1CAN079402, Monthly Operating Rept for June 1994 for ANO Unit 1

Monthly Operating Rept for June 1994 for ANO Unit 1

ML20071H533
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/30/1994
From:	Hayes K, Mims D ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1CAN079402, 1CAN79402, NUDOCS 9407190296
Download: ML20071H533 (7)

Text

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ICAN079402 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555 1

Subject:

Arkansas Nuclear One - Unit 1 Docket No. 50-313

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License No. DPR-51 Monthly Operating Report Gentlemen:

The Arkansas Nuclear One - Unit 1 Monthly Operating Report (MOR) for June 1994 is attached. This report is submitted in accordance with ANO-1 Technical Specification 6,12.2.3.

Very truly yours,

$ $fC.v!L ;

Divight C. Mims Director, Licensing DCM/jrh Attachment -

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9407190296 940630

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U.'S. NRC

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1CAN079402 Page 2 cc:

Mr. Leonard 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 Russellville, AR 72801 Mr. George Kalman NRR Project Manager, Region IV/ANO-1 & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 i

OPERATING DATA REPORT DOCKET NO:

50-313 DATE:

July 6,1994 COMPLETED BY: K. R. Hayes TELEPIIONE:

(50l) 964-5535 QRIMTING STATUS 1.

Unit Name: Arkansas Nuclear One - Unit 1 2.

Reporting Period:

June 1 30,1994 3.

Licensed Thermal Power (MWt): 2,568 4.

Nameplate Rating (Gross MWe): 902.74 5.

Design Electrical Rating (Net MWe): 850 6.

Maximum Dependable 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 MONTH YR-TO-DATE CUMULATIVE 11.

llours in Reporting Period.

720.0 4,343.0 171,210.0 12.

Number of Hours Reactor was l

Critical.

720.0 4,240.8 124,839.2 13.

Reactor Reserve Shutdown Ilours.

0.0 0.0 5,044.0 14.

Hours Generator On Line.

720.0 4,227.4 122,571.0 15.

Unit Reserve Shutdown Hours.

0.0 0.0 817.5 16.

Gross Thermal Energy Generated (MWil).

1,836,594 10,810,466 282,861,028 17.

Gross Electrical Energy Generated (MWH).

618,450 3,689,995 94,483,030 18.

Net Electrical Energy Generated (MWH)..

591,529 3,532,361 89,859,497 19.

Unit Service Factor.

100.0 97.3 71.6 20.

Unit Availability Factor.

100.0 97.3 72.1 21.

Unit Capacity Factor (Using MDC Net).

98.3 97.3 62.8 22.

Unit Capacity Factor (Using DEC Net).

96.7 95.7 61.7 23.

Unit Forced Outage Rate.

0.0 2.7 11.0 24.

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

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 CRITICALITY 08/06/74 INITIAL ELECTRICITY 08/17/74 COMMERCIAL OPERATION 12/19/74 l

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-313 UNIT:

One DATE:

July 6,1994 COMPLETED BY: K. R. Hayes TELEPIIONE:

(501) 964 5535 MONTil lyne 1994 DAY AVERAGE DAILY POWER L.EVEL (MWe-Net) 1 835 2

835 3

833 4

833 5

832 6

830 7

829 8

831 9

831 10.

830 11.

710 4

12.

756 13.

824 14 830 15.

829 16.

828 17.

826 18.

827 19.

827 20.

827 21.

827 22.

827 23.

825 24.

826 25.

826 26.

826 27.

824 28.

823 29.

823 30.

819 3I.

1. N/A AVGS: 822 lb'SLRUCTION 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

i JUNE 1994 i

UNIT ONE t

i Arkansas Nuclear One, Unit One, began the month operating at 100% power. On the l

tenth at 2328 hours0.0269 days <br />0.647 hours <br />0.00385 weeks <br />8.85804e-4 months <br />, the unit load was decreased to 95% to perform planned testing of the turbine throttle / governor valves.

Following the turbine valve testing, power was decreased to 80% to allow the isolation of a condenser waterbox so tube leaks could be l

identified and repaired. The unit increased power to 92% during the tube leak repairs. On the thirteenth at 0445 hours0.00515 days <br />0.124 hours <br />7.357804e-4 weeks <br />1.693225e-4 months <br /> the unit was returned to 100% power after leak repairs were completed.

[

t Unit 1 operated at full power for the remainder of the month.

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UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT FOR June 1994 DOCKET NO.

50-313 UNIT NAME ANO Umt I DATE July 6, I994 COMPLETED BY K. R. Ilayrs TELEPIIONE 501-964-5535 METIIOD OF LICENSEE DURATION SIIUTIING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO M

DATE TYPE' (IIOURS)

REASON 8 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 - 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 (Esplain)

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DATE: June 1994 REFUELING INFORMATION 1.

Name of facility: Arkansas Nuclear On.e - Unit 1 2.

Scheduled date for next refueling shutdown. February 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 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)?

Technical Specification change to relocate additional cycle specific parameters to the Core Operating Limits Report (COLR).

5.

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

August 1994.

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.

None olanned.

7.

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

a) 177 b)685 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 assuming the present licensed capacity.

DATE: 1996 (Loss of full core off-load capability) l