ML20072S726

Monthly Operating Rept for Mar 1991 for Fort Calhoun Unit 1

ML20072S726
Person / Time
Site:	Fort Calhoun
Issue date:	03/31/1991
From:	Edwards M, Gates W OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-91-121R, NUDOCS 9104170009
Download: ML20072S726 (9)

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Omaha Pubtle Power District 444 South 16th Street Mall Omah" Nebtaska 081024.247 402/036 2000 April ll, 1991 LIC 91 121R V. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station Pl-137 Washington, DC 20555

Reference:

Docket No. 50 285 Gentlemen:

SUBJECT:

Ma'ch Monthly Operating Report (HOR)

Please find enclostd the March 1991 Monthly Operating Report for the fort Calhoun Station Uni No. I as required by Tecinical Specificati6n Section 5.9.1.

If you should have any questions, pleese contact me.

Sincerely, 1

bW.,G.$. Gates Division Manager Nuclear Operations WGG/sel l Enclosures c: LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator, Region IV R. P. Hullikin, NRC Senior Resident inspector j D. I: Sentell, Combustion Engineering R. J. Simon, Westinghouse /

Office of Mana?cment & Program Analysis (2) /

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! AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 285 UNIT fort talhoun Station DATE April 3, 1991 COMPLETED BY R.L. Edwards TELEPHONE T4U71536-2451 MONTH _ March 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 327 _____

17 .328 2 327 18 ___

327 3 328 19 326 4 328 20 326 5 328 21 326 6 328 22 326 7 327 23 326 8 327 24 326 9 328 25 327 10 327 26 327 11 327 27 326 12 328 28 325 13 327 29 326 14 292 30 327 15 325 31 326 16 328 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.

. CPERATING DATA REPORT DOCKET NO. 50-285 UNIT fort Calhoun Station DATE April 3, 1991 COMPLETED BY R.L. Edwards TELEPHONE T4Ii2T635~743I l

O ERATING STATUS

1. Unit Names Fort Calhoun Station Notes

2. Reporting Period: March 1991

3. Licensed Thermal Power (MWt): 1500

4. NameplateRating(GrossMWe): 50~2

5. Design Electrical Rating (Net MWe): 478

6. MaximumOcpendableCapacity(GrossMWe): 502

7. MaximumDependableCapacity(NetMWe): ~478

8. If changes occur in Capacity Ratings (Item Numbers 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_ 2,160.0 ~

153,530.0

12. Number of Hours Rear, tor was Critical 744,0 "

1,980.0 118,76E7~

13. Reactor Reserve Shutdown Hours 0.0 0. 0 _ 1,309.5

14. Hours Generator On-Line 744.0 1.969.2 ll7.399 T

15. Unit Reserve Shutdown Hours OT 0.0 0.0

16. GrossThermalEnergyGenerated(MWH) 778 550.9 2,408,311.6 153,691,800.9

17. Gross Electrical Energy Generated (MWH) Y574EE0~ 802,290 T 50 552,416.2

18. HetElectricalEnergyGenerated(MWH) T4D5BT 759.276.2_ ~~4d744,052.5

19. Unit Service Factor 100.0 91.2 76.5 ~

20. Unit Availability Factor ITiOTO 91.2 ~

76.5

21. UnitCapacityFactor(UsingMDCNet) TE1 73.5 68.1

22. Unit Capacity Factor (Using DER Net) 66.1 73.5 66.6

23. Unit forced Outage Rate 0.0 ..

8.8 3.6

24. Shutdowns Scheduled Over Hext 6 Months (Type, Date, and Duration of Each):

25. If Shut Town 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 _

Refueling Information Fort Calhoun Unit No. 1 Report for the month ending _tiarch 1991

1. Scheduled date for next refueling shutdown, lanary_J1.1992

2. Scheduled date for restart following refueling. tiny _L_192

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

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 determine whether any unreviewed safety questions are associated with the core reloao. tyA

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

4. Scheduled date(s) for submitting proposed licensing action and support information. Novembe d 1).

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. New fuel supplier tiew LOCA Analysis

6. The number of fuel assemblies: a) in the core 113 Ang_mAligt b) in the spent fuel pool 477 Assemblies c) spent fuel pool storage capacity 129 Assemblies d) planned spent fuel pool Planned to be increased storage capacity with higher density spent fuel racks.

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1995

• Capability of full core offload of 133 assemblies lost.

Prepared by b jlMC- Date 44 1'

DOCKET l'O. 50-285 UNIT NME Fort Calhoun Station DATE April 8, 1991 UNIT SilUIDOWNS AND POWER REDUCTIONS COMPEETED BY M _ L_ Edwards TEEEPIIONE (4021 636-2 tis t REPORT M0 Hill Mareh 1991

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E S 0 H 4 N/A ZZ ZZZZZZ Continued operation at reduced power 91-01 910211 level (701) to allow extension of the fuel cycle to' January 1992.

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OMAHA PUBLIC POWER DISTRICT fort Calhoun Station Unit No.1 MARCH 1991

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Monthly Operating Report ()iOR) 4

1. OPERATIONS

SUMMARY

With the exception of March.14, fort Calhoun Station (fCS) operated at 70% ,

a power during March, 1991. On March 14, during monthly surveillance testing i 4

of the safety injection tank boron concentration, one of the four-tanks was l found to contain less than the 1900 )pm boron concentration as required by Technical Specifications. A plant slutdown was initiated when the concentration could not be corrected within the one hour limiting condition for operation. The power decrease was stopped at 45% when the safety injection tank was returned to an operable condition with greater than 1900

. ppm boron concentratio.1. An investigation of this event is continuing and ,

all four safety injection tanks have had concentrated boric acid added to prevent recurrence of the condition.

has been revising and/or reconstituting '

Omaha the FCS electrical Public Power designDistrict basis ca(OPPD)lculations and analyses over the past eighteen months. This review has discovered the following two design basis issuest As mentioned-in the february 1991 MOR, OPPD has discovered a potentici  ;

condition outside.the design basis for the station's Offsite Power Low  ;

- Signal (OPLS) degraded voltage protection system. The OPLS design basis requires that the 480 VAC system be maintained above 90% of rated voltage for all safeguards loads. The potential existed that in some heavily loaded conditiens with a degraded 161XV system, the 480 VAC system could fall below the design basis without OPLS actuating as designed. New OPLS setpoints based on an acceptable-configuration of the stations electrical distribution system were installed February 13, 1991. Additionally, restrictions on bus loading were implemented to limit the potential for falling below the design basis limits. further analysis is being performed to determine if station loading restrictions can be refined to allow more operational . flexibility.

An analysis of the-161KV system down to the 480 volt motor control center (MCC) molded case circuit breaker coordination has been reviewed. OPPD has discovered that some of the 480 volt loads have circuit breakers with trip curves that slightly overlap with the'480 volt load center feeder breaker trip curves. The curve overlap could result in the tripping of a MCC due to a fault on one of its non coordinated loads. . Twenty-one-breakers were found to have this problem. Two loads- for which the load breakers trip curves overlap are in a harsh environment. As a precautionary measure, one of the. tw0 breakers has been tagged o>en until a. satisfactory solution can ,

be implemented and the other breaker las had the identified load removed.

- The NRC was notified of this design basis problem on March 20, 1991. A Safety Analysis for Operability (SAO) was approved by the Plant Review

. Committee (PRC) on March 25, 1991.to justify continued plant operation until the breaker coordination problem can be resolved.

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Monthly Operating Report Page 2 March 1991 During March 1991, the following tests and modifications were performed on the diesel generators:

Air flow testing through each diesel generator (DG) radiatr* was performed following radiator steam cleaning and fin straightening. flow increases of approximately 8% for DG 1 and 4% for DG 2 wer casured. This should correspond to DG jacket water operability temperature limit increases of approximately one degree for each percentage increase in tir flow. Presently, the jacket water operability temperature limit for DG 1 is 103*F. (outdoor ambient air temperature) and 100' f. (outdoor ambient air temperature) for DG-2.

A modification installed a new engine speed sensing device on DG 1 and DG-2.

The following NRC inspections took place in March:

IR 91 05 first portion of Resident inspectors' Routine Inspection IR 91 01 Electrical Distribution System functional Inspection (EDSft)

(to April 5, 1991) 1R-91-06 Security The following LERs were submitted:

LER 91-02, " VIAS Actuation During Primary System Sampling" LER 91-03, " Containment Penetration M-3 Outside Design Basis" LER-91-04, 'Off site Power low Signal Outside Design Basis" A. SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED None B. RESULTS OF LEAK RATE TESTS The reactor coolant leak rate tests showed that the reactor coolant system (RCS) and chemical and volume control system (CVCS) had a very low leak rate during March, 1991. During the month RCS leakage averaged 0.08 gpm divided equally between "known' and " unknown" leakage.

There were a few instances of negative leak rates which are attributed to normal random variation of the test data in conjunction with the low average leak rate.

The maximum leak rate for the month was recorded on March 9, when leakage from charging pump CH-1A was suspected. The operating charging pump was switched and CH 1A was isolated. A repeat of the leak rate test showed a reduction in the total leak rate from 0.360 gpm to 0.040 gpm and a reduction in the unknown leak rate from 0.328 gpm to 0.005 gpm. This verified that the leakage was from CH 1A which was subsequently re-packed and satisfactorily tested, i

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1 i [MonthlyOperatingReport Page 3 March 1991 C. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10 CFR 50.59 6!pendment No. Descrintion 137 This amendment makes changes to the fort Calhoun Station Technical Specifications to allow operation of the chemical and radiation protection / radioactive waste processing building.

138 This amendment makes changes to the fort Calhoun Station Technical Specifications to add the hydrogen purge system.

D. SIGNiflCANT SAFETY RELATED MAINTENANCE FOR THE MONTH Of MARCH 1991 During surveillance testing, an engineered safeguards lockout relay (86A/PPLS) failed to trip although the supervisory light indicated that the relay was getting a trip signal. The cause of failure was traced to binding of the relay's mechanical linkage. The mechanical linkage was adjusted, lubricated and post maintenance testing determined that the relay operated satisfactorily.

During trouble shooting, the backwash control valve (HCV 28050) for raw water strainer AC 12B was found to have a torn rubber liner. A new valve liner was installed and operability testing verified that there were no flange leaks with the valve in service.

The solenoid valve (HCV 480A 20) for the component cooling water inlet valve to shutdown cooling heat exchanger AC 4A was leaking air through the vent. The cause of failure was determined to be normal wear and the solenoid was replaced. Applicable sections of the surveillance test were performed to verify operability.

During predictive maintenance order testing, containment spray pump S1 30 showed abnormal vibration. The coupling alignment and motor magnetic check were found to be within tolerance. The survelliance test was performed and the vibration readings were found to be within the specifications.

The manual racking interlock for 51-3C was out of adjustment and failed to operate the breaker during the calibration procedure. The interlock was adjusted and operability was verified during post maintenance testing.

Diesel work for the month included:

DG-1 Access doors were installed in the radiator duct work, the radiator core exterior was steam cleaned, and the cooling fins were straightened. The radiator exhaust duct work and associated chimney area were inspected.

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'. ' Monthly Operating Report Page 4 Mhrch 1991 DG 2 Access doors were installed in the radiator duct work, the radiator core exterior was steam cleaned, the cooling fins were straightened and the fan pitch was adjusted. Performed radiator fan blade pitch testing which verified that the fan pitch is set at its optimum level.

During surveillance testing, the fuel oil transfer pump motor (f0 4A 2 M) tripped the breaker when attempting to start. A new pump motor was installed after a short circuit in the motor windings was found. Applicable sections of the surveillance test were performed to verify pump operability.

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