ML20059G563
| ML20059G563 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/31/1993 |
| From: | Hayes K, Yelverton J ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1CAN01902, 1CAN1902, NUDOCS 9401240265 | |
| Download: ML20059G563 (7) | |
Text
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cc Td 501%4 ENG Jerry W. Yelverton W.c heklent Opxatuys AND January 14,1994 ICAN019402 U. S. Nuclear Regulatory Commission i
Document Control Desk Mail Station PI-137 Washington, DC 20555 f
Subject:
Arkansas Nuclear One - Unit 1 j
Docket No. 50-313 License No. DPR-51 Monthly Operating Report i
Gentlemen; i
The Arkansas Nuclear One - Unit 1 Monthly Operating Report (MOR) for December,1993 is attached. This report is submitted in accordance with ANO-1 Technical Specification
- 6. I 2.2.3.
Very truly yours,
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9401240265 931231 PDR-ADOCK 05000313 p
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U.S.NRCL.
- January 14,1994-I ICAN019402 Page 2 l
t cc:
Mr. James L. Milhoan Regional Administrator l
U. S. Nuclear Regulatory Commission i
Region IV 611 Ryan Plaza Drive, Suite 400 l
Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801
.{
Mr. Roby Bevan
-l NRR Project Manager, Region IV/ANO-1 i
U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 i
Mr. Thomas W. Alexion i
NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 i
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OPERATING DATA REPORT
+
DOCKLT NO:
50-313 DATE:
January 4,1994 l
COMPLETED BY: K. R. Ilayes
-l TELEPHONE:
(501) 964-5535
[
QPERATING STATUS
- l 1.
Unit Name: Arkansas Nuclear One - Unit 1 2.
Reporting Period:
December 1-31,1993
}
3.
Licensed Thennal Powcr (MWI): 2.568 4.
Nameplate Rating (Gross MWe): 902.74
.j 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 l
Last Report, Give Reasons:
9.
Power Level To Which Restricted. If Any (Net MWe): Nonc 10.
Reasons For Restrictions. If Any:
None
~i MONTII YR-TO-DATE QUMULATIVE j
i l 1.
Ilours in Reporting Period.
744.0 8760.0 166867.0 j
12.
Number ofIlours Reactor was Critical.
744.0 7599.4 120598.4 13.
Reactor Reserve Shutdown 0.0 0.0 5044.0
'i llours.
14 Ileurs Generator On-Line.
744.0 7521.9 118343.6 i
15.
Unit Reserve Shutdown llours.
0.0 0.0 817.5 i
16.
Gross Thermal Energy Generated r
(MWII)..
1909752 18913408 272050562 17.
Gross Electrical Energy i
Generated (MWII).
655445 6415165 90793035 18.
Net Electrical Energy Generated (MWII).
628849 6126535 86327136-19.
Unit Service Factor.
100.0 85.9 70.9 i
20.
Unit Availability Factor.
100.0 85.9 71.4 l
21.
Unit Capacity Factor l
(Using MDC Net).
101.1 83.7 61.9 22.
Unit Capacity Factor
-l (Using DEC Net).
99.4 82.3 60.9 23.
. Unit Forced Outage Rate.
0.0 2.7 I1.2
'i 24 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
l 1l 25.
If Shut Down At End of Report Period. Estimated Date of Startup:
-l 26.
Units in Test Status (Prior to Commercial Operation):
f Forecast Achieved INITIAL CRITICALITY 08/06/74 i
INITIAL ELECTRICITY 08/17/74' i
COMMERCIAL OPERATION 12/19/74 i
t t
i n
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-313 UNIT:
One DATE:
Januarv 4,1994 COMPLETED BY: K. It Hayes TELEPHONE:
(501) 964-5535 MONTH December.1993 DAY AVERAGE DAILY POWER LEVEL (MWe-Nc0 1
845 2
845 3
843 4
845 5
845 6
845 7
845 8
345 9
846 10 845 11 845 12.
345 13.
845 14.
846 15.
846 16.
845 17.
845 18.
847 19 845 20.
845 21.
846 22.
845 23.
845 24.
845 25.
845 26.
846 27.
846 28.
845 29.
845 30 845 31.
845 AVGS: 845 INSTI1QCT_LQN On this format, list the average daily unit power level in MWe-Net for each day in reporting month. Compicte to the nearest whole megawatt.
8 i
NRC MONTIILY OPERATING REPORT
[
OPERATING
SUMMARY
DECEMIIER 1993 UNIT ONE Arkansas Nuclear One, Unit One, began the month operating at 100% power. On the third at 21:00 hours, the unit power was decreased to 95% to perform scheduled testing l
of the turbine throttle / governor valves. The unit power was returned to 100% at 22:25 hours on the same day. Unit 1 operated at full power for the remainder of the month.
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UNIT SilUTDOWNS AND POWER REDUCTIONS REPORT FOR DECE31BER,1993 DOCKET NO.
50-313 UNIT NA31E ANO Unit i DATE Januarv 4,1994 COStPLETED BY K. R. lisws l
TELEPilONE 501 964-5535 4
31ETIlOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEN1 COSIPENENT CAUSE & CORRECTIVE ACTION TO M
DATE TYP E' (IIOURS)
REASON 2 REACTOR 8 REPORT #
CODE' CODES PREVENT RECURRENCE NONE 4
I 2
3 4
l F: Forced Reason:
Afethod:
Exhibit G -Instructions S: Scheduled -
A - Equipment Failure (Explain) 1 - 51anual for Preparation of Data B - 51mintenance of Test 2 - Af anual Scram.
Entry Sheets for Licensee C - Refueling 3 - Automatic Scram.
Event Report (LER) File (NUREG-0161)
D - Regulatory Restriction 4 - Continuation E-Operator Training & Lkense Examination 5 - Lead Reduction F-Administration 9 - Osher 5
G - Operational Error Exhibit I-Same Source II-Other (Explain)-
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DATE: December,1993
'I
'l REFUELING INFORMATION i
1.
Name offacility; Arkansas Nuclear One - Unit i 2.
Scheduled date for next refueling shutdown. Ecbruary 14.1995 3.
Scheduled date for restart following refueling. April 7.1995 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 l
with the core reload (Ref.10 CFR Section 50.59)?
Unknown at this time m
5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
Unknown at this time 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.
i 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
a) 177 b)685 i
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 assembhes.
i present 968 increase size by 0 j
9.
The projected date of the last refueling that can be discharged to the spent-fuel pool 1
assuming the present licensed capacity.
I DATE: 1996 (Loss of full core off-load capability)
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