ML20046D425
| ML20046D425 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/31/1993 |
| From: | Hayes K ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20046D424 | List: |
| References | |
| NUDOCS 9308190354 | |
| Download: ML20046D425 (5) | |
Text
. _ -
'i OPERATING DATA REPORT DOCKET NO:
50-313 DATE:
August 3,1993 COMPLETEI BY: K. R. Hayes TELEPHOW :
(501) 964-5535 OPER ATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 1 2.
Reporting Period: July 1-31,1993 3.
Licensed Thermal Power (MW ): 2,568 4.
Nameplate Rating (Gross MWe): 902.74 5.
Design Electrical Rating (Net MWe): 850 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 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 I1.
Hours in Reporting Period.
744.0 5087.0 163194.0 12.
Number of Hours Reactor was Critical 744.0 5045.8 118044.8 13.
Reactor Reserve Shutdown llours 0.0 0.0 5044.0 14 Hours Generator On-Line.
744.0 5025.5 115847.2 15.
Unit Reserve Shutdown Hours..
0.0 0.0 817.5 16.
Gross Thermal Energy Generated l
(MWH) 1908940 12676900 265814054 17.
Gross Electrical Energy Generated (MWH).
635575 4310765 88688635 l
18.
Net Electrical Energy Generated (MWH)..
607620 4125253 84325854 19.
Unit Service Factor...
100.0 98.8 71.0 20.
Unit Availability Factor.
100.0 98.8 71.5 21.
Unit Capacity Factor (Using MDC Net)..
97.7 97.0 61.8 22.
Unit Capacity Factor (Using DEC Net).
96.1 95.4 60.8 23.
Unit Forced Outage Rate..
0.0 1.2 11.4 24.
Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):
' Refueling Outace IRI1 is scheduled to begin on September 7.1993, and end on October 19,1993.
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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 08/06/74-9308190354 930813 W
PDR ADOCK 05000313 R
PDR g
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-313
'i UNIT:
One DATE:
August 3.1993 COMPLETED BY; K. R. Hayes j
TELEPIIONE:
(501) 964-5535 i
MONTH Julv.1993 1
6 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) r f
1 822 2
820 3
819 4
820 5
821 6
822 l
7 821 8
821 9.
819 10.
818 11.
818 12.
818 13..
818 14.
817 15.
817 16.
814 17, 815 18.
816
'f 19..._..
816 20.
816 21.
814
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- 22...
815 23.
816 24.
813 25..
813 26.
812 l
27.
812 28.
815 29.
812 30.
814 31.
814 AVGS: 817 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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NRC MONTIILY OPERATING REPORT l
OPERATING
SUMMARY
JULY 1993 i
UNIT ONE
+
Unit one began the month operating at 100% power. On the sixteenth at 20:05 hours, the unit load was decreased to 95% to perform scheduled testing of the turbine throttle / governor valves. The unit power was then returned to 100% power at 21:10 hours on the same day. The unit operated at full power for the remainder of the month.
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I k
,,s,,,..
4 UNIT SilUTDOWNS AND POWER REDUCTIONS REPORT FOR JULY,1993 DOCKET NO.
50-313 UNIT NAME ANO Unit 1 DATE August 3,1993 l
COMPLETED BY K. R. Ilayes TELEPIIONE 501-WA-5535 l
l METIIOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPENENT CAUSE & CORRECTIVE ACTION TO E
DATE TYPE 8 (IlOURS)
REASON:
REACTOR 5 REPORT #
CODE' CODE 5 PREVENT RECURRENCE NONE l
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2 3
4 F: Forced Reason:
Method:
Exhibit G -Instructions S: Scheduled A - Equipment Failure (Explain) 1 - Manual for Preparation of Data B - Maintenance of Test 2 - Manual Scram.
Entry Sheets for Licensee C - Refueling 3 - Automatic Scram.
Esent Report (LER) File (NUREG-0161)
D - Regulatory Restriction 4 - Continuation E - Operator Training & License Examination 5 - Load Reduction F-Administration 9 - Other 5
G - Operational Error Exhibit I-Same Source II-Other (Explain)
.s
.a A
a.m a
DATE: July, 1993 l
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5 REFUELING INFORMATION j
i 1.
Name of facility: Arkansas Nuclear One - Unit 1
[
2.
Scheduled date for next refueling shutdown.
September 7, 1993 l
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3.
Scheduled date for restart following refueling. October 19, 1993 i
4.
Will refueling or resumption of operation thereafter require a i
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 l
Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?
Yes, Technical Specification change to reference B&W Topical Report BAW-10179P for the Core Operatin.g Limits Report. TS change increasing j
fuel enrichment from 3.5% to 4.1% was approved June 28, 1993, t
a 5.
Scheduled date(s) for submitting proposed licensing action and supporting information. A Technical Specification change request to
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reference B&W Topical Report BAW-10179P was submitted on May 7, 1993.
6.
Important licensing considerations associated with refueling, e.g.,
new j
or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating i
procedures.
l None.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 625 I
8.
The present IIcensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is i
planned, in number of fuel assemblies.
}
r present 968 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 fullcore offload capability)
This date changed due to the recent recovery of 59 storage
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spaces that had previously been considered unavailable due to physical interferences. The licensed or designed storage i
capacity did not change.
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