ML20043A602
| ML20043A602 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/30/1990 |
| From: | Schaubroeck D ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20043A600 | List: |
| References | |
| NUDOCS 9005220298 | |
| Download: ML20043A602 (5) | |
Text
P R
OPERATING DATA REPORT DOCKET N0:
50-313 DATE:
April, 1990 COMPLETED BY:C. A. Schaubroeck TELEPHONE:
(501) 964-3743 OPERATING STATUS 1.
Unit Name:
Arkansas Nuclear One - Unit 1 j
2.
Reporting Period:
April 1-30, 1990 l
3.
Licensed Thermal Power (MWt):
2,568 4.
Nameplate Rating (Gross MWe):
902.74 I
5.
Design Electrical Rating (Net MWe):
850 i
6.
Maximum Dependable Capacity (Gross MWe):
883 7.
Maximum Dependable Capacity (Net MWe):
836 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since j
Last Report, Give Reasons:
l 9.-
Power Level To Which Restricted.
If Any (Net MWe):
80%
10.
Reasons For Restrictions.
If Any (Net MWe):
A License Amendment j
was issued limiting operation to 80% due to a newly identified small 4
break LOCA in the High Pressure Injection Line Piping.
l-MONTH YR-TO-DATE CUMULATVE l
11.
Hours in Reporting Period....
719.0 2,879.0 134,682.0 12.
Number of Hours Reactor was Critical.....................
710.3 2,795.5 94,006.7 l
13.
Reactor Reserve Shutdown
]
Hours........................
0.0 0.0 5,044.0 14.
Hours Generator On-Line......
706.0 2,758.5 92,058.4 I
15.
Unit Reserve Shutdown Hours..
0.0 0.0 817.5 16.
Gross Thermal Energy Generated (MWH)........................
1,400,595.0 5,551,598.0 207,576,053.0 17.
Gross Electrical Energy Generated (MWH)..............
472,965.0 1,882,940.0 68,935,415.0 18.
Net Electrical Energy Generated (MWH)..............
447,857.0 1,781,999.0 65,494,249.0 19.
Unit Service Factor..........
98.2 95.8 68.4 1
20.
Unit Availability Factor.....
98.2 95.8 69.0 21.
Unit Capacity Factor (Using MDC Net)..............
74.5 74.0 58.2 22.
Unit Capacity Factor (Using DER Net)..............
73.3 72.8 57.2 l
23.
Unit Forced Outage Rate......
0.0 3.8 13.6 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
1R9 Refueling Outage is scheduled to begin September, 1990; and the scheduled date for restart is December, 1990.
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 ELECTRICITY COMMERCIAL OPERATION 9005220298 900515 PDR ADOCK 05000313 R
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AVERAGE DAILY DNIT POWER LEVEL-c DOCKETJNO:
50-313 UNIT:
One
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DATE:
April, 1990 -
COMPLE7ED BY: D.A. Schaubroeck
' MONTH April, 1990 p
DAY-AVERAGE DAILY POWER LEVEL-
-(MWe-Net)
^w
-1'..............
.663 2l.............
663 l3.............
- 663-4.............
662 h
L5.............
663 6...............
663 x
17'........'.....
645 8.............
561
.9.............
660 10............
662 11............
661 j
12............
661 1
13............
659 14............
661 15............
661
- 16-............
661 17............
660-
-18............
660 19............
661 J20............
661 21............
661 l
22............
661 23............
.660-24-............
659 25............
659 26-............
658
- 27............
657 28:............
69.
29............
319 l30............
576-AVGS:
623
..I_NSTRUCTION On. this format, list the average daily unit power level in MWe-Net for each day in reporting month. Compute to the nearest whole megawatt.
l 5
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t' NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
APRIL, 1990 UNIT ONE Unit One began the month operating at 80% power.
Operation at this level is based on analysis pertaining to a postulated high pressure injection line break.
On the seventh at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, a power reduction to ~25% was commenced for turbine governor valve / throttle valve testing.
The unit was returned to 80%
power at 0815 Itours on the eighth.
The unit operated at 80% power until 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on the twenty-eighth, at which time a power reduction was commenced to take the unit off line for snubber inspections.
The unit was removed from service at 0708 hours0.00819 days <br />0.197 hours <br />0.00117 weeks <br />2.69394e-4 months <br /> on the twenty-eighth and remained off line until 2010 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.64805e-4 months <br /> that same day.
At that time, the unit was placed back on line and a power escalation commenced.
Following a hold at 44% at the dispatcher's request, power was escalated to 80% power which was attained at 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> on the thirtieth.
The unit remained at 80% power through the end of the month.
t
t UNIT SHUTDOWNS AND POWER REDUCTIONS
+
8tEPORT FOR APRIL,1990 DOCKET NO 50-313 UNIT NAME One DATE April, 1990
' COMPLETED BY D. A. Schaubroeck TELEPHONE (501)964-3743 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action To No.
Date Type (Hours)-
Reason 2 Down Reactor 3 Report #
Code 4 Code 5 Prevent Recurrence l
90-05 900407 5
0.0 B
5 N/A SB V
Power reduction for turbine governor valve / throttle valve testing.
90-06 900428 5
13.0 H
1 N/A AB SNB Unit off line for snubber inspections.
1 2
3 4
F:
Forced Reason:
Method:
Exhibit G - Instructions S:
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 (NUREG-D-Regulatory Restriction 4-Continuation 1022)
E-Operator Training &
5-Load Reduction License Examination 9-Other 5
F-Administrative Exhibit I - Same Source G-Operational Error (Explain)
H-Other (Explain)
F1 l:*J
i h
,5
~
I DATE: April, 1990 i
P REFUELING INFORMATION 1.
Name of facility:
Arkansas Nuclear One - Unit 1 l
2.
Scheduled date for next refueling shutdown.
September, 1990 3.
Scheduled date for restart following refueling. December. 1990 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? If answer i
is yes, what, in general, will there 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)?
Normal Technical Specification changes associated with submission of the ANO-1 Cycle 10 Reload Report.
t 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
July, 1990 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.
A debris resistant, extended solid end cap design fuel rod will be used
[
in the reload fuel, batch.
E 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, a) 177 b) 508 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 968 increase size by 0 9.
The projected date of the last refueling that can be discharged to the l
spent fuel pool assuming the present licensed capacity.
DATE:
1994 (Loss of fullcore offload capability) r s
s 1
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