1CAN039403, Monthly Operating Rept for Feb 1994 for ANO Unit 1

Monthly Operating Rept for Feb 1994 for ANO Unit 1

ML20064J489
Person / Time
Site:	Arkansas Nuclear
Issue date:	02/28/1994
From:	Hayes K, Mins D ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1CAN039403, 1CAN39403, NUDOCS 9403210251
Download: ML20064J489 (7)

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March 15,1994 1CANO39403 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station Pl-137 Washington, DC 20555

Subject:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Monthly Operating Report Gentlemen-The Arkansas Nuclear One - Unit 1. Monthly Operating Report (MOR) for February,1994 is attached. This report is submitted in accordance with ANO-1 Technical Specification

6. I 2.2.3.

Very truly yours, 8...hf(Cv)f.c Dwight C. Mims Director, Licensing

-r DCM/jrh Attachment i

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9403210251 940229 PDR -ADOCK:05000313.

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U.S.NRC h1 arch 15,1994

,1CAN039403 Page 2 cc:

Afr. I.conard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission

Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 8064 NRC Senior Resident inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road Russellvi!!c, AR 72801 Mr. George Kalman NRR Project Manager, Region IV/ANO 1 U S. Nuclear Regulatory Commission NRR Mail Stop 13-11-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Mr Thomas W. Alexion NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Re;,tulatory Commission NRR Mail Stop 13-11-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 o

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4 OPERATING DATA REPORT DOCKET NO:

50 313 DATE:.

March 1,1994 COMPLETED BY; K. R. Ilaycs TELEPIIONE:

(501) 964 5535

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Unit Name: Arkansas Nuclear One Unit 1 2.

Reporting Pesiod:

February 1 28,-1994 3.

Licensed Thermal Power (MWt): 2.56M 4.

Nameplate Rating (Gross MWe): 902.74 5.

Design Electrical Rating (Net MWe): X50 6.

Maximum Dependable Capacity (Gross MWe): 883 7.

Maximum Dependable Capacity (Net MWe): 816 8.

If Changes occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9.

Power Level To Which Restricted. If Any (Net MWe): Nonc 10.

Reasons For Restrictions If Any:

None MQElli X.R-TO-DATE CUMUL631YE '

i 1.

Ilours in Reporting Period.

672.0 1416.0 168283.0 12.

Number ofIlours Reactor was C itical.

647.5 1391.5 121989.9-13.

Reactor Reserve Shutdown Ifouls 0.0 0.0

' 5044,0 '

14.

Ilours Generator On Line.

641,7 1385.7 119729.3 15.

Unit Reserve Shutdown llours.

0.0 0.0 817,5 16.

Gloss Thermal Energy Generated (MWil).

1635270 3544960 275595523 17.

Gross Electrical Energy Generated (MWII)...

560260 1215935 92008970 18.

Net Electrical Enctgy Generated (MWil).

53628l 1165269 87492405 19.

Umt Service Factor.

95.5 97.9 71.1 20.

Unit Availability Factor.

95.5 97.9 71 6 21.

Unit Capacity Factor i

(Using MDC Neo.

95.5 98.4 62.2 22 Unit Capacity Facim (Using DEC Net).

93.9 96.8 61.2 21.

Unit Forced Outage Rate.

45 2.1 11.1 24.

Shutdowns Scheduled Over Next 6 Months (T)pe, Dale, and Duration of Each):

1 25.

If Shut Down At End of Report Period. Estimated Date of Startup:

26.

Units in Test Strtus (Prior to Commercial Operation):

Forecast Achicted INITI AL CRITICALITY 08/06/74

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INITI AL ELECTRICrrY 08/17/74 COMMERCI AL OPERATION 12/19/74

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50 313 UNIT:

One DATE:

March 1,1994 COMPLETED BY: K.R.liayes TELEPilONE:

(501) 964 5535 MONTil Esbngryd994 DAY AVERAGE DAILY POWER LEVEL (MWe-Net).

1 363 2

35 3

827 4

844 l

5 843 6

846 7

846 8

846 9

846 10.

845 11.

845 12.

845 13 845 14 845 15.,

845 16..

846 17.

845

' i 18.

845 I

19.

845 20.

845 21 846 22.

845 23.

845 24.

840 i

25.

841 26.

845 27.

845 28.

845 29.

1. N/A 30.

1. N/A 31.

AN/A AVGS: 798

[NETRUCTION On this fonnat, list the average daily unit power level in MWe-Net for each day in reporting nwnth. Complete to the nearest whole megawatt.

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m UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT FOR February,1994 DOCKET NO.

50-313

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UNIT NAME ANO Urut I DATE March 1,1994 COMPLETED BY K. R Hees TELEPHONE 501-9M-5535 METHOD OF LICENSEE DURATION SHUTTING DOW.*=

EVENT SYSTEM COMPENENT CAUSE & CORRECTIVE ACTION TO M

DATE TYPE' (IIOUR9 REASON 2 REACTOR 5 REPORT

• CODE' CODE 5 riTVENT RECURRENCE S4-01 940^01 F

30.3 A

1 94-001 JE LT Unit taken off-line to repair a Steam j

Generator lesel transtnitter and an escore nuclear instrumentation sensor.

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4 1

2 3

4 F: Forced Reason:

Method:

Esiilbit G - lastructions S: Scheduled A-Equipment Failure (Explain) 1 - Manual for Preparation of Data B - Maintenance of Test 2 - Mannat Scram.

Entry Sheets for Licensee C - Refueling 3 - Automatic Scram.

Event Report (LER) File (NUREG-0161)

D - Regulatory Restriction 4 - Continuation E - Operator Training & License Examination 5 - Isad Reduction F-Administration 9 - Other 5

G - Operational Error Estibit I-Same Source II-Other (Explain) e

4 A

NItC MONTilLY OPEIIATING ltEPOltT

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OPEllATING SUMM AltY FEllitUAltY 1994 UNIT ONE 1

Arkansas Nuclear One, Unit One, began the month operating at 100% power. On the First at 09:05 hours, the unit began a power decrease to hot shutdown to repair a steam generator level transmitter and an excore nuclear instrumentation sensor. The unit went l

offline at 12:43 hours on the first. The steam generator level transmitter was replaced

.l and the excore instrument was repaired. The unit was put back on line at 19:00 hours on

'I the second. Full unit load was reached at 02:20 hours on the third.

On the twenty fourth at 09:25 hours, the unit load was decreased to 98% power to allow isolation of a condenser waterbox for tube leakage repair. The unit was returned to 100%

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power at 11:50 hours on the same day. Unit 1 operated at full power for the remainder of the month.

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j D ATE: February,1994 '

REFUELING INFORM ATION 1.

Narne of facility: Arkansas Nuclear One - Unit 1 2.

Scheduled date for next refueling shutdown. Echntary 14.1995 3.

Scheduled date for restart following refueling. April 7.1995 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? If answer is yes, what, in general, will there be? If answer is i

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 reload (Ref,10 CFR Section 50.59)?

Unknown at this timi 5.

Scheduled date(s) for submitting proposed licensing action and supporting information.

1 Unknown at this time.

6.

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.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, a) 177 b) 6_M 8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

present 968 _

increase size by 0 9.

The projected date of the last refueling that can be discharged to the spent fuel pool j

assuming the present licensed capacity.

DATE: 1996

(' Loss of ftdl core oft-load capability)

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