2CAN109403, Monthly Operating Rept for Sept 1994 for ANO Unit 2
| ML20149G282 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/30/1994 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN109403, NUDOCS 9410200134 | |
| Download: ML20149G282 (7) | |
Text
,
ob
. ' -- Entcrgy Rw 3 B'x 13;fa"
'"c-5"'~~*"
0Eerations
- =
p so n9amo October 14,1994 2CAN109403 U. S. Nuclear Regulatory Commission Document Control Desk Mail Ststion PI-137 Washington, DC 20555
Subject:
Arnansas Nuclear One - Unit 2 Doi:ket No. 50-368 License No. NPF-6 Monthly Operating Report Gentlemen:
The Arkansas Nuclear One - Unit 2 Monthly Operating Report (MOR) for September 1994 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.
Very truly yours, l
/7btb[b d
[ Dwight C. Mims 7L-i Director, Licensing DCM/jrh Attachment 10bCiU 9410200134 94o930
[DR ADOCK 05000369 l }
U.S.NRC October 14,1994 2CAN109403 Page 2 cc:
Mr. Leonard J. Callan Regional Administrator
]
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 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 i
\\
OPERATING DATA REPORT DOCKET NO:
50-368 DATE:
October 3,1994 COMPLETED BY: M. S. Whitt TELEPIIONE:
(501) 964-5560 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 2 2.
Reporting Period:
September 1-30. 1994 3.
Licensed Thermal Power (MWt): 2,815 4
Nameplate Rating (Gross MWe): 942.57 5.
Design Electrical Rating (Net MWe): 912 6.
Maximum Dependable Capacity (Gross MWc): 897 7.
Maximum Dependable Capacity (Nct 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:
Nonc MONTil YR-TO-DATE CUMULATIVE I 1.
Ilours in Reporting Period.
720.0 6,551.0 127,247.0 12.
Number ofIlours Reacto was Critical.
720.0 5,530.6 98,352.3 13.
Reactor Reserve Shutdown Ilours.
0.0 0.0 0.0 14.
Ilours Generator On-Line.
720.0 5,498.1 96,424.1 15.
Unit Reserve Shutdown llours.
0.0 0.0 0.0 16.
Gross Thermal Energy Generated (MWil).
2,026,300 15,160,430 256,140,413 17.
Gross Electrical Energy Generated (MWil).
667,127 4,981,387 84,303,724 18.
Net Electrical Energy Generated (MWII).
637,632 4,749,068 80,221,976 19.
Unit Service Factor.
100.0 83.9 75.8 20.
Unit Availability Factor.
100.0 83.9 75.3 21.
Unit Capacity Factor (Using MDC Net).
103.2 84.5 73.5
'22.
Unit Capacity Factor (Using DEC Net)..
97.1 79.5 69.1
~ 23.
Unit Forced Outage Rate.
0.0 0.0 10.6 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 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:
October 3,1994 COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 964-5560 MONTli Scotember 1994 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 882 2
884 3
883 4
881 5
878 6.
880 7
882 8
882 9
882 10.
884 11.
882 12.
880 13.
879 14.
874 15.
880 16.
885 17.
887 18.
890 19.,
889 20.
891 21.
888 22.
894 23.
893 24.
894 25.
893 26.
892 27.
893 28.
889 29.
888 30.
887 31..
- N/A AVGS: 886 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.
t F
NRC MONTIILY OPERATING REPORT OPERATING SUMMAR. Y SEPTEMBER 1994 UNIT TWO i
The unit operated the month of September at 100% power.
i e
r--
,,,,73,--7--*e-,
gi
UNIT SIlUTDOWNS AND POWER REDUCTIONS REPORT FOR SEPTEMBER 1994 DOCKET NO, 50-368 UNIT NAME ANO Unit 2 DATE October 3,1994 COMPLETED BY M. S. Whitt TELEPilONE 501-964-5560 METIIOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPONENT CAUSE A CORRECTIVE ACTIONTO M
DATE TYPE' OIOURS)
REASON 2 REACTOR 8 REPORT #
CODE' CODES PREVENT RECURRENCE I
None 1.
l l
l l
l l
l l
i l
i 1
2 3
4 F: Forced Reason:
Method:
Exhibit G -Instructions S: Scheduled A - Equipment Failure (Explain) 1 - Manual for Purparation of Data B - Maintenance of Test 2 - Manual Scram.
Entry Sheets for Ucensee C-Refueling 3 - Automatic Scrant.
Event Report (LER) File (NUREG-0161)
D-Regulatory Restriction 4 - Continuation E - Operator Training & Ucense Examination 5 - I. mad Reduction F-Administistion 9 - Other 5
l G - Operational Error Exhibit I-Same Source -
l H - Other (Explain)
{
i 1
DATE: September 1994 PEFUEL ING INFORMATION l
1.
Name of facility: Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown. September 22.1995 3.
Scheduled date for restan 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 r
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 50.50)7 Delete requirement for verification of position stoos for the high pressure safety iniection throttle valves. Revise Technical Specifications to account for the replacement of part-t length 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.
Hong_ planned.
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 s.nd 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 refuelint that can be discharged to the spent fuel pool assuming the present licensed capacity.
DATE: 1997
-(Loss of full core off-load capability)
..g"
,p-,
'