ML20072T644
| ML20072T644 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/31/1991 |
| From: | Whitt M ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20072T640 | List: |
| References | |
| NUDOCS 9104180208 | |
| Download: ML20072T644 (6) | |
Text
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OPERATING DATA REPORT DOCKET NO:
19-368 DATE:
April 1991 COMPLETED llY#1L,3 d hitt TELEPil0NE :
(501 964,,,5560 QEEEATING STATUS 1.
Unit Name: Ariannaa_Enlear one Unit 2 2.
Reporting Periodi,jiarsh 1-31. 1991 3.
Licensed Thermal Power (MWt):
2.815 4.
Nameplate Rating (Gross MWe): 942.57 5.
Design Electrical Rating (Net MWe):
912 6.
Maximum Dependable Capacity (Gross MWe):
897 7.
Maximum Dependable Capacity (Not MWo):
858 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): Ecnn 10.
Reasons For Restrictions.
If Any: None h0HIH YR-TO DATE CUMULATIVE
- 11. Ilours in Reporting Period....
744.0 2,160.0 96,552.0
- 12. Number of Ilours Reactor was Critical.....................
0.0 1.249.1 71,859.8.'
- 13. Reactor Reserve Shutdown llours........................
0.0 0.0 1,430.1 i
'14.
Ilours Generator On-Line......
0.0 1,242.8 70,236.6
- 15. Unit Reserve Shutdown llours..
0.0 0.0 75.0 16._ Gross Yhrtmal Energy Generated
( M W il )........................
0.0 3,216,025.0 184,034,866.0
- 17. Gross Electrical Energy G en e ra t ed ( MWil)..............
0.0 1,077,770.0 60,507,016.0
- 18. Not Electrical Energy Genera ted (MWil)..............
-2,073.0 1,026,975.0 57,533,513.0
.19.
Unit Service factor..........
0.0 57.5 72.7
- 20. ' Unit Availability Factor.....
0.0
'7.5 72.8 21.
Unit Capacity Factor (Using MDC Net)..............
-0.3 55.4 69.5 22.
Unit Capacity Factor (Using DEC Net)..............
-0.3 52.1 65.3
- 23. Unit Forced Outage-Rate......
0.0 2.2 12.5-24.
Shutdowns Scheduled Over Next 6 Months (Tyre Date, and Duration of Each):
2R8 Refueline Outage began February 22. 19911 the scheduled date for restart of Unit 2 in Anril 20. 1991.
25.
If Shut Down At End of Report Period.
Estimated Date of Startup: See___ item 24-above 26.
Units in Test Status (Prior to Commercial Operation):
l-Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY l.
COMMERCIAL OPERATION 91041802cs 93o433
{DR ADOCK 05000360 PDR
AVERAGE DAll.Y UNIT POWER 1.EVEI.
DOCKET NO:
iq-J68 UNIT:
Iwo DATE:
ApLil., 1991 COMPl.ETED llY: 11. S. Witit L____
D 01) 964 5560 TEI.EPil0NE :
0 MONTil tiar ch. ___1991 DAY AVERAGE DAll.Y POWER 1.EVEI, (MWe-Net) 1..............
-3 2..............
-3 3..............
-3 4..............
-3 5..............
-3 6..............
-3 7..............
-2 8..............
-2 9..............
-1 10.............
-3 11.............
-3 12.............
-3 13.............
-3 14.............
-3 15.............
-3 16.............
-3 17.............
-1 18.............
2 19.............
-3 20.............
-3 21.............
-3 22.............
-3 23.............
-3 24.............
-3 25.............
-3 26.............
-3 27.............
-3 28............
-3 29.............
-3 30.............
-4 31.............
-3 AVGS:
-3 INSTRUCTION On this format, list the average daily unit power level in MWe-Not for each day in reporting month.
Compute to the nearest whole megawatt.
l NRC HONTHlY OPERATING REPORT OPERATING
SUMMARY
1 J
MARCH, 1991 UNIT Th'O Unit Two remained off lino continuing the 2R8 Refueling Outage.
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UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR MARCH, 1991 DOCKET NO.
50-368 UNIT NAME Two DATE April. 1991 COMPLETED BY M. S. Whitt TELEPHONE (501) 964-5560 Method of Licensee Cause & Corrective Duration Shutting Event Systes Component Action to No.
Date Tvre" (Hours)
Reason
- Down Reactor Report #
Code' Code' Prevent Recurrence S
91-02 910301 S
744.0 C
4 N/A ZZ ZZZ Unit off line for 2RB i
Refueling Outage.
4 1
i i
i l
1 2
3 l
F: Forced Reason:
Method:
Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Continuation 1022)
E-Operator Training &
5-Load Reduction S
License Examination 9-O:ber F-Administrative Exhibit I - Sane Source G-Operational Error (Explain)
E-Other (Explain) i i
u m
m
DATEt March, 1991 REFUEL,1NG INFORMATION 1.
Name of facility:
AItanzas Nuclear One _ Unit _2 2.
Scheduled date for next refueling shutdown.
The end of Cvele 8 was Fehrnary 21. 1991.
Shutdegn f rom evele 9 is talgrind f or bugust 15, 1992.
3.
Scheduled date for restart following refueling. Arr11 20. 1991 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 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 50.59)?
No.
The Cvele 9 Reload Reoort has been revinged by t he_l'lant _ Sa f e t y Gommittee.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information. Hone _Rnqu1Ltd.
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 denign, new operating procedures.
Cvele 10 inngth of 456 EPPD is being qqnsidered.
7.
The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool, a) 177 b) 489 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 (l.oss of fullcore offload capability)
I PAGE 1 0F 2 ATTACHMENT A (CORRECTED COPY)
NRC HONTilLY OPERATING REPORT OPERATING
SUMMARY
AUGUST, 1990 UNIT TWO 1
l The unit began the month operating at 100% full power (PP).
On the twenty first at 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br />, the reactor was automatically tripped duo j
]
to a solenoid valve failure causing "B" Hain Steam Isolation Valvo (MSIV) to j
close. After replacing the solenoid valvo, the unit wan placed back i
on-lino on the twenty second at 1031 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.922955e-4 months <br />.
I The unit attained 100% power on the twenty-second at 2135 hours0.0247 days <br />0.593 hours <br />0.00353 weeks <br />8.123675e-4 months <br />, and operated at thin icvol through the end of the month, c
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