1CAN129501, Monthly Operating Rept for Nov 1995 for Arkansas Nuclear One
| ML20095H298 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/30/1995 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1CAN129501, NUDOCS 9512220273 | |
| Download: ML20095H298 (7) | |
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-::~ ENTERGY "48 S n m Russeihin AR /2801 Tei 5018%5000 December 15,1995 ICAN129501 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station Pl-137 Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 i
Monthly Operating Report Gentlemen:
The Arkansas Nuclear One - Unit 1 Monthly Operating Report for November 1995 is attached.
This report is submitted in accordance with ANO-1 Technical Specification 6.12.2.3.
Very truly yours, j
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Dwight C. Mims j
Director, Nuclear Safety DCM/eas J
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U. S. NRC
. December 15,1995 ICAN129501 Page 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 i
NRR Project Manager Region IV/ANO-1 & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 j
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OPERATING DATA REPORT DOCKET NO:
50-313 DATE:
December 15,1995 COMPLETED BY: M. S. Whitt TELEPHONE:
(50l) 858-5560 OPERATING STATUS I
1.
Unit Name: Arkansas Nuclear One - Unit I 2.
Reporting Period:
November 1-30
}
3.
Licensed Thermal Pow.;(P iWO. 2J68
)
4.
Nameplate Rating (Gross MWe): 903 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 4
Last Report, Give Reasons:
9.
Power Level To Which Restricted. If Any (Net MWe):
10.
Reasons For Restrictions. If Any:
}
1 MONTH
_B-TO-DATE CUMULATIVE
(
11.
Hours in Reporting Period.
720.0 8,016.0 183,643.0 12.
Number of Hours Reactor was Critical.
720.0 6,831.8 136,088.0 13.
Reactor Reserve Shutdown Hours.
0.0 0.0 5,044.0 14.
Hours Generator On-Line..
720.0 6,750.0 133,737.9 15.
Unit Reserve Shutdown Hours.
0.0 0.0 817.5 16.
Gross Thermal Energy Generated (MWH).
1,844,686 16,419,395 310,573,285 17.
Gross Electrical Energy Generated (MWH)....
634,878 5,596,139 103,908,059 18.
Net Electrical Energy Generated (MWH).
608,795 5,337,673 98,863,162 19.
Unit Service Factor.
100.0 84.2 72.8 20.
Unit Availability Factor.
100.0 84.2 73.3 21.
Unit Capacity Factor (Using MDC Net).
101,1 79.7 64.4 22.
Unit Capacity Factor (Using DER Net)...
99.5 78.3 63.3 23.
Unit Forced Outage Rate.
0.0 2.I 10.2 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 IN~ITIAL CRITICALITY 08/06/74 INITIAL ELECTRICITY 08/17/74 COMMERCIAL OPERATION 12/19n4
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50 313 UNIT:
One DATE:
December 15,1995 COMPLETED BY: M. S. Whitt TELEPHONE:
(50l) 858 5560 MONTH November 1995 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 848 2...
845 3.
839 4....
846 5...
848 6........
848 7.
847 8
848 9..
848 10.......
848 11.
847 12....
848 13...
846 14....
839 15........
835 16.
836 17........
846 18.................
S(6 19..........
847 20........
848 21......
848 2 2.......
847 23.......
846 24........
845 25................
841 j
26....
844 j
27.
844 28.....
851 29.
851 30.
850 AVGS: 846 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.
.l 1
NRC MONTIILY OPERATING REPORT OPERATING
SUMMARY
NOVEMBER 1995 UNIT ONE The unit began the month of November operating at 100% power.
At 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on the third, a power reduction to 88.5% was conunenced for turbine governor and throttle valve stroke testing. Following completion of the testing, power was returned to 100% at 0006 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> on the fourth. Power was reduced to 94% at 1650 hours0.0191 days <br />0.458 hours <br />0.00273 weeks <br />6.27825e-4 months <br /> on the sixteenth due to a main condenser tube leak repair evolution. After plugging the damaged tubes in the condenser, power was returned to 100% at 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br /> on the sixteenth. A power reduction to 90% was commenced at 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br /> on the twenty-sixth due to degrading main condenser vacuum. The drop in condenser vacuum was the result of macro fouling of the condenser tubesheet. After cycling the condenser waterboxes to dislodge the macro fouling, power was returned to 100% at 0205 hours0.00237 days <br />0.0569 hours <br />3.38955e-4 weeks <br />7.80025e-5 months <br /> on the twenty-seventh. A second power reduction to 98% due to macro fouling of the condenser tubesheet was commenced at 1544 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.87492e-4 months <br /> on the twenty-seventh, and power was returned to 100% at 1559 hours0.018 days <br />0.433 hours <br />0.00258 weeks <br />5.931995e-4 months <br /> on that same day.
I The unit operated the remainder of the month at 100% power.
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UNIT SiiUTDOWNS AND POWER REDUCTIONS REPORT FOR NOVEMBER 1995 DOCKET NO.
50-313 UNIT NAME ANO Unit I DATE December 15,1995 COMPLETED BY M. S. Whitt TELEPHONE 501-858-5560 METHOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO i
M DATE TYPE' (HOURS)
REASON 2 REACTOR 3 REPORT #
CODE' CODES PREVENT RECURRENCE
\\
i 1
2 3
4 F: Forced Reason:
Method:
Exhibit G -Instructions S: Scheduled A - Equipament Failure (Expl9in) 1 - Manual for Preparation of Data B - Maintenance of Test 2 - Manual Scram.
Entry Sheets for Ucensee C-Refueling 3 - Autoenatic Scram.
Event Report (LER) File (NUREG-0161)
D-Regulatory Restriction 4 - Continuation E - Operator Training & Ilcense Examination 5 - Land Reduction F-Adniinistration 9 - Other 5
G - Operational Error Exhibit I-Same Source H - Other (Explain)
A Reporting Period: November 1995 REFUELING INFORMATION 1.
Name of facility: Arkansas Nuclear One - Unit 1 2.
Scheduled date for next refueling shutdown: _Ssptember 20.1996
. 3.
Scheduled dab 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 determine 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:
O I
J 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.
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None olanned 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
a) J12 b) 2 M 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 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 full core off load capability)
.