1CAN129402, Monthly Operating Rept for Nov 1994 for ANO Unit 1
| ML20080C960 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/30/1994 |
| From: | Hayes K, Mims D ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1CAN129402, NUDOCS 9412220109 | |
| Download: ML20080C960 (7) | |
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Ent:rgy Operction:,In3.
7 f&ve 3. Box 137G OperatlOl1S
- ^s 7280 i Td 501964 3100 December 15,1994 1CAN129402 U. S. Nuclear Regulatory Commission Document Control Desk l
Mail Station PI-137 l
Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Monthly Operating Report Gentlemen:
l The Arkansas Nuclear One - Unit 1 Monthly Operating Report (MOR) for November 1994 is attached. This report is submitted in accordance with ANO-1 Technical Specification 6.12.2.3.
Very truly yours, dyCWM j
Dwight C. Mims Director, Licensing I
DChVjrh Attachment I
f 9412220109 941130 PDR ADOCK 05000313 f
MWWfV
U.S.NRC December 15,1994 1CAN129402 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 l
Arkansas Nuclear One 1448 S. R. 333 Russellville, AR 72801 l
Mr. George Kalman i
NRR Project Manager, Region IV/ANO-1 & 2 U. S. Nuclear Regulatory Commission l
NRR Mail Stop 13-H-3 l
One White Flint North l
11555 Rockville Pike l
Rockville, Maryland 20852 l
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OPERATING DATA REPORT 4
DOCKET NO:
50-313 DATE:
December 1,1994 COMPLETED BY: K. R. Hayes TELEPHONE:
(501) 858-5535 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 1 2.
Reporting Period:
November 1-30.1994 3.
Licensed Thermal Power (MWt): 2,568 4.
Nameplate Rating (Gross MWe): 902.74 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, Giw Reasons:
9.
Power Level To Which Restricted. If Any (Net MWe): None 10.
Reasons For Restrictions. If Any:
None 1
1 i
MOEm YR-TO-DATE CUMULATIVE 11.
Hours in Reporting Period....
720.0 8,016.0 174,883.0 12.
Number of Hours Reactor was Critical.,.
720.0 7,913.8 128,512.2 13.
Reactor Reserve Shutdown l
Hours..
0.0 0.0 5,044.0 l
14.
Hours Generator On-Line.
720.0 7,900.4 126,244.0 i
15.
Unit Reserve Shutdown Hours.
0.0 0.0 817.5 16.
Gross Thermal Energy Generated (MWH).
1,847,776.0 20,212,118.6 292,262,680.7 17.
Gross Electrical Energy Generated (MWH).
631,735.0 6,872,105.0 97,665,140.0 l
18.
Net Electrical Energy Generated (MWH).
605,683.0 6,578,445.0 92,905,581.0 19.
Unit Senice Factor.
100.0 98.6 72.2 20.
Unit Availability Factor...
100.0 98.6 72.7 21.
Unit Capacity Factor (Using MDC Net).
100.6 98.2 63.5 22.
Unit Capacity Factor I
(Using DEC Net)..
99.C 96.5 62.5 i
23.
Unit Forced Outage Rate..
0.0 1.4 10.7
(
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
l Refueling outage 1R12 is scheduled to begin February 14,1995.
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 08/06n4 INITIAL ELECTRICITY 08/17n4 COMMERCIAL OPERATION 12/19n4
~.
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-313 UNIT:
One DATE:
December 1,1994 COMPLETED BY: K. R. Hayes TELEPHONE:
(501) 858-5535 t
MONTH November 1994 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 844 2
843 3
843 4
843 5.
843 6
844 7
838 8
843 9..
833 10......
841 11............
839 12...
841 13....
841 14..
841 15...
841 16.
841 17..
841 18.
841 19.
8J:
l 20.
s; 21.
84 22...
84; 23....
841 24-842 25.
842 26.
841 27...
841 28..
841 29.
841 30..
840
- 31....
- N/A AVGS: 841 JNSTRUCTION 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.
NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
NOVEMBER 1994 UNIT ONE The unit operated the month of November at 100% power.
UNIT SHUTDOWNS AN'3 POWER REDUCflONS REPORT FOR Nevesaber 1994 DOCKET NO.
50313 UNIT NAME ANO Unit 1 DATE December 1,1994 COMPLETED BY K. R. llaves TELEPHONE 501-858-5535 METHOD OF LICENSEE i
DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO MQ DATE TYPE' (HOURS)
REASON' REACTOR' REPORT #
CODE' CODES PREVENT RECURRENCE None 4
l 1
2 3
4 F: Forced Reason:
Method.
Exhibit G -Instructices S: Scheduled A-Equipment Failure (Explais) 1 - Manual for Preparation of Data B - Malatemance of Test 2 - Manual Screma.
Entry Sheets for IJcensee C-Refueling 3 - Automastic Screet Event Report (LER) File (NUREG-4161)
D - Regulatory Restriction 4 - Continuation E - Operator Training & License Exammination 5 -Imad Reduction F-A:Intimistration 9 - Other 5
G - Operational Error Exhibit I-Samme Source H - Other(Explain) l
l DATE: November 1994 j
REFUELING INFORMATION l
1.
Name of facility: Arkansas Nuclear One - Unit 1 2.
Scheduled date for next refueling shutdown. February 14.1995 t
3.
Scheduled date for restait following refueling. April 7.1995 i
4.
Will refueling or resumption of operation thereafter require a technical specification change l
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.10 CFR Section 50.59)?
Technical Specifica...,a change to relocate alditional cycle specific narameters to the Core l
Operating Limits Reoort (COLR1 Technical Soecification channe to allow modification of I
the vital instrument electrical o. ower system.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
These changes were submitted August 30.1994.
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.
i a)177 b) (M I
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 %8 increase size by Q l-9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
l DATE: 19 %
(Loss of full core off-load capability) l l
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