1CAN039304, Monthly Operating Rept for Feb 1993 for Ano,Unit 1

Monthly Operating Rept for Feb 1993 for Ano,Unit 1

ML20044C397
Person / Time
Site:	Arkansas Nuclear
Issue date:	02/28/1993
From:	James Fisicaro, Hayes K ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1CAN039304, 1CAN39304, NUDOCS 9303220411
Download: ML20044C397 (7)

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'g-Operations m ~ # usa, m 501.oe.4.aw March 15, 1993 1CANO39304 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station F1-137 Washington, DC 20555 i

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, 1993 is attached. This report is submitted in accordance with ANO-1 Technical Specification 6.12.2.3.

i Very truly yours, ll tri M '

ames Fisicaro t/

Director, Licensing

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9 U. S. NRC-

' March 15, 1993 ICANO39304' Page 2 l

cc:

Mr. James L. Milboan Regional Administrator U. S. Nuclear Regulatory Commission l

Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064

.l NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road i

Russellville, AR 72801 i

Mr. Roby Bevan 1

NRR Project Manager, Region IV/ANO-1 f

U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-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 Regulatory Commission NRR Mail Stop 13-H-3 l

One White Flint North 11555 Rockville Pike r

Rockville, Maryland 20852 s

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OPERATING DATA REPORT

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DOCKET NO.

50-313 DATE:

March 3,1993 COMPLETED BY: K. R. Hayes TELEPliONE:

(501) 964-5535 OPERATING STATUS 1.

Unit Name: Arkansas Nuclear One - Unit 1 2.

Reponing Period:

Februan' l-28.1993 3.

Licensed Thermal Power (MWt): 2.568 4.

Nameplate Rating (Gross MWe): 902.74 5.

Design Electrical Rating (Net MWe): 850 6.

Maximum Dependabic Capacity (Gross MWe): 883 7.

Maximum Dependable Capacity (Net MWe): 836 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): None 10.

Reasons For Restrictions. If Any:

None MONTil YR-TO-DATE CUMULATIVE I 1.

Ilours in Reporting Period.

672.0 1416.0 159523.0 12.

Number ofIlours Reactor was Critical.

672.0 1416.0 1144~5.0 13.

Reactor Reserve Shutdown llours.

0.0 0.0 5044.0 14.

Ifours Generator On-Linc.

672.0 1416.0 112237.7 15.

Unit Reserve Shutdown 11ours.

0.0 0.0 817.5 16.

Gross Thermal Energy Generated (MWii).

1724812 3634601 256771755 17.

Gross Electrical Energy Generated (MWil).

592545 1249155 85627025 18.

Net Electrical Energy Generated (MWii).

568409 1198182 81398783 19.

Unit Senice Factor.

100.0 100.0 70.4 20.

Unit Availability Factor.

100 0 100.0 70.9 21.

Unit Capacity Factor (Using M0r Net).

101.2 101.2 61.0 22.

Unit Capacity Factor (Using DEC Net).

99.5 99.5 60.0 23.

Unit F aced Outage Rate.

0.0 0.0 11.6 24.

Shutc$ns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

25.

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

26.

Units in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 08/06n4 INITI AL ELECTRICITY 08/17/74 COMMERCIAL OPERATION 12/19n4

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AVERAGE DAILY UNIT POWER LEVEL g

DOCKET NO:

50-313 UNIT:

One DATE:

March 3,1993 -

COMPLETED B'l: K. R. Hayes TELEPHONE:

(501) 964-5535 MONTH Februarv.1993 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 847 2

846 3

846 4

846 5

846 6

846 7

846 8

846 9

846

10..

846 11.

846 12.

843 13.

843 14..

844 15.

846 16..

346 17.

845 18.

846 19.

846 20.

846 21.

847 22.

847 23.

846 24...

846 25.

847 26.

846 27..

846 28.

846 29.

1. N/A 30.

1. N/A 31.

1. N/A AVGS: 846 INSTRUCTION On this format, list the average daily unit power level in MWe-Net for each day in reporting month. Complete to the nearest whole megawatt.

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NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

FEBRUARY 1993 UNIT ONE Unit one began the month operating at 100% power.

On the Twelfth at 19:00 hours, the unit load was decreased to 95%

to perform scheduled testing of the turbine throttle / governor valves.

The unit power was then returned to 100% power at 21:30 hours on the same day.

The unit operated at full power for the remainder of the month.

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UNITSIIUTDOWNS AND POWER REDUCTIONS REPORT FOR FEBRUARY.1993 DOCKET NO.

50-313 UNIT NAME ANO Unit i DATE March 3,1903 COMPLETED BY K. R. llaves TELEPilONE 501-964-5535 METIIOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPENENT CAUSE & CORRECTIVE ACTION TO E

DATE TYPE' (IIOURS)

REASON 2 REACTORS REPORT #

CODE' CODE 8 PREVENT RECURRENCE None 1

2 3

4 F: Forced Reason:

Method:

Exhibit G

• Instructions 5: Scheduled A - Equipment Failure (Explain) 1 - Manual for Preparation of Data B - Maintenance of Test 2 - Manual Scram.

Entry Shects for Ucensee i

C - Refueling 3-Automatic Scram.

Esent Report (LER) File (NUREG-0161)

D - Regulatory Restriction 4 - Continuation E - Operator Training & Ucense Esemination 5 -Imad Reduction F-Administration 9 - Other 5

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

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4 DATE: February, 1993 REFUELING INFORMATION 1.

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

Scheduled date for next refueling shutdown. September 17, 1993 3.

Scheduled date for restart following refueling. November 12, 1993 4.

Will refuelirt 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 no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unroviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

Yes, Technical Specification change to increase fuel enrichment from 3.5% to 4.1% and to reference B&W Topical Report BAW-10179P for the Core Operating Limits Report.

5.

Scheduled date(s) for submitting proposed licensing action and supporting information. The fuel enrichment Technical Specification change request was submitted to the NRC on June 27, 1991 (1CAN069108).

A Technical Specification change request to reference B&W Topical Report' BAW-10179P is scheduled to be submitted in April, 1993.

6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design >r performance analysis methods, significant changes in fuel design, new operating procedures.

None.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

a) 177 b) 625 8.

The present liccused spent fuel pool storago 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 assuming the present licensed capacity.

DATE:

1995 (Loss of fullcore offload capability)

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