2CAN109207, Monthly Operating Rept for Sept 1992 for Ano,Unit 2
| ML20115D252 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/30/1992 |
| From: | James Fisicaro, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN109207, NUDOCS 9210200309 | |
| Download: ML20115D252 (6) | |
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e m" e en s October 15, 1992 2CAN109207 U.
S. Nuclear Regulatory Commission Document Control Desk Mail Stop P1-137 Washington, D.C.
20555
SUBJECT:
trkansas Nuclear One - Unit 2 iocket No. 50-368 License No. NPF-6 Monthly Operr. ting Report Gentlemen:
Monthly Operating Report statiw'.ics for Arkansas Nuclear One, Unit-2, for September, 1992 is attached.
This ret, ort is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.
V ry truly yours, hNcn
- Pw ames Fisicaro Director, Licensing JJF/JRH/sjf Attachment cc:
Mr. James L. Milhoan Regional Administrator U.
S. Nuclear Regulatory Ccmmission Region IV 611 Ryan Plaza Drive, Suite 400
- rlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. Thomas W.
Alexion NRR Project Manager, Region IV/ANO-1 U.
S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Ms. Sheri Peterson NRR Project Manager, Region IV/ANO-2 U.
- 3. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint-Nerth 11555 Rockville Pike Rockville, Maryland 20852 go amu **gna y p
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OPERATING DATA REPORT
- DOCKET NO:
50-368 DATE:
October 1,1992 COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 964 5560 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One l'ait 2 2.
Reporting Period:
September 1-30. 1992 4
3.
Licensed Thermal Power (MWt): 2.815 1
4 Nameplate Rating (Gross MWe): 942.57 5.
Design Electrical Rating (Net MWe): 912 6.
Maximum Dependable Capacity (Gross MWe): 897 i
7.
Maximum Dependable Capacity (Net MWe): 858 l'
8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Smcc Last Report, Give Rasons:
9.
Power Levci To Whicii Restricted. If Any (Net MWe): None 10.
Reasons For Restrictions. If Any:
Nonc 3
MONTH YR-TO-DATE
_C@iULATIVE 11.
Hours in Reporting Period.
720.0 6,575.0 109,727.0 i
12.
Number ofIlours Reactor was Critical.
97.5 4,665.I 82,640.5 3
13.
Reactor Reserve Shutdown i
Heurs.,
0.0 0.0 0.0 14 Ilours Generator On-Line.
97.5 4,647.7 80,834.9 15.
Unit Reserve Shutdown Hours.
0.0 0.0 0.0 p
16.
Gross Thermal Energy Generated j
(MWH).
268.556 12,869,887 213,128,995
=
17.
Gross ElectricalEnergy Generated (MWII).
88,135 4,238,545 70,091,376 18.
Net Electrical Energy 4-Generated (MWH).
80,951 4,036,493 66/>64,306 19.
Unit Service Factor.
13.5 70.7 73.7 20.
Unit Availability Factor.
13.5 70.7
'3.7 l
21.
Unit Capacity Factor (Using MDC Net).
13.1 71.6 70.8 22.
Unit Capacity Factor (Using DEC Net)...
12.3 67.3 66 6 23 Unit Forced Outage Rate.
00 21.9 12.4 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
,2R9 refueling outage begsgj eptember 4.1992, and will last approximately 52 days.
25.
If Shut Eav..; At End of Report Puiod. Estimated Date of Startup:
26.
Units in Test Status (Prior to Commercial Operation):
Forecast Achieved I
INITIAL CRITICALITY 12/05/78 INITIAL ELECTRICITY 12/26/78 COMMERCIAL OPERATION 03/26/80 4
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t AVERAGE DAILY UNIT POWER f EVEL DOCKET NO:
50-368 UNIT:
Two-DATE:
October 1,1992 COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 964 5560-MONTH Eqpigmber.1992 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 874 2
871 3
870 4
856 5
9 6
-14 7
-13 8
-7 9
4 10
-4 11.
-4:
12.
-4 13.
4 14..
4 15.
4 16.
-4 17.
-3 18..
-3 19.
-3
- 20..
21.
-3 22..
4 e
23.
-2 24.
-3 25.
-2 26...
-2 27.
-3 28.
-3 o
29.
-3 30.
-3 31.......
AVGS: 112 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.
i 1
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NRC MONTill,Y OPERATING REPORT l
J OPERATING
SUMMARY
SEPTEMBER 1992 1
UNIT T% 0 The unit began the month of Sentember in a core coastdown in preparation for 2R9.
l At 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> on the fifth, the plant was taken off line for refaciing ou' age 2R9.
The unit was off line for th. remainder of the month.
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9 UNIT SilUTDOWNS AND POWER REDUCTIONS
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REPORT FOR SEPTEMBER,19')2 DOCKET NO.56-368 UNIT NAME ANO Unit 2 DATE Octo$cr 1.1992 COMPLETED BY M. S Whitt TELEPIIONE 501-9M-5560 i
METilOD OF LICENSEE DURAlION SilUTTING DOWN EVENT SYSTEM COMPENENT CAUSE & CORRECTIVE ACTION TO NA DATE-TYPFf (IlOURS)
REASON 2 REACTOR 8 REPORT #
CODE' CODES PREVENT RECURRENCE 5
92-03 929905 S
622 5 C
1 N/A ZZ ZZZZZZ Unit offline for 2R9 Refueling, Outage.
a i
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2 3
4 F: Forced Reason:
Method:
Exhibit G - Instructions S: Scheduled A - Equipment Failure (Explain) 1 - Manual for Preparatiou of Data B - Maintenance of Test 2 - Manual Scram.
Entry Sheets ft r licensee
~
C - Refueling 3 - Automatic Scram.
Event Peport (LEH) File (NUREG-0161)
D-Regulatory Restr.; tion 4 - Continuation E - Operator Training & License Examination 5 - lead Reduction F-Administration 9 - Other 5
G - Operational Es.vr Exhibit I-Same Source 11 - Other (Explain)
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DATE:
September, 1992'
{
REFUELING INFORMA1 ION a_
1-1.
Name of facility:
Arkansas Nuclear One - Unit 2 4
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2.
Scheduled date for-next <efueling shutdown.
September 4, 1902 3.
Scheduled date for restart following refueling.
October 17, 1992 a '
4.
Will refueling or-resumption of operation thereafter require a 4
j tuchnical specification change or other license amendment?- If answer 4
it yes, what, in general, will there be?
If answer le no,-has the reload fuel design and core configuration been reviewed by your Plant
]
Safety Review Committee to determina whether any unreviewed safety questions are associateu with the core reload (Ref. 10 CFR Section
}
50.59)?
No Telhnical Specification chinoes or license amendments are anticipated as a result of the reload.
5.
Scheduled date(s) for submitting proposed. licensing action and supporting informatien-Previousiv submitted l
6.
Important li:ensing 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 i
operating procedures, i
None 7.
The number of_ fuel assemblies (a) in the core'and (b) in tho spent fuel storage pool.
a) 177 b) 565 t
8.
The present licensed spent fuel pool storage caphrity 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 C.
The projected date of the last refueling that can be discharged to the spent fuel poor assuming the present licensed capacity.
1 DATE:
1997 (Loss of fullcore offload capability) t S
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