2CAN049512, Monthly Operating Rept for Mar 1995 for ANO Unit 2
| ML20082K115 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/31/1995 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN049512, 2CAN49512, NUDOCS 9504190076 | |
| Download: ML20082K115 (7) | |
Text
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- h Entern operauons,inc.
c= ENTERGY 1a8sn 333 ReaMe. AR 72801 1
Tel 501858-5000 April 14,1995 2CAN049512 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 March 1995 is attached.
The report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.
Very truly yours, k
'W Dwight C. Mims Director, Licensing DCM/dwb Attachments 1000:/4 95o4190076 950331 II A#
PDR ADOCK 05000368 f
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U. S. NRC April 14,1995 2CAN049512 Page 2
-cc:
Mr. Leonard J. Callan
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Regional Administrator U. S. Nuclear Regulatory Commission j
j Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector.
5 Arkansas Nuclear One p
1448 S. R. 333 Russellville, AR 72801 i
Mr. George Kalman 4
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 4
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OPERATING DATA REPORT DOCKET NO:
50-368 DATE:
April 14,1995 COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858-5560 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 2 2.
Reporting Period:
March 1-31 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 4
7.
Maximum Dependable Capacity (Net MWe): 858 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since j
Last Report, Give Pasons:
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, Steam Generator Tube Inspection Outage, in January 1995.
MONTH YR-TO-DATE CUMULATIVE 11.
Hours in Reporting Period.
744,0 2,160.0 131,616.0 12.
Number of Hours Reactor was Critical.
744.0 1,736.4 102,297.8 13.
Reactor Reserve Shutdown Hours.
0.0 0.0 0.0 14.
Hours Generator On-Line.
744.0 1,732.0 100,365.1 15.
Unit Reserve Shutdown Hours.
0.0 0.0 0.0 16.
Gross Thermal Energy Generated (MWH)..
2,058,607 4,674,226 267,016,435 17.
Gross Electrical Energy Generated (MWH)...
693,473 1,570,715 87,940,288 18.
Net Electrical Energy Generated (MWH).
663,042 1,495,025 83,692,814 19.
Unit Scryice Factor.
100.0 80.2 76.3 1
20.
Unit Availability Factor..
100.0 80.2 76.3 21.
LNit Capacity Factor (UsMg MDC Net).
103.9 80.7 74.1 22.
Unit Ccoacity Factor (Using D2R Net).
97.7 75.9 69.7 23.
Unit Force 1 Outage Rate.
0.0 4.5 10.3 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
2R11 Refaeling Outage to start September 22,1995 with a scheduled duration of 45 days.
4 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 12/26D8 COMMERCIAL OPERATION 03/26/80
I AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-368 UNIT:
Two DATE:
April 14,1995 COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858-5560 i
MONTH March 1995
' DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 J
1..
894 2
894 3
893 4......
894 893 5
6 893 7
893 8
895 9
893 10.
893
- 11...
891 12 890 13.
889 14.
891 15.
890 l
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- 16......
890 17.....
890 i
18.....
889 19......
889 20..
890 21...
890 2 2.......
885 l
- 23...
889 24 886 25.
891 l
26......
888 l
27.
893 28.
893 l
29...
893 30_
893
- 31...
894 AVGS: 891 l
INSTRUCTION On this format, list the average daily unit power level in MWe-Net for each l
day in reporting month. Complete to the nearest whole megawatt.
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NRC MONTHLY OPERATING REPORT.
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OPERATING
SUMMARY
MARCH 1995 i
5 i
UNIT TWO r
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The unit operated the entire month ofMarch at 98.3% power.
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UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR MARCH 1995 DOCKET NO.
50-368 UNIT NAME ANO Unit 2 DATE April 14,1995 COMPLETED BY M. S. Whitt TELEPHONE 501-858-5560 METHOD OF LICENSEE TsUR*JION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO M
DATE TYPE' oiGimS)
REASON 2 REACTOR 8 REPORT #
CODE' CODgs PREVENT RECURRENCE none i
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 - Manuel Scrani.
Entry Sheets for Ucensee C-Refueling 3 - Automatic Scram.
Event Report (LER) File (NUREG-4161)
D-Regulatory Restriction 4 - Continuation E - Operator Training & Ucense Examination 5 -Imad Reduction.
F-Administration 9 - Other 5
G - Operational Error Exhibit I-Some Source H - Other (Explain) i
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Reporting Period: March 1995 '
REFUELING INFORMATION 1.
Name of facility: Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown: September 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 vnendmant? 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 I
determme whether any unreviewed safety questions are associated with the core reload (Ref.10CFR Section 50.59)?
l Delete reauirement for verification of nosition stons for the hinh oressure safety iniection throttle i
valves. Revise Technical Soecifications to account for the reolacement of part-lennth 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 determininn.
core ooeratina limits. Relocate the value used to decrease the core oower operatinn limit based on DNBR when neither CEAC is onerable to the Core Oneratina Limits Reoort. Revise containment coolina system response time to account for modification to eliminate water hammer.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
Submitted durina March and Aoril 1995 i
6.
Important licensing considerations associated whh refueling, e.g., new or different fuel design or supplier, unreviewed design or performance :.aalysis methods, significant changes in fuel design, new operating procedures.
l None olanned 7.
The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool:
a) 171 b) 6H 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 288 increase size by 0 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the 9.
present licensed capacity:
DATE:
1997 (Ioss of full core off-load capability)
,