2CAN089607, Monthly Operating Rept for July 1996 for ANO-2
| ML20116M616 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/31/1996 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN089607, 2CAN89607, NUDOCS 9608200233 | |
| Download: ML20116M616 (7) | |
Text
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- ENTERGY l$T""ffl"" ""*'
ResdWe AR /2201 Tel 501858 LOGO August 15,1996 2CAN089607 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555
)
Subject:
Arkansas Nuclear One - Unit 2 i
Docket No. 50-368 License No. NPF-6 Monthly Operating Report Gentlemen:
The Arkansas Nuclear One - Unit 2 Monthly Operating Report for July 1996 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.
Very truly yours, MhC%
Dwight C. Mims Director, Nuclear Safety DCM/eas attachment 9608200233 960731 PDR ADOCK 05000368 YSy/
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200011
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, U. S. NRC August 15,1996 2CAN089607 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 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
OPERATING DATA REPORT DOCKET NO:
50-368 DATE:
August 15,1996 COMPLETED BY: M. S. Whitt TELEPilONE:
(50l) 858-5560 OPERATING STATUS l.
Unit Name: Arkansas Nuclear One - Unit 2 2.
Reporting Period:
July 1-31 1
3.
Licensed Thermal Power (MWt): 2,815 l
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): 890 10.
Reasons For Restrictions. If Any:
Selfimposed power restriction to ~ 97.9% power based on T-hot limitations in combination with current steam generator plugging and fouhng levels.
MONTH YR-TO-DATE CUh.0LATIVE 11.
Hours in Reponing Period.
744.0 5,111.0 143,327.0 12.
Number of Hours Reactor was Critical.
744.0 5,il1.0 112,581.8 I
13.
Reactor Reserve Shutdown 4
Hours.
0.0 0.0 0.0 14.
Hours Generator On-Line.
744.0 5,111.0 110,389.1 15.
Unit Reserve Shutdown Hours..
0.0 0.0 0.0 16.
Gross Thermal Energy Generated (MWH).
2.050,280 14,081,966 294,344,451 17.
Gross Electrical Energy Generated (MWH).
682,524 4,724,09^
97,073,693 18.
Net Electrical Energy Generated (MWH).
651,796 4,514,492 92,395,158 19.
Unit Sersice Factor.
100.0 100.0 77.0 20.
Unit Availability Factor..
100.0 100.0 77.0 21.
Unit Capacity Factor (Using MDC Net).
102.1 102.9 75.1 22.
Unit Capacity Factor (Using DER Net).
96.1 96.9 70.7 23.
Unit Forced Outage Rate.
0.0 0.0 9.8 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
None 25.
If Shut Down At End of Report Period. Estimated Date of Startup:
N/A 26.
Units in Test Status (Prior to Commercial Operation):
None Forecast Achieved j
INITIAL CRITICALITY 12/05n8 INITIAL ELECTRICITY 12/26n8 COMMERCIAL OPERATION 03/26/80 l
AVERAGE DAILY UNIT POWER LEVEL DOCYIT NO:
50-368 UNIT:
Two DATE:
August 15,1996 COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858-5560 MONTH July 1996 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 874 2
873 3.
874 4
882 5
879 6
874 7
871 8.
873 9
880 10..
883 11.
883 12..
880 13.
877 14.
876 15.
879 16..
876 17.
874 i
18.
873 19.
872 20.
871 21.
870 22....
871 23.
876 2 4..
876 25.
879 26...
880 27.
879 28.
876 29.
876 30.
878 31.
877 AVGS: 876 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.
~
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR JULY 1996 DOCKET No.
50-368 UNIT NAME ANO Unit 2 DATE August 15,1996 COMPLETED BY M. S. Whitt TELEPHONE 501-858-5560 METHOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO 3
REPORT #
CODE' CODE 5 PREVENT RECURRENCE M
DATE TYPE' (HOURS)
REASON 2 REACTOR none f
1 I
i 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 - Manual Scram.
Entry Sheets for Licensee C-Refueling 3 - Automatic Scram.
Event Report (LER) File (NUREG-0161)
D-Regulatory Restriction 4 - Continuation E - Operator Training & License Examination 5 - Lead Reduction F-Administration 9 - Other 5
G - Operational Errur Exhibit I-Same Source
.- a m.
m-a m-mx -
7
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NRC MONTHLY OPERATING REPORT l
OPERATING
SUMMARY
JULY 1996 UNIT TWO The unit operated the entire month of July at 97.9% power.
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Reporting Period: July 1996 REFUELING INFORMATION 1.
Name of facility: Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown: April 11.1997 3.
Scheduled date for restart following refueling: May 11.1997 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendinent? 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)?
Yes. increase fuel enrichment limit from 4.1 weiaht percent to 5.0 weinht percent. relocate reactor coolant system (RCS) flow limit to Core Operatina Limits Report and reference additional NRC approved methodolonies. and revise RCS volume in the design features section.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
August 1996 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) 117 b)721 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 988 increase size by 0 I
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
DATE:
1997 (Lost of full core off-load capability)
'