air Check Valve for RW Discharge Valves This modification replaced non-CQE check valves with CQE check valves. Did a function check of accumulators and check valves.

MR-FC-85-028 Respirator Decontamination System This modification installed a respirator decontamination system which will decontaminate 50 to 100 mask per hour and reuse much of its water,  !

therefore reducing liquid waste.

MR-FC-85-067 Electrical Service for Mag Particle I This modification provided power for Quality Control Magnetic Particle Examination Equipment, 480 volt, 1 phase, 150 amp or 240 volt, 1 phase, 300 amp service 4 in room 69 behind stairway to the Spent Fuel Pool for '

operation of magnetic particle testing equipment as required by IE Bulletin 82-02.

FC-87-048 Diverse Scram Syste'm Testing l

This modification provided for completion of testing for Diverse Scram System (installed previously by modification MR-FC-84-203, ATWS Rule Modifications).

MR-FC-88-67 Dedicated N2 Supply for Isolation Valves This modification provided for backup motive pneumatic force to HCV-4388/D. LCV-303-1/-2, and HCV-344/345.

N2 supplies will provide actuation capabilities in the event of an IA outage. j E. RESULTS OF LEAK RATE TESTS Reactor Coolant Leak rate tests have been consistently less than .4 GPM for the entire month.

P 1

I Monthly Operations Report April 1989 Page Four  ;

F. CHANGES IN PLANT OPERATING STAFF John Borger and Pat Cronin, obtained Reactor Operator licenses G. TRAINING During the month of April, the written and walkthrough portions of the licensed operator requalification examinations were administered to five (5) license holders (3 SR0's and 2 R0's) by the NRC. The simulator portion of the examinations was administered at the CE PWR simulator.

All five licensees passed the walkthrough and simulator portions of the examination. One (1) SR0 failed the written examination. These results, ,

combined with the results of the 1987 program year examinations, upgrade the licensed operator requalification program from a conditionally satisfactory status to a satisfactory status. Both of the R0 candidates passed their initial NRC RO written and oral examinations. This brings the total number of licensed operators to 36, consisting of 10 R0's and 26 SR0's. Non-licensed operator training is in progress for Equipment Operator - Nuclear (Auxiliary Building). A Reactor Operator training class is in progress.

A job analysis for emeroency preparedness positions was distributed in April. This questier.haire is the first phase in developing a performance-based '.mergency preparedness training program. The industrial safet) contractor position was filled in April. A preliminary manager / supervisor industrial safety training program outline has been developed. An initial instructor training course was conducted in the month of April.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION f AUTHORIZATION PURSUANT TO 10CFR50.59 None II. MAINTENANCE (Significant Safety Related) .

i See attached printout.

Gary R. Peterson I Manager-Fort Calhoun Station 1

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