ML20149K251
| ML20149K251 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/31/1996 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN02605, 2CAN2605, NUDOCS 9602220085 | |
| Download: ML20149K251 (8) | |
Text
,
Entargy Operations, Inc.
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Tel 501858-5930 l
E February 15,1996 2CAN029605 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 205$5
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 for January 1996 is attached.
This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6. Also, in accordance with ANO-2 Technical Specification 6.9.1.5.c and NUREG-0737, Item II.K.3.3, attached is the 1995 Annual Report of Failures and Challenges to Pressurizer Safety Valves.
Very truly yours, 8s%W4 Dwight C. Mims Director, Nuclear Safety _
DCM/cas attachment h
220031 9602220085 960131 ADOCK0500g8 gg DR
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U. S. NRC Fe'bruary 15,1996 2CXN029605 Page 2 cc:
Mr. Leonard J. Callan i
Regional Administrator U. S. Nuclear Regulatory Commission Region IV i
611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 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, MD 20852 i
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OPERATING DATA REPORT 4
DOCKET NO:
50 368 DATE:
February 15,1996 COMPLETED BY: M. S. Whitt TELEPHONE:
(50l) 858 5560 QEERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 2 2.
Reporting Period:
January 131
[
l 3.
Licensed Thermal Power (MWt): 2,815 L
4.
Nameplate Rating (Gross MWe): 942.57 i
5.
Design Electrical Rating (Net MWe): 912 6.
Maximum Dependable Capacity (Gross MWe): 897 l
1 7.
Maximum Dependable Capacity (Net MWe): 858 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: N/A 9.
. Power Level To Which Restricted. If Any (Net MWe): 890 10.
Reasons For Restrictions. If Any:
Selfimposed power restriction to ~ 97.9% power based on T-hot limitations in combination with current steam generator plugging and fouling j
levels.
MONTH YR-TO-DATE CUMULATIVE 11.
Hours in Reporting Period....
744.0 744.0 138,960.0 l
12.
Number of Hours Reactor was Critical.
744,0 744.0 108,214.8 i
13.
Reactor Reserve Shutdown Hours.....
0.0 0.0 0.0 4
14.
Hours Generator On-Line......
744.0 744.0 106,022.1 15.
Unit Reserve Shutdown Hours...
0.0 0.0 0.0 16.
Gross Thermal Energy Generated (MWH).....
2,048,925 2,048,925 282,311,410 17.
Gross Electrical Energy i
Generated (MWH).....
690,418 690,418 93,040,021 18.
Net Electrical Energy j
Generated (MWH).......
660,042 660,042 88,540,'/08 19.
Unit Service Factor...
100.0 100.0 76.3 20.
Unit Availability Factor.........
100.0 100.0 76.3 21.
Unit Capacity Factor (Using MDC Net).............
103.4 103.4 74.3 22.
Unit Capacity Factor (Using DER Net).......
97.3 97.3 69.9 23.
Unit Forced Outage Rate.......
0.0 0.0 10.2 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
None 25.
If Shut Down At End of Report Period. Estimated Date of Startup:
N/A 26.
Units in Test Status (Prior to Commercial Operation):
None 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:
February 15,1996 COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858-5560 MCl4Til January 1996 DAY AVERAGE DAILY POWER LEVEL (MWe Net) 1.
888 2
887 3......
h88 4
888 5.........
889 6
888 7..
877 8
887 9......
887 10....
888 11.,
887 12.....
888 13.....
887 14..
887
- 15...
888 16..
884 17......
873 18..
887 19..
889 20..
889 21..
889 22....
889 23.....
888 2 4............
889 25...
889 26..
889 27.
889 28......
888 29............
888 30.........................
889 31......................
889 AVGS: 887 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.
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR JANUARY 1996 DOCKET NO.
50-368 UNIT NAME ANO Unit 2 DATE Fetxuary 15,1996 COMPLETED BY M. S. Wititt TELEPHONE 501-858-5560 METHOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO E
DATE TYPE' GIOURS)
REASON 2 REACTORS REPORT #
CODE' CODES PREVENT RECURRENCE None l
1 2
3 4
F: Forced Reason:
Method:
Exhibit G - Instructions S: Scheduled A - Equipment Failure (Explain)
I - 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 (NUREG-0161)
D-Regulatory Restriction 4 - Continuation E - Operator Training & Ucense Examination 5 - Load Reduction F-Administration 9 - Other 5
G - Operational Error Exhibit I-Same Source 11 - Other (Explain) 1 1
NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
JANUARY 1996 UNIT TWO l
l The month began w:ih the unit operating at 97.9% power.
Power was reduced to 90% on the seventh in order to secure circulating water pump 2P-3 A for repairs. The repairs were completed the same day and power was returned to 97.9%. A second power reduction to 90% was itstiated on the sixteenth to allow additional repairs to pump 2P-3 A.
Following completion of the repairs, power was returned to 97.9% on the seventeenth.
The unit operated the remainder of the month at 97.9% power.
Reporting Period: January 1996 REFUELING INFORMATION 1.
Name of facility: Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown: March 21.1997 3.
Scheduled date for restart following refueling: May 5.1997 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.10CFR Section 50.59)?
Yes. increase fuel enrichment limit from 4.1 weicht percent to 5.0 weicht percent.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
June 1996 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) 171 b) 221 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:
present9]L8 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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ATTACHMENT ANNUAL REPORT OF PRESSURIZER SAFETY VALVE FAILURES AND CHALLENGES This annual report is submitted in the January Monthly Operating Report in response to requirements implemented as a result of NUREG-0737, Item II.K.3.3 and to fulfill Technical Specification reporting requirements (TS 6.9.1.5.c).
For ANO-2, there were no failures or challenges to the primary system code safeties during 1995.
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