1CAN079203, Monthly Operating Rept for June 1992 for Ano,Unit 1

Monthly Operating Rept for June 1992 for Ano,Unit 1

ML20101T408
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/30/1992
From:	James Fisicaro, Hayes K ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1CAN079203, 1CAN79203, NUDOCS 9207210102
Download: ML20101T408 (7)

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!;U. S. Nuclear-Regulatory Commission Document Control Desk-

. Mail-Stop P19137 Washington,'D.C. :205551-y

'SUBJECTr -~ Arkansas' Nuclear-One'- Unit 1

' Docket No. 50-313

- License No.'DPR-51 2 Monthly Operatirg Report Gd) lemen 4

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--Monthry: Operating. Report statistics for Arkansas Nuclear One, Unit 1, for

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June,;1992 issattached. This report is submitted in accordance with ANO-1 Technical.'Speci(1 ation 6.12.2.3.

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James J' - Fisicaro

-Director, : Licensing.

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JU. S. NRC-

' July:151 1992.

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Mr., James I.

Milhoan-Regional Administrator U.- S. Nuclear Regulatory Commission

, Region IV 611 Ryan Plaza _ Drive, Suite 400

' Arlington, TX-76011-8064-c NRC Senior Resident Inspector

'Q1 Arkansas Nuclear-One - ANO-1 6 ?

Number-1, Nuc1 car-Pinnt Road Russellville, AR 72801 tir. Thomas-W. Alexion

-NRR Project Mar.ager Region IV/ANO-1 U. S.' Nuclear Regulatory Commission NRR Mail Stop 13-11-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852

.Ms.-Sheri Peterson NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 1.

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0PERATING' DATA REPORT _

3 DOCKET NO:

50-313 DATE:

July 1 1992 COMPLETED BY: K. R. Hayes TELEPil0NE:

(50 Q 964-5535,_

OPERATING STATUS

?l; JUnit Names-LArkansas Nuclear One - Unit 1 2.-

. Reporting Period: June 1-30,-1992 3.

. Licensed Thermal Power (HWt): g,568 4.

Nr.meplate Rating (Gross MWe): 902.74 5.;

Denign Electrical: Rating (Net MWe):

850 6,. ' Maximum Dependable Capacity _(Gross MWe):

883 7_

Maximum Dependable Capacity (Not MWe):

836 8.-

-If Changos10ccur in Capacity Ratings (Items Number 3 Through 7) Since n

-Last; Report,;Give Reasons:

9.

Power Level To:Which Restricted, If Any (Not MWe):

None 10.tLReasons For Restrictions.

If Any: None HDHIQ-YR-TO-DATE GUMELATIVE

-l 11; Hours in Reporting Period....

720.0 4,367.0 153,690.0 12.

Number of Hours Reactor.was Critical-.....................

720.0 2,720.8 108,582.0

.13, Reactor Reserve Shutdown Hours...........i...........

0.0 0.0 5,044.0.

14. -ilours Generator On-Line......

720.0 2,671.9 106,404.7 15.

Unit Reserve ~ Shutdown licurs 0.0 0.0 817.5-

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16. :Grcss! Thermal Et.ergy Generated (MWli).......................'. 1,847,446.0 6,652,175.0 241,833,613.0 17.

Gross Electrical Energy

- G enerated (MWil):..............

624,945.0 2,268,600.0 80,547,140.0

18.

Not; Electrical Energy

~ Generated (MWH)....-..........

598,420.0 2,158,667.0 76,533,915.0

-19.

= Unit. Service Factor..........

100.0 61.2 69.2

-20. IUnit Availability Factor.....

100.0 61.2 69.8

-21

. Unit" Capacity; Factor (Using: MDC _ Not)..............

99.4 59.1 59.6 22'. (Unit Capacity Factor (Using DEC Net)..............

97.8 58.2-

-58.6 23.

Unit Forced-Outage Rate......

0.0 0.2' 12.2 24.

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

None-i f25.,1f Shut Down At End _of Report Period.

Estimated Date of Startup:

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26.'

Units 11n Test Status (Prior to Commercial Operation):

h Forecast Achieved INIT1.'.L CRITICALITY 08[Q6/24 COMMERCIAL OPERATION

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08/17/74 INITIAL ELECTRIC 1rY 12f_19[7_4

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AVERAGE DAILY UNIT. POWER LEVEL-

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,g DOCKET NO:

50-313

-UNIT:

One DATE:

July 811992

-COMPLETED BY:. K. R. liges TELEP110NE:

f501) 964-5535-

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MONTH J_uno. 1992-DAY-AVERAGE DAILY POWER LEVEL

'-(MWo-Not)-

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1c......-........

835-1-2"..............-

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^d 34.......4....:

837 4'..=.............-

837

-5................

835 6...............

834' 7-...............

--834

-8............'...-

833 9:.'.c...........

834-

'10r_.............

833 l11-..............

834-12'.. '..........-

830' 13.......'......

834-:

14J........".....

'831

15'.............

-832

.16c.............-

-830' 829 117D....-.........

18'.........'....

'829 19.............-

828 p

120:.........q...

828; 21 '..............828

' 2 2 L..'. i....... - 1830:

y 623...'..~..'.....

828

-24...'..........

829-

-25,.............-

827

-26'.............

828

-27............. '828

--28'........

827:

29e.............

828-30p.............

829 4

TAVGS: 831 INSTRUCTION on'.this format, list the average daily unit power icvel in MWe-Net for each day in reporting month.

Compute to the nearest whole megawatt.

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MONTilLY OPERATTNG REPORT OPERATING

SUMMARY

JUNE, 1992 UNIT ONE Unit One begna the month operating at 100% power. On the twnifth at 19:00 hours, the unit Icad was decreased to 92% to perform the scheduled turbine throttle / governor valve testing. The unit power was then returned to 100%

at 20:53 hours on the same day.

The unit operated at ful1 power for the remainder of the month.

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DATE: June, 1992

'l I

REFUELING INFORMATION 1.

Fame of faullity: Arkansas Nuclear One - Unit 1

'2.

Scheduled date for next refueling _ shutdown.

September. 17 _1993 t

3.

Scheduled _date for restart following refueling. November 12,_1993 r

4.

1W111'refvaling 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 associa' ed with the core re'oad -(Ref. 10 CFR Section 50.59)?

Yes.~ Technical Specification change to increase fuel enrichment from 3.5% to 4.1%.

-5.-

Scheduled date(s) for submitting proposed licensing _ action and supporting information._ The Technical Specification change request was submitted to the NRCaon June 27; 1991 J1CAN069108).

6.

=Importint; licensing considerations; associated with refueling, e.g., new or _different fuel design or: supplier, unroviewed design or performance

analysis; methods,Lsignificant changes' in fuel design, new op# cating procedures.

.None.

7,-

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

storage pool.. a) 177 b) 625-i

?The--presentflicensed spent fuel pool storage capacity.and the size of 8.

any, increase:In _ licensed storage capacity that has been requested or is planned, in' number of fuelfassemblies.

presents 968-increase size by.0

9..

l The. projected date of _ the last refueling that can be discharged to the spent fuel-pool assuming the present licensed capacity.

l DATE:

1995 (Loss of fullcore offload capability) i n

7

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