2CAN039501, Monthly Operating Rept for Feb 1995 for Arkansas Nuclear One
| ML20081D869 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/28/1995 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN039501, 2CAN39501, NUDOCS 9503210049 | |
| Download: ML20081D869 (7) | |
Text
J Entergy operations, Inc.
1
== ENTERGY iua n 3n R ece.e.AR 72301 4
Tei 501858-5000 March 15,1995 2CAN039501 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Monthly Operating Report Gentlemen:
The Arkansas Nuclear One - Unit 2 Monthly Operating Report for February 1995 is attached.
The report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.
Very truly yours,
& cy'@.W/4 I
Dwight C. Mims Director, Licensing DCM/dwb l
Attachments 210113 9503210049 950228
{DR ADOCK 05000368
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U. S. NRC March 15,1995 2CANO39501 Page 2 cc:
Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission Region IV l
611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One 1448 S. R. 333 Russellville, AR72801 Mr. George Kalman 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 l
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OPERATING DATA REPORT DOCVET NO:
50-368 DATE:
March 15,1995 COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858-5560 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 2 2.
Reporting Period:
February 1-28 3.
Licensed Thermal Power (MWt): 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): 895 '
10.
Reasons For Restrictions. If Any: Selfimposed power restriction to - 98.4% power based on T-hot limitations and the additional 300 steam generator plugs installed during 2P95-1.
MObrlTI YR-TO-DATE CUMULATIVE 11.
Hours in Reporting Period...
672.0 1,416.0 130,872.0 12.
Number of Hours Reactor was Critical.................
672.0 992.4 101,553.8 13.
Reactor Reserve Shutdown Hours.
0.0 0.0 0.0 14.
Hours Generator On-Line..
672.0 988.0 99,621.1 15.
Unit Reserve Shutdown Hours...
0.0 0.0 0.0 16.
Gross Thermal Energy Generated (MWH).
1,857,981 2,615,619 264,957,828 17.
Gross Electrical Energy Generated (MWH)..........
625,666 877,242 87,246,815 18.
Net ElectricalEnergy Generated (MWH)..........
598,284 831,984 83,029,772 19.
Unit Service Factor..
100.0 69.8 76.1 4
]
20.
Unit Availability Factor.
100.0 69.8 76.1 21.
Unit Capacity Factor (Using MDC Net).
103.8 68.5 73.9 22.
Unit Capacity Factor (Using DER Net).
97.6 64.4 69.6 23.
Unit Forced Outage Rate..
0.0 7.6 10.4 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 1
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Q*
y AVERAGE DAILY UNITPOWER LEVEL DOCKET NO:
50-368 UNIT.
Two DATE:
March 15,1995 COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858-5560 MONTH February 1995 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1...........
888 2...
886 3.........
888 4..
890 5..
890 6
891 7...
890 8
889 9.
887 10..
889 11.
892 12.
891 13.....
892 14..
892 15....
891 16.....
892 17.
892 18...........
892 19...........
891 20.
891 21..
886 22...
891 23.
889 24..
892 25...
892 26.
892 27...
890 28....
893 29......
N/A 30.
N/A 31.
N/A AVGS: 890 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 MONTHLY OPERATING REPORT i
OPERATING
SUMMARY
FEBRUARY 1995 UNIT TWO l
i I
The unit operated the entire month of February at 98.3% power.
4 4
l
UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT FOR FEBRUARY 1995 DOCKET NO.
50-368 UNIT NAME ANO Unit 2 DATE March 15,1995 COMPLETED BY M. S. %1utt TELEPIiONE 501-858-5560 METIIOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECITVE ACTION TO M
DATE TYPE' (IIOURS)
REASON 2 REACTORS REPORT #
CODE' CODES PKEVENT RECURRENCE none 1
2 3
4 F: Forced Reason:
Method:
Exhibit G -Instructions S: Scheduled A - Equipment Failure (Explain) 1 - Manual forPreparation of Data B-Malatenance of Test 2 - Manual Scrant Entry Sheets for Licensee C - Refueling 3 - Automatic Scrant Event Report (LER) File (NUREG-0161)
D-Regulatory Restriction 4 - Continuation E - Operator Training & IJcense Examination 5 -Imad Reduction F-Administration 9 - Other 5
G - Operational Error Exhibit I-Same Source II-Other (Explain)
Reporting Period: February 1995 1
REFUELING INFORMATION 1.
Name of facility: Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown: Scotember 22.1995 3.
Scheduled date for restart following refueling: November 6.1995 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 wre 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)?
Delete reauirement for verification of oosition stoos for the hiah pressure safety in_iection throttle valves. Revise Technical Soecifications to account for the reolacement of part-length control element assemblies with full-lenath control element assemblies. Revise the reference in the Administrative Controls section to allow use of the Modified Statistical Combination of Uncertainties for determinina core cocratina limits. Relocate the valug used to decrease the core oower coeratinn limit based on DNBR when neither CEAC is operable to the Core Occratinn Limits Report. Revise contammejn coolina system responscjime to account for modification to eliminate water hamme_L 5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
March and April 1995 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 planned 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
a) 171 b)#37 3
8.
'Ihe 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 spent fuel pool assuming the present licensed capacity:
DATE:
1997 (Loss of full core off-load capability)
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