ML20044B216

Monthly Operating Rept for June 1990 for Fort Calhoun Station Unit 1.W/900713 Ltr

ML20044B216
Person / Time
Site:	Fort Calhoun
Issue date:	06/30/1990
From:	Gates W, Stice D OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-90-0577, LIC-90-577, NUDOCS 9007180131
Download: ML20044B216 (8)

Text

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• 1 I Omaha Public Power District 1623 Harney Omaha, Nebraska 68102 2247 402/536 4000 July 13, 1990 LIC-90 0577 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, DC 20555

References:

Docket No. 50 285 Gentlemen:

SUBJECT:

June Monthly Operating Report (MOR)

Please find enclosed the June 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, 4V). N W. G. Gates Division Manager Nuclear Operations

~WGG/sel c: LeBoeuf, Lamb, Leiby & MacRae A. Bournia, NRC Project Manager

.R. D. Martin, NRC Regional Administrator, Region IV P. H. Harrell, NRC Senior Resident inspector 90071e0131 900630 '

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I . AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT fort Calhoun Station DATE July 12, 1990 COMPLETED BY D. L. Stice TELEPHONE (402)636-2474 MONTH June'1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 100 17 447 2 111 18 449 3 112 19 471 4 130 20 472 5 245 21 473 6 298 22 103 7 423 23 0 8 467 24 35 9 469 25 240 10 404 26 218 11 449 27 299 12 424 28 453 13 442 29 467 14 443 30 469 15 445

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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 July 12, 1990 COMPLETED BY D. L. Stice TELEPHONE (402)636-2474 OPERATING STATUS

1. Unit Names fort Calhoun Station Notes

2. Reporting Period: June 1990

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): 502

5. Design Electrical Rating (Net MWe): 478

6. 302

?. Maximum Dependable Max? mum Dependable Capacity Capacity ((Gross478MWeb NetMWe):

8. If coanges 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 720.0- 4,343.0 146,953.0

12. Number of Hours Reactor wcs Critical 720T 2,011.6 113,177.9

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5

-14. Hours Generator On-Line 669.8 1,856.7 111,862.1

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. GrossThermalEnergyGenerated(MWH) 793,202.7 2,490,728.5 146,105,839.7

17. GrossElectricalEnergyGenerated(MWH) 256,408.0 ~ 809,138.0 48,019,246.2

18. Net Electrical Energy Generated (MWH) 241,548.2 -

768.124.0 45,835,676.8

19. Unit Service Factor 93.0 42.8 76.1

20. Unit Availability factor 93.0 42.8 76.1

- 21. Unit Capacity Factor (Using MDC Net) 70.2 37.0 67.7

22. Unit Capacity factor (Using DER Net) 70.2 37.0 65.1

23. Unit Forced Outage Rate 0.0 0.0 2.9

24. Shutdowns Scheduled Over Next 6 Months (lype, Date, and Duration of Esch):

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 I

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.._q DOCKET NO. 50-285' .

UNIT llAPE Fort Calhoun ' Station ' ~

DATE July 12,'1990

• UllIT SHUTDOWNS AND POWER REDUCTIONS COPFLETED BY D. L. ' Stice '

TELEPHONE (402) 636-2474

. REPORT' MONTH June 1990 E

Ucene gI E Cause a conoceve E 87 {j Action to '!

No. . Date e '% } {- e! Event g g I

c 2& 3 Report e # 3 Prevent Recurrece c S $ =E 8

90-02 900622 S 42.58 B 4* N/A XX XXXXX Maintenance Outage commenced due to

1. 8 Bearing high vibration on the -

turbine and Level Control Valve LCV-101-2 controls erratic. Rebalar,r.ed

1. 8 Bearing and refurbished LCV-101-2.

valve and operator. - Adjusted LCV-101-1 operator.

90-03 900624 5 6.46 B 4* N/A XX XXXXX Maintenance Outage commenced to i rebalance #8 Bearing on the turbine due to high vibration.

90-34 900626 F 32.2 A 4* N/A XX XXXXX Power reduced from 95% to 42% due 'to potential design concern on diesel generator voltage regulators.. Concern related to possible temperature related I

degradation of regulator components.

Interim fix consisted of removing panel doors to improve cooling. -  ;

l 1 -2 3 4 <

F-Force d Reason: . Method: Exhedt G - hatructione S-Schedided A-Egidpne FaBure (Explain) 1-Manuel for Properation of Data B-Maintenance or Test ~ 2-4denuel Scram Entry SIMets for Ucensee C-RefueInc 3-Automenc Scram Event Report (LER) File FILNEG-01619 D-Regidatory Restriction Other (Explaint .

E-Ogreator Tralrdno a 1.icense Examinetton 5 F-Adrrdnistative . Extett 1 - Some Source G-Operational Error .

H-Omer (Explain) .

• Reduced Load s (reactor remained critical) ,

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Refueling Information-

. Fort Calhoun - Unit No. I g Report for the month'ending June 19j!Q 1.4 Scheduled date for next refueling shutdown. Seotember 1991

-2. EScheduled date for restart following refueling. e November 1991  ;

L 3.: 'Wil1' refueling or resumption of operation Q thereafter require a technical- specification j change or other license' amendment? Yes i

a. If. answer is'yes, what, in general, will

, these be?-

us L Incorporate specific L, , requirements resulting i from reload safety analysis.

be - If answer is.no,.has the reloaa fuel design and ,

- core configuration been reviewed by your Plant . 1 m Safety. Review Committee to determine whether any unreviewed safety questions'are associated with the core reload. N/A R :c. ' If no such review has taken place, when is

-.it scheduled? E N/A

4. LSchedulsdLdate(s);for submitting proposed

, , licensing action and support information.

June 1991

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5. Important licensing considerations associated- y L with refueling,z e.g. , new or_ different- fuel l design.or supplier, unreviewed design or-L  ; performance analysis _ methods, significant b l changes in fuel design,,new ope Ai.ing .

pl; procedures. New fuel supplier (

g 4 Ng -LOCA Analysis N 6.e The nrber of fudl. assemblies: a) in the core . . 133 Assemblies- e u, , b) in the spent fuel pool 477 Assembl ies - l 4 c) spent fuel pool storage.

E"

! capacity .729 Assemblies

, d) planned spent fuel pool Planned. to be ' increased q storage capacity- with higher dansity spent ,

fuel racks, >

7 w o .

3 s

'7 . The projected;date of the last refueling that can be ,'

_ , cdischarged to the spent fuel pool assuming'the present licensed capacity.- 1994*

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• sCapabilityf of full core offload of 133 assemblies lost.

' Prepared by N -

Date- 7-It b s

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H OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 I

June 1990 Monthly Operating Report I. OPERATIONS

SUMMARY

Fort Calhoun Station returned to 30% power June 1,-1990, after repairing an electro-hydraulic control (EHC) oil leak on the turbine. After steam generator chemistry limits were met, power was increased beyond the 30%  ;

holdpoint. A power level of 98% was reached on June 8, On June 10, power was reduced to 94% in preparation for moderator temperature coefficient (MTC) testing. On June 12, an emergency power reduction was initiated due to a heater drain pump suction relief valve failure. Power reduction commenced and was stopped at 76%. Power was returned to 95% after the pump was' isolated. Upon completion of MTC testing, power was increased to 100%

on June 18. On June 22, the unit was taken off-line far balancing of the main generator to reduce vibration. Auxiliary feedwater pump full flow

' tests were also conducted. The unit was reloaded, taken off-line for additional balancing, and reloaded to 95% power on June -25. Due to questionable die:el generator operability (see discussion below), a unit ,

shutdown was initiated June 26, but stopped at 42% power. On June 27, Fort Calhoun Station regained 100% power operation after the diesel generator operability concern was resolved.

During the month of June, two failures occurred on the emergency diesel generator number one (DG-1) voltage regulator. The first failure occurred on June 15 durina a diesel coolant system performance test. After i approximately three hours of operation on a warm (85'F) day, a voltage regulator alfunction occurred which-caused a sudden increase in generator output current. The operator was forced to trip the generator output a breaker and subsequently shut down DG-1. -Troubleshooting revealed a blown i fuse,and 4 degraded diode bridge rectifier. These components were replaced and the surveillance test was performed on June 20 to verify DG-'l'

-operability. Subsequently on June 25 (again:during an extended engine run  :

- on an:85'F day) a similar loss of regulation occurred necessitating an ~i engine' shutdown. - - A degraded germanium transistor in the ~ voltage regulator and a blown fuse were determined to be the immediate cause of the problem.

However,!it was also noted that the -voltage regulator cabinet was quite j warm to the touch. Consultation with the regulator manufacturer (GE) h determined that the cabinet containing the regulator was-improperly-L; . ' designed, in that no ventilatian was- provided for cooling the regulator

• ' componeats. A temporary modification was immediately implemented to remove both the DG-1 and DG-2 regulator panel doors in order to provide the necessary cooling. Further DG. testing was performed during warm weather (S0'F) to verify proper operation. No operational problems occurred during a 6.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> test of DG 1 at full load. 0G-1 was declared operable on June 27.

. AnLINP0 evaluation team was on site for two weeks for the annual review of

. pl an't oper ' ons.

Three operators received Reactor Operator licenses in June.

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- Monthly Operating Report

- June 1990 1 Page Two -]

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During the month of June 1990, the work performed during the 1990 i Refueling Outage was completed or reviewed in the post maintenance work j review process. Significant maintenance is outlined below: )

The' differential pressure transmitter for the steam driven auxiliary feedwater pump, FW-10, was replaced. This transmitter is used to control-the speed, and therefore discharge pressure, of the pump. In addition,-

the steam chest drain valve for the steam turbine was- replaced. ,

' Capacitors were replaced in instrument inverters "C" and "D". This action

, was required due to inservice / shelf-life age of the capacitors.  :

During preventive maintenance activities on high pressure safety injection loop valve HCV-311, low megger readings-were observed on the motor for the ,

operator. It was discovered that a motor lead was broken about two inches from the motor. The lead was repaired. There was no indication that the valve-was' inoperable prior to discovery of the broken wire. It is OPPD's c opinion that this is an isolated case sad occurred during the preventive ,

u maintenance activity.

During performance of _the annual diesel generator overhaul for DG-1, it was discovered that the cylinder number five failed its exhaust valve leakage test. .The measured pressure was 42 PSIG vice a minimum acceptable  ;

pressure of 56 PSIG. The powcr pack for cylinder number five was replaced. The diesel vendor was on site for the replacement as this is the first failure of a power pack at Fort Calhoun Station.

The following NRC inspections.took place in June:

IR90-30 Residents' Monthly Inspection (05/15/90 thru 06/14/90)

IR90-32 Residents' Monthly Inspection (from 06/15/90 to present) -

The following LERs were submitted: Date Submitted 90-015 Non-Conservative Setpoints for the Low June 7, 1990 Temperature Overpressure Protection System 1.90-016 Potential for Overpressurization of Auxiliary June 11, 1990  ;

Feedwater Piping

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90-017 Failure to Perform Local Panel Surveillance June 27, 1990 Required by-Inappropriate Technical Specifications t

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.i i< Monthly Operating Report.

-June 1990.

Page Three A.. SAFETY VALVES OR PORY CHALLENGES OR FAILURES WHICH OCCURRED -

'None ,

B. RESULTS.0F LEAK RATE TESTS The results of the Reactor Coolant System (RCS) leak rate tests for the month of June 1990, indicate a continuation of the very low RCS leakage trend following the-1990 refueling and maintenance outage. 3 The known leakage to the Reactor Coolant Drain Tank and the Pressurizer Quench Tank varied throughout the month from 0.0.tc 0.035

.gpm. The total leak rate, which is the sum of both the known and unknown leak rates, peaked on June 17, 1990 with 0.264 gpm calculated.

Because reactor power w changed several times during the month, a .

great deal' of Deaerateo adter and Boric Acid was added to the' RCS to l 0 control reactivity. This caused more than the normal number of negative leak rate' indications and compromised the accuracy of those tests performed during reactivity changes. It is expected that reactor power will be held relatively constant throughout the summer months, therefore, more accurate leak rate tests should result.

Ci _ CHANGES; TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 r 4 Amendment No. Description  ;

None II.- MAINTENANCE (Significant Safety Related)

, See Section'I' Operations Summary L

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Gary R..Peterson E Manager-Fort Calhoun Station L.

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