ML20077R350
| ML20077R350 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/31/1994 |
| From: | Hayes K, Mims D ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9501200161 | |
| Download: ML20077R350 (7) | |
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3 Entstgy operations, Inc.
?3 ENTERGY iussa m ikraMe AR 72801-Tel 501853-5000 I
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January 13,1995 ICAN019503 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington,DC 20555
Subject:
Arkansas Nuclear One-Unit 1 i
Docket No. 50-313 Licensa No. DPR-51 Monthly Operating Report Gentlemen:
The Arkansas Nuclear One - Unit 1 Monthly Operating Report (MOR) for December 1994 is attached. This report is submitted in accordance with ANO-1 Technical Specification 6.12.2.3.
Very truly yours, dbkf)fC M Dwight C. Mims Director, Licensing 1
DCM/irh Attachment 100082
' 9501200161 941231
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PDR ADOCK 05000313 L',
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l U. S. NRC l
January 13,1994 ICAN019503 Page 2 l'
cc:
Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission l
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 I
i 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
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l OPERATING DATA REPORT DOCKET NO:
50-313 DATE:
January 4,1995 COMPLETED BY: K. R. Hayes TELEPHONE:
(501) 858-5535 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 1 2.
Reporting Period:
December 1-31, 1994 -
3.
Ih-d Thermal Power (MWt): 2.568 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): None 10.
Reasons For Restrictions. If Any: None MOEIB YR-TO-DATE CUMULATIVE 11.
Hours in Reporting Period......
744.0 8,760.0 175,627.0 12.
Number of Hours Reactor was Critical..
744.0 8,657.8 129,256.2 13.
Reactor Rxrve Shutdown Hours 0.0 0.0 5,044.0 14.
Hours Generator On-Line....
744.0 -
8,644.4 126,988.0 15.
Unit Reserve Shutdown Hours..
0.0 0.0 817.5 16.
Gross Thermal Energy Generated (MWH)...
1,891,208.5 22,103,327.1 294,153,889.2 17.
Gross Electrical Energy Generated (MWH)............
646,780.0 7,518,885.0 98,311,920.0 18.
Net Electrical Energy Generated (MWH) =
620,116.0 7,198,561.0 93,525,697.0 i
19.
Unit Service Factor.
100.0 98.7 72.3 20.
Unit Availability Factor..
100.0 98.7 72.8 21.
Unit Capacity Factor (Using MDC Net).......
99.7 98.3 63.7 22.
Unit Capacity Factor (Using DER Net)....
98.1
%.7 62.6 23.
Unit Forced Outage Rate..........
0.0.
1.3 10.6 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling outage 1R12 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 08A)6n4 INITIAL ELECTRICITY 08/17n4 COMMERCIAL OPERATION 12/19n4
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l AVERAGE DAILY UNIT POWER LEVEL
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DOCKET NO:
50-313 i
UNIT:
One DATE:
Januan 4,1995 COMPLETED BY: K. R. Hayes TELEPHONE:
(501) 858-5535 MONTH December 1994 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 841 l
2 734 l
3.......
691 l
4 839 5
841 l
6..,
833 l
7.
337 l
8 M3 9.
843 10.
843 11.
843 12..
842 l
l 13.
843 14.
844 15.......
843 l
16.
843 17.
843 18.
843 19.
842 20.
M3 21.
836 22......
839 23.
843 24.
842 25.
843 26..
841
- 27..
846 28..
845
- 29......
843 30.
843 31.
844 l
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l AVGS:
833 INSTRUCTION On this format, list tin average daily unit power level in MWe-Net for each day in reporting month Cornplete to the nearest whole megawatt.
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NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
DECEMBER 1994 UNIT ONE The unit began the month operating at 100% power.
On the second at 18:02 hours, power was decreased to 40% for maintenance activities on both Main Feedwater Pumps and the E3 A Feedwater Heater. On the third at 04:30 hours, the unit power was increased following completion of the planned maintenance work.
Two other minor power reductions occurred during the month to allow maintenance retivities.
Unit 1 operated at full power for the remainder of the month.
UNIT SHUTDOWNS AND POWER REDUCTIONS RE%RTFOR Deccamber 1994 DOCKET NO.
50-313 UNIT NAME ANO Unit I DATE January 5,1995 COMPLETED BY K. R. Ilayes TELEPHONE (501) 858-5535 ME1110D OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO i
E DATE IXPI' (HOURS)
REASON' REACTORS REPORT #
CODE' CODES PREVENTRECURRENCE Nome a
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1 2
3 4
F: Forced Reason:
Method.
Exhibit G-Instructions S: Scheduled A - Equipment Failure (Explain) 1 - Manuel for Preparation of Data B - Maintemence of Test 2 - Manual Scram.
Entry Sheets for Th C -Refheling 3 - Automaatic Scream.
Event Repost (LER) File (NUREG-0161)
D - Regulatory Restriction 4 - Continuation E - Operator Training & Ucense Examination 5-Imed Reduction F-Administration 9 - Other 5
G - Operational Error Exhibit I-Seune Source H - Other (Explain)
j DATE: December 1994 REFUELING INFORMATION i
j 1.
Name of facility: Arkansas Nuclear One - Unit 1 l
2.
Scheduled date for next refueling shutdown. February 14.199_1 i
3.
Scheduled date for restart following refueling. April 7.1995 4.
Will refueling or resumption of operation thereafter require a technical specification change i
or other license amendment? If answer is yes, what, in general, will there be? If uswer 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 j
with the core reload (Ref.10 CFR Section 50.59)?
i Technical Specification change to relocate additional cycle specific parameters to the Core Operating Limits Reoort (COLR1 Technical Specification change to allow modification of the vital instrument electrical oower 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 olanned.
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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 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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