2CAN039302, Monthly Operating Rept for Feb 1993 for Ano,Unit 2
| ML20034H581 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/28/1993 |
| From: | James Fisicaro, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN039302, 2CAN39302, NUDOCS 9303190030 | |
| Download: ML20034H581 (7) | |
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March 15, 1993 2CAN039302 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station P1-137 Washington, DC 20555 o
Subject:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 l
Monthly Operating Report q
Gentlemen:
Monthly' Operating Report statistics for Arkansas Nuclear One,' Unit-2, for February,-1993 is attached. This report is submitted in accordance' i
with ANO-2 Technical Specification 6.9.1.6.
Very truly yours, l
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a J. Fisicaro-l Dd Di tor, Licensing t
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l March 15, 1993 i
2CANO39302' Page 2
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Mr. James L. Milhoan
.I Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400
'l Arlington, TX 76011-8064 i
NRC Senior Resident Inspector j
Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. Roby Bevan NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission
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NRR Mail Stop 13-H-3 p
One White Flint North 11555 Rockville Pike i
Rockville, Maryland 20852 Mr. Thomas W. Alexion i
NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 1
One White Flint North 11555 Rockville Pike Rockville, Maryland 20852
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R OPERATING DATA REPORT DOCKET NO:
50-368 i
DATE:
March 1,1993 COMPLETED BY: M. S. Whitt TELEPPONE:
(501) 964-5560 l
. OPERATING STATUS 1
Unit Name: Arkansas Nuclear One - Unit 2 I
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2.
Reporting Feriod:
Febman' l-28,1993 3.
Licensed ThermalPower(MWI): 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 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 CUMULATIVE
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Hours in Reporting Period.
672.0 1,416.0 113,352.0 12.
Number of Hours Reactor was Critical.
672.0 1,416.0 85,847.3.
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13.
Reactor Reserve Shutdown Hours...
0.0 0.0
. 0.0 14.
Hours Generator On-Line.
672.0 1,416.0 83,995.4 15.
Unit Reserve Shutdown Hours..
0.0 0.0
' O.0 16.
Gross Thermal Energy Generated (MWH);
1,879,633 3.970,288 221,737,091 17.
Gross Electrical Energy Generated (MWH)..
623,830 1,320,010.
72,950,201 18.
Net Electrical Energy Generated (MWH).
596,384 1,262,214 69,390,333 19.
Unit Service Factor..
100.0 100.0 74.1 20.
Unit AvailabilityFactor.
100.0
'100 0, 74.1 21.
Unit Capacity Factor (Using MDC Net).
103.4 103.9 71.3 22.
Unit Capacity Factor (Usig DEC Net).
97.3 97.7 67.1' 23.
Unit Forced Outage Rate..,
0.0 0.0 12.0 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 12/05n8 INITIAL ELECTRICITY 12/26n8 COMMERCIAL OPERATION 03/26/80
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' AVERAGE DAILY UNIT POWER' LEVEL v;*a-
[13 DOCKET NO:
30-368 UNIT:
.Two DATE:
March 1,1993 COMPLETED BY: M. S. Whitt TE1 FPHONE:
(501) 964-5560 MONTH Februarv.1993 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 891 2
892 3
891
+
4 892 5
888 6.
892 7
892 8
892
.9 891 10.
!!93 11.
392 12..
~395 13..
894
- l
- 14.
893 15.
892
- 16.
894
.17..
893 18.....
890 19.....
.889'
- 20..
889 21..
775 22.
882' 23...
-895 24.....
894 25.
893 26..
893 27....
892 28.
892 29.
- N/A 30.
- N/A 31.
- N/A i
AVGS: 887 INSTRUCTION
- On this format, list the average daily unit power level in MWe-Net for each ~
- day in reporting month. Complete to the nearest whole megawatt.
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t NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
FEBRUARY 1993 UNIT TWO The unit began the month of February at 100% power.
At 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on the twenty-first, a power reduction to 80%
was commenced due to a condenser tube leak.
After the tube leak was located and plugged, a power increase was initiated-and 100% power was attained at 0445 hours0.00515 days <br />0.124 hours <br />7.357804e-4 weeks <br />1.693225e-4 months <br /> on the twenty-second.
The unit operated at 100% for the remainder of the. month.
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i 2
m UNIT SIlUTDOWNS AND POWER REDUCTIONS REPORT FOR FEBRUARY,1993 DOCKET NO.
50-368 UNIT NAME ANO Unit 2 DATE March 1,1993 COMPLETED BY M. S. Whitt -
TELEPIIONE 501-964-5560 METIlOD OF LICENSEE DURATION SliU1 TING DOWN EVENT SYSTEM COMPENENT CAUSE & CORRECTIVE ACTION TO M
DALE TYPE 8 (110URS)
REASON 8 REACTOR 8 REPORT #
CODE' CODE' PREVENT RECURRENCE none I_
I 2
3 4
F: Forced Reason:
Method:
Exhibit G -Instructions S: Scheduled A - Equipment Failure (Explain)
I - Manual for Preparation of Data B - Maintenance of Test 2 - Mr.nual Scram.
Entry Sheets for Ucensee C - Refueling 3 - Automstic Scram.
Event Report (LER) File (NUREG-0161) -
D-Regulatory Restriction 4 - Continuation E - Operator Training & Ucense Examination 5 - Imad Reduction F-Administration 9 - Other 5-G - Operational Error Exhibit I - Same Source II-Other(Explain).
9 a,
y DATEi February,1993 REFUELING INFORMATION 9
t 1.
Name of facility: Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown. March 25. 1994
.'t 3.
Scheduled date for restart following refueling May 16. 1994 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 a
your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Raf. 10 CFR Section 50.59)?
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No Technical Specification changes or license amendments are known to be required at this time.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information. None Required 5
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.
None.
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7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
a) 177 b) 565 j
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 r
spent fuel pool assuming the present-licensed capacity.
DATE:
1997 (Loss of fu11 core offload. capability)
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