2CAN099006, Monthly Operating Rept for Aug 1990 for Arkansas Nuclear One Unit 2
| ML20059K978 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/31/1990 |
| From: | James Fisicaro, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN099006, 2CAN99006, NUDOCS 9009260002 | |
| Download: ML20059K978 (7) | |
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0 September 17, 1990
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-U.-:S. Nuclear. Regulatory Commission
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' Document Control Desk ol
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-Washington,.D.C.. 20555-
SUBJECT:
. Arkansas: Nuclear One --Unit 2 3
Docket No. 50-368
' License No. NPF-6 Monthly Operating Report e
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. Gentlemen:
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.i Tho' Arkansas' Nuclear One
. Unit 2. Monthly Operating. Report for.
- 1
. August, 1990 is; attached.
-Veryftruly yours.,.
)Mf.&
James J.
'isicato Manager, Licensing
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JJF/SAB/1r
. Attachment.
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9009260002,90'0031-
. PDR! ; ADOCK :05000368
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4 U. S. NRC--. Ssptcabar. 17, 1990 lp,?';l: L} l ' ' "'
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Mr. Robert'D. Martin Regional Administrator i
U. S.-Noclear Regulatory Commission Region IV t.
F 611-Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
-NRC. Senior Resident Inspescor
.!i Arkansas Nuclear One - ANO-1 & 2
-Number.1, Nuclear; Plant Road, fi Russellville, AR 72801 l-1 f#
Hr. Thomas W. Alexion NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR' Mail Stop 11-B One White Flint: North s
10 11555 Rockville Pike
-Rockville' Maryland _20852 4
6 Mr. Chester;Poslusny NRR Project Manager, Region IV/ANO-2 g
U. S.1 Nuclear. Regulatory Commission NRR Mail Stop 11-B-19 l
One White Flint North g;.
11555-Rockville Pike
- Rockville, Maryland 20852 k
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OPERATING DATA REPORT Dvg DOCKET NO: _
10-368 DATE:
August. 1990 COMPLETED BY: M. S. Whitt TELEP110NE:
C5011 964-3743 OPERATING STATUS 1 ~.
Unit Names' Arkansas Nuclear One - Unit 2 m
-2.
Reporting Period:: _ August 1-31. 1990 3.
Licensed Thermal Power (MWt):
2.815 4.-
Nameplate Rating (Gross MWo):
942.57
- 5.~
Design Electrical Rating-(Net MWe):: 912 6.
Maximum Dependable Capacity (Gross-HWe):
897 7.,
-Maximum Dependable Capacity (Not MWe): 358
- 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 j
s MONTH YR-TO-DAIE CUMULATVE 11 3 llours in Reporting Period....
744.0 5,831.0
-91,463.071 12.L. Number of Ilours Reactor was
,13.-
Reactor Reserve Shutdown
. 67,703.1, C r i t ica l '......................
716.3 5,338.8 llours........................
0.0 0.0 1,430.1 11 4. Ilours Generator On-Line......
711.7 5,307.8 66,088.5 2
' 15.
Unit Reserve Shutdown liours..
0.0 0.0 75.0= j l6.
Gross Thermal Energy' Generated z
.(HWII)........................
1,984,154.0 14,463,562.0 172,672,092.0 j L \\
17., Gross Electrical Energy 56,721,856.0j L e n e r a t ed = ( MWII)..............
650,630.0 4,764,380.0
=18.
Net-Electrical Energy
. G enera t ed > (MWil)..............
620,359.0 4,540,464.0 53,917,434.0]
19.
Unit Service factor..........
95.7 91.0 72.3 a 20.
Unit: Availability Factor.....
95.7
- 91.
72.3~j
~ 21.
Unit Capacity Factor.
-(Using MDC Not)..............
97.2 90.8 68.7-l 22.
Unit Capacity Factor
.l (Using DER Not)..............
91.4' 85.4 64.64 23.
Unit Forced Outage Rate......
4.3 5.3 13.2
. 24. - Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of-l Each):
D8 Refueling Outage is scheduled to begin February. - 1991; -
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_and ti-heduled date for restart is April,1991.
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-25.
If Shu
, wn At End 'of Report Period. Estimated Date of
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Startup l
26.
Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION h,
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i AVERAGE D'.ILY-UNIT. POWER LEVEL DOCKET.NO:
50-368-UNIT:
Two DATE:.
August. 1990 COMPLETED BY: M. S. Whitt TELEPil0NE:
(501F 964-3743 MONTH Aunust. 1990 DAY
' AVERAGE DAILY POWER LEVEL-~
(MWe-Net) f 1.............
884-ji 2.............
- 882
.3.............
880 G'
41...-..........
881 5.............
882
'6.............
888 7.-.............
891
'81.............-
891 J.
9.............
887 10............
'885-
,11:............
883 1
-121.............
884 13~............
882
-144~............
883 15.......'.....
882
_16_-............
880 17............
878-18...........'..
879:
19c...........
880 20............
880~
21............
- 55' 22.....'.'......-
261 23.........'....
874 E
'24....'........
875
'25............
2876 s
.26............
-868 27c............
871:
28
..a.........
873-
'29'............
872 30'.............
881 31*............
883 AVGSt. -834-e O.
. INSTRUCTION On this' format, list the average daily unit power level in MWe-Net for each day in reporting month. Compute to the nearest whole megawatt.
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'NRC MONTIILY 0PERATING REPORT-OPERATING
SUMMARY
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AUGUST, 1990 UNIT TWO
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.The unit began the month operating at 100% full power (FP).
On-the twenty-first at 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br />, tho' reactor was. manually tripped due to-a solenoid valve. failure causing "B" Main Steam isolation Valve (MSIV)=to
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~ close. After replacing the solenoid valve, the unit was placed back
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on-line on the twenty-second.at 1031 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.922955e-4 months <br />.
Y The unit attained 100% power.on the twenty-second at 2435 hours0.0282 days <br />0.676 hours <br />0.00403 weeks <br />9.265175e-4 months <br />, and operated at this level through the end of the month.
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UNIT SHUTDOWNS AND POWER REDUCTIONS
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REPORT FOR AUGUST, 1990 DOCKET NO.- 368 UNIT NAME-
~Two DATE Auaust; 1990 COMPLETED BY M. S. Whitt-
-TELEPHONE 501-964-3743 Cause & Corrective Method of Licensee Duration Shutting Event ~
. System Component Action to h
Date Type (Hours)
Reason
- Down Reactor
' Report #
_ Code' Code' Prevent Recurrangg 8
2
'90-05 900821 F
32.3-
'A 2-2-90-019 SB PSV The reactor was manually.
-tripped'after the "B"
Main Steam Isolation Valve'(MSIV) closed due to a failure in a solenoid. valve. 'The solenoid valve was replaced; further investigation is being-conducted to determine.
the root cause of the failure.
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F: Forced.
Reason:
Method:
Exhibit G --Instructions S: Scheduled A-Equipment' Failure (Explain) 1-Manual for' Preparation of Data -
~B-Maintenan'e or Test 2-Manual Scram.
Entry Sheets for Licensee c
C-Refueling 3-Automatic Scram.
Event Report (LER) File-(NUREG-D-Regulatory Restriction 4-Continuation 1022)
-E-Operator Training &
5-Load Reduction 5
License Examination 9-Other-Exhibit I - Same Source
'F-AdministrativeJ
- G-Operational Error (Explain)
H-Other (Explain) iI
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, y j Ic e4 ~ DATE: ~Aunurt. 1990 t D REFUELING INFORMATION-4 1.. Name of. facility: Arkansas Nuclear One - Unit 2 2.- Scheduled date for next refueling shutdown. February 1991 (Beninnine of Cycle 8 criticality was 11/18/891: [ 23. Scheduled date for restart following refueling._Aeri'.'1991 4. Will refueling or resumption of operation thereafter require a technical specification-change or other license amendment? 11f answer is yes, what, in general, will thers be? If answer ~is no, has the' reload-fuel design and core configuration been reviewed by'your plant i Safety Review Committee to determine whether;any unreviewed safety questions are associated with the core reload.(Ref. 10:CFR Section 50.59)? None Eroected. Reload fuel desinn is in ororress. 5.1 Scheduled date(s) for submitting proposed licensing. action and ' ) supporting information. None Reauired i 6.
- Important licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or-performance ir analysis methods, significant changes in fuel design, new operating procedures. To ob'tain the cresentiv'olanned evele 8 lennth of 420 EFPD. It will-be-necessary to raise the current ocak rod burnur limits. A report justifyino an increase was submitted in July. 1989. 7. The number of fuel assemblies (a) in the core and (b)Jin the spent fuel ~ storage pool, a) 177 b) 421 .j i 8.-.The present licensed spent fuel pool' storage' capacity and the. size of. . i any increase in licensed storage capacity that has been requested or is L planned,~1n number of fuel assemblics. present 1988 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 fu11 core offload capability) f ' 8 ._m _}}