2CAN089402, Monthly Operating Rept for Jul 1994 for ANO Unit 2
| ML20072E791 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/31/1994 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN089402, 2CAN89402, NUDOCS 9408230089 | |
| Download: ML20072E791 (7) | |
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! M 30141-3 K)O August 15,1994 2CAN089402 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Monthly Operating Report Gentlemen:
The Arkansas Nuclear One - Unit 2 Monthly Operating Report (MOR) for July 1994 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.
Very truly yours, hmf#C.W Dwight C. Mims Director, Licensing
- DCM/jrh Attachment b). 3_
9408230089 940731 PDR.- ADOCK 05000369 1I R
U. S. NRC August 15,1994 2CAN089402 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 - ANO-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. George Kalman NRR Project Manager, Region IV/ANO-l & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852
OPERATING DATA REPORT DOCKET NO:
50 368 DATE:
August 9,1994 COh1PLETED BY: hl. S. Whitt TELEPHONE:
(501) 964-5560 QPEMTING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 2 2.
Reporting Period:
July 1-31,1994 3.
Licensed Thermal Power (h1Wt): 2,815 4.
Nameplate Rating (Gross h1We): 942.57 5.
Design Electrical Rating (Net htWe): 912 6.
hiaximum Dependable Capacity (Gross hiWe): 897 7.
hiaximum Dependable Capacity (Net htWe): 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 htWe): None 10.
Reasons For Restrictions. If Any:
None MONTH YR-TO-DATE CUMULATIVE I 1.
Ilours in Reporting Period.
744.0 5,087.0 125,783.0 12.
Number ofilours Reactor was Critical.
744.0 4,066.6 96,888.3 13.
Reactor Reserve Shutdown Hours.
0.0 0.0 0.0 14.
Ilours Generator On-Line.
744.0 4,034.1 94,960.1 15.
Unit Reserve Shutdown llours.
0.0 0.0 0.0 16.
Gross Thermal Energy Generated (hiWH).
2,093,732 11,040,135 252,020,118 17.
Gross Electrical Energy Generated (MWII).
686,555 3,628,675 82,951,012 18 Net Electrical Energy Generated (MWH).
655,764 3,456,446 78,929,355 19.
Unit Service Factor.
100.0 79.3 75.5 j
20.
Unit Availability Factor.
100.0 79.3 75.5 21.
Unit Capacity Factor
- (Using MDC Net).
102.7 79.2 73.1 22.
Unit Capacity Factor (Using DEC Net).
96.6 74.5 68.8 23.
Unit Forced Outage Rate.
0.0 0.0 10.8 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
A midecle steam generator inspection is scheduled for two weeks in mid January 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 12/05n8 INITIAL ELECTRICITY 12/26n8 COMMERCIAL OPERATION 03/26/80
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-368 UNIT:
Two DATE:
August 9,1994 COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 964 5560 MONTH July 1994 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 879 2
881 3
877 4
878 5
878 6
878 7
879 8
880 9
884 10.
884 11.
883 12.
882 13.
883 14.
883 15.
880 16.
881 17.
881 18.
883 19.
879 20.
878 21.
880 22.
881 23.
878 24.
879 25.
882 26.
883 27.
887 28.
887 29.
886 30.
885 31.
884 AVGS: 881 INSTRUCTION On this fornut, list the average daily unit power level in MWe-Net for each day in reporting month. Complete to the nearest whole megawatt.
NRC MONTIILY OPERATING REPORT l
OPERATING
SUMMARY
JULY 1994 UNIT TWO 1
The unit operated the month of July at 100% power.
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UNIT SIIUTDOWNS AND POWER REDUCrlONS REPORT FOR JULY 1994 1
DOCKET NO.
50-368 g
UNIT NAME ANO Unit 2 DATE August 9,1994 i
COMPLETED BY M. S. Whitt TELEPliONE 501-964-5560 i
METilOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO fjO.
DATE TYPE' OIOURS)
REASON 2 REACTOR 2 REPORT #
CODE' CODES PREVENT RECURRENCE none 8
4
'i i
k 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 Ucensee C - Refueling 3 - Automatic Scram.
Event Report (LER) File (NUREG4161) l D-Regulatory Restriction 4 - Continuation I
E - Operator Training & Ucense Examination 5 -Ioad Reduction i
F - Administration 9 - Other 5
C - Operational Error Exhibit I-Same Source H - Other (Explain)
+
7 m
DATE: July 1994 l
REFUELING INFORMATION 1.
Name of facility: Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown. Sspigmber 22.1995 3.
Scheduled date for restart following refueling. November 6.1995 i
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.10 CFR Section 50.59)?
Delete requirement for verification of oosition stoos for the hiah oressure safety iniection
~
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throttle valves. Revise Technical Specifications to account for the replacement of part-length control element assemblies with full-length control element assemblist 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
March 1995.
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) 177 b) 6_32 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 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 full core off-load capability)
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