1CAN059604, Monthly Operating Rept for April 1996 for Ano,Unit 1
| ML20117F995 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/30/1996 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1CAN059604, 1CAN59604, NUDOCS 9605200336 | |
| Download: ML20117F995 (7) | |
Text
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Russcu, AR 72801 Tel 5018%5000 May 15,1996 1CAN059604 U. S. Nuclear Regulatory Commission Document Control Desk.
Mail Station Pl-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 April 1996 is attached.
This report is submitted in accordance with ANO-1 Technical Specification 6.12.2.3.
Very truly yours, l
IM.TE l
Dwight C. Mims Director, Nuclear Safety I
DCM/eas attachment I
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1 200132 i
9605200336 960430 p,
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1 U. S. NRC
' May 15,1996 1CAN059604 Page 2 cc:
Mr. Leonard J. Callan Regional Administrator l
U. S. Nuclear Regulatory Commission i
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 l
NRR Project Manager Region IV/ANO-1 & 2 l
U. S. Nuclear Regulatory Commission j
NRR Mail Stop 13-H-3 l
One White Flint North l
11555 Rockville Pike l
Rockville, MD 20852 l
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OPERATING DATA REPORT DOCKET NO:
50-313 DATE:
May 15,19%
COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858-5560 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 1 2.
Reporting Period:
April 1-30 3.
Licensed Thermal Power (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 i
MONTH YR-TO-DATE CUMULATIVE 11.
Hours in Reporting Period..
719.0 2,903.0 187,290.0 12.
Number of Hours Reactor was i
Critical.
719.0 2,903.0 139,735.0 13.
Reactor Reserve Shutdown l
Hours.
0.0 0.0 5,044.0 14.
Hours Generator on-Line...
719.0 2,903.0 137,384.9 1
15.
Unit Reserve Shutdown Hours.
0.0 0.0 817.5 16.
Gross Thermal Energy Generated l
(MWH)....
1,842,687 7,276,768 319,750,684 17.
Gross ElectricalEnergy Generated (MWH)..
642,427 2,532,808 107,102,854 l
18.
Net ElectricalEnergy Generated (MWH)..
616,212 2,427,741 101,925,954 l
19.
Unit Senice Factor..
100.0 100.0 73.4 20.
Unit AvailabilityFactor...
100.0 100.0 73.8 21.
Unit Capacity Factor (Using MDC Net).
102.5 100.0 65.1 22.
Unit Capacity Factor (Using DER Net).
100.8 98.4 64.0 l
23.
Unit Forced Outage Rate.
0.0 0.0 10.0 24.
Shutdowns Scheduled Over Next 6 Mc,nths (Type, Date, and Duration of Each):
Refueling outage IR13, scheduled to commence September 20,19% with an approximate duration of 39 days.
{
25.
If Shut Down At End of Report Period. Estimated Date of 1
Startup:
N/A 26.
Units in Test Status (Prior to Commercial Operation):
Now
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Forecast Achieved
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INITIAL CRITICALITY 08/06n4 INITIAL ELECTRICITY 08/17n4 l;
COMMERCIAL OPERATION 12/19n4 1
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-313 UNIT:
One DATE:
May 15,19%
COMPLETED BY: M. S. Whitt TEIFPHONE:
(501) 858-5560 MONTH April 19%
DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1..........
860 2..
860 3
859 4...
859 5
8@
6........
859 7
859 8
859 9
858 10.......
858 1 1............
859
- 12......
858 l
13.
857'
' 14..........-
855 l
l 15..
858 f
16.......
859 17.
857 18...
857 19; 856 20..
854 21.
854 22=
853 23........
854 24..
855 2 5.........
855 26..
857 2 7...........
856 28........
855 29.
856 30.
856 i
l AVGS: 857 INSTRUCTION 4
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.
4 e
..m UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR APRIL 1996 DOCKET NO.
50-313 UNIT NAME ANO Unit 1 DATE May 15,1996 COMPLETED BY M. S. Whitt TELEPHONE 501-858-5560 METHOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO M
DATE M8 (HOURS)
REASON 2 REACTOR 8 REPORT #
CODE' CODE' PREVENT RECURRENCE none i
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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 Scrant Entry Sheets for Ucensee l
C-Refueling 3 - Automatic Scram. -
Event Report (LER) File (NUREG-0161)
D-Regulatorv Restriction 4 - Continuation E - Operator Training & Ucense Examination 5 -I. mad Reduction F-Administration 9 - Other 5
G - Operational Error Exhibit I-Same Source H - Other (Explain)
L
NRC MONTHL'Y OPERATING REPORT l
OPERATING
SUMMARY
APRIL 1996 UNIT ONE t
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The unit operated the entire month of April at 100% power.
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t Reporting Period: April 1996 REFUELING INFORMATION 1.
Name of facility: Arkansas Nuclear One - Unit 1 2.
Scheduled date for next refueling shutdown: September 20.1996 3.
Scheduled date for restart following refueling: November 4.1996 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 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-temDerature Drotective limits and the variable low RCS oressure trio to the Core Operatina Limits Reoort.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
Aoril 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 olanned 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
a) jlZ b).7_45 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 261 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:
1996 (Loss of full core off-load capability) l