2CAN059304, Monthly Operating Rept for Apr 1993 for Ano,Unit 2

Monthly Operating Rept for Apr 1993 for Ano,Unit 2

ML20036A992
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/30/1993
From:	James Fisicaro, Whitt M ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN059304, 2CAN59304, NUDOCS 9305180043
Download: ML20036A992 (7)

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Operations g; y May 14, 1993 2CAN059304 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:

Monthly Operating Report statistics for Arkansas Nuclear One, Unit-2, for April, 1993 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.

Very truly yours, zAs%

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James J. Fisicaro Director, Licensing JJF/JRH/prg Attachment i

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Il PDR ADOCK 05000368

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U. S. NRC

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,'May 14, 1993 2CAN059304 - Page 2 cc:

Mr. James L. Milhoan 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 - AND-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. Roby Bevan NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, itsryland 20852 Mr. Thomas W. Alexion NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mall Stop 13-H-3 One White Flint North 11555 Rockville Pike Eockville, Maryland.20852

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e OPERATING DATA REPORT l

l DOCKET NO:

50-368

{

DATE:

May 4.1993 COMPLETED BY: M. S. Whitt l

TELEPHONE:

(501) 964-5560

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OPERATING STATUS 1.

Unit Name: Arkansas Nuclear One - Unit 2 2.

Reporting Period:

April 1-30,1993 3.

Licensed Thermal Pourr(MWI): 2.815 4

Nameplate Rating (Gross MWe): 942.57

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5.

Design Electrical Rating (Net MWe): 912 i

f 6.

Maximum Dependable Capacity (Gross MWe): 897 7.

Maximum Dependable Capacity (Net MWe): 858 i

8.

If Changes Occur in Capacity Ratings (ltems Number 3 Through 7) Since i

Last Report, Give Reasons:

9 Power level To Which Restricted. If Any (Net MWe): None

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i 10.

Reasons For Restrictions. If Any: None i

f MONTH YR-TO-DATE CUMULATIVE 11.

Hours in Reporting Period....

719.0 2,879.0 114,815.0 12.

Number of Hours Reactor was Critical..

719.0 2,879.0 87,310.3 13.

Reactor Reserve Shutdown Hours.

0.0 0.0 0.0 14.

Hours Generator On-Line.

719.0 2,879.0 85,458.4 15.

Unit Reserve Shutdown Hours..

0.0 0.0 0.0 16.

Gross Thermal Energy Generated (MWH) 2,017,613 8,061,161-225,827,965 17.

Gross Electrical Energy Generated (MWH) _

671,430 2,680,290 74,310,481 18.

Net Electrical Energy Generated (MWH) 641,888 2,562,608 70,690,727 l

19.

Unit Scrvice Factor..

100.0 100.0 74.4 20.

Unit Availability Factor.,

100.0 100.0 74.4 i

21.

Unit Capacity Factor j

(Using MDC Net)..

104.1 103.7 71.8 22.

Unit Capacity Factor (Using DEC Net) 97.9 97.6 67.5' 23 Unit Forced Outage Rate.

0.0 0.0 11.8 i

24.

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

Planned Steam Generator inspection outace to begin May 1.1993 and last approximately 18 days.

25.

ET.ihut Down At End of Report Period. Estimated Date of l

Startup:

26.

Units in Test Status (Prior to Commercial Operation):

Forecast Achieved lhTTIAL CRITICALITY 12/05/78 INITIAL ELECTRICITY 12/26D8 COMMERCIAL OPERATION 03/26/80

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i AVERAGE DAILY UNIT POWER LEVEL l

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DOCKET NO:

50-368 UNIT:

Two j

DATE:

May 4.1993 l

COMPLETED BY: M. S. Whitt l

TELEPHONE:

(501) 964-5560 l

MONTH April.1993 l

I DAY AVERAGE DAILY POWER LEVEL l

(MWe-Net) i l

1 855 l

2 896 l

3 895 4

895 l

5.

895 l

6.

894

}

893 7

8 893

[

9.

894 10.

893 11.

893 12.

893 j

13.....

892 j

14.

894 15-897 l

16...

897 17..

896 18.

895 I

19.

892 20.

896 21.

896

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22.

895 23..

893 24-891 j

25........

894 26 894

-l 27.........

893 l

28-893 29 -

894 f

30 893 31

1. N/A AVGS: 893 i

i 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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c NRC MONTIILY OPERATING REPORT OPERATING

SUMMARY

APRIL 1993 UNIT TWO i

The unit began the month of April at 75% power per System Dispatcher request.

At 0532 hours0.00616 days <br />0.148 hours <br />8.796296e-4 weeks <br />2.02426e-4 months <br /> on the first, the dispatcher released the unit from the 75% power hold. The I

unit escalated to full power and attained 100% at 0759 hours0.00878 days <br />0.211 hours <br />0.00125 weeks <br />2.887995e-4 months <br /> on the first.

The unit ran at 100% power for the remainder of the month.

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9 UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT FOR APRIL,1793 DOCKET NO.

50.16R UNIT NAME ANO Unit 2 DATE

_May 4,1993 COMPLETED BY M. S. %%itt TELEPIIONE 501 064-5560 METIIOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPENENT CAUSE & CORRECTIVE ACTION TO M

DATE TYPE' UIOURS)

REASON' REACTOR' REPORT #

CODE' CODES PREVENT RECURRENCE none l

I l-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 - Manuel Scram. -

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

Esent Report (LER) File (NURECr4161)

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

G - Operational Error Exhibit I-Same Source

. H - Other (Explain) l f.-

.. _. _.. _ _ _ _ _ _.. -.. - _ - - _. _,... _.... _.~ ~ _.. _ _.-, _ _.-.. -. _,.. _ _.~ _.. _..... -- _.., _ _ _. ~.-..-. _. _

1 i

DATE: April, 1993 i

f REFUELING INFORMATION l

I 1.

Name of facility: Arkansas Nuclear One - Unit 2

.j 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 amendment? If

.f 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 j

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

Yes, Technical Specification changes to relocate cycle specific j

parameters to a Core Operating Limits Report and to make the Technical Specification requirements for Azimuthal Power Tilt

-j consistent with accident analyses.

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5.

Scheduled date(s) for submitting proposed licensing action and j

supporting information. August, 1993 6.

Important licensing considerations associated with refueling, e.g.,

i new or different fuel design or supplier, unreviewed design or i

performance analysis methods, significant changes in fuel design, l

new operating procedures.

j None.

7.

The number of fuel assemblies (a) in the core and (b) in the spent i

fuel storage pool. a) 177 b) 565 j

t S.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been j

requested or is planned, in number of fuel assemblies.

i present 988 increase size by 0 i

9.

The projected date of the last refueling that can be discharged to the

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spent fuel pool assuming the present licensed capacity.

DATE:

1997 (Loss of fu11 core offload capability)

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