1CAN049304, Monthly Operating Rept for Mar 1993 for Ano,Unit 1
| ML20035E705 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/31/1993 |
| From: | James Fisicaro, Hayes K ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1CAN049304, 1CAN49304, NUDOCS 9304190125 | |
| Download: ML20035E705 (7) | |
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.i Ii April 15, 1993 j
i ICAN049304 U. S. Nuclear Regulatory Commission Document Control Desk
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Hall Station F1-137 r
Washington, DC 20555 Subj ect.: Arkansas. Nuclear One - Unit 1 l
Docket No. 50-313 l
License No. DPR-51
. Monthly Operating Report i
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Gentlemen:
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'The Arkansas Nuclear One - Unit 1 Monthly Operating Report (MOR) for.
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Harch, 1993 is attached.
This report is submitted in accordance with-ANO-1 Technical. Specification-6.12.2.3.
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Very,truly yours, j
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James J. Fisicaro l
Director, Licensing JJF/JRH/prg Attachment i
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M U. S. NRC April ~15,'1993 i
JCAN049304 Page 2 i
cc: - Mr. James L. Milhoan -
Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400
. Arlington, TX 76011-8064 i
NRC Senior Resident inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant. Road Russellville, AR 72301 i
Mr. Roby Bevan NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint' North El 11555 Rockville Pike
- I Rockville,_ Maryland 20852 Mr. Thomas W. Alexion NRR Project Manager, Region IV/ANO-2 j
.U. S. Nuclear Regulatory Commission NRR Mail Stop 13-11-3 J
One White Flint North i
11555 Rockville" Pike Rockville, Maryland 20852 t
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j OPERATING DATA' REPORT DOCKET NO:
50-313
-i DATE:
April 6.1993 COMPLETED BY: K. R. Haves TELEPHONE:
(501) 964-5535 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 1 l
2.
Reporting Period:
March 1-31.1993 3.
Licensed Thermal Power (MW1): 2.568 4
Nameplate Rating (Gross MWe): 902.74 l
5.
Design Electrical Rating (Net MWe): 850 l
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 l
10.
Reasons For Restrictions. If Any: None i
MONT_H YR-TO-DATE CUMULATIVE I 1.
Hours in Reporting Puiod...
744.0 2160.0 160267.0 12.
Number of Hours Reactor was Critical..
702.8 2118.8 115117.8
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13.
Reactor Reserve Shutdown Hours..
0.0 0.0 -
5044.0
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l4.
Hours Generator On-Line.
682.5 2098.5
.I12920.2
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15.
Unit Reserve Shutdown Hours..
0.0 0.0 817.5-16.
Gross Thermal Energy Generated (MWH).....
1716868 5351469 258488623 1
17.
Gross Electrical Energy Generated (MWH).
587910 1837065 86214935 18.
Net Electrical Energy Generated (MWH)..
561455 1759637 81960238 4
19.
Unit Service Factor..
91.7
.97.2 70.5' 20.
Unit AvailabilityFactor.
91.7 97.2 71.0 21.
Unit Capacity Factor
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(Using MDC Net).
90.3 97.4 61.2 22.
Unit Capacity Factor (Using DEC Net).
88.8 95.8 60.2 23.
Unit Forced Outage Rate..
8.3 28 11.6 3
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):-.
v 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 1
INITIAL ELECTRICITY 08/17n4 COMMERCIAL OPERATION 12/19n4 i
4
~ AVERAGE DAILY UNIT POWER LEVEL i
.l DOCKET NO:
50-313 UNIT:
One DATE:
April 6,1993 COMPLETED BY: K. R.llayes TELEPHONE:
(50l) 964-5535 MONTH March.1993 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) i 1.-
846 2
846
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3 846 4
846 5
487 6
-33 1
7
-34
'k 8
549 9..
745
'f 10.
819 11.
848 12.
847 13....
847 14...
848
- 15..
847 16.
847 17.
848
~ 18..
847 19 847 20..
848 21.
847 22..
84 7 23.
84 7 84 l
24...
25..
841 26.
847 l
27.
708
- 28..
704
- 29...
815 846 304
- 31......
846 AVGS: 755 t
INSTRUCTION f
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 MONTIILY OPERATING REPORT OPERATING
SUMMARY
MARCII 1993 UNIT ONE Unit one began the month operating at 100% power. On the fifth at 14:12 hours, the unit experienced an automatic turbine / reactor trip. This trip was initiated by a ground in the turbine lock-out circuit. The unit was returned to operation at 03:45 hours on the eighth and reached full power at 12:37 hours on the same day. On the ninth at 15:49 hours the unit experienced an automatic mnback when the A2 bus was deenergized. The runback was terminated at 62% power. The unit returned to full power at 04:15 hours on the tenth. On the twenty sixth at 23:30 hours, the unit load was reduced to 85% per the load dispatcher's request. During the load reduction, the monthly turbine governor and throttle valve testing was completed. The unit returned to full power on the twenty ninth at 05:58 hours. The unit operated at full power for the remainder of the month.
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i UNIT SilUTDOWNS AND POWER REDUCTIONS
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REPORT FOR MARCII 1993 DOCKET NO.
50-313 UNIT NAME ANO Unit I DATE Apni 6,1993 COMPLETED BY K. R. Hayes TELEPIIONE 501-964-5535 METilOD OF LICENSEE DURATION S11UTTING DOWN EVENT SYSTEM COMPENENT CAUSE & CORRECTIVE ACTION TO M
DATE TYPE' (IIOURS)
REASON 2 REACTOR 2 REPORT #
CODE' CODE' PREVENT RECURRENCE A cable in the turbine lock-out circuit 93-01 930305 F
61.5 A
3 1-93-001 TA CBL3 caused a ground of the circuit & initiated a turbine / reactor trip.
93-02 930309 F
0 G
5 1-93-002 EA 52 Improper racking of a breaker caused bus lock-out & subsequent power runback.
I 2
3 4
F: Forced Reason:
Method:
Exhibit G -Instructions S: Scheduled A - Equipment Failure (Explain) 1 - Manual for Preparation of Data 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 E - Operator Training & License Examination 5 -Imad Reduction F - Administration 9 - Other 5
G - Operational Error Exhibit I-Same Source II-Other (Explain)
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c DATE: March, 1993 t'
REFUELING INFORMATION i
1.
Name of facility: Arkansas Nuclear One - Unit 1 2.
Scheduled date for next refueling shutdown.
September 17, 1993 3.
Scheduled date for restart following refueling. November 12, 1993 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? If answer
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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
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50.59)?
Yes Technical Specification change to increase fuel enrichment from j
3.5% to 4.1% and to reference B&W Topical Report BAW-10179P for the Core
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Operating Limits Report.
7 i
5.
Scheduled date(s) for submitting proposed licensing action and supporting information. The fuel enrichment Technical Specification change request was submitted to the NRC on June 27, 1991 (ICAN069108).
A Technical Specification change request to reference B&W Topical Report i
BAW-10179P is scheduled to be submitted in April, 1993.
t' 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.
7.
The number of fuel assemblies (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)
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