2CAN099501, Monthly Operating Rept for Aug 1995 for ANO Unit 2
| ML20092G319 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/31/1995 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN099501, 2CAN99501, NUDOCS 9509190229 | |
| Download: ML20092G319 (7) | |
Text
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Te!501858 5r00 September 14,1995
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2CAN099501 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 August 1995 is attached.
This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.
Very truly yours,
&C.??(A Dwight C. Mims Director, Licensing DCM/eas Attachments 1C0130 9509190229'950831 IbN PDR ADOCK 05000368 pl
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U. S. NRC September 14,1995
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2CAN099501 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 Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 i
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OPERATING DATA REPORT DOCKET NO:
50-368 DATE:
September 14,1995 COMPLETED BY: M. S. Whitt TELEPHONE:
(50l) 858-5560 QPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 2 2.
Reporting Period:
August 131 3.
Licensed Thermal Power (MWt): 2,815 4.
Nameplate Ra'.ing (Gross MWe): 942.57 5.
Design Electrical Rating (Net MWe): 912 6.
Maximum Dependable Capacity (Gross MWe): 897 l
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:
Self imposed power restriction to ~ 98.4% power based on i
T-hot limitations and the additional 300 steam generator plugs installed during 2P95-1.
MONTH YR-TO-DATE CUMULATIVE 11.
Hours in Reporting Period..
744.0 5,831.0 135,287.0 12.
Number of Hours Reactor was Critical..
744.0 5,407.4 105,968.8 13.
Reactor Reserve Shutdown Hours.
0.0 0.0 0.0 14.
Hours Generator On-Line....
744.0 5,403.0 104,036.1 15.
Unit Reserve Shutdown Hours..
0.0 0.0 0.0 16.
Gross Thermal Energy Generated (MWH)....
2,015,177 14,750,932 277,093,141 17.
Gross Electrical Energy Generated (MWH).
666,735 4,930,312 91,299,885 l
18.
Net Electrical Energy Generated (MWH).
636,056 4,703,664 86,901,452 19.
Unit Service Factor.
100.0 92.7 76.9 20.
Unit Availability Factor.
100.0 92.7 76.9 21.
Unit Capacity Factor (Using MDC Net)......
99.6 94.0 74.9 22.
Unit Capacity Factor (Using DER Net).
93.7 88.5 70.4 23.
Unit Forced Outage Rate.
0.0 1.5 10.0 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):-
Refueling Outage 2RI1 commencing September 22,1995 with a scheduled duration of 29 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 i-L____ _ ____ _ __ _ _ _ _ ___ _ _ _ _ ___.____
.-. _ _ _ - _ _. _ _ _. - ~ _ _ _
AVERAGE DAILY UNIT POWER LEVEL i
DOCKET NO:
50-368 i
UNIT:
Two DATE:
September 14,1995 i
COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858-5560 9
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MONTH August 1995 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) -
i l-1 877
[
2 876 l
3...
875 875 4
l 5......
876 6
876 i
7 874 l
8 873 9.................
871 i
10.
874 l
11..
871 12.........
791 13.
489 14.
712 l
'5.
875 16.
874 i
17.
875 18.
873 i
19...
875 l
20...
872 j
21.....
877 22.
877 23..
882 I
24.
882 25.
876 a
26..
875 27..
876 2 8..
877 29.
877 l
30.....
876 31...
876 3
i AVGS: 855 i
4 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 MONTIILY OPERATING REPORT OPERATING
SUMMARY
AUGUST 1995 UNIT TWO i
The unit began the month of August at 98.3% power.
At 1325 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.041625e-4 months <br /> on the tweiflh, a power reduction to 60% was commenced to allow isolation of feedwater heater 2E-6B for tube leak repairs. Following the completion of the repair work on the feedwater heater, the unit increased power and reached 98.3% at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on the foudeenth.
The unit operated the remainder of the month at 98.3% power.
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UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR August 1995 DOCKET NO.
50-368 UNIT NAME ANO Unit 2 DATE September 14,1995 COMPLETED BY M. S %1utt TELEPHONE 501-853-5560 l
METilOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO NO.
DATE TYPEI (HOURS)
REASON 2 REACTOR 3 REPORT #
CODE 4 CODES PREVENT RECURRENCE 95-03 950812 F
0 A
5 N/A SD IIX The unit reduced power to locate and plug leaking tubes in feedw ster heater 2E-6B.
Inspections are planned during refueling outage 2RIl to determine nhat caused the leaLing tubes.
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F: Forced Reason:
Method:
Ethibit G -Instructions S: Scheduled A - Equipment Failure (Explain) 1 - Manual for Prrparation of Data B - Maintenance of Test 2 - Manual Scram.
Entry Sheets for Ucensee C - Refueling 3 - Automatic Scram.
Event Report (LER) File (NUREG-e161) l D-Regulatory Restriction 4 - Continuation E - Operator Training & License Examination 5 -lead Reduction F-Administration 9 - Other 5
i G - Operational Error Exhibit I-Same Source H - Other (Eiplain)
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Reporting Period: August 1995 RFFUELING INFORMATION 1.
Name of facility: Arkansas Nuclear One - Unit 2 e
2.
Scheduled date for next refueling shutdown: Scotember 23.1995 i
3.
Scheduled date for restart following refueling: October 22.1995 i
4.
Will refueling or resumption of operation thereafter require a technical specification change or other license anx:ndment? 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)?
Delete reauiremgnt for verification of oosition stops for the hiah pressure safety iniection throttle valves. Revise Technical Specifications to account for the replacement of oart length control element assemblies with full-length control element assemblies. Revise the reference in the Administrative Controls section to allow use of the Modified Statistical Combination of Uncertainties for determinina core operating limits. Relocate the value used to decreasc the core nower operatina limit based on DNBR when neither CEAC is operable to the Core Operating 1.,imits iteoort. Revise containment coolina system response time to account for modification to eliminate water hanuner.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
i Submitted durina March and April 1995 6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or i
supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
None olanned 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
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a).l_7_7 b) 637 7
8.
'Ihe present licensed spent fuel pool storage capacity and the size of any increase in licensed j
storage capacity that has been requested or is planned, in number of fuel assemblies:
present R M increase size by Q 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) l l
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