2CAN019301, Monthly Operating Rept for Dec 1992 for Ano,Unit 2
| ML20127E617 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/31/1992 |
| From: | James Fisicaro, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN019301, 2CAN19301, NUDOCS 9301190412 | |
| Download: ML20127E617 (7) | |
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Operations USOfEm tu totsta go 1anuary 15, 1993-2CAN019301 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station P1-137 Washington, DC-20555
Subject:
Arkansas Nuclear _One - Unit 2 Docket No. 50-368 License No. NPF-6 Monthly Operating Report Gentlemen:
Monthly Operating Report statistics ' for Arkansas Nuclear One, Unit-2, for December, 1992 is attached. This report is submitted in accordance-with ANO-2 Technical Specification 6.9.1.6.
Very truly yours, M
James-Fisicato Direct r, Licensing JJF/JRH/jt Attachmente i
93r)1190412L921231'
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9 U. S. NRC January 15, 1993 2CAN019301 Page 2 cc:
Mr. James I.. Milhoan Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 a
NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. Roby Bevan NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Thomas W. Alexion NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852
4 OPERATING DATA REPORT-DOCKET NO:
50 368 DATE:
Januarv 5,1992 l
COMPLETED BY: M. S. Whitt j
TELEPHONE:
(501) 964 5560 i
OPERATING STATUS i
1.
Unit Name: Arkansas Nuclear One Unit 2 i
2.
Reporting Period:
December 131 l
3.
Licensed Thermal Power (MWt): 2.815 4
4 Nameplate Rating (Gross MWe): 942.57 i
5.
Design Electrical Rating (Net MWe): 912 6.
Maximum Dependable Capacity (Gross MWe): 897 7.
Maximum Dependable Capacity (Net MWe): 858 l
8.
If Changes Occur in Capacity Ratings (ltems Number 3 Through 7) Since
]
Last Report, Give Reasons:
9.
Power Level To Which Restricted. If Any (Net MWe): None 10.
Reasons For Restrictions. If Any:
Nonc 3
J htQEIli YR TO-DATE CUMULATIVE i 1.
Ilours in Reporting Period.
-744.0 8,784.0 111,936.0 j
12.
Number of Hours Reactor was i
Critical..
744,0 6,433.9 84,431.3 13.
Reactor Reserve Shutdown l
Hours.
0.0 0.0 0.0 l
14.
Hours Generator On-Line.
744.0 6,392.2 82,579.4 j
15.
Unit Reserve Shutdown Hours..
0.0 0.0 0.0 16.
Gross Thermal Energy Generated (MWH).
2,091,329 17,507,696 217,766,804 2
17.
Gross Electrical Energy l
Generated (MWH).
695,565 5,777,360 71,630,191 18.
Net Electrical Energy i
Generated (MWH).,
665,227 5,500,306 68,128,119 l
19.
Unit Service Factor...
100.0 72.8 73.8 20 Unit Availability Factor.
100.0 72.8 73.8 21.
Unit Capacity Factor -
4 (Using MDC Net)..
104.2 73.0-70.9 22.
Unit Capacity Factor (Using DEC Ne').
98.0 68 7 66.7 23.
Unit Forced Outage Rate.
0.0 17.0 12.2 l
24.
Shutdowns Scheduled Over Next 6 Months (Typc, Date, and D tration of Each):
4 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 f
INITIAL ELECTRICITY 12/26/78 COMMERCIAL OPERATION 03/26/80 i
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.. _. _ _ _ _.. _. _ _ _ _.. ~
t AVERAGE DAILY UNIT POWER I EVEL DOCKET NO:
50 368 l
UNIT:
Two j.
DATE:
. January 5.1992 COhiPLETED BY: hi. S. Whitt TELEPilONE:
(501) % 4 5560 l
MONTH December.1992 i
DAY AVERAGE DAILY POWER LEVEL (MWe-Net) t 1
895 l
2 895 3
896 i
4 896 i
5..
897 j
6 896 7
895 8
S94 I
9 894 10 891 11.
889 12.
895 3
l 13.
894 14.
893 i
15.
893 i
16.
894 l
17.
894 18..
893 i
19.
893
}
20..
894 i-21.
894 l
22.
895 23.
893 24..
896 25..
8%
26.
896 l
27.
896 i
28.
895 5
29.
891 30.
890 31.
895 AVGS: 894 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.
m-
-,4
- +
NRC h10NTilLY OPERATING REPORT OPERATING SUhth1ARY i
l DECEh1BER 1992 l
UNIT TWO The unit operated the entire month of December at 1007c power.
1 i
UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT FOR DECEMBER,1992 1
DOCKET NO.
50-368 UNIT NAME ANO Unit 2 DATE Januarv 5,1993 COMPLETED BY M. S Wlutt TELEPIIONE 50lN4 5560 METIIOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPENENT CAUSE & CORRECTIVE ACTION TO M
DATE TYPE' OIOURS)
REASON 2 REACTOR 8 REPORT #
CODE' CODE' PEEVENT RECURRENCE I
none t
I i
1 2
3 4
F: Forced
. Reason:
Method:
Exhibit G -Instructi<ms S: Scheduled A - Equipment Failure (Explain)
I - Manual for Preparation of Data B - Maintenance of Test 2 - Manual Scram.
Entry Sheets for Ucensee C-Refueling 3-Automatic Scram.
Esent Report (LER) File (NUREG-4161)
. D-Regulatory Restriction 4 - Continuation E-OperatorTraining & Ucense Examination 5 -Imad Reduction F-Administration 9 - Other 5
G - Operational Error Exhibit I-Same Source II-Other (Explain)
DATE:
December, 1992 i.
REFUELING INFORMATION 1
1.
Name of facility:
Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown. March 4, 1994 3.
Scheduled date for restart following refueling. April 25. 1994 2
4.
Will refueling or resumption of operation thereaf ter 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 j
Safety Review Comrittee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?
No Technical Specification changes or license amendments are known to be required at this time.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information. None Required 6.
Important licensing considerations associated with refueling, e.g.,
new or dif ferent fuel design or supplier, unroviewed design or performance analysis methods, significant changes in fuel desiga, new operating procedures.
None i
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, r.)
177 b) 565 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 Q_
l 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 fu11 core offload-capability) 4 4
V