ML19253B687
| ML19253B687 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/12/1979 |
| From: | Pendergraft R ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19253B685 | List: |
| References | |
| NUDOCS 7910170233 | |
| Download: ML19253B687 (5) | |
Text
.
AVER AGE D AILY UNIT POWER LEVEL DOCKET NO.
50-368 exij ANO-2 D ATE 10/12/79 C0\\tPLE".YD BY Rex Pendergraft TELEP!!ONE 501/968-2519
\\t0 NTH September 1979 DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (if h e-Net )
4.stwe.Neis 1
167 0
i; 2
287 is 0
3 401 to 0
4 403 20 0
5 406
- I 0
6 400 0
399 23 0
s 79
- 4 0
9 0
0 25 10 0
0 23 0
47 I:
0 189
- s 13 0
199 39 14 0
196 3o l5 0
NA 3:
16 0
INSTRUCTIONS On this format.hst the acoge dal) urut pimer laelin \\twe Net for e.sh day m the reportme month. Compute to
.he nearest whole mepwatt.
1148 347 (9/77) 7 910170 d 3]
OPERATING DATA REPORT DOCKET.'. J.
50-368 DmTE 10-12-79 COSIPLETEf BY Rex Pendergraft TELEPH 3NE cm /oco_9519 OPERATING STATUS N
Arkansas Nuclear One - Unit 2
- 1. Unit Name:
SeDtember 1 - 30, 1979
- 2. Reporting Period:
- 3. Licensed Thermal Power (51W ):
2815 953
- 4. Nameplate Rating (Gross SlWel:
912
- 5. Design Flectrical Rating (Net SIWE):
- 6. 51aximum Dependable Capacity (Gross 51We): NA NA
- 7. 51aximum Dependable Capacity (Net 51Wel:
S. If Changes Occur in Capacity Ratings (Irems Number 3 Through 7) Since Last Report. Give Reasons:
NONE
- 9. Power Letel To hhich Restricted. If Any (Net 5the):
NONE
- 10. Reasons For Restrictions. If Any:
NA This 51onth Yr. to Date Cumularise 720.0 6551.0 7295.0 i1. Hours in Reporting Penod
- 12. Number Of Hour 3 Reactor has Critical 356.7 2709.6 3144.5
- 13. Reactor Resene Shutdown Hours 232.3 2142.9 2285.1
- 14. Hours Generator On Line 262.9 2369.0 2421.8
- 15. Unit Resene Shutdown Hours 0.0 21.7 21.7
- 16. Gross Thermal Energy Generated tilh H, 301072.0 2533092.0 2577670.0
- 17. Gross Electrical Energy Generated iMhH) 84555.0 695308.0 700875.0 76006.0 620243.0 624227.0 IS. Net Electrical Energy Generated IMWHI
- 19. Unit Senice Factor
- 20. Unit Asailability Factor NA UNTIL COMMERCIAL CPERATION
- 21. Unit Capacity factor (Using.\\lDC Neti
- 22. Unit Capacity Factor (Using DER Nett
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Next 6 Slonths tTspe. Date, and Duration of Each t:
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operationi:
Forecast Achiesed INITI A L CRITIC \\ LITY 12-5-78 12-26-78
- l. ITI 4L ELECTRICITY N
CO\\l\\lERCI AL OPER AT!ON 1-20-80 1148 348 im
(
DO( K E I' NO.
'in-3fi8
)
UNil Siltill> OWNS AND POWElt Ill.DtlCliONS UNI I' N AM E _ANO-llait Twn i
i i
l DA1E __.lQ-12-79 COMPLETED tlY _Rdx, Eende raft 111 POlt T MON lli 3Dtembe r TELEPil0NE 8iOI 4 fir 7 4 f
u
[g
'h I stensee j g, Cause & Corrective l No.
D.sle C-
~E 4
.555 lhent 3?
N Atlion to
~
S j$
5 3 5 =!
ltepost :
(E 0 5'
Prevent llecurrente l
0 6
79-21 9-8-79 F
457.1 A
1 None llc llTEXCll Condensor tube ruptures and cracks in ilotwell False Floor I
I i
l 1
4 12: l'osceJ Itcason :
Melbod:
1:shibit G -Instinclions S Sc heduled A-l'quipinent 1 ailnic (l'xpl.nn) l M anual fo Preparanon of Data It M.iintenance or Test 2 M.anu.d St e.un.
l~nisy Shecis l'ne I icensee C-Itcinchng 4 Autor:utie Scr.un.
INent Itepoti ll.1 It) 1 de (NUltl'G-U D-Itegniatory Itesitichon Other l Explain) 01611 5':=
l Opentor lunung & I n ense I unnnation W
1 Ailonunisali.e 5
G Opciaininal i eror (l.splai.o 1.sinbis 1 - S.une Sonite pl/71) 11 Othes (! xplau.)
^
REFUELING INFORMATION 1.
Name of facility.
Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown.
2/1/81 3.
Scheduled date for restart following refueling.
4/1/81 4.
Will refueling or resumption o# operation thereafter require a technical specification changa or other license amendment?
If answer is yes, what, in general, will these 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 associated with the core reload (Ref. 10 CFR Section 50.59)?
Yes.
Description of effects of new core loading 5.
Scheduled dar 's) for submitting proposed licensing action and supporting 1 ormation.
12/1/80 6.
Important licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or perfor=ance analysis methods, significant changes in fuel design, new operating procedures.
NONE 7.
The nu=ber of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
a) 177 b) 0 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 asse=blies, 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
)\\h0 b
NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
- SEPTEMBER,1979 UNIT II The 50% power plateau testing continued from the previcus month.
The unit was manually shutdown on the 9-8 due to high chlorides in the seconda ry.
Condensor tube ruptures and cracks in the condensor false floor kept the unit down until 9-22.
While returning to power, the reactor tripped on low DNBR.
The unit was returned to power on 9-25 and power operation has continued throughout the remainder of the month.
1i48 351 i