2CAN079306, Monthly Operating Rept for June 1993 for Ano,Unit 2

Monthly Operating Rept for June 1993 for Ano,Unit 2

ML20045H414
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/30/1993
From:	James Fisicaro, Whitt M ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN079306, 2CAN79306, NUDOCS 9307200186
Download: ML20045H414 (7)

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July 15, 1993 2CAN079306 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station F1-137 Washington, DC 20555

Subject:

Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Monthly Operating Report Gentlemen:

The Arkansas Nuclear One - Unit 2 Monthly Operating Report (MOR) for June, 1993 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.

Very truly yours,

/

f w o;. h A< w James J. Fisicaro Director, Licensing JJF/JRH/prg Attachment 1

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'l 9307200186 930630 g

PDR -ADOCK 05000368 h@l R

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U. S. NRC

-July 15, 1993 l

2CAN079306 - Page 2 cc: -Mr. James L. M11hoon l

Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400' Arlington, TX 76011-8064 i

NRC Snnfor Resident Inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road a

Russellville, AR 72801 Mr. Roby Bevan NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H 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 One White Flint North 11555 Rockville Pike l

Rockville, Maryland 20852 3

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j OPERATING DATA REPORT DOCKET NO:

50-368 DATE:

July 6.1993 COMPLETED BY: M. S. Whitt TELEPHONE:

(501) 964-5560 QPf; RATING STATUS i

- 1.

Unit Name: Arkansas Nuclear One - Unit 2 I

2.

Reporting Period:

June 130,1993 3.

Licensed, Thermal Power (MWI): 2,815 4.

Nameplate Rating (Gross MWe): 942.57 5.

Design Electrical Rating (Net MWe): 912 6.

Maximum Dependable Capacity (Gross MWe): 897 7

Maximum Dependable Capacity (Net MWe): 858 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

.f MONTH YR-TO-DATE CUMULATIVE 11.

Hours in Reporting Period.

720.0 4,343.0 116,279.0 12.

Nmaber of Hours Reactor was Critical.

720.0 3,973.4 88,404.7 13.

Reactor Reserve Shutdown Hours.

0.0 0.0

- 0.0 14.

Hours Generator On-Line.

720.0 3,966.6 86,545.9 15.

Unit Reserve Shutdown Hours.

0.0 0.0 0.0 16.

Gross Thermal Energy Generated (MWH).

2,023,305 11,042,891 228,809,695 17.

Gross Electrical Energy Generated (MWH),,

668,435 3,665,585 75,295,776 18.

Net Electrical Energy Generated (MWH).

638,956 3,498,790 71,626,909 19 Unit Service Factor.

100.0 91.3 74.4 20.

Unit Availability Factor.

100.0 91.3 74.4 21.

Unit Capacity Factor (Using MDC Net).

103.4 93.9 71.8

- 22.

Unit Capacity Factor (Using DEC Net).

97.3 88.3 67.5 -

23.

Unit Forced Outage Rate..

0.0 0.0 11.7

.)

24.

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

3

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

26.

_ Units in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICAll'iY 12/05/78 INITIAL ELECTRICITY 12/26/78 COMMERCIAL OPERATION 03/26/80 i

,c

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-368 -

UNIT:

Two l

DATE:

July 6,1993 COMPLETED BY: M. S. Whitt.

TELEPIIONE:

(501) 964-5560 MONT11 June.1993 DAY

' AVERAGE DAILY POWER LEVEL (MWe-Net) 1-893 2

891 3

888 4.

887 5...

893 6

888 7

886 8

887 9....

885 10..

890 11.

889 12..

888 I3..

888 14.

886 15.

888 16.

887 17.

885 18..

886 887 i

19.

20 888

21...

888 22.

887 23.

887 24 887 25.

886 26.

889 27 889 l

28 ~..

887 a

29..

883

' 30....

882 31.

1. N/A AVGS: 887 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 MONTIILY OPERATING REPORT OPERATING

SUMMARY

JUNE 1993 UNIT TWO The unit ran at 100% power for the entire month of June.

s 4 *

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UNIT SilUTDOWNS AND POWER REDUCTIONS REPORT FOR JUNE.1993 DOCKET NO.

50-368 UNIT NAME ANO Umt 2 DATE July 6,1993 COMPLETED BY M S. Whitt TELEPIIONE 501-964-5560 METIIOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO M

DATE TYPE' (IIOURS)

REASON 2 REACTORS REPORT #

CODE

• CODES PREVENT RECURRENCE none 1

2 3

4 F: Forced Reason:

Method:

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

Entry Sheets for Ucensee C Refueling 3 - Automatic Scram.

Event Report (LER) File (NUREG-0161)

D-1 gulatory Restriction 4 - Continuation E - Operator Training & Ucense Examination 5 - lead Reduction F-Administration 9 - Other 5

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

a.

i DATE: June, 1993 REFUELING INFORMATION.

1.

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

Scheduled date for next refueling shutdown. March 25, 1994 3.

Scheduled date for restart following refueling. May 16, 1994 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendmenp?

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 unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

Yes, Technical Specification changes to relocate cycle specific parameters (i.e., shutdown margin MTC, CEA Position and insertion limits, LHR, Azimuthal Tilt, DNBR Margin, and ASI) to a Core Operating Limits Report and revise the definition of shutdown margin to be consistent with NUREG-1432, Revision 0.

5.

Scheduled date(s) for submitting proposed licensing action and supporting information. July 22 1993

.i 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.

i None.

1 7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, a) 177 b) 565 l

s j

8.

The present licensed spent fuel pool storage capacity and the size l

of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

'l present 988 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:

1997 (Loss of fu11 core offload capability)

.