1CAN109501, Monthly Operating Rept for Sept 1995 for ANO Unit 1

Monthly Operating Rept for Sept 1995 for ANO Unit 1

ML20093G684
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/30/1995
From:	Mims D, Whitt M ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1CAN109501, NUDOCS 9510190196
Download: ML20093G684 (7)

Text

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Rzsc0vk. AR 72301 Tel501858 5000 October 16,1995 1CAN109501 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 for September 1995 is attached.

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

Very truly yours, k/"lb Y/5 Dwight C. Mims Director, Licensing DCM/eas 1

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.9510190196 950930 PDR ADOCK 05000313 a

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U. S. NRC

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' October 16,1995 1CAN109501 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 P.O. Box 310 London, AR 72847 Mr. George Kalman 1

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, MD 20852 1

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o OPERATING DATA REPORT DOCKET NO:

50-313 DATE:

October 16,1995 COMPLETED BY: M. S. Whitt TELEPHONE:

(501) 858-5560 OPERATING STATUS 1.

Unit Name: Arkansas Nuclear One - Unit i 2.

Reporting Period:

September 130 3.

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

Nameplate Rating (Gross MWe): 903 5.

Design Electrical Rating (Net MWe): 850 6.

Maximum Dependable Capacity (Gross MWe): 883 2

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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):

10.

Reasons For Restrictions. If Any:

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1 MONTH YR-TO-DATE CUMULATIVE 11.

Hours in Reporting Period.

720.0 6,551.0 182,178.0 12.

Number of Hours Reactor was Critical.,

720.0 5,366.8 134,623.0 13.

Reactor Reserve Shutdown Hours......

0.0 0.0 5,044.0 14.

Ilours Generator On-Line.

720.0 5,285.0 132,272.9 15.

Unit Reserve Shutdown Hours.

0.0 0.0 817.5 16.

Gross Thermal Energy Generated (MWH).

1,845,410 12,665,411 306,819,300 17.

Gross Electrical Energy Generated (MWH).

629,193 4,305,105 102,617,025 18.

Net Electrical Energy Generated (MWH)..

602,026 4,100,246 97,625,735 19.

Unit Service Factor...

100.0 80.7 72.6 20.

Unit Availability Factor.

100.0 80.7 73.1 21.

Unit Capacity Factor (Using MDC Net).

100.0 74.9 64.1 22.

Unit Capacity Factor (Using DER Net)..

98.4 73.6 63.0 23.

Unit Forced Outage Rate...

0.0 2.6 10.3 24.

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

)

25.

If Shut Down At End of Report Period. Estimated Date of J

Sunup:

26.

Units in Test Status (Prior to Co nmercial Operation):

Forecast Achicsed INITIAL CRITICALITY 08/06/74 INITIAL ELECTRICITY 08/17/74 i

COMMERCIAL OPERATION 12/19/74 i

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-313 UNIT:

One DATE:

October 16.1995 COMPLETED BY: M. S. Whitt TELEPflONE:

(501) 858 5560 MONTH Septemhgtl225 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 826 2....

828 3

828 4

831

.5 832 6

831 7

831 8..

830 9

834 10..

835 11.

836 12...

835 13..

836 14.

836 15.

828 16.

837 17..

838 18.

836 i

19..

836 4

20.

839 21.

840

.s 22.,

840 l

23...

841 24..........

841 25.

842 i

26.

843 2 7........

843 28.

845 i

29.

844 30......

844 31.

O AVGS: 836 INSTRUCTION l

On this format, list the average daily unit power level in MWe-Net for each L

day in reporting month. Complete to the nearest whole megawatt.

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NRC MONTIILY OPERATING REPORT OPERATING

SUMMARY

SEPTEMBER 1995 UNIT ONE l

The unit began the month of September operating at 100% power.

At 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> on the fifteenth, a power reduction to 91% was commenced for turbine governor and throttle valve stroke testing. Following completion of the testing, the unit was returned to 100% power at 2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br /> the same day.

The unit operated the remainder of the month at 100% power.

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UNIT SHUTDOWNS AND POWER REDUCI' IONS REPORT FOR SEPTEMBER 1995 DOCKET NO.

50-313 UNIT NAME ANO Unit 1 DATE October 16,1995 COMPLETED BY M. S. Whitt TELEPHONE 501 458-5560 METHOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO E

DATE TYPE' OfOURS)

REASON:

REACTOR 5 REPORT #

CODE' CODE 5 PREVENT RECURRENCE none i

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F: Forced Reason:

Method:

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

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

Event Report (LER) File (NUREG-0161)

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

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

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Repocing Period: September 1995 REFUELING INFORMATION 1.

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

Scheduled date for next refueling shutdown: September 20.1996 3.

Scheduled date for restart following refueling: November 4.1996 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.10CFR Section 50.59)?

No,No 5.

Scheduled date(s) for submitting proposed licensing action and supporting infornution:

NA 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 operatirg procedures.

None olanned 7.

The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool:

a) 111 b) 2_41 4

8.

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

present 2f!8 increase size by 0 9.

The projected date of the last refueling that can be discharged to the spent f. el pool assuming the present licensed capacity:

DATE:

1996 (Loss of full core off-load capability)

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