05000368/LER-1978-022-01, /01T-0 on 781219:safety Group Control Element Assembly A-52 Stopped Withdrawing at 144 Inches Withdrawn. Caused by Failed Lift Coil

/01T-0 on 781219:safety Group Control Element Assembly A-52 Stopped Withdrawing at 144 Inches Withdrawn. Caused by Failed Lift Coil

ML19267A345
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/03/1979
From:	Shively C ARKANSAS POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19263B246	List: 05000368/LER-1978-022, Forwards LER 78-022/01T-0 05000368/LER-1978-022-01, /01T-0 on 781219:safety Group Control Element Assembly A-52 Stopped Withdrawing at 144 Inches Withdrawn. Caused by Failed Lift Coil
References
LER-78-022-01T, LER-78-22-1T, NUDOCS 7901150071
Download: ML19267A345 (4)

LER-1978-022, /01T-0 on 781219:safety Group Control Element Assembly A-52 Stopped Withdrawing at 144 Inches Withdrawn. Caused by Failed Lift Coil

Event date:
Report date:
3681978022R01 - NRC Website

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Repor?4ble Occurrence Report TJo. 50-368/7t!-22 2.

Report Date: 01-03,79 3.

Occurrence Date: 12-19 78 4

Facility: Arkansas Nuclear One-Unit 2 Russellville, Arkansas 5.

Identification of Occurrence:

This ROR concerns the failure to take corrective action required by technical specification 3.1.3.1.

6 Conditions "rior to Occurrence:

Steady-State Power Reactor Power MWth Hot Standby X

Net Output HWe Cold Shutdown Percent of Full Power Refueling Shutdown load Changes During Routine Power Operation Routine Startup Operation Routine Shutdown Operation Other (speci fy) 7.

Description of Decarrence:

During approach to criticality, safety group CEA A-52 stopped withdrawal at approximately 144 inches withdrawn due to a failed lift (011.

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Reporta>1e Occurrence Report No.

50-368/78-22 8.

Designation of Apparent Cause of Occurrence:

Design Procedure Ibnufacture Unusual Service Condition including Environmental Installation /

Const ruct ion Component Failure (See Failure Data)

Operator Other (specify)

X NRC inspector interpretation of technical specification 9.

Analysis of Occurrence:

1he CEA was known to be trippabic, aligned within 7 inches of other group A rods, and was within limits for full out position; Therefore, the CEA was considered as operational, and mode 2 operation was established.

Reportable Occurrence Report No. 50-368/78-22 10.

Corrective Action

With the NRC ruling that the CEA was inoperabic, the plant should have confomed with the requirements of action statement T.S. 3.1.3.1.c, which would not allow the mode change from 3 to 2.

11.

Failure Data:

'Ihis incident did not endanger the health and safety of the public since the CEA was trippable and is considered an isolated occurrence.