1CAN019301, Monthly Operating Rept for Dec 1992 for Ano,Unit 1
| ML20127E613 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/31/1992 |
| From: | James Fisicaro, Hayes K ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1CAN019301, 1CAN19301, NUDOCS 9301190409 | |
| Download: ML20127E613 (7) | |
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ks 501-%3 t93 January 15, 1993 1CAN019301 U. S. Nuclear Regulatory Commission Document Control Desk
- Mail Station P1-137 Washington, DC 20555
Subject:
Arkansas Nuclear.One C Unit 1 Docket No. 50-313 License'No. DPR-51 Monthly Operating Report Gentlemen:
Monthly Operating Report statistics for Arkansas Nuclear One, Unit 1, for December,1992 is ' attached. This report is submitted in accordance:
with ANO-1 Technical Specification 6.12.2.3.
Very truly yours, h5/w.
James Fisicato Director, Licensing JJF/JRil/jt Attachments
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U. S. NRC January 15, 1993 1CAN019301.Page 2 J
i cc:
Mr. James L. Milhoan Regional Administrator U. S. Nuclear Regulatory Commission I
Region IV f
611 Ryan Plaza Drive, Suite 400 4
Arlington, TX 76011-8064 i
1
-l l
NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 l
Number 1, Nuclear Plant Road Russellville, AR 72801 3
3 Mr. Roby Bevan l
NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North i
11555 Rockville Pike Rockville, Maryland 20852 i
Mr. Thomas W. Alexion NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission i.
NRR Mail Stop 13-H-3 i
One White Flint North 11555 Rockville Pike i.
Rockville, Maryland 20852 I
i i.
4 i
I
OPERATING DATA REPORT DOCKET NO:
50 313 DATE:
Januarv 6.1992 COMPLETED BY: K.R.flayes TELEPliONE:
(501) 964 5535 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One Unit 1 2.
Reporting Period:
December 1-31. 1992 3
Licensed Thermal Power (MW ): 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 MWc): None 10.
Reasons For Restrictions. If Any:
None MONTil XB-TO-DATE CUMULATIVE 11.
11ours in Reponing Period.
744.0 8784.0 158107.0 12.
Number oflicurs Reactor was Criticrl 744.0 7137.8 112999.0 13.
Reactor Reserve Shutdown -
llours.
0.0 0.0 5044.0 14.
Hours Generator On-Linc..
744,0 00F "
110821.7 15.
Unit Reserve Shutdown 11ours.
0.0 0.0 817.5 16.
Gross Thermal Energy Generated (MWil)..
1909754 17955716
.253137154 17.
Gross Electrical Energy Generated (MWil).
655765 6099330 84377870 18.
Net Electrical Energy Generated (MWil).
628841 5825353 80200601 19.
Unit Senice Factor.
100.0 80.7 70.I 20.
Unit Availability Factor.
100.0 80.7 70.6 21.
Umt Capacity Factor (Using MDC Net).
101.1 79.3 60.7 22.
Unit Capacity Factor -
(Using DEC Net).
99.4 78.0 59.7 23.
Unit Forced Outage Rate....
0.0 0,1 11 8 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
M 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 08/06/74 INITIAL ELECTRICITY 08/17n4 -
COMMERCIAL OPERATION 12/19n4 i
a
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
5(b313 UNIT:
One DATE:
Januar** 6.1992 COMPLETED DY: K. R. Ilayes TELEPilONE:
(501) 964 5535 MONTH December.1992 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 845 2
846 3
846 4
845 5.
846 6
846 7
846 8
846 9
346 10.
845 11.
845 12.
845 13.
845 14..
845 15.
845 16.
843 f
17.
844 18.
838 1
19.
846 20.
846 21.
846 22.
846 23.,.
846 24.
846 25.
846 26..,
846 27.
846 28.
846 29.
846 30.
845 31.
846 AVGS: 845 k
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.
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NRC MONTillX OPERATING REPORT OPERATING
SUMMARY
DECEMilER 1992 UNIT ONE
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..--..-- =-----------------,== -
_ _ _ =
Unit one began the month operating at 100% power. On the seventeenth at 23:47 hours, the unit load was decreased to 98% to allow the isolation of a condenser waterbox for manual cleaning. The unit was returned to full power at 00:57 hours of the following day. On the eighteenth at 18:50 hours, the unit load wns decreased to 97% to perfonn scheduled tcsting of the turbine throttle / governor valves. The unit power was then returned to 100% at 20:32 hours on the same day. The unit operated at full power for the remainder of the month.
m..
m UNITSIIUTDOWNS AND POWER REDUCTIONS REPORT FOR DECEMBER 1992 DOCKET NO.
50 313 UNIT NAME ANO Unit i
- 1) ATE Januarv 9,19'u COMPLETED BY K. R lines TELEPIIONE 501-964-5535 s
METIIOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPENENT CAUSE & CORRECTIVE ACTION TO p'Q DATE TYPE' (IIOURS)
REASON:
REACTORS REPORT #
CODE' CODES PREVENT RECURREN I None i
I 2
3 4
F: Forced Reason:
Method:
Exhibit G - Instructions S: Scheduled
- A-Equipment Failure (Explain) 1 - Manual for Preparatbn of Data a
i B - Maintenance of Test 2 - Manual Scram.
Entry Sheets for licensee C-Refueling 3 - Automatic Scram.
Event Report (LER) File (NUREG-0161)
~
D - Regulatory Restriction 4 - Continuation 1
E - Operator Training & License Examination 5 -lead Reduction F-Administration 9 - Other 5
G - Operational Error Exhibit I-Same Source II - Other (Explain) i
l 4
DATE:
December, 1992 REFUELING INFORMATION y
1.
Name of facility: Arkansas Nuclear One - Unit 1 2.
Scheduled date for next refueling shutdown.
September 17, 1993 4
3.
Scheduled date for restart following refueling. November 12, 1993 j
,i 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 j
reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety i
questions are associated with the core reload (Ref. 10 CFR Section i
50.59)?
i Yes, Technical Specification change to increase fuel enrichment from 3.5% to 4.1%.
l 5.
Scheduled date(s) for submitting proposed licensing action and supporting information. The Technical Specification change request was_.
submitted to the NRC on June 27, 1991 (ICAN069108).
i 6.
Important licensing considerations associated with refueling, e.g.,
new I
or different fuel design or supplier, unroviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
None.
7.
The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool, a) 177 b) 625 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:
1995 (Loss of fu11 core offload capability) i,
,