ML19210C942

Monthly Operating Rept for Oct 1979

ML19210C942
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/14/1979
From:	Pendergraft R ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19210C937	List: ML19210C935 ML19210C942
References
NUDOCS 7911200347
Download: ML19210C942 (5)

Text

• L AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-368 UNIT ANO-2 DATE 11/la/70 COMPLETED BY

_R.A. Pendergraft 501-968-2519 TELEPHONE MONTH mtnher 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMWe Net)g gwe.geg, 1 307 0 ,7 389 0 2__jg 3 398 0 39 4}01 0 20 5 0 21 0 6 0 22 0 7 23 0 0 8 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 0 29 14 0 0 30 0 15 0 33 16 0 1361 338 INSTRUCTIONS On this tormat, hst the ascrage dail) unit pimer leselin MWe Net for each day in the reporting inonth. Compute to the nearest whole megawatt.

19/77)7911200 h[

'4 OPERATING DATA REPORT 50-368 DOCKET NO.

DATE 11/'a /'o COMPLETED BY R. A. P' ndergraft e TELEPHONE 501-968-2519 OPERATING STATUS Notes 1. Unit Name: Jrkansas Niiclew nnn _ tin ; , , 2. Reporting Penod:

October 1-31. 1979

3. Licensed Thermal Power (MWt):

2815 959 4. Nameplate Rating (Gross MWel 912 5. Design Electrical Rating (Net MWel:

NA 6. Maximum Dependable C:pacity (Gross MWe):

_#7. Maximum Depnuable Capacity (Net MWe).

8. If Char.ges Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:

Non+9. Powet Lesel To which Restricted. lf Anv (Net MWel:

None NA 10. Reasons For Restricticas. If Any:

This Month Yr..to-Date Cumulatise I1. Ilours in Reporting Period 745.0 7296 n an4o n 12. Number Of ' aurs Reactor was Critical 78.0 2787.6 3999 s 0.0 2142.9 2285.1 13. Reactor Rewne Shutdown Hours

14. Ilours Generator On.Line 78.0 2447.0 2493.8 15. Unit Resene Shutdown Hours 0.0 21.7 71 _7 105867.0 2638959.0 2683537.0 16. Gross Thermal Energy Generated (MWill

17. Gross Eleevical Energy Generated iMWH) 31215.0 796971 n- 7non_n 18. Net Electrical Energy Generated (MWHi 28698.0__fMfLo41 o sq,o9q n__19. Unit Service Factor

]20. Unit Availability Factor I 21. Unit Capacity Factor (Using MDC Net) 7 NA UNTIL C0FNERCIAL OPERATION

1. 22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each1:

None November 22, 1979

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

26. Units in Test Status t Prior to Commercial Operationi:

Forecast Achiesed INITIA L CRITICA LITY 5-78 INITIAL ELECTRICITY

-w h 78 COMMERCIAL OPER ATION Jan. 1980' " ' " '1361 339

>4 1 50-368'UNIT SIIUTDOWNS AND POWER RLDUCTIONS DOCKETNO.7NO-Unit 2

• UNI r N A%IE DATE 3714/79 REPORT A10NTil October 005tPLE IED BY R. 3. Penderaraft TEl.EPilONE 501-968-2519

,,...: c.5 '?3$ $l'Licensee g-r, y *., Cause & Coniective

, No.Dale&53 4 is5 Event?'s '?Action to jE 5 5 iji =Repors =EU 5'Preseni Recurrente H g u e C.79-22 10-4-79 S 667 H 2 None IF AIRDRY loss of Instrument Air caused Unit to trip on same day as scheduled outage was to occur. Outage was scheduled for Reactor Internals Inspection.

-u I 2 3 4~F; Fosted Reason: hie hixt: 1%1 obit G - Instinctions S Scheduled A Equipnent Failure (17.xplain) '

l htanual for Psep. nation ol' Data

^*U.htaintenance or l'est 2-hf annal Scram.

I'ntr> Sheci> t'or I i.ensee

• C Refieling 3- Autoinatic Sstam.

laent Repois (1.1 R1 l ile (NilRI G-C-D Regulatory Restriction 4 Osher (Lsplain) 01611 l' Openalor Ts.sinnig & I hense I sananation F- A d nu nist rai n e 5 G. Opes ational i e sor (l.splaia l L sinbei 1 Saux Souice 08/77)11 Other (INplaini

• <REFUELING INFORMATION 1.Name of facility.

Arkansas Nuclear One - Unit 2 2.Scheduled date for next refueling shutdown.

9 1/g1 3.Scheduled date for restart following refueling.

3/1/q1 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 tha 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)?

Yes.Description of effects of new core loading 5.Scheduled date(s) for submitting proposed licensing action and supporting information.

12/1/80.6.Important licensing considerations 2:sociated 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 7.The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

a)_177 b)0 8.The present lic nsed spent fuel pool storage capacity and the size of any incr:sse in licensed storage capacity that has been requested or is planned.

.'n number of fuel assemblies.

present 486 increase size by 566 9.The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

DATE: 1993 136!341

• e NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- OCTOBER, 1979 UNIT II The 50% power plateau testing continued from the previous month.

At 0600 on 10-4, the reactor was manually tripped when all instrument air was lost due to an inoperable instrument air dryer valve. This trip occurred on the same day as the scheduled outage was to occur.

The unit has remained at 0 power for the remainder of the month while reactor internals inspection and diesel generator replacement is being accomplished.

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