ML20006F714
| ML20006F714 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/31/1990 |
| From: | Schaubroeck D ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20006F710 | List: |
| References | |
| NUDOCS 9003010050 | |
| Download: ML20006F714 (5) | |
Text
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.c OPERATING DATA REPORT DOCKET NO:
50-313 DATE:
January, 1990 COMPLETED BY:D. A. Schaubroeck TELEPHONE:
(501) 964-3743 OPERATING STAT,US 1.
Unit Name:
Arkansas Nuclear One - Unit 1 i
2.
Reporting Period:
January 1-31, 1990
[
3.
Licensed Thermal Power (MWt):
2,568 j
4.
Nameplate Rating (Gross MWe):
902.74
[
5.
Design Electrical Rating (Net MWe):
850 6.
Maximum Dependable Capacity (Gross MWe): 883 1
7.
Maximum Dependable Capacity (Net MWe):
836 l
8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since i
Last Report, Give Reasons:
9.
Power Level To Which Restricted.
If Any (Net MWe):
80%
10.
Reasons For Restrictions.
If Any (Net MWe):
A License Amendment was issued limiting operation to 80% due to a newly identified small i
break LOCA in the High Pressure Injection Line Piping, i
MONTH YR-TO-DATE CUMULATVE 11.
Hours in Reporting Period....
744.0 744.0 132,547.0 12.
Number of Hours Reactor was Critical.....................
744.0 744.0 91,955.2 13.
Reactor Reserve Shutdown Hours........................
- 0. 0 0.0 5,044.0 14.
Hours Generator On-Line......
719.3 719.3 90,019.2 15.
Unit Reserve Shutdown Hours..
- 0. 0 0.0 817.5 16.
Gross Thermal Energy Generated (MWH)........................
1,437,357.0 1,437,357.0 203,461,812.0 17.
Gross Electrical Energy Generated (MWH)..............
487,705.0 487,705.0 67.540,180.0 18.
Net Electrical Energy Generated-(MWH)..............
461,573.0 461,573.0 64,173,823.0 19.
Unit Service Factor..........
96.7 96.7 67.9 20.
Unit Availability Factor.....
96.7 96.7 68.5 21.
Unit Capacity Factor (Using MDC Net)..............
74.2 74.2 57.9 22.
Unit Capacity Factor
'(Using DER Net)..............
73.0 73.0 57.0 23.
Unit Forced Outage Rate......
3.3 3.327.6 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 ELECTRICITY COMMERCIAL OPERATION 9003010000 900215 D
i-PDR ADOCK 05000313
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PDC d
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AVERAGE DAILY UNIT POWER LEVEL h
DOCKET NO:
50-313 UNIT:
One DATE:
January, 1990 COMPLETED BY: D.A. Sch?ubroeck TELEPHONE:
(501) 964-3743 MONTH January, 1990 DAY AVERAGE DAILY POWER LEVEL f
(MWe-Net) 1.............
661 p
2..-...........
661-3.............
661 4.............
663 5.............
663 6.............
659 7..............
664 8.............
652 9.............
19 10............
163 11............
485 12............
665 13............
666 14............
664 15.............
664 16............
665 17............
664 18............
663 19............
663 20............
661 21............
662 22............
662 23............
662 24............
663 25............
666 26............
666 27............
665 28............
-666 29............
666 30............
667 31............
664 h..
-AVGS:.620 INSTRUCTION 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.
- O NRC MON 1HLY OPERATING REPORT 1
OPERATING
SUMMARY
JANUARY 1990 UNIT OtlE The unit began the month limited to 80% power based on an analysis 4
b pertaining to a postulated High Pressure Injecting Line Break.
On the eighth at 2140 hours0.0248 days <br />0.594 hours <br />0.00354 weeks <br />8.1427e-4 months <br />, a power reduction was commenced in order to take the unit off line for repair of the high pressure turbine governor valves.
The unit went off line on the ninth at 0332 hours0.00384 days <br />0.0922 hours <br />5.489418e-4 weeks <br />1.26326e-4 months <br />.
On the ninth at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />, the unit was placed back on line and power was escalated to 40%
and was held at this level to investigate Main Feedwater Pump problems.
The unit was taken aff line again on the tenth at 1728 hours0.02 days <br />0.48 hours <br />0.00286 weeks <br />6.57504e-4 months <br /> to allow for repair of the heater drain piping.
The unit was placed back on line on the eleventh at 0013 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> and power was escalated to 80% with a brief hold at 50% for Main Feedwater Block Valve testing. The unit attained 80% power at 7
1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> and remained at that level through the end of the month.
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mn
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u UNIT SHUTDOWNS AND POWER REDUCTIONS
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REPORT FOR JANUARY,1990
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DOCKET NO 50-313 UNIT MAME One DATE January, 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 dF Code
- Code 5 Prevent Recurrence 2
90-01 900109 F
18.0 A
9 N/A SB V
Unit off line for repair of the high pressure turbine governor valves.
90-02 900110 F
6.7 A
9 N/A SN PSP Unit off line for repair of eroded heater drain piping.
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 5
License Examination 9-Other F-Administrative Exhibit I - Same Source G-Operational Error (Explain)
H-Other (Explain)
. ~.
L OATE: January, 1990 t
REFUELING INFORMATION 1.
Name of facility:
Arkansas Nuclear One - Unit I
- s. -
2.
Scheduled date for next refueling shutdown.
September, 1990 3.
Scheduled date for restart following refueling. December, 1990 o
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 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.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
June, 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.
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 I
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
DATE:
1994 (Loss of fu11 core offload capability)
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