1CAN089603, Monthly Operating Rept for July 1996 for ANO-1
| ML20116M664 | |
| 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 | |
| 1CAN089603, 1CAN89603, NUDOCS 9608200257 | |
| Download: ML20116M664 (7) | |
Text
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. = ENTERGY fE2! !'"" "'"
H.w:hi!c. AR 72301 ici501858 5000 i
l August 15,1996 ICAN089603 i
U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Monthly Operating Report Gentlemen:
The Arkansas Nuclear One - Unit 1 Monthly Operating Report for July 1996 is attached. This report is submitted in accordance with ANO-1 Technical Specification 6.12.2.3.
Very tmly yours, 8&C %
Dwight C. Mims Director, Nuclear Safety DCM/eas attachment 9608200257 960731 PDR ADOCK 05000313 J
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U. S. NRC
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August 15,1996 ICAN089603 Page 2 1
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cc:
Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission Region IV j
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 3
U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 1
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OPERATING DATA REPORT DOCKET NO:
50-313 DATE:
August 15,1996 COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858-5560 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 1 2.
Reporting Period:
July 1-31 3.
Licensed ThermalPower (MWt): 2,568 4.
Nameplate Rating (Gross MWe): 903 5.
Design Electrical Rating (Net MWe): 850 6.
Maximum Dependable Capacity (Gross MWe): 883 7.
Maximum Dependable Capacity (Net MWe): 836 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: N/A 9.
Power Level To Which Restricted. If Any (Net MWe): None 10.
Reasons For Restrictions. If Any:
N/A MONTH YR-TO-DATE CUMULATIVE I 1.
Hours in Reportmg Period..
744.0 5,111.0 189,498.0 12.
Number of Hours Reactor was Critical.
744.0 4,989.5 141,821.6 13.
Reactor Reserve Shutdown Hours.
0.0 0.0 5,044,0 14.
Hours Generator On-Line.
744.0 4,969.1 139,451.0 15.
Unit Reserve Shutdown Hours.
0.0 0.0 817.5 16.
Gross Thermal Energy Generated (MWH).
1,906,874 12,349,724 324,823,639 17, Gross Electrical Energy Generated (MWH).
650,536 4,264,565 108,834,610 18.
Net Electrical Energy Generated (MWH).
622,880 4,078,007 103,576,220 19.
Unit Senice Factor.
100.0 97.2 73.6 20.
Unit Availability Factor.
100.0 97.2 74.0 21.
Unit Capacity Factor (Using MDC Net).
100.1 95.4 65.4 22.
Unit Capacity Factor (Using DER Net).
98.5 93.9 64.3 23.
Unit Forced Outage Rate.
0.0 2.8 9.9 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling outage IR13 scheduled to commence September 17,1996 with an approximate duration of 30 days.
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 INITIAL CRITICALITY 08/06/74 INITIAL ELECTRICITY 08/17/74 COMMERCIAL OPERATION 12/19/74
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-313 UNIT:
One DATE:
August 15,1996 COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858-5560 MONTH luly 1996 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 833 2...
832 3..................
830 4........
832 5.
835 6
837 7.
837 8....
836 9...
835 10.
837 11...
841
- 12...
846 13......
845 14.
843 15..
844 16..............
843 17..
842 18...
840 19..
839 20......
837 21...
837 22..
836 23..............
837 24...
835 25....................
836 26.....
835 27.
834
- 28..
833 29.
834
- 30.....
837 31....
836 AVGS: 837 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 l'EPORT FOR JULY 1996 DOCKET NO.
50-313 UNIT NAME ANO Unit 1 DATE August 15,1996 COMPLETED BY M. S Whitt TFLEPHONE 501-858-5560 METHOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE A CORRECTIVE ACTION TO E
DATE TYPE 8 (HOURS)
REASON 2 REACTOR 8 REPORT #
CODE' CODES PREVENT RECURRENCE none i
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2 3
4 F: Forced Reason:
Method:
Exhibit G -Instructions 5: Scheduled A - Equipment Failure (Explain) 1 - Manuel for Preparation of Data B - Maintenance of Test 2 - Manual Scras:.
Entry Sheets for Licensee C-Refueling 3 - Automatic Scrant.
Event Report (LER) File (NUREG-0161)
D-Regulatory Restriction 4 - Continuation E - Operator Training & Ucense Examination 5 - Imad Reduction F-Administration 9 - Other 5
G - Operational Error Exhibit I-Same Source
NRC MONTilLY OPERATING REPORT OPERATING
SUMMARY
JULY 1996 UNIT ONE The unit operated the entire month ofJuly at 100% power.
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Reporting Period: July 1996 REFUELING INFORMATION i
1.
Name of facility: Arkansas Nuclear One - Unit I 2.
Scheduled date for next refueling shutdown: September 17.1996 3.
Scheduled date for restart following refueling: October 17.1996 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 i
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. relocate the reactor coolant system (RCS) pressure-temocrature protective limits and the variable low RCS pressure trip to the Core Operatina Limits Report.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
Submitted in April 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)J12 b)2.5 4
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 968 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:
1995 (Loss of full core off-load capability) i
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