1CAN019602, Monthly Operating Rept for Dec 1995 for ANO-1
| ML20096F632 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/31/1995 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1CAN019602, 1CAN19602, NUDOCS 9601240048 | |
| Download: ML20096F632 (7) | |
Text
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Entstgy Opsrations, Inc.
=~IENTERGY
'assa 333 RceMic AR 72801 Td 501858JA00 January 16,1996 ICAN019602 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Monthly Operating Report Gentlemen:
The Arkansas Nuclear One - Unit 1 Monthly Operating Report for December 1995 is attached.
This report is submitted in accordance with ANO-1 Technical Specification 6.12.2.3.
Very truly yours, k&C17/A Dwight C. Mims Director, Nuclear Safety DCM/eas 1
230142 i
9601240048 951231
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U. S. NRC Januaq 16,1996 ICAN019602 Pagd 2 cc:
Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Mr. George Kalman NRR Project Manager Region IV/ANO-1 & 2 U. S. Nuclear Regulatoy Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rochille Pike Rockville, MD 20852
OPERATING DATA REPORT DOCKET NO:
50 313 DATE:
January 16,19%
COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858-5560 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 1
)
2.
Reporting Period:
December 1-31 3.
Licensed ThermalPower(MWt): 2,568 l
4.
Nameplate Rating (Gross MWe): 903 1
5.
Design ElectricalRating (Net MWe): 850 6.
Maximum Dependable Capacity (Gross MWe): 883 7.
Maximum Dependable Capacity (Net MWe): 836 i
8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: N/A
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9.
Power Level To Which Restricted. If Any (Net MWe): N/A 10.
Reasons For Restrictions. If Any: N/A MONTH YR-TO-DATE CUMULATIVE 11.
Hours in Reporting Period....
744.0 8,760.0 184,387.0 12.
Number of Hours Reactor was Critical...
744.0 7,575.8 136,832.0 13.
Reactor Reserve Shutdown Hours.
0.0 0.0 5,044.0 14.
Hours Generator On-Line...
744.0 7,494.0 134,481.9 15.
Unit Reserve Shutdown Hours..
0.0 0.0 817.5 16.
Gross Thermal Energy Generated (MWH)................
1,900,631 18,320,027 312,473,916 17.
Gross Electrical Energy Generated (MWH)......
661,986 6,258,125 104,570,045 18.
Net ElectricalEnergy Generated (MWH),
635,051 5,972,724 99,498,213 i
19.
Unit Service Factor...
100.0 85.5 72.9 20.
Unit AvailabilityFactor.
100.0 85.5 73.4
)
21.
Unit Capacity Factor (Using MDC Net).
102.1 81.6 64.5 l
22.
Unit Capacity Factor (Using DER Net).
100.4 80.2 63.5 23.
Unit Forced Outage Rate.
0.0 1.9 10.2 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
None 25.
If Shut Down At End of Report Period. Estimated Date of Startup:
N/A 26.
Units in Test Status (Prior to Commercial Operation):
None Forecast Achieved INITIAL CRITICALITY 08/06n4 INITIAL ELECTRICITY 08/17/74 COMMERCIAL OPERATION 12/19/74
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-313 UNIT:
One DATE:
Jamtary 16,1996 COMPLETED BY: M. S. Whitt TELEPHONE:
[501) 858-5560 MONTH December 1995 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 1 8/9
' 2...
850 3.
852 4...
852 5
851 6........
852 7.
852 8...
851 9........
853 10..
855 11....
856 12..
856 13.......
856 14......
856 15.............
855 16=
855 17.............
855 18..................
852 19....
849 20..........
853 21..........
854 22..........
855 23....................
855 24................
853 25..........
852 26...............
854 27....
854 28.
855
- 29..
855 1
30..
856 31..
856 AVGS: 854 INSTRUCTION On this format, list the average daily unit power level in MWe-Net for each j
day in reporting month. Complete to the nearest whole megawatt.
j
UNITSIIUTDOWNS AND POWER REDUCTIONS REPORT FOR DECEMBER 1995 DOCKET NO.
50-313 UNIT NAME ANO Unit I DATE January 16,19%
COMPLETED BY M. S. Whitt TELEPHONE 501-85R-5560 METIIOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO E
DATE TYPE 8 GIOURS)
REASON 2 REACTOR 5 REPORT #
CODE' CODE 8 PREVENT RECLTRENCE None 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 of Test 2 - ?4anual Scram.
Entry Sheets for Ucensee C-Refueling 3 - Automatic Scram.
Event Report (LER) File (NUREG-0161)
D-Regulatory Restriction 4 - Continuation E - Operator Trainirig & Ucense Examination 5 - Lead Reduction F-Administration 9 - Other 5
G - Operational Error Exhibit I-Same Source II-Other (Explain)
NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
DECEMBER 1995 UNIT ONE The month ofDecember began with the unit operating at 100% power.
A power reduction to 88.0% was commenced at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br /> on the eighth for turbine governor and throttle valve stroke testing. At completion of the testing on the ninth, power was returned to 100%. The month ended with the unit operating at 100% power.
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,e Reporting Period: December 1995 REFUELING INFORMATION 1.
Name of facility: Arkansas Nuclear One - Unit 1 i
- 2.
Scheduled date for next refueling shutdown: Scotember 20.1996 3.
Scheduled date for restart following refueling: November 4.1996 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 detennine whether any unreviewed safety questions are associated with the core reload (Ref.10CFR Section 50.59)?
No.No 5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
N4 l
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.
1 None olanned l
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
a) 171 b) 245 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 268 increase size by 0 1
i 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
I DATE:
1996 (less of full core off-load capability)