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AVERAGE DAILY UNIT POWER LEVEL.

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DOCKET NO. 50-285UNIT Fort Calhoun StationDATE April 14. 1989COMPLETED BY B. E. Stanlev

| TELEPHONE 402-636-2456

,-

MONTH March 1989 !

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL(MWe-Net) (MWe-Net)

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1 472 17 469 |2 472 18 469

3 472 19 469

4 471 20 469

5 470 21 469

6 470 22 468

| 7 470 23 468

8 461 24 4681 9 469 25 467

10 468 26 467

11 469 27 466

12 469 28 468

13 469 29 468_

14 469 30 468

15 470 31 469

16 470

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INSTRUCTIONSi

On this format, list the average daily unit power level in MWe-Net for each dayin the reporting month. Compute to the nearest whole .negawatt.

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8904250087 890331 "

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OPERATING DATA REPORT-

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IDOCKET N0. 50-285 l

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UNIT Fort Calhoun StationDATE April 14. 1989

COMPLETED BY B. E. StanlevTELEPHONE 402-636-2456

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1

OPERATING STATUS

1. Unit Name: Fort Calhoun Station Notes2. Reporting Period: March 19893. LicensedThermalPower(MWt): 15004. Nameplate Rating (Gross MWe): 502 .

5. Design Electrical Rating (Net MWe): 478 I6. Maximum Dependable Capacity (Gross MWe): 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. 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 2.160.0 136.010.012. Number of Hours Reactor Was Critical 744.0 l'478.5 104.828.3.

13. Reactor Reserve Shutdown Hours 0.0 0.0 1.309.514. Hours Generator On-Line 744.0 1.423.2 103.838.5

;

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 1

16. GrossThermalEnergyGenerated(MWH) 1.111.925.9 1.864.823.7 134.753.817.6 i17. GrossElectricalEnergyGenerated(MWH) 365.414.0 608.010.0 44.352.138.218. Net Electrical Energy Generated (MWH) 348.889.1 576.969.4 42.348.474.219. Unit Service Factor 100.0 65.9 76.320. Unit Availability Factor 100.0 65.9 76.321 UnitCapacityFactor(UsingMDCNet) 98.1 55.9 67.422. Unit Capacity Factor (Using DER Net) 98.1 55.9 65.723. Unit Forced Outage Rate 0.0 0.0 2.924. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

On the weekend startina April 28. 1989. Fort Calhoun Station plans to shutdown toperform turbine overspeed trip test. Startup will commence on April 30. 1989.

25. If Shut Down at End of Report Period, Estimated Date of Startup: N/A26. Units In Test Status (Prior to Commercial Operation): Forcast Achieved

INITIAL CRITICALITY____

INITIAL ELECTRICITY N/ACOMMERCIAL OPERATION

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Refueling InformationFort Calhoun - Unit No. 1

Report for the month ending March 1989

1. Scheduled date for next refueling shutdown. February 1990

2. Scheduled date for restart following refueling. May 1990 1

3. Will-refueling or resumption of operation thereafter! require a technical specification change or other

- license amendment? Yes

i a. If answer is yes, what, in general, willthese-be?

| - Incorporate specific requirements| resulting from reload safety analysis ;

lb. If answer is no, has the reload fuel design j

and core configuration been reviewed by]your Plant Safety Review Committee to deter-1

mine whether any unreviewed safety questions a

are associated with the core reload,

c. If no such review has taken place, when isit scheduled?

4. Scheduled date(s) for submitting proposed licensingaction and support information. January 1990

5. Important licensing considerations associated withrefueling, e.g., new or different fuel design orsupplier, unreviewed design or performance analysismethods, significant changes in fuel design, new '

operating procedures. None Planned

6. The number of fuel assemblies: a in the core 133 eesembliesb in the spent fuel pool 437 "

c spent fuel pool |

storage capacity.

729 "

d) planned spent fuel pool May be increasedstorage capacity via fuel ein

consolidation

7. The 3rojected date of the last refueling that can bedisclarged to the spent fuel pool assuming the presentlicensed capacity. 1994*

* Full core offload of 133 assenslies lost.i

Prepared by %%A Date April 11, 1989:

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OMAHA PUBLIC POWER DISTRICT i'Fort Calhoun Station Unit No. 1

March 1989Monthly Operations Report

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I. OPERATIONS SUMMARY

Fort Calhoun Station operated at a nominal 100% power throughout the month,

of March, 1989. Major operational items included the loss of the 161 KV'

offsite power source. Five towers were damaged by a storm and took amajor effort by the line department to repair. A containment entry wasrequired to repair a damper on containment cooling and filtering unitVA-3A. Circulating water pump CW-1A was removed from service for ;

inspection / repair and for replacement of the discharge expansion joint.

The design basis reconstitution effort identified stresses above codelimits at the point where new feedwater regulating valves had beeninstalled. A temporary modification was installed which reduced thestress on the piping. The removal of the General Employee Training ;building was started. An Emergency Plan drill was conducted on March 29, j

1989. ji

Annual Licensed Operator simulator training at Combustion Engineering in !Windsor, Connecticut started March 6, 1989. This training introduces thetwo column format for the E0P's. ;

1The following inspection activities took place during the month of March,1989. The regular monthly inspection was conducted by Mr. Phil Harrell,and Mr. Terry Reis. Mr. R. A. Caldwell inspected the Security area duringthe week of March 27 through March 31, 1989. Mr. Ricketson and Mr.

i

Nicholas inspected the radwaste and effluent program during the week ofFebruary 27 through March 3, 1989.

The NRC Maintenance Team Inspection was conducted during the week of March.

13 and March 27. Team members were Dennis Kelley, Amarjit Singh, John |Huang, Jeff Hansen, Bob Vickrey and Mike Skow. Mr. Jim Gagliardo was also |at Fort Calhoun during most of the inspection. '

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One Licensee Event Report, 89-006, was issued during March. This LERconcerned failure to complete surveillance test ST-FO-2 within therequired interval.

No safety valves or PORV challenges or failures occurred.

A. PERFORMANCE CHARACTERISTICS i

None

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Monthly Operations Report i

March 1989Page. Two ;

B. CHANGES IN OPERATING METHODS

None

C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS

Required Surveillance Tests completed satisfactorily.

D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSIONAPPROVAL'

i

SP-FW-3 Feedwater Heater 4A Eddy-Current Testing

| This procedure did not constitute an unreviewedsafety question as defined.by 10 CFR 50.59 becausethe procedure only verifies the integrity of thefeedwater heater tubes by a non-destructivetesting method (Eddy-Current Testing). Therecommendations in the test have been implemented.

System Acceptance Committee Packages for March 1989:

Packaae Description / Analysis

MR-FC-89-004 Kerotest 3-Way Valve Replacement

This modification _provided for the replacement ofthe FT-343 Kerotest 3-way Valve manifold with aDragon 3-way Valve manifold. The modificationupgraded the 3-way manifold to a more efficientdesign.

MR-FC-88-ll8 Instrument Air Test Tees

This modification provided for Test tees for YCV1045A/1045B.

MR-FC-87-063 Diesel Generator Radiator Exhaust Damper Valves

This modification is-to replace the DieselGenerator radiator exhaust damper operator with anoperator which will not be dependent on a smallported orifice pilot valve.

MR-FC-87-32 Air Maintenance for Fire Protection Deluge

This modification provided air compressors for thefire protection deluge system for Room 19 and forDiesel Generator Room.

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Monthly Operations Report. March 1989Page Three

MR-FC-86-096 RPS Power Supplies

This modification provided for replacementcalibration and testing for Reactor ProtectiveSystem (RPS) matrix relay and axial powerdistribution calculator power-supplies.

MR-FC-84-159 Metrascope Changeout

This modification provided for removal of existingmetrascope equipment, modification of CB-4 andCB-4 AUX control panel, installation of new CEAPISequipment, the interconnection of CEAPIS

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components. Testing consisted of calibration andcomparison / verification of associated components.

MR-FC-84-012 RPS Isolated Outputs

This modification installed new signal isolatorsto prevent interference and allow permanentconnection of the VLPM.

MR-FC-87-054 Fire Protection System Upgrade

This modification builds in redundant supplycapabilities between the turbine building andauxiliary building.and between the. turbinebuilding standpipe and supply loops.

MR-FC-89-008 Main Steam Line Penetration M-94 & M-95 Bellows |

Pad Re-enforcement

This modification provides for protection to thestructural system which is the floor slab AX-303and beams B-53 & B-54. This requirement is theresult of the possible occurrence of a main steam

iline break at the containment penetration No. M-94 j& M-95. '

4

E. RESULTS OF LEAK RATE TESTS |

During the months of February and March, twelve Containment entrieswere made, followed by Type B Leak Rate Tests on the Personnel Access-Lock'(PAL)0-ringSeal. No leakage in excess of allowable limits wasdetected. No other Leak Rate Tests were performed.

F. CHANGES IN PLANT OPERATING STAFF<

| None

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Monthly Operations ReportMarch 1989Page Four

G. TRAINING

During the month of March, Licensed and Non-licensed OperatorRequalification Training was conducted. Classroom training for theSR0 class continued. Training using the Combustion Engineering PWRsimulator began. Preparation of the written, walkthrough (i e.,.

JPM's), and simulator portions of the upcoming licensed operatorrequalification examinations was completed. One SR0 license wasdropped on March 31, 1989. The total number of licenses is now 34,consisting of eight R0's and 26 SR0's. The sixth week-of SystemEngineer training was completed. Subject Matter Expert ~(SME)interviews were conducted on all General Employee Training lessonplans. Completion of the job analysis survey for EmergencyPreparedness (EP)trainingwascompleted. Requalification EPtraining continued. A total of 65 maintenance classes wereconducted. The initial Chemistry and Radiation Protection ShiftQualification training was ongoing throughout the month..

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORYCOMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59

None

II. MAINTENANCE (Significant Safety Related)

See attached printout.

| AV hW. Gary G~esManager-Fort Calhoun Station

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Omaha Public Power District1623 Harney Omaha. Nebraska 68102 2247

402/536 4000

April 14, 1989

|LIC-89-193

U. S. Nuclear Regulatory CommissionDocument Control DeskMail Station P1-137Washington, DC 20555

Reference: Docket No. 50-285

Gentlemen:

SUBJECT: March Monthly Operating Report E)

Pursuant to Technical Specification Section 5.9.1, and 10 CFR Part 50.4(b)(1),please find enclosed one copy of the March 1989 Monthly Operating Report forthe Fort Calhoun Station Unit No. 1.

Sincerely,

r7 ; j [is/ %.?K', J'. Morr

'

Div'ision ManagerNuclear Operations

KJM/bes

Enclosures

c: P. H. Harrell - NRC Senior Resident inspectorNRC Regional OfficeOffice of Management & Program Analysis (2)R. M. Caruso - Combustion EngineeringR. J. Simon - WestinghouseNuclear Safety Analysis CenterINP0 Records CenterAmerican Nuclear Insurers

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