ML20113F298

Monthly Operating Rept for Dec 1984

ML20113F298
Person / Time
Site:	Fort Calhoun
Issue date:	12/31/1984
From:	Andrews R, Munderloh D OMAHA PUBLIC POWER DISTRICT
To:	Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-85-004, LIC-85-4, NUDOCS 8501230596
Download: ML20113F298 (9)

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OPERATING DATA REPORT DOCKET NO.

50-285 DATE Januarv 4, 1985 COMPLETED BY D. J. Munderloh TELEPilONE 402-536-4001 OPERATING STATUS Notes Fort Calhoun Station

1. Unit Name:

2. Reporting Period:

December, 1984 1500

3. Licensed Thermal Power (MWt):

501

4. Nameplate Rating (Gross MWe):

478

5. Design Electrical Rating (Net MWe):

501

6. Maximum Dependable Capacity (Gross MWe):

478

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

N/A N/A

9. Power Level To which Restricted,if Any (NoneNet MWe):

10. Reasons For Restrictions.If Any:

This Month Yr.-to-Date Cumulative 744.0 8,784.0 98,786.0

11. Hours In Reporting Period 715.7 5,386.3 75.280.2

12. Number OfIlours Reactor Was Critical 0.0 0.0 1,309.0

13. Reactor Reserve Shutdown flours 701.5 5,264.9 74,667.4'

14. Ilours Generator On.Line 0.0 0.0 0.0

15. Unit Resene Shutdown flours

16. Gross Thermal Energy Generated (MWil) 944,280.7 7,427,053.3 94,186,767.0

17. Gross Electrical Energy Generated (MWil) 317,164.0_,

2,452,056.0 30,769,625.0 301,110.2 2,331,768.6 29,411,637.3

18. Net Electrical Energy Generated (MWill 94.J 59.9 75.6

19. Unit Senice Factor 94.3 59.9 75.6

20. Unit Availability Factor 84.7 55.5 64.8

21. Unit Capacity Factor (Using MDC Net) 84.7 55.5 62.6

22. Unit Capacity Factor (Using DER Net) 5.7 6.3 3.8

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Nest 6 MonthsIT)pe. Date.and Duration of Each):

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):

N/A Forecast Achieved INITIAL CRITICALITY INITI AL ELECTRICITY COMMERCIAL OPER ATION 9501230596 841EUI PDR ADOCK 05000285 (9/77)

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?,'o AVERAGE DAILY UNIT POWER LEVEL n

50-285 DOCKET NO.

UNIT Fort Calhoun Unit. 1 DATE January 4. 1985-D. J. Munderloh COMPLETED BY TELEPHONE 402-536-4001 MON 111 December, 1984 DAY AVERAGE DAILY POWER LEVEL

-DAY AVERAGE DAILY POWER LEVEL (MWe-NetI (MWe-Net) 0.0

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482.4 g

37 483.2 2

2.1 33 483.8 96.7 39 3

484.5 101.6 20 4

433.6 187.9 5

21 436.4 484.8 6

22 475.4 484.6 l

7 33 482.4 484.3 8

24 483.0 484.5 9

25 482.5 484.8 10 26 485.2 483.0 27 gi 482.3 473.1 12 28 40I'9 339.6 13 29 481.7 337.4

,4 30 482.5 426.2 g3 3

483.0

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INSTRUCTIONS On this forniat. list the aserage daily unit power level in MWe Net for each day in the reporting inonth. Cinnpute to the nearest whole nwgawatt.

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50-285 DOCKET NO.

Fort Calhe-n Unit No.

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT N AME DATE Jnnunrv 4_

1985 COMPLETED BY D. J. Munderloh December, 1984 TELEPHONE 402-536-4001 REPORT MONTH

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Cause & Corrective 5_ E

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Y Ucensee E-r, o-'

Action to f'8 S.

Date i

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a 2sS Event u?

Prevent Recurrence tN O

$5 5

j5g Report

• 6 84-04 841118 F

335.65 A

1 N/A CB VALVEX Unit was taken off-line 1852 on November 18, 1984 to repair a leaking pressurizer spray valve. While down for repair, other routine maintenancc was performed. Unit returned to ser-vice December 2, 1984.

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2 Method:

Exhibit G-Instructions 1 Manual for Preparation of Data F: Forced Reason:

S: Scheduled A-Equipment Failure (Explain) 2 Manual Scram.

Entry Sheets for Licensee 3 Automatic Scram.

Event Report (LER) File (NUREG-H. Maintenance of Test C Refueling 4-Other (Explain) 0161)

D-Regulatory Restriction EOperator Training & Ucense Examination 5

F-Administrative Exhibit I-Same Source GOperational Error (Explain)

(9/77) llother(Explain) e em O*

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t Refueling Information Ibrt Calhoun - Unit No.1 Report for the nonth ending December 1984 1.'

Scheduled date for next refueling shutdown.

October 1985 2.

Scheduled date for restart following refueling.

December 1985 3.

Will refueling or restmption of operation thereafter require a technical specification charge or other Yes license amendment?

a.

If answer is yes, what, in general, will these be?

Technical Specification change to accommodate increased radial peaks due to further reduction in radial leakage, b.

If answer is no, has the reload fuci design and core configuration been reviewed by your Plant Safety Review Comnittee to deter-mine whether any unroviewed 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 subnitting proposed licensing action and support information.

September 1985 5.

Inportant licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or perfonnance ulysis methods, significant changes in fuel design, new operating procedures.

Methodology Changes June 1985 6.

The number of fuel assenblics: a) in ta. core 133 assent:11es b) in the spent fuel pool 305 c) spent fuci pool storage capacity 729 d) planned spent fuel pool flay be increased storage capacity via fuel Din consolidation 7.

'Ihe projected date of the last refueling that can be discharged to the spent fuel pool asstming the present licensed capacity.

1996 aM Date January 2. 1985 Prepared by i

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OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 December, 1984 Monthly Operations Report I.

OPERATIONS

SUMMARY

Fort Calhoun Station went back online December 2,1984, after repair of the pressurizer spray valves.

Power was held at.30% for three days while secondary chemistry was brought into specification.

Power was maintained at 100% from December 7 until December 28 when a reduction to 74% was commenced for repair of a leaking feedwater heater manway flange. On December 31 power was returned to 100%.

Administration of the annual requalification examinations for all NRC licensed personnel was completed.

One auxiliary operator-nuclear was hired.

No safety valve or.PORV challenges or failures occurred.

A.

PERFORMANCE CHARACTERISTICS LER Number Deficiency 84-022 Non-Functional Fire Barriers.

B.

CHANGES IN OPERATING METHODS None C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D.

CHANGES TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-VA-80 HydroJen Purge System Test.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because this proce-dure only checks operability of fans and cleanliness of the filters.

e Monthly Operations R: port December, 1984 Page Two D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

Procedure Description SP-FAUD-1 Fuel Assembly Uplift Condition Detection.

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This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only involved the evaluation of data from a surveillance test to verify that a fuel assembly uplift condition did not exist.

SP-PSV-3 Machining Procedure for PCV-103 Valves.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because it provided for machining the valves to appropriate dimensions to improve the gasket sealing.

There is no change in the operation of the valves.

SP-FH-2 Fuel Hoist Removal From Mast.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because it only provided for maintenance work on the fuel hardling equipment and appropriate radiation protection prccc-dures were addressed.

E.

RESULTS OF LEAK RATE TESTS None F.

CHANGES IN PLANT OPERATING STAFF Mr. Alexander Peters was hired as an auxiliary operator-nuclear on December 3, 1984.

G.

TRAINING Training for December,1984, consisted of: annual requalification exams for NRC licensed personnel were completed; the training program for three Shift Technical Advisors was completed; non-licensed opera-tors continued training in math, electrical theory and fire brigade; other plant personnel received training on systems, emergency plan and UF6 procedures.

' Monthly Operations R p:rt

~ December,1984

.Page.Three H.

CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT T010CFR50.59 None II. MAINTENANCE (Significant Safety Related)

None N.

W. Gary Gates Manager Fort Calhoun Station i

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donthly Op2 rations Report Page Seven January,1984 D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

Package Description / Analysis DCR 78-36 Noise Spikes in Plant Instrumentation.

This modification only installed noise spike suppressing devices across the relay cofis of. specific val ves. Operation of the valves or associated system was not effected. This modification has no adverse effect on the safety analysis.

EEAR FC-79-111 Instrument and Control Shop Modification.

This modification expanded the Instrument and Control Shop only and is not safety related. This modification has no adverse effect on the safety analysis.

EEAR FC-80-111 Waste Holdup Tank Instrument Line.

This modification is intended to provide a recircula-tion path so that the gas space may be circulated through a charcoal filter. This would provide a method of removing noble gases from the gas space so the tank could be oper.ed to the atmosphere for inspection. This modification has r.o adverse effect on the safety analysis.

EEAR FC-80-138 Storeroom Power Cable.

This modification rerouted a power cable in the storeroom in conduit. This modification has no adverse effect on the safety analysis.

E.

RESULTS OF LEAK RATE TESTS Procedure Results ST-CONT-2. F.2 PAL 60 psig test - 3800 seem (700 seem greater than previous test).

F.

CHANGES IN PLANT OPERATING STAFF None w

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Omaha Public Power District 1623 Hamey Omaha Nebraska 68102 402/536 4000 January 14, 1985 LIC-85-004 Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555

Reference:

Docket No. 50-285

Dear Mr. DeYoung:

December Monthly Operating Report Please find enclosed ten (10) copies of the December Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

Also attached is a changed page to the January, 1984 Monthly Operation Report.

Revision was made to Section I.E., "Results of Leak Rate Tests", in the report The change is denoted by a vertical black line in the right-hand margin.

Sincerely,

/

R. L. Andrews Division Manager Nuclear Production RLA/TPM/dao

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Enclosures cc:

NRC Regional Office Office of Management I. Program Analysis (2)

Mr. R. R. Mills - Combustion Engineering Mr.

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F. Polk - Westinghouse Nuclear Safety Analysis Center INPO Records Center American N'aclear Insurers NRC File h

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