2CAN099403, Monthly Operating Rept for Aug 1994 for ANO Unit 2
| ML20073B595 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/31/1994 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN099403, 2CAN99403, NUDOCS 9409220132 | |
| Download: ML20073B595 (7) | |
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September 15,1994 2CAN099403 U. S. Nuclear Regulatory Commission Document Control Desk hiail Station PI-137 Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 hionthly Operating Report Gentlemen:
The Arkansas Nuclear One - Unit 2 hionthly Operating Report (hf0R) for August 1994 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.
Very truly yo rs, j'W wight. hiims 7[
Direct r, Licensing DChi/jrh Attachment O n It ".1
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U. S. NRC September 15,1994 2CAN099403 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 1448 S. R. 333 Russellville, AR 72801 Mr. George Kalman NRR Project Manager, Region IV/ANO-1 & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852
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OPERATING DATA REPORT DOCKET NO:
50-368 DATE:
September 2,1994 COMPLETED BY: M. S. Whitt TELEPIiONE:
(501) 858-5560 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 2 2.
Reporting Period:
August 1-31, 1994 3.
Licensed Thermal Power (MWI): 2,815 4.
Nameplate Rating (Gross MWe): 942.57 5.
Design Electrical Rating (Net MWe): 912 6.
Maximum Dependable Capacity (Gross MWe): 897 7.
Maximum Dependable Capacity (Net MWe): 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 MWe): None 10.
Reasons For Restrictions. If Any:
None MONTH YR-TO-DATE CUMULATIVE I 1.
Hours in Reporting Period.
744.0 5,831.0 126,527.0 12.
Number of Hours Reactor was Critical.
744.0 4,810.6 97,632.3 13.
Reactor Reserve Shutdown Hours.
0.0 0.0 0.0 14.
Hours Generator On-Line.
744.0 4,778.1 95,704.1 l
15.
Unit Reserve Shutdown Hours.
0.0 0.0 0.0 16.
Gross Thermal Energy Generated (MWH).
2,093,995 13,134,130 154,114,113 17.
Gross Electrical Energy Generated (MWH)..
685,585 4,314,260 83,636,597
-l 18.
Net Electrical Energy Generated (MWH).
654,989 4,111,435 79,584,344 19.
Unit Senice Factor.
100.0 81.9 75.6 20.
Unit Availability Factor.
100.0 81.9 75.6 21.
Unit Capacity Factor (Using MDC Net).
102.6 82.2 73.3 22.
Unit Capacity Factor (Using DEC Net).
96.5 77.3 69.0 23.
Unit Forced Outage Rate.
0.0 0.0 10.7 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
A mid-cycle steam generator inspection is scheduled for two weeks in mid January 1995.
25.
If Shut Down At End of Report Period. Estimated Date of I
1 Stanup:
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:
September 2,1994 COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858-5560 MONTil Aprust 1994 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 883 2
882 3
882 4
880 5
884 6
884 7
883 8
881 9
880 10.
880 11.
878 12.
874 13.
877 14.
878 15.
886 16.
885 17.
885 18.
882 19.
883 20.
882 21.
883 22.
882 23.
881 24.
879 25...
878 26.
878 27.
876 28.
876 2 9..
875 30.
876 31.
878 AVGS: 880 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.
l
NRC MONTIILY OPERATING REPORT OPERATING
SUMMARY
AUGUST 1994 UNIT TWO The. unit operated the month of August at 100% power.
i
a UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT FOR AUGUST 1994 DOCKETNO.
50-368 UNIT NAME ANO Unit 2 DATE September 2,1994 COMPLETED BY M. S. Whitt TELEPIIONE 501-858-55(4 METIIOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACrlON TO E
DATE TYPE' OfOURS)
REASON 8 REACTORS REPORT #
CODE' CODES PREVENT RECURRENCE None 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 Scrum.
Entry Sheets for Licensee C-Refueling 3 - Automatic Scram.
Event Report (LER) File (NUREG-0161)
D-Regulatory Restriction 4 - Continuation
- E - Operator Training & License Examination 5 -Imad Reduction
- F-Administration 9 - Other.
5.
~ G - Operational Error Exhibit I-Same Source H - Other (Explain)
DATE: August 1994 REFUELING INFORMATION 1.
Name of facility: Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown. Seotember 22.1995 3.
Scheduled date for restart following refueling. November 6.1995 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)?
Dslete requirement for verification of oosition stops for the high pressure safety injection throttle valves. Revise Technical Specifi_qations to account for the replacement of eart-kngth control element assemblies with full-length control element assemblies.
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 olanned.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
a) 177 b) 637 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)
J