1CAN109401, Monthly Operating Rept for Sept 1994 for ANO Unit 1
| ML20149G294 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/30/1994 |
| From: | Hayes K, Mims D ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1CAN109401, NUDOCS 9410200183 | |
| Download: ML20149G294 (7) | |
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1 October 14,1994 1CAN109401 2
U. S. Nuclear Regulatory Commission Document Control Desk Mail Station Pl-137 t
Washington, DC 20555 l
t
Subject:
Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Monthly Operating Report l
Gentlemen:
j The Arkansas Nuclear One - Unit 1 Monthly Operating Report (MOR) for September 1994 is attached. This report is submitted in accordance with ANO-1 Technical Specification -
~
6.12.2.3.
Very tmly yours, wight C. Mims Director, Licensing DCM/jrh Attachment t
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9410200183 940930
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DR ADOCK 05000313 PDR
1 U.S.NRC October 14,1994 1CAN109401 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
1 f
OPERATING DATA REPORT DOCKET NO:
50-313 DATE:
October 6,1994 COMPLLTED BY; K. R. Hayes TELEPHONE:
(501) 858-5535 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 1 2.
Reporting Period:
September 1-30, 1994 3.
Licensed Thermal Power (Mw1):
2568 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, Give Reasons:
9.
Power Level To Which Restricted. If Any (Net Mwe): Nonc 10.
Reasons For Restrictions. If Any: None MONTil YR-TO-DATE CUMUIEDVE 11.
Hours in Reporting Period.
720.0 6,551.0 173,418.0 12.
Number ofIIours Reactor was Critical.
720.0 6448.8 127,047.2 13.
Reactor Reserve Shutdown Hours..
0.0 0.0 5044.0 14.
Ilours Generator On-Line.
720.0 6,435.4 124,779.0 15.
Unit Reserve Shutdown llours.
0.0 0.0 817.5 16.
Gross Thermal Energy Generated (MWH).
1,822,550.6 16,452,243.4 288,502,805.6 17.
Gross Electrical Energy Generated (MWH)..
615,160.0 5,587,285.0 96,380,320.0 18.
Net Electrical Energy Generated (MWH).
5R8,384.0 5,347,244.0 91,674,380.0 19.
Unit Service Factor.
100.0 98.2 72.0 20.
Unit Availability Factor.
100.0 98.2 72.4 21.
Unit Capacity Factor (Using MDC Net)..
97.8 97.6 63.2 22.
Unit Capacity Factor (Using DEC Net).
96.1 96.0 62.2 23.
Unit Forced Outage Rate.
00 1.8 10.8 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling outage IR12 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:
Octoter 6,1994 COMPLETED BY: K. R. Hayes TELEPilONE:
(501)S58-5535 MONTH S.otember 1994 c
DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 825 2
827 3
826 4
828 5
828 6
828 7
827 8
788 9
636 10.
671 11.
806 12.
827 13.
828 14.
828 15.
828 16.
829 17 829 18.
831 19.
832 20.
832 21.
832 22.
832 23.
836 24.
838 25.
838 26.
839 27.
838 28.
838 29.
836 30.
836 3I.
- N/A AVGS:
817 INSTRUCTION On this fonnat, list the average daily unit power level in MWe-Net for each day in reporting month. Complete to the nearest whole megawatt.
1 NRC MONTIILY OPERATING REPORT OPERATING
SUMMARY
SEPTEMBER 1994 UNIT ONE Arkansas Nuclear One, Unit One, began the month operating at 100% power.
On the eighth at 20:01 hours, the unit load was decreased to 70% to isolate a condenser waterbox so tube leaks could be found and repaired. Power was returned to 80-85%
during the repair work. On the eleventh at 03:00 hours, the condenser work was completed and power was increased to 90% to perform planned testing of the turbine throttle / governor valves. The testing was completed and the unit returned to full power at 04:53 hours on the eleventh. Unit 1 operated at full power for the remainder of the month.
9 L
o UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT FOR September 1994 DOCKET NO.
50-313 UNIT NAME ANO Unit 1 DATE October 6,1994 COMPLETED BY K. R. Ilayes TELEPHONE 501-858-5535 METIIOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPONENT CAUSE A CORRECTIVE ACTION TO l
M DATE TYPE 8 (IIOURS)
REASON 2 REACTOR 8 REPORTS CODE' CODES PREVENT RECURRENCE l
None l
I l
l l
l
[
1 2
3 4
F: Forced Reason:
Method:
Exhibit G - Instructions l
S: Scheduled A - Equipment Failure (Explain) 1 - Manual for Preparation of Data B - Maintenance of Test 2 - Manual Scrum.
Entry Sheets for IJcensee C - Refueling 3 - Automatic Scrum.
Event Reprt (LER) File (NUREG-0161)
D - Regulatory Restriction 4 - Continuation E - Operator Training & License Examination 5 -load Reduction F-Administration 9 - Other 5
G - Operational Error Exhibit I-Same Source H - Othe r (Explain)
i 1
DATE: September 1994 REFUELING INFORMATION 1.
Name of facility: Arkansas Nuclear One - Unit 1 2.
Scheduled date for next refueling shutdown. Februs.rv 14.1995 3.
Scheduled date for restart following refueling. April 7.1995 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 c
with the core reload (Ref.10 CFR Section 50.59)?
Technical Spf.c_ification change to relocate additional cycle specific carameters to the Core i
Operating Limits Report (COLR). Technical Specification change to allow modification of Ibe vital instrum_gnt electrical power 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 planne.dm 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
a) 177 b)685 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed i
storage capacity that has been requested or is planned, in number of fuel assemblies.
present 968 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: 1996 (Loss of full core off-load capability)
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