ML19263B942

Monthly Operating Rept for Dec 1978

ML19263B942
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/12/1979
From:	Shively C ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19263B941	List: ML19263B940 ML19263B942
References
NUDOCS 7901250165
Download: ML19263B942 (5)

Text

.

AVER AGE D AILY UNIT P0wER LEVEL DOCKETNO.

20-'ll UNI T ANO-1 D ATE 01 17 70 C0\\tPLETED 8Y C. N. Shively TELEPHONE 501/968-2519 siONni December DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (stWe Net) i stWe. Net )

I 911 17 829 2

832 is 831 3

830 829-i9 4

8 30 20 307 5

831 21 538 6

974 22 75d 7

828 23 745 s

P28 24 749 9

9 'l 25 751

'831 746 to 26 11 829 747 12 410 23 744 13 826 748 29 14 477 30 740 15 831 267 3

16 R?l INSTRUCTIONS On this formst. list the atri. ige da's unn power iesci ni N1%e. Net for each day ni the ter :ing m.:n:h. Com.rure to the nearest whcie mepwatt.

( I' I

790125016 7

OPERATING DAl A REPORT DOCKET NO. 40 117 DATE 01 10 70 C05fPLETED BY F N <hively TELEPHONE "M /CCR-7519' OPERATING STATUS

~

1. Unit Name:

Arkansas Nuclear One-Unit 1 N

'*5

2. Reporting Period:

ha r a"'h a r 1-11 1078

3. Licensed Thennal Power (51Wt):

?"#P

4. Nameplate Rating (Gross 5the).

902.74 S.. Design Electrical Rating (Net AlWey.

850

6. Siaximum Dependable Capacity (Gross hiWe):

883

7. Staximum Dependable Capacity (Net ?!We):

836

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

Mena

9. Power Lesel To Which Restricted. !f Any (Net 5!We):

None

10. Reasons For Restrictions,if Any:

NA This hf onth Yr..to.Dat e Cumulative i1. Hours In Reporting Period 7aa n A760.0 37371.0

12. Number Of Hours Reactor Was Critical 770 4 6781.1 25710.I

13. Reactor Reserse Shutdown Hours 23.6 671.2 1989.9

14. Hours Generator On Line 716.0 6678.3 25213.7

15. Unit Reserse Shutdown Hours 00 117 7 70C ?

16. Gross Thermal Energy Generated (51WH) 1755888.0 16364183.0 cococ700 0

17. Gross Electrical Energy Generated (5fWH) 593880,0..

5494770.0 20240681.0 IS. Net Electrical Energy Generated (SIWH)

CAA177 0 52d9796.0 19310546.0

19. Unit Senice Factor CA ?

76.2 71.3

20. Unit Availability Factor 96.2 77.5 71.9

21. Unit Capacity Factor (Using.\\tDC Net) 01 1 71 7 AE.3

22. Unit Capacity Factor (Using DER Net)

PC A 70 C 64.2 23.' Unit Forced Outage Rate 1 - A Q.7 10.9

24. Shutdowns Scheduled Over Next 6 5 font % (Type. Date,and Duration of Each):

Scheduled refuelina, Ma,

.t 1979, 6 weeks

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

'l ? f12 "V 22. 1979

26. Units in Test Status (Prior to Commercial Operation s:

Forecast Achieved INITIA L CRITICA LITY INITIA L ELECTRICITY CONT %1ERCIAL OPER ATION N/77)

DOCKETNO. __50:.313 UNITSituTUOWNS AND POWER REDUCllONS 3

UNIT N AME AN0_1 DATE 01-12-70 COMPLElED 51Y

_. U l ShiVCly itEPORT MONTil December 1ELEPitt.NE _ _501496a=2SL9.

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Licensec

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{1, Cause & Corretlive Eg 4

gsE Even 37 eE Action to No.

D.u c c.

Report a mO EO Prevent Ithurience jE y

y ;c,3 H

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6 78-8 781220 '

F 12.9 A

3 NA ilA INSTRU Main Turbine Governor Valve LVDT Failure 78-9 781231 F

15.1 A

1 NA ilA TURBIN Main Low Pressure Turbine Failure.

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4 12 l.*s t c.l iteason:

Meiliod:

Exinin G - losirutilons S N l. 1.le.1 A-liguipment F.nluie (Expl. sin)

I -Man ual for Picparatiois.il D.ita Il-Maintenance or Tes 2 Manual Seeain linesy Sheets tu.1.icensec C-Itcfucting

.l. Antionatic S(sain.

livent Ileposi i1.1 111 I1!c (Niilti (.

1). Regulatory itesisiccion 4-Oilica (1:= plani) 01611 1 Operato Tsaniing & licisw I.xanunaison 17 Aileninnisative 5

G-Opesalional I esos (1:spl.na) 1:sliiliin I - S.nne Sousic l'3/ 71 ) -

II Ollier (1: spl. sin )

E: December 1978 REFUELING INFOR%\\E ON 1.

Name of facility, arkansas Nuclear One-Unit I r

2.

Scheduled date for next refueling shutdown.

3-1-79 3.

Scheduled date for restart following refueling. 5-01-79 4.

Will refueling or resumption 'f operation thereafter require a o

technical specification change or other license a=end:ent?

If answer is yes, what, in general, will these be?

If answer is no, has the reload fuel design and core configuratien been reviewed by your Plant Safety Review Co=mittee to deter =ine u.hether any unreviewed safety questions are associated.fth the core reload (Raf.10 CFR Section 50.59)?

Yes, see letter to Reid dated 11/9/78.

Scheduled date(s) for submitting proposed licensing action and 5.

supporting information.

11/9/78 (Actual) 6.

Important licensing censiderations associat'ed with refueling, e.g.,

new.or different fuel design or supplier, unreviewed design or perfor=ance analysis cethods, significant changes.in fuel design, new operating procedures.

Will reload 64 fresh fuel assemblies and operate for a nnrnvi-= tol v 16 mon ths.

7.

The number of fuel asse=blies (a) in the core and b in the spent fuel storage pool, a) 177 b)

I 8.

The~ present licensed spent fuel pool storage capacity and the si:a of any increase in licensed storage capacity that has been requested or is planned, in nu=ber of fuel asse=blies.

present 590 increase size by 0

9.

The projected date cf the last refueling thct een be discharged to"the opent fuel pool casu=ing the present licenced ccpacity.

DATE:

March 19R8 9