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Omaha Public Power District1623 Harney Ornaha, Nebraska 68102 2247.

402/536-4000

May 15, 1990LIC-90-0410

U. S. Nuclear Regulatory CommissionAttn: Document Control DeskMail Station PI-137Washington, DC 20555

References: Docket No. 50-285

Gentlemen:

SUBJECT: April Monthly Operating Report (MOR)

Please find enclosed one copy of the April 1990 Monthly Operating Report forthe Fort Calhoun Station Unit No. I as required by Technical SpecificationSection 5.9.1.

If you should have any questions, please contact me.

Sincerely,

m 2. A s.W. G. GatesDivision ManagarNuclear Operations

WGG/dls

c: LeBoeuf, Lamb, Leiby & MacRaeR. D. Martin, NRC Regional Administrator, Region IVP. H. Harrell, NRC Senior Resident InspectorR. M. Caruso - Combustion EngineeringR. J. Simon - Westinghouse

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Office of Management & Program Analysis (2);Nuclear Safety Analysis CenterINP0 Records CenterAmerican Nuclear Insurers

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9005180170 900430

{DR ADOCK05002p3

45 5W Empiovmen un uaiopponunnu

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AVERAGE DAILY UNIT POWER LEVEL {,.

DOCKET NO. 50-285UNIT Fort Calhoun StationDATE May 11, 1990COMPLETED BY D. L. SticeTELEPHONE (402)636-2474 >

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MONTH _ April 1990 ,

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

1- 0 17 0 *

2 0 18 0'

3 0 19 0

4 0 20 0_

5 0- 21 0

6 0 22 0

7 0 23 0

8 0 24 0

9 0 25 0 4

10 0 26 0

11 0 27 0

12 0 28 0

13 0 29 0

I 14 0 30 0

15 0

16 0

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-. q,

DOCKET NO. 50-285 !UNIT Fort Calhoun StationDATE May ll,1990COMPLETED BY D. L. SticeTELEPHONE (402)636-2474 ;

OPERATING STATUS

1.. Unit Name Fort Calhoun Station Notes-2. Reporting Period: April 19903. Licensed Thermal Power (MWt): 15004. NameplateRating(GrossMWe): 5025. Design Eler.trical Rating (Net MWe):- 4786. MaximumDependableCapacity(GrossMWe): 5027. Maximum Dependable Capacity (Net MWe):- 4788. If changes occur in Capacity Ratings (Item Numbers 3 through 7)'Since Last Report,

Give Reasons: 4N/A ,

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9. PowerLeveltoWhichRestricted,ifAny(NetMWe): N/A10. Reasons for Restrictions, If Any: N/A

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 719.0 2,879.0 145,489.0_

12. Number of Hours Reactor was Critical 0.0 1,142.1 112.308.4 i13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5

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14. Hours Generator On-Line 0.0 1,130.6 111.136.0 .15. Unit Reserve Shutdown Hours 0.0- 0.0 0.016. Gross Thermal Energy Generated (MWH) 0.0 1,675,900.7 145,291,011.917. Gross Electrical Energy Generated (MWH) 0.0 546,866.0 47,756,974.218. Net Electrical Energy Generated (MWH) 0.0- 521,906.2 45,589,459.019. Unit Service Factor 0.0 39.2 76.420. Unit Availability Factor 0.0 39.2 76.421. UnitCapacityFactor(UsingMDCNet) 0.0 37.9 68.022. Unit Capacity Factor (Using DER Net) 0.0 37.9 66.423. Unit Forced Outage Rate 0.0 0.0 2.924. Shutdowns Scheduled Over Next 6 Months (Type,-Date, and Duration of Each):

The 12th Refuelino Outage commenced on February 17, 1990 with startupscheduled for May 22, 1990.

25. If Shut Down at End of Report Period, Estimated Date of Startup: May 22,199026. Units in Test Status (Prior to Commercial Operation): Forcast Achieved

INITIAL CRITICALITYINITIAL ELECTRICITY N/ACOMMERCIAL OPERATION

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DOCKET NO. 50-285UNIT NAE Fort Calhoun Station -

DATE May 11, 1990UNIT SHUTDOWNS AND POWER REDUCTIONS COPFLETED BY D. L. ~ Stice '

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TELEPHONE (402) 636-2474 -

REPORT MONTH April. 1990_

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E oo5 ucense. 7 )s cause a corrective::- g-b hykh

' EventNo. Date ~5 8 Action te

C E- ) Report * 5 8 M&o u8

90-01 900217 5 1748.4 C 1 N/A XX XXXXXX On February 17, 1990, the 12th FortCalhoun Station Refueling Outagecommenced.

1 2 3 -4

F-Forced Reasert - Method ExNbit G - hetructicosS-Scheduled A-Equipment Fagure (Explain) 1-4 Annual for Preparation of Data

B-Maintenance or Test 2-teanuel Scram Entry Shoots for t.lcanoesC-RefueIng 3-Automatic Scram'. Event Report it.ER) F5e IPUEG-0181|D-Regulatory Restriction 4-Other (ExplaintE-Operator Training & Ucense Examination 5F-Administative ExNbit 1 - Same SourceC-Operational Ener -H-Other (Explain)

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' R:fus11ng Information-'

Fcrt C:lh:un - Unit No. 1',,

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. Report for the month ending April 1990

1. Scheduled date for next refueling shutdown. February 17. 1990

2. Scheduled date for restart following refueling. May 22. 1990

3. Will refueling or resumption of operation thereafterrequire a technical specification change or otherlicense amendment? Yes

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

1) Decrease the total unrodded integratedradial-penking factor from 1.80 to 1.70.

2) Decrease the total unrodded planar radialpeaking factor from 1.80 to 1.75.

3) Decrease the PLHGR from 15.22 to 14.4 Kw/ft4) Change the TM/LP P equation to reflect avar

change in the gamma term from -11350 to -11240.

b. If answer is no, has the reload fuel designand core configuration been reviewed.byyour Plant Safety Review Committee to deter-mine whether any unreviewed safety questionsare associated with the core reload. N/A >

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

4. Scheduled date(s) for submitting proposed licensing iaction and support.information. Submitted Jan. 1990

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refueling, e.g., new or different fuel design or,

supplier, unreviewed design or performance analysismethods, significant changes in fuel-design, newoperating. procedures. None

6. The number of fuel assemblies: a) in the core 133 assembliest.b) in the spent fuel pool 437 =

c) spent fuel poolstorage-capacity 729 " <

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

consolidationor dry cask storage i

| 7. The projected date of the last refueling that can be| discharged to the spent fuel pool assuming the present >| licensed capacity. 1994*

* Capability of full core offload of 133 assemblies lost.

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l Prepared by eIC 6fdM Date May 8. 1990

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OMAHA PUBLIC POWER DISTRICTFort Calhoun Station Unit No. 1

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April 1990 !Monthly Operating Report

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I. OPERATIONS SUMMARYtFort Calhoun Station continued with its twelfth refueling and maintenance

outage. Outages for trip testing and preventive maintenance were-conducted on 345 KV off-site power, an in house 4160 V bus,,and several480 V buses. Maintenance and testing were also conducted on 120 VAC <

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instrument buses.' The annual inspection was started on emergency diesel

|generator DG-2.

| The component cooling water system and the raw water system were returnedto service from extensive maintenance outages. Ten incore detectors werereplaced. The s)ent fuel ppol cooling system was returned to service with;completion of t1e component cooling water system and raw water system-

outages. The temporary spent fuel pool cooling system was. removed.from-service. The reactor core was reloaded and the reactor internals were 'replaced. Emergency Safety Feature (ESF) testing was performed. Duringreplacement of the reactor vessel head, the head prematurely contac'ed thealignment pins. Both alignment pins were bent and there was superficialdamage to the head flange. The alignment pins were straightened and minorrepairs to the head flange were completed. The polar crane:was thor)ughly

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inspected and all affected equipment was evaluated and determined to beoperable. The reactor vessel head was then set and tensioned. Coup 1ing -of the Control Element Drive Mechanism was- started.

L The following are some of the modifications that'were in progress duringApril: DC sequencer replacement; diesel generator fuel oil pumps;redundant power supply for raw water / component cooling interface valves;'increasing the minimum flow of the main feedwater pumps; replacement ofarea radiation monitors; redistribution of loads on the DC buses andinverters; control room heating, ventilation and air conditioning (HVAC)habitability upgrade; containment equipment hatch crane; emergencyresponse facility computer terminal; addition of third auxiliary feedyrerpump; reactor coolant' system narrow range mid-loop level indication; steamgenerator blowdown tank erosion; feedwater regulating valve supports;steam driven auxiliary feedwater pump speed control; alternate shutdownpanel for fire protection; auxiliary feedwater valve supports; limitorquevalve operator thermal overloads; and containment sump pump levelindication and control.

The following modifications for control room design review for human ifactors have been in progress: reactor regulating system / steam dump and ibypass alarms; meter scales; replacement of oddly shaped switch handles;labeling, demarcation, meter banding, and color padding.

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;. . , .Monthly Operating ReportPage Two

The following NRC inspections took place in April:

IR 90-13- Residents' Monthly Inspection (continued fromi

March 1,-1990)4 IR-90-22 Follow-up Non-Destructive Examination

IR-90-23_ Safety Enhancement Program Items.IR-90-2S Security

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IR-90-26 Residents'< Monthly Inspection (from April"15,1990)-

IR-90-27- Maintenance Testing _IR-90 28 Modification and Design ChangesIR-90-29 Emergency Planning

The following LERs were submitted: Date Submitted l!.

90-003 Rev 1 Containment Piping System.0utside Design ~ . April 16, 1990 iBasis-

90-007 Rev 1 Main Feedwater Piping Outside Design April 23, 1990,Basis

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90-008 Inadvertent Actuation of Pressurizer April 05,1990 1Pressure Low Signal

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90-009 Potential Over-Pressurization of April'23,-1990,

Auxiliary Feedwater Piping,

90-010 Unplanned Attempted Start of Emergency ' April 26, 1990 .!| Diesel Generator- || J

| A. SAFETY VALVES OR PORY CHALLENGES OR FAILURES WHICH OCCURRED- !'

aNo PORV or Safety Valve challenges or failiares occurred. a

B. RESULTS OF LEAK RATE-TESTS 4

|' During the month of April'1990, the Reactor was in refueling-shutdown-i condition (Mode 5). Therefore, the Reactor Coolant System Leak. Rat( test, ST-RLT-3 F.1, was not performed. j

C. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY l..

COMMISSION' AUTHORIZATION PURSUANT TO 10CFR50.59- i

Amendment No. Descriotion

No. 126 This amendment modifies the Fort Calhoun- Technical i' Specifications to support -the cycle 13 operation

and makes corrections -to some typographicalerrors.

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Monthly Operating ReportPage Three

Amendment No. Descriotion

No. 127 - This amendment modifies the Fort Calhoun Technical-Specifications to allow performance of afunctional test of the steam driven auxiliary

-feedwater pump prior,to achieving criticality.--This amendment also makes some administrativechanges.

No. 128 .This amendment makes changes to the Fort CalhounTechnical Specifications to provide limitingconditions for operation and surveillance 'requirements consistent with modifications thatwill be made to the control room air treatment- !system. I

No. 129 This amendment removes the-provision of-the' FortCalhoun Technical Specification 3.0.1 that limits

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-the combined time interval for any three--. 1

consecutive surveillances to less:than 3.25 times qthe specified interval. The remaining interval

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for surveillance is 25 percent.

II. MAINTENANCE (Significant Safety Related)

See Section I Operations Summary !lq

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Gary R. PetersoniManager-Fort Calhoun Station j

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