2CAN069502, Monthly Operating Rept for May 1995 for ANO 2
| ML20085H368 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/31/1995 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN069502, 2CAN69502, NUDOCS 9506210131 | |
| Download: ML20085H368 (7) | |
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EnterDy Operations, Inc.
- m ENTERGY ma sa m fkssdM:ia. AR 72801 id 5018584.400
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June 15,1995 l
U. S. Nuclear Regulatory Commission i
Document Control Desk Mail Station PI-137.
Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit 2 l,
Docket No. 50-368 License No. NPF-6 Monthly Operating Report Gentlemen:
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The Arkansas Nuclear One - Unit 2 Monthly Operating Report for May 1995 is attached. The report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6 Very truly yours, hf WA Dwight C. Mims Director, Licensing DCM/dwb Attachments 9506210131 950531 PDR ADOCK 05000368
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-U. S. NRC.
- June 15,1995_
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' 2CAN069502 Page 2-4 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 1448 S. R. 333 l
Russellville, AR 72801 Mr. George Kalman NRR Project Manager Region IV/ANO-1 & 2 '
1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 w
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' OPERATING DATA REPORT DOCKET NO:
50-368 i
DATE:
June 15,1995 COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858 5560 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One -Unit 2 2.
Reporting Period:
May 1-31 3.
Licensed Thermal Power (MWt): 2,815 4.
Nameplate Rating (Gross MWe): 942.57 j
5.
Design Electrical Rating (Net MWe): 912 6.
Maximum Dependable Capacity (Gross MWe): 897 j
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.
MONTH YR-TO-DATE CUMULATIVE i1.
Hours in Reporting Period..
744.0 3,623.0 133,079.0 12.
Number of Hours Reactor was Critical..
744.0 3,199.4 103,760.8 13.
Reactor Reserve Shutdown Hours.........
0.0 0.0 0.0 14.
Hours Generator On-Line..
744.0 3,195.0 101,828.1 15.
Unit Reserve Shutdown Hours...
0.0 0.0 0.0 16.
Gross ThermalEnergy Generated (MWH).
2,024,227 8,686,284 271,028,493 17.
Gross Elxttical Energy Generafed (MWH)..
677,754 2,916,594 89,286,167 18.
Net Elestrical Energy Generr.ted (MWH)...
647,221 2,780,894 84,978,682 19.
Unit Service Factor.
100.0 88.2 76.5 20.
Unit AvPilability Factor..
100.0 88.2 76.5 21.
Unit C4pacity Factor j
(Using MDC Net).
101.4 89.5 74.4 22.
Unit Capcity Factor (Using DER Net)....
95.4
_84.2 70.0 23.
Unit Forced Outage Rate.
0.0 2.5 10.2 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
2RI1 Refueling Outage to start September 22,1995 with a scheduled duration of 45 days.
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
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-368 ~
UNIT:
Two DATE:
June 15,1995 i
COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858-5560 MONTH May 1995 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 892 2
892 1
3 891 4........
890 889 6
889 7
887 8.
889 9.
886 10...
798 11.
566 12.....
'807 13.
875
'l 14.
879 j
15........
885
- 16....
881 17.
881 18.
8E 19.....
390 j
20.
389 21......
888 22..
886 I
23...
883 24...,.
883 25.
884 26....
879 27....
882 28......................
884 29...........
287 30...
887
- 31...
888 AVGS: 870 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.
t NRC MONTIILY OPERATING REPORT
. OPERATING
SUMMARY
MAY 1995 -
UNIT TWO ~
I The unit began the month ofMay at 98.3% power.
At 1148 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.36814e-4 months <br /> on the tenth,'a turbine 16ad reduction was requested per the System Dispatcher -
- due to damage to the Mabelvale 500 KV transmission line Following repairs to the transmission line, the dispatcher released the unit from the derate at 0120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> on the twelfth. The unit attained 98.3% power at 1405 hours0.0163 days <br />0.39 hours <br />0.00232 weeks <br />5.346025e-4 months <br /> that same day.
The unit operated the remainder of the month at 98.3% power.
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UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR MAY 1995 DOCKET NO.
50-368 UNIT NAME ANO Unit 2 DATE June 15,1995 COMPLETED BY M. S. Whitt TELEPHONE.
501-858-5560 METHOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO M
DATE TYPE' (HOURS)
REASON 2 REACTORS REPORT #
CODE' CODES PREVENT RECURRENCE 95-02 950510 F
0 H
5 N/A ZZ ti">>-
The System Dispatcher requested a load reduction due to damage to the Mabelvale 500 kV line.
I-2 3
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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 - Manual Scram.
Entry Sheets for IJcensee C-Refueling 3 - Automatic Scrant Event Report (LER) File (NLIREG-4161)
D-Regulatory Restriction 4 - Continuation E - Operator Training & License Examination 5 - I ned Reduction F-Administration 9 - Other 5
G - Operational Error Exhibit I-Same Source H - Other (Explain)
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. Reporting Periodi May 1995
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l REFUELING INFORMATIO.N
- 1. _ Name of facility: Arkansas Nuclear One - Unit 2 -
U 2.
Scheduled date for next refueling shutdown: Seotember 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 core configuration been reviewed by your Plant Safety Review Committee to
' Section 50.59)?
H determine whether any unreviewed safety questions are associated with the core reload (Ref,10CFR.
Dslete reauirement for verification of oosition stoos for the high pressure safety iniection throttle -
I valves. Revise Technical Specifications to account for the reolacement of oart-lenath control element
- assemblies with full-length control element assemblies. Revise the refue..cc in the Administrative Controls section to allow use of the Modified Statistical Combination of Uncertainties for deteindning l
core operatina limits. Relocate the value used to decrease the core power operatina limit based on DNBR when neither CEAC is ooerable to the Core Operatina Limits Report. Revise containment cooline 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
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- 6. - Important licensing considerations associated with refueling, e.g., new or different fuel design or
-l supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
None olanned L
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7, The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
a) M b) M j
8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage
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capacity that has been requested or is planned, in number of fuel assemblies:
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present 9.88 increase size by 0 i
8 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the i.
present licensed capacity:
l DATE:
1997 (Loss of full core off-load capability) i i
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