1CAN119403, Monthly Operating Rept for Oct 1994 for ANO Unit 1

Monthly Operating Rept for Oct 1994 for ANO Unit 1

ML20080A817
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/31/1994
From:	Hayes K, Mims D ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1CAN119403, NUDOCS 9411210388
Download: ML20080A817 (7)

Text

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November 15,1994 1CANI19403 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 (MOR) for October 1994 is attached. This report is submitted in accordance with ANO-1 Technical Specification

6. I 2.2.3.

Very truly yours,

/MgifC:W1J Dwight C. Mims Director, Licensing DCM/jrh Attachment J

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i U.S.NRC November 15,1994 ICANI19403 Page 2 i

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 1448 S. R. 333 Russellville, AR72801 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 Rockvil'.e Pike Rockville, Maryland 20852 1

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OPERATING DATA REPORT 1

DOCKET NO:

50-313 DATE:

November 3,1994 COMPLETED BY: K. R. Hayes TELEPilONE:

(50l) 858-5535 OPERATING.1TATUS 1.

Unit Name: Arkansas Nuclear One - Unit i 2.

Reporting Period:

October 1-31, 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 MONTil YR-TO-DATE CUMULATIVE I 1.

IIours in Reporting Period.

745.0 7,296.0 174,163.0 12.

Number of flours Reactor was Critical.

745,0 7,193.8 127,792.2 13.

Reactor Reserve Shutdown Hours.

0.0 0.0 5,044.0 14.

Ilours Generator On-Line.

745.0 7,180.4 125,524.0 15.

Unit.Rescive Shutdow n flours.

0.0 0.0 817.5 16.

Gross Thermal Energy Generated (MWII).

1,912,099.I 18,364,342.5 290,414,904.7 17.

Gross Electrical Energy Generated (MWil).

653,085.0 6,240,370.0 97,033,405.0 18.

Net Electrical Energy Generated (MWll).

625,518.0 5,972,762.0 92,299,898.0 19.

Unit Service Factor.

100.0 98.4 72.1 20.

Unit Availability Factor.

100.0 98.4 72.5 21.

Unit Capacity Factor (Using MDC Net).

100.4 97.9 63.4 22.

Unit Capacity Factor (Using DEC Net).

98.8 96.3 62.3 23.

Unit Forced Outage Rate.

0.0 1.6 10.7 24.

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

Refueling outage 1R12 is scheduled to begin February 14,1995.

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 08/06n4 INITI AL ELECTRICITY 08/17n4 COMMERCIAL OPERATION 12/19/74

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-313 UNIT:

One DATE:

November 3,1994 COMPLETED BY: K. R. Hayes TELEPHONE:

(501) 858-5535 MONTil October 1994 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 836 2

837 3

836 4

837 5

835 6

837 7

836 8

836 9

837 10.

838 11.

839 12.

839 13.

840 14.

837 15.

840 16.

840 17, 840 18.

840 19.

840 20.

841 21.

841 22.

841 23.

842 24.

841 25.

842 26.

843 27.

843 28.

843 29.

843 30.

843 31 844 AVGS:

840 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.

NRC MONTIILY OPERATING REPORT OPERATING

SUMMARY

OCTOBER 1994 UNIT ONE The unit operated the month of October at 100% power.

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UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR October 1994 DOCKET NO.

50-313 UNIT NAME ANO Unit 1 DATE November 1,19M COMPLETED BY K. R. Haves 2

TELEPHONE (501)858-5535 METHOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO M

DATE TYPE 8 (HOURS)

REASON 2 REACTOR 8 REPORT #

CODE' CODES PREVENT RECURRENCE None i

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1 2

3 4

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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 Scrani.

Ent:7 Sheets for IJcensee C - Refueling 3 - Automatic Scram.

Event Report (LER) File (NUREG-8161)

D - Regulatory Restriction 4 - Continuation E - Operator Training & License Examination 5 - Iend Reduction l

F-Administration 9 - Other 5

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

r DATE: October 1994 REFUELING INFORMATION 1.

Name of facility: Arkansas Nuc! gar One - UniLL 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 thereafler 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 (COLR1 Technical Specification change to allow modification of the vital instrument electrical power system.

5.

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

These changes were submitted August 30.1994.

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.

Nonc planned.

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) i P

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