05000313/LER-1980-034-03, /03L-0:on 800905,during Normal Operation,Small Primary to Secondary Leak Developed from Steam Generator E24A.Caused by Flow Induced Vibration Crack in Tube 74-2. Tube Was Plugged & Unit Returned to Svc

/03L-0:on 800905,during Normal Operation,Small Primary to Secondary Leak Developed from Steam Generator E24A.Caused by Flow Induced Vibration Crack in Tube 74-2. Tube Was Plugged & Unit Returned to Svc

ML19338F163
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/01/1980
From:	Shively C ARKANSAS POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19338F151	List: 05000313/LER-1980-034, Forwards LER 80-034/03L-0 05000313/LER-1980-034-03, /03L-0:on 800905,during Normal Operation,Small Primary to Secondary Leak Developed from Steam Generator E24A.Caused by Flow Induced Vibration Crack in Tube 74-2. Tube Was Plugged & Unit Returned to Svc
References
LER-80-034-03L-01, LER-80-34-3L-1, NUDOCS 8010070582
Download: ML19338F163 (1)

LER-1980-034, /03L-0:on 800905,during Normal Operation,Small Primary to Secondary Leak Developed from Steam Generator E24A.Caused by Flow Induced Vibration Crack in Tube 74-2. Tube Was Plugged & Unit Returned to Svc

Event date:
Report date:
3131980034R03 - NRC Website

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NRc toRu ssa u. s. Nuc.t AR Recut Afonv ComuissioN LICENSEE EVENT REPORT EXHIBIT A CONTROL SLOCat: l l l l l l lh IPLE ASE PRINT OR TYPE ALL REQUtRED INFORMAfl0N) 0 l 0l 0 l-l 0 ]O l g g l 1 l 1 l1 l 1 l g l cl.1 g

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EVENT oAfg 24 7b HE,oHT04TE to EVENT OtSCRIPTION AND PROSA8LE CONSEQUENCES h i During nonnal power operation, a s:nall primary to secondary leak developed, o,

i as indicated by an increase of the Condenser Vacuum Pump exhaust radiatiom rm i fBTil I monitor indication.

Leakage was verified to be from Steam Generator.

I i E24A, by analysis of the secondary system activity.

The RCS leak rate I

o s I limit per T.S. 3.1.6.1 and the secondary system activity limit per T.S.

I o.

i 3.10 were not exceeded.

An orderly unit shutdown was executed.

Similar i o,

i to occurrence LER 50-313/80-026.

Reportable per T.S. 6.12.3.2.d.

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33 J4 JS 36 33 40 el 42 e3 as op CAust DESCRIPTION AND CORRECflVE ACTIONS 27 8 I Following unit shutdown. testing identified the leaker to be tube 74-2.

I ITTrl i Eddy Current (NDE) inspection was conducted of four rows on each side of i i the "open lane", a samplino of tubes around the leaker and special i

i i 3 Iinterest tubes. Cause of failure "is believed to be due to a Flow Inducedi i Vibration crack propagating from defect.. Tube 74-2 was plugged and unit i e,ggturned to service.

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• a MLt45tO of A(L{ ASE ApovNf oF ACTty,Tv LOCA,,0N oF Mf t t ASE 36 LGj @ LN.J@l50 curies.Pred Xe-133 l Primary to Secondary to Londenser. tol

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