ML19211A300
| ML19211A300 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear |
| Issue date: | 12/14/1979 |
| From: | Bramlett L ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19211A299 | List: |
| References | |
| NUDOCS 7912170335 | |
| Download: ML19211A300 (5) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL DOCKET No.
50-313 UNIT ANO-Unit-1 12/14/79 DATE CO?fPLETED 8Y L. S. Bramlett TELEPHONE 501/968-2519 November 1979 MONni DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL OfWe Net) iMWe-Net i 1
0 0
17 0
0 2
is 0
3 19 0
4 0
262 20 S
0 279 21 0
650 6
7 0
23 793 8
0 815 24 0
9 25 R17 10 0
26 820 11 0
824 2;
0 826 12
,g 0
13 29 828 14 0
827 30 15 0
"A 0
16 INSTRUCTIONS On this format, list the asctge daily unit pimer leselin MWe Net for each day m the repo-im. month. Compute to the nearest whole megawatt.
1593 309 c> m,
7012170 33r
OPERATING DATA REPORT DOCKET NO.
50-313 DATE 12/14/79 COMPLETED BY L, S Aramlett TELEPHONE Su /968-2519 OPERATING STATUS N '"
Arkansas Nuclear One - Unit 1
- 1. Unit Name:
November 1-30. 1979
- 2. Reporting Period:
2,568
- 3. Licensed Thermal Power (MWI):
902.74
- 4. Nameplate Rating (Gross MWe):
850
- 5. Design Electrical Rating (Net MWel:
883
- 6. Maximum Dependable Capacity (Gross MWe):
836
- 7. Maximum Dependable Capacity (Net Mhe):
- 8. If Changes Occur in Capacity RatinFs (Items Number 3 Through 7) Since Last Report. Gise Reasons:
None
- 9. Power Lesel To Which Restricted. lf Any (Net MWel: None
- 10. Reasons For Restrictions. lf Any:
N/A This Month Yr.-to.Date Cumulatis e 720.0 8016.0 43387.0
- 11. Hours In Reporting Period 275.0 3685.3 29395.4
- 12. Number Of Hour, Reactor was Critical
- 13. Reactor Resene Shutdown Hours 0.0 2267 6 apa7 a
- 14. Hours Generator On.Line 262.1 3514.6 Ps72A 1
- 15. Unit Resene Shuidown Hour, 0.0 591.5 796 7 587982.0 8557997.0 69364706.0
- 16. Gross Thermal Energy Generated (MWH, 195340.0 2842175.0 23082856.0
- 17. Gross Electrical Energy Generated (MWH) 185747.0 2712411.0 22022957.0 IS. Net Electrical Enerps Generated (MWHI 36.4 43.8 66.2
- 19. Unit Senice Factor
- 20. Unit Asailability Factor 36.4 51.2 68.1
~
30.9 40.5 60.7
- 21. Unit Capacity Factor (Using MDC Neti 30.4 39.8 59.7
- 22. Unit Capacity Factor (Using DER Net) 0.0 40.2 15.9
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Nest 6 Months (Type. 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 o Commercial Operationi:
Forecast Achiesed INITI A L CRITICA LITY INITI AL ELECTRICITY COMMERCI AL OPER ATION 1592 310 i.,g >,
DATE: November 1979 REFUELING INFORMATION 1.
Name of facility.
Arkansas Nuclear One - Unit 1 2.
Scheduled date for next refueling shutdown. 11/01/1980 3.
Scheduled date for restart following refueling. 01/01/1981 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 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. Reload Report and associated proposed Technical Specification Changes.
5.
' Scheduled date(s) for submitting proposed licensing action and supporting information. 09/01/1980 6.
leportant licensing considerations associated with refueling, e.g.,
new or ditferent fuel design or supplier, unreviewed design or performance at.alysis methods, significant changes in fuel design, new operating procedures.
Will reinad 68 fresh fuel assemblies and operate for approxir.ately 16 months 7.
The number of fuel assemblies (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, 590 present 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.
1986 1592 311 DATE:
1-DOCKET NO.
50-313 UNir SiltlIDOWNS AND POWER Rf DUCTIONS UNIT NAME ANO - Ifnit 1 DATE _12/ 4/79 T
COMPI' ETED RY
_L. S. Brarglett_
'Q ItFI' ORT MONill Novr mher IELEPilONE 501 968-2519 N
C3
'5 ta 5 5
M
=
-, E 4 '
I.kenwe E -r,,
- - 7.
Cause & Corretiste 7,
.E _r-
$S Attion so No.
Daic 3,
3g j
.g g y 1:ven yy g
$E c2 35g Report :
iE C EU Prevent Recurrente H
,=2 O
3==
F IIII PUMPXX Commitment to NRC to provide vital 79-05 791020 S
457.9 11 1
NA RC INSTRU power to P7B, Emergency Feedwater pump and modify In-Core Temperature Detection Devices.
W I
3 4
F. I'orced Reason:
M et hoil:
l'.xhibit G - Instructions N
S: Sc heiluleil A l'quipment 1:aibue (i.xpl.un) 1 Mannal foi Piccaration of D.ita 11.Maintenante os l'est
.' Manual Scram.
1.nis) Shecis fos I icensee U
C-ItcIuchng 0 Auf omatic Scram.
I vent Itep.nl (I I RI I sie INURI:G-D Rcr.nla'"') RCsi'8 8"n
-I-Oshesliarlain) 01611 N
I -Opciator liainmg & I kense laJininJtion 17 Adennustrati.e 5
I.stohis t. S.nne Souvie G Operational I en., llTpl.on)
P7/77) 11 Ot her (lapland
NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
- NOVEMBER 1979 CNIT I The unit was off line for the first 19 days of the month.
This outage was scheduled for provision of vital power to P7B Emergency Feedwater Pump and modification of In-Core Temperature Detection Devices per NRC requirements.
Also, maintenance was performed' on Reactor Coolant Pump Seals.
On_ November 20, the unit was placed on line and held a 40% power until repairs were made on "A" Main Feedwater Pump. On November 24, the unit reached 100% power and operated there for the remainder of the month.
1592 313
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