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 i9 829-4 8 30 20 307 5 831 21 538 6 974 22 75d 7 828 23 745 s P28 24 749 -

9 9 'l 751 25 to '831 26 746 11 829  :: 747 12 410 23 744 13 826 29 748 14 477 30 740 15 831 3 267 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)

UNITSituTUOWNS AND POWER REDUCllONS DOCKETNO. __50:.313 3

, UNIT N AME AN0_1 DATE 01-12-70 COMPLElED 51Y _. U l ShiVCly itEPORT MONTil December 1ELEPitt .NE _ _501496a=2SL9.

C

g

.'5 Cause & Corretlive

-, "h j E '_'; Licensec ,E t,, {1,

c. Eg gsE eE Action to No . D.u c 4 y

Even 37 mO H jE y ;c,3 =

e Report a EO u

Prevent Ithurience 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.

e l l 3 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 )

REFUELING INFOR%\E ON E: December 1978

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 o'f operation thereafter require a 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.

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