1CAN099402, Monthly Operating Rept for Aug 1994 for ANO Unit 1

Monthly Operating Rept for Aug 1994 for ANO Unit 1

ML20073B600
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/31/1994
From:	Hayes K, Mims D ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1CAN099402, 1CAN99402, NUDOCS 9409220134
Download: ML20073B600 (7)

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September 15,1994 1CAN099402 U. S. Nuclear Regulatory Commission Document Control Desk hiail Station PI-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 August 1994 is attached. This report is submitted in accordance with ANO-1 Technical Specification

6. I 2.2.3.

Very truly your,

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wight C fims Directors icensing I

I DCM/jrh Attachment l

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U. S. NRC September 15,1994 l

l 1CAN099402 Page 2 l

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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 RusselMlle, AR 72801 Mr. George Kalman NRR Project Manager, Region IV/ANO-1 & 2 U. S. Nuclear Regulatory Commission i

NRR Mail Stop 13-H-3 One White Flint North f.

I1555 Rockville Pike Rockville, Maryland 20852 l

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OPERATING DATA REPORT DOCKET NO:

50-313 DATE:

September 8,1994 COMPLETED BY: K. R. Hayes TELEPIlONE:

(501) 858-5535 OPERATING STATUS 1.

Unit Name: Arkansas Nuclear One - Unit 1 2.

Reporting Period:

August 1-31, 1994 3.

Licensed Thermal Power (MWt): 2.568 4.

Nameplate Rating (G oss MWe): 902.74 5.

Design Electrical Rating (Net MWe): 850 6.

Maximum Dependable Capacity (Gross MWe): 883 7.

Maximum Dependable Cspacity (Net MWe): 836 8.

If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Repos., 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 i

11.

Hours in Reporting Period.

74t0 5,831.0 172,698.0 12.

Number of Hours Reactor was Critical.

744.0 5,728.8 126,327.2 13.

Reactor Reserve Shutdown Hours.

0.0 0.0 5,044.0 14.

Hours Generator On-Line..

744.0 5,715.4 124,059.0 15.

Unit Reserve Shutdown Hours.

0.0 0.0 817.5 16.

Gross Thermal Energy Generated (MWH)....

1,909,366 14,629,693 286,680,255 17.

Gross Electrical Energy Generated (MWH).

641,580 4,972,125 95,765,160 18.

Net Electrical Energy Generated (MWII).

613,764 4,758,860 91,085,996 19.

Unit Scryice Factor.

100.0 98.0 71.8 20.

Unit Availability Factor.

100.0 98.0 72.3 21.

Unit Capacity Factor (Using MDC Net).

98.7 97.6 63.1 22.

Unit Capacity Factor (Using DEC Net).

97.1 96.0 62.1 23.

Unit Forced Outage Rate.

0.0 2.0 10.9 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

)

Stanup:

26.

Units in Test Status (Prior to Commercial Operation):

I Forecast Achieved INITIAL CRITICALITY 08/06n4 INITIAL ELECTRICfW 08/17/74 COMMERCIAL OPERATION 12/1954 i

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-313 UNIT:

One DATE:

September 8,1994 COMPLETED BY: K. R. Hayes TELEPHONE:

(501) 858-5535 MONTil Aucust 1994 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 826 2

824 3

825 4

825 5

824 6

826 7

826 8

826 9

825 10.

824 11.

825 12.

822 13 822 14.

822 15..

823 16.

825 17..

824 18..

823 19.

825 20.

828 21.

829 22.

828 23.

827 24.

826 25.

826 26.

826 27.

826 28.

825 29.

824 30.

823 31.

824 AVGS:

825 INSTRUCTION On this fonnat, list the average daily unit power level in MWe-Net for each day in reporting month. Complete to the nearest whole megawatt.

j NRC MONTIILY OPERATING REPORT OPERATING

SUMMARY

AUGUST 1994 UNIT ONE The unit operated the month of August at 100% power.

UNITSHUTDOWNS AND POWER REDUCTIONS REPORT FOR August 1994 DOCKET NO.

50-313 1INIT NAME ANO Umt I DATE September 2,1994 COMPLETED BY K. R. Hayes TELEPIIONE 501-858-5535 METIIOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPONEhT CAUSE & CORRECTIVE ACTION TO (IIOURS)

REASON 2 REACTOR 8 REPORT #

CODE' CODES PREVENT RECURRENCE E

DATE TYPE 8 None

'l 2

3 4

F: Forced Reason:

Method:

Exhibit G -Instructions -

5: S(heduled A - Equipment Failure (Explain) 1 - Manual for Preparation of Data B - Maintenance of Test 2 - Manual Scram.

Entry Sheets for Ucensee -

C - Refueling Automatic Scram.

Ewat Report (LER) File (NUREG-016l)

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

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

DATE: August 1994 REFUELING INFORMATION 1.

Name of facility: Arkansas Nuclear One - 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 (COLR1 Technical Specification change to allow modification of the vital instmment 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.

None planned.

7.

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

i a) 177 b) 685 i

4 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)

-