ML20096F328
| ML20096F328 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/31/1992 |
| From: | Hayes K ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20096E715 | List: |
| References | |
| NUDOCS 9205210067 | |
| Download: ML20096F328 (2) | |
Text
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REVISED COPY UNIT SHUTDOWNS AND POWER REDU'TIONS REPORT FOR MARCH, 1992 DOCKET.NO.
50-313 UNIT NAME ANO Unit 1 DATE April 13, 1992 COMPLETED BY K. R. Hayes
~ELEPHONE (501) 964-5535 I
l Method of Licensee Cause & Corrective Duration Shutting Event
' System Component Action to s
No.
Date
-Type-(Hoursl Reason ~
Down Reactor
- Report #
Code' Code Prevent Recurrence.
o?-01 920301 S
744 C
4 NA NA NA Unit offline continuing.
IRIO refuelimg outage.
I 3
4 1
2 F: Forced Reason:
Methodi Exhibit G - Instructions 5: Scheduled.
A-Equipment' Failure (Explain) 1-Manual for. Preparation of Data B-Haintenance or Test 2-Manual.Scra2.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D-kegulato n Restriction-4-Continuation 1022)
E-Operator Training 6-5-Load Eeduction 8
License Examination 9-Other F-Administrative Exhibit I.- Same Source G-Operational Error (Explain)
H-Other (Explain) a
.s
DATE:
April, 1992 REFUELING INFORMATION 1.
Name of faci) tty:
Arkansas-Nuclear One - Unit 1 2.
Scheduled date for next refueling shutdown. Februa ry_29 1992 u
3.
Scheduled date for restart following refueling. May 9_u1992 4.
Will refueling or resumption of operation thereniter require a technical specification change or other license amendment? If annwar is yes, what, in general, will there be?
If answer is no, haa
te reload fuel design and core configuration been reviewed by yeur P1nnt Safety Review Committen to determine whether any unreviewed safoty questions are associated with the core reload (Ref. 10 CFR Section 50.59)?
Yes.
Technical Specification changes per GL 88-16Acorpora_ ting use of a_
Core Operating,Limi*s Report (COLR} was submitted to.the NRC.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information. The COLR Technical Specification clange request g
i submitted to the NRC was approved April 17, 1992. The 50.59 for the Re-
.l_on!._ Report was approved _by_ plant Safety Committee for Cycb_1 Loperstigg 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.
N9B '.
7.
The number of fuel assemblias (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 requestnd or is planned, in number of fuel assemblins.
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 lic-, sed capacity.
DATE:
1995 (Loss of fullcoze offload capability)
Changed due to the addition of 60 discharged assemblics during 1R10.
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