ML20006F667
| ML20006F667 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/31/1990 |
| From: | Whitt M ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20006F663 | List: |
| References | |
| NUDOCS 9002280280 | |
| Download: ML20006F667 (5) | |
Text
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OPERATING DATA REPORT S
DOCKET NO:
50-368 m'
DATE:
January, 1990 COMPLETED BY:M. 5. Whitt
- s' TELEPHONE:
(501) 964-3743 OPERATING STATUS 1.
Unit Name:
Arkansas Nuclear One - Unit 2 2.
Reporting Period: January 1-31, 1990 3.
Licensed Thermal Power (MWt):
2.815 4.
Nameplate Rating (Gross MWe):
942.57 5.
Design Electrical Rating (Net MWe):
912 6.
Maximum Dependable Capacity (Gross MWe):
897 7.
Maximum Dependable Capacity (Net MWe):
858 i-8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9.
Power Level To Which Restricted.
If Any (Net MWe):
None 10.
Reasons For Restrictions.
If Any:
None MONTH YR-TO-DATE CUMULATVE 11.
Hours in Reporting Period....
744,0 744.0 86,376.0 12.-
Nu;nber of Hours Reactor was Critical.....................
602.7 602.7 62,966.9 13.
Reactor Reserve Shutdown Hours........................
0.0 0.0 1,430.1 14.
Hours Generator On-Line......
599.6 599.6 61,380.3 15.
Unit Reserve Shutdown Hours..
0.0 0.0 75.0 16.
Gross Thermal Energy Generated (MWH)........................
1,493,744.0 1,493,744.0 159,702,274.0 o
17.
Gross Electrical Energy Generated (MWH)..............
493,205.0 493,205.0 52,450,681.0 18.
Net Electrical Energy
~ Generated (MWH)..............
467,639.0 467,639.0 49,844,609.0 19.
Unit Service Factor..........
80.6 80.6 71.1 20.
Unit Availability Factor.....
80.6 60.6 71.1 j
21.
Unit Capacity Factor I
(Using MDC Net)..............
73.3 73.3 67.3 22.
Unit Capacity Factor (Using DER Net)..............
68.9 68.9 63.3 23.
Unit Forced Outage Rate......
19.4 19.4 13.8 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
25.
If Shut Down At End of Report Period.
Estimated Date of Startup:
26.
Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICIlY COMMERCIAL OPERATION g
j%
9002280280 900215 PDR ADOCK 05000368 f-
.R PDC-g
n
'?--
-3 AVERAGE DAILY UNIT POWER LEVEL 4
i U_
DOCKET NO:
50-368 UNIT:
-Two DATE:
January. 1990 L
COMPLETED 8Y: M. S. Whitt TELEPHONE:
(501) 964-3743 L
' MONTH January. 1990
(;
DAY.
AVERAGE DAILY POWER LEVEL L
(MWe-Net) 1.............
-24 2'.............
-10 3...............
-10
!L 4.............<
-10 5.............
-15 n
6............. !
7.............
129 8.............
213 E
9'.............
340 10............
714 11.'...........
803 12....
812 l
13............-
810 14............
810 L-15-............
807 16............
809 17............
868 18............
887 i
19............
890' l-2 0.............
.889-l-
21.............
891 22............
891' N
23...........
889 24............
891 25............
892 26............
891 l
L
-27............
890-28.........-...
892' 29'............
892-30............
891 31.............
890-AVGS: '629 l
l INSTRUCTION l-L On this format. list the average daily unit power level in MWe-Net for each L
day in reporting month.
Compute to the nearest whole megawatt.
t:
[.
I E
NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
JANUARY 1990 UNIT TWO The unit began the month off line for the repair of a loose connection in a feedwater control cabinet.
On the seventh, at 0021 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br />, the unit was placed on line; and power was increased with some hold points for normal unit startup.
On the tenth, at 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br />, the power escalation was stopped at 90% due to a condenser tube leak.
Following the repair _of the condenser tube leak, the unit remained at 90% power due to radwaste fan and feedwater control problems.
After resolving the radwaste and feedwater problems, the unit attained 100% full power on the seventeenth at 0716 hours0.00829 days <br />0.199 hours <br />0.00118 weeks <br />2.72438e-4 months <br />.
The unit remained at 100% power through the end of the month.
a
r.
UNIT SHUTDOWNS AND POWER REDUCTIONS y
REPORT FOR JANUARY,.1990 DOCKET NO.
50-368 UNIT MAME AND Unit 2 DATE January, 1990 COMPLETED BY M. S. Whitt TELEPHONE 501-964-3743 Method of Licens;e Cause & Corrective Duration Shutting Event System Component Action to No.
Date Type (Hours)
Reason 2 Down Reactor 3 Report #
Code *
-Code 5 Prevent Recurrence l
89-08 900101 F
144.4 A
4 2-89-024 5J FC0 Unit began the month off line due to a loose q
connection in a feedwater control cabinet causing the unit to trip on high level in the "B" Steam Generator.
1 2
3 4
F:
Forced Reason:
Method:
Exhibit G - Instructions 5:
Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (HUREG-D-Regulatory Restriction 4-Continuation 1022)
E-Operator Training &
5-Load Reduction License Examination 9-Other s
F-Administrative Exhibit I - Same Source G-Operational Error (Explain)
H-Other (Explain)
p
~
i l
DATE:
January. 1990 I
REFUELING INFORMATION l'
1.
Name of facility:
Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown.
February 1991 (Beginning of Cycle 8 criticality was 11/18/89) 3.
Scheduled date for restart following refueling. April 1991 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 there be? If answer is no, has the r
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)?
r None Expected.
Reload fuel design is in progress.
I 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
None Required 6.
Important licensing considerations associated 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.
To obtain the presently planned cycle 8 length of 420 EFPD. it will be necessary to raise the current peak rod burnup limits.
A report justifying an increase was submitted in July. 1989.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, a) 177 b) 421 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.
present 988 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.
DATE:
1996 (Loss of fu11 core offload capability) w