2CAN129406, Monthly Operating Rept for Nov 1994 for ANO Unit 2
| ML20080C965 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/30/1994 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN129406, NUDOCS 9412220112 | |
| Download: ML20080C965 (7) | |
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ic' 501964 3100 December 15,1994 2CAN129406 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555 S >bject:
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 November 1994 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.
Very truly yours, L/c sta Dwight C. Mims Director, Licensing j
4 DCM/jrh Attachment
[p 9412220112 941130 PDR ADOCK 0500 0
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U. S. NRC December 15,1994 2CAN129406 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 r
OPERATING DATA REPORT l
DOCKET NO:
50-368 l
DATE:
December 6,1994 COMPLETED BY: M. S. Whitt TELEPHONE:
(50l) 858-5560 QPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 2 2.
Reporting Period:
November 130,1994 3.
Licensed Thermal Power (MWt): 2,815 4.
Nameplate Rating (Gross MWe): 942.57 5.
Design Electrical Rating (Net MWe): 912 i
6.
Maximon Dependable Capacity (Gross MWe): 897 i
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 l
l MONTH YR-TO-DATE CUMULATIVE I1.
Hours in Reporting Period..
720.0 8,016.0 128,712.0 12.
Number of Hours Reactor was Critical.
720.0 6,995.6 99,817.3 13.
Reactor Resene Shutdown Hours.....
0.0 0.0 0.0 14.
Hours Generator On-Line..
720.0 6,%3. I 97,889.1 15.
Unit Reserve Shutdown Hours.
0.0 0.0 0.0 16.
Gross Thermal Energy Generated (MWH) -
2,026,381 19,283,520 260,263,503 17.
Gross Electrical Energy j
Generated (MWH).
672,031 6,347,702 85,670,039 18.
Net Electrical Energy Generated (MWH)...
642,595 6,055,530 81,528,438 19.
Unit Service Factor..
100.0 86.9 76.1 20.
Unit Availability Factor.
100.0 86.9 76.1 21.
Unit Capacity Factor (Using MDC Net) =
104.0 88.0 73.8 22.
Unit Capacity Factor (Using DEC Net)...........
97.9 82.8 69.5 23.
Unit Forced Outage Rate......
0.0 0.0 10.5 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
A mid-cycle steam sencrator inspection is scheduled to begin January 6,1994 and last -12 days.
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 12/0$n8 INITIAL ELECTRICITY 12n6n8 COMMERCIAL OPERATION 03n6/80 t
' AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-368 UNIT:
Two DATE:
December 6,1994 l
COMPLETED BY: M. S. Whitt TELEPHONE:
(50l) 858-5560 l
MONTH November 1994 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 895 2..........
892 3..........
888 4
889
=..
5..
892 6.
889 i
7 892 8
890 9.
890 10 894 11.
893 12.
892 13....
890 14 890 15 892 16.
893 l
17.
893 18.
891 19.
893 20.
892 i
21.
893 22.
895 23..
8%
24.......
893 25..
892 26....
895 27..
892 28....
896 29.
895 30.
897 l
- 31..
- N/A AVGS: 892 INSTRUCTION l
l On this format, list the average daily unit power level in MWe-Net for cach day in reporting month. Complete to the nearest whole megawatt.
NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
NOVEMBER 1994 UNIT TWO The unit operated the month of November at 100% power.
1 l
1 1
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR NOVEMBER 1994 DOCKET NO.
50-368 UNITNAME ANO Unit 2 DATE December 6,1994 COMPLETED BY M. S. Whitt
- TELEPHONE (50I) 858-5560 ME1110D OF LICENSEE CL~dATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO 8
MO DATE IXP18 (HOURS)
REASON 8 REACTOR REPORT #
G}DE' CODE 8 PREVENT RECURRENCE a
Nome 1
2 3
4 F: Forced Ressen.
Method.
Exhibit G -Instructions S: Scheduled A - Equipaneet Failure (Explain) 1 - Manual for Preparation of Data B - Maintenance of Test 2 - Masent Screen.
Entry Sheets forIJcensee C-Refseling 3 - Antessatic Scrams.
Event Report (LER) File (NL' REG-4161)
D-Regulatory Restriction 4 - Continuaties E - Operator Training & IJcense Examalaatica 5 -Imad Reducties F-Adaministration 9 - Other 5
G - Operational Erre?
Exhibit I-Sense Source H - Other (Explain)
O DATE: November 1994 REFUELING INFORMATION 1.
Name offacility: Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown. September 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)?
Delete requirement for verification of oosition stops for the high pressure safety in_iection throttle valves. Revise Technical Soecifications to account for the replacement of oart-lenath settol element assemblies with full-lenath control element assemblies. Revise the reference in the Administrative Controls section to allow use of the Modified Statistical Combination of Uncertainties for determining core ooerating limits. Relocate the value used to decrease the core oower operating limit based on DNBR when neither CEAC is operable to the Core Operating Limits Report.
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) 612 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) i r