ML19305A852

Monthly Operating Rept for Feb 1980

ML19305A852
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/14/1980
From:	Bramlett L ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19305A850	List: ML19305A848 ML19305A852
References
NUDOCS 8003180501
Download: ML19305A852 (6)

Text

O AVERAGE DAILY UNIT POWER LEVEL DOCKET No.

50-313 AN0-1 exty D ATE 3/14/80 C0\\tPLETED BY L. S.B raml ett TELEPHONE (501)968-2519

.\\t0 NTH February, 1980 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL t\\tw Net) t %1We Net) e 0

768 17 2

0 769 ig O

767 3

i, 4

0 768 2a 5

0 769 21 6

0 768 O

768 23 s

0 769 24 9

70 25 767 to 601 765 26 728 767 2,

12 743 767

,3 725 769 13

,9 14 728 NA 30 is 756 NA 3,

16 767 INSTRUCTIONS On this forrnat.hst the ac ge daily umt,> ewer lesel in siwe Net for caeh day m the reportmg month. Compute to

he nearest whole megawa :

(9/77 )

I goosiso 9/

OPERATING DATA REPORT DOCKET NO.

50-313 DATE 3/14/80 COMPLETED BY L. S. B raml ett TELEPHONE I cini i OFR-2519 OPERATING STATUS Arkansas Nuclear One - Unit 1 Not"

1. Unit Name:

2. Rep'orting Period:

February 1-29. 1980

3. Licensed Thermal Power (SlWI):

25_68 902.74

4. Nameplate Rating (Gross stWel:

850

5. Design Electrical Rating (Net alwel:

883

6. Maximum Dependable Capacity (Gross MWe):

836

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (1: ems Number 3 Through 7) Since Last Report. Gise Reasons:

Nnna

9. Power Level To which Restricted. lf Anv (Net MWel:

None

' NA

10. Reasons For Restrictions. If A ny:

This Month Yr..t o-Da t e Cumulatis e 696.0 1440.0 45571.0 i1. Hours In Reporting Period

12. Number Of Hour. Reactor kas Critical 493.3 493.3 30631.5 0.0 0.0 4247.4

13. Reactor Reserse Shutdown Hours

14. Hours Generatcr On-Line 488.8 488.8 29959.3 0.0 0.0 796.7

15. Unit Resene Shutdown Hours 1205311.0 1205311.0 72467355.0

16. Gross Thermal Energy Generated (MWHi 379570.0 379570.0 24100726.0

17. Grow Electrical Energy Generated IMWHi 362342.0.

362342.0 22996378.0

18. Net Electrical Energy Generated (MbHi 70.2 33.9 65.7-

19. Unit Senice Factor 70.2 33.9 67.5

20. Unit Availability Factor 62.3 30.1 60.4

21. Unit Capacity Factor (Using MDC Neti 61.2 29.6 59.4

22. Unit Capacity Factor (Using DER Neti 0.0 0.0 15.4

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date,and Duration of Eacht:

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

26. Units in Test Status tPrior io Commercial Operation):

Forecast Achiesed INITI A L CRITICA LITY INITIAL ELECTRICITY COMM ERCIA L OPER ATION (0/77 l l

an, M80 RE1W LING INFORMATION 1.

Name of facility.

Ar' kansas Nuclear One - Unit 1 2.

Scheduled date for next refueling shutdown.

12/1/80 2'1/81 3.

Scheduled date for restart following refueling.

/

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 these be?

If answer is no, has the relcad fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewen cafety. questions are associated with the core reload (Ref.10 CFR Section 50.59)?

Yes. reload report and associated proposed Techr.ical Specification chances. Also, the safety analysis of four demonstration hiah burn-uo assamblies will be orovided.

5.

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

9/1/80 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.

Will reload 68 fresh fuei assemblies and operate for approximately 16 months.

Four of which will be hich burn-up test assemblies.

7.

"Dae number of fuel asse=blies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 176 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 590 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:

1986

, :t 3

IN N M I' NO. 3-M tiNil Sililli' OWNS AND POWEH Hi tillrilONS IJNI l' N Ahlii ANO-linIt i DA1E.3/,14/nn COMI't.ETED llY I,.

S. Ilramlett Hi!POR I AIONill February- - - -

lit.EPilONE. 501-968-2519 n

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Date r;

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.i if, =1 Repint :

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Prevent itecunente v

6 79-06 791231 S

207.2 11 1

NA Cll INSTRU Commitment to NRC to provide TM1 11 related modifications.

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l F: l'orced Itcason:

Eleiln il:

INinliii G. Insanicei.iis i

S: Silicilnied A lil sipinent Failure (! xpl. sin) 141ainal fin l'icpas,itann of Dan

. h1anual Sciain.

1.nia) Shecis lin I accince it f.laintenance on Icst C Itefueling

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D Regulatin) Itcsisiction 1.Osher(Fsplain) 01(. I )

I.. Operator l'saining & I hense laanunation 17 Adnunistrative G O pesationalI n us(l.spl.n.i)

1. sinbit i. S.une S.nnce P8/77) lI ()lher ilisplain)

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NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- FEBRUARY, 1980 UNIT I During the first eight days of February, the unit remained shutdown in continuation of outage 79-06.

During this outage the low pressure, turbine "B" was modified due to cracks in the turbine rotor. Because of this modification, Westinghouse put a limit of 780 MWe gross on unit output.

The unit was placed on line February 9 and reached the 780 MWe limit on February 11. During this period of operation, the number 1 governor valve stem on the HP Turbine failed. This caused approximately a 30 MWe output loss until the valve operation was restored on February 14.

On February 15, Westinghouse lif ted the 780 MWe limit and the reactor power was taken to 100%. This increased unit output to approximately 805 MWe where the unit is now li=ited because of the modification to LPT "B" blading. The unit continued operation for the remainder of

~

the month.

9 9

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ARKANSAS NUCLEAR ONE - UNIT I Periodic' Core Power Distribution Comparison A Radial Power Distribution comparison was performed at 127.2 EFPD.

The RMS (root mean square) of the differences between measured and predicted at the 52 instrumented fuel assembly locations was 0.0285 which is well within the acceptance criterion of 0.073.

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