05000334/LER-1980-116-03, /03L-0:on 801217,degassifier a Recovery Heat Exchanger BR-E-12A2 Steam Leak Found to Be Cracked Weld. Cause Unknown.Exchanger Isolated & Drained.Weld Grounded Out & Temporary Mod to Seal Weld Performed

/03L-0:on 801217,degassifier a Recovery Heat Exchanger BR-E-12A2 Steam Leak Found to Be Cracked Weld. Cause Unknown.Exchanger Isolated & Drained.Weld Grounded Out & Temporary Mod to Seal Weld Performed

ML20002D929
Person / Time
Site:	Beaver Valley
Issue date:	01/15/1981
From:	Lacey W DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20002D928	List: 05000334/LER-1980-116-03, /03L-0:on 801217,degassifier a Recovery Heat Exchanger BR-E-12A2 Steam Leak Found to Be Cracked Weld. Cause Unknown.Exchanger Isolated & Drained.Weld Grounded Out & Temporary Mod to Seal Weld Performed 05000334/LER-1980-117-03, /03L-0:on 801218,during Physics Testing,Delta Flux Left Low Side of Target Band When Power Decreased Rapidly.Caused by Rapid Insertion of Control Rods During Power Decrease.Rods Partially Borated Out of Core ML20002D927
References
LER-80-116-03L, LER-80-116-3L, NUDOCS 8101230471
Download: ML20002D929 (2)

LER-1980-116, /03L-0:on 801217,degassifier a Recovery Heat Exchanger BR-E-12A2 Steam Leak Found to Be Cracked Weld. Cause Unknown.Exchanger Isolated & Drained.Weld Grounded Out & Temporary Mod to Seal Weld Performed

Event date:
Report date:
3341980116R03 - NRC Website

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U. S. NUCLEA10 REGutATCGY COMMtSSl!N R AC FC".M 364

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40 68 OOCKET NUMSER nd 69 EVENT OATE la IS REPCRT Q ATE 80 EVENT DESCRIPTION ANO PROSA8LE CONSEQUENCES h ITTT1 I on 12/17/80, the source of a steam leak on the "A" necastrier Recovery lle.it l

ITTT1 I Eschancer (BR-E-12A21 was found to be a cracked weld. This abnormal decradation in l

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The health and l ITT71 I (BR-E-12A2] is reportable under Technical Specification 6.9.1.9.d.

101 s 1 I safety of the public was not jeopardized since ebe higher than normal background g l radiation levels in the auxiliary building Caused in part by this leak were still l

1o 171 l within the 10 CFR 20 MPC limits.

Isolating [BR-E-12A2] reduced these levels by l

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44 4y 33 33 36 31 40 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h lilOf1 The cause of the cracked weld is unknown. With the heat exchanger isolated and

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i building were I Q l drained. further releases of radioactive materials into the auxiliary iii2i i prevented. The weld was ground out and a temo'orary modification was made to seal l

IiI 3 I l the weld. A permanent modification is planned.

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Attachment To LER 80-Ilfs/03L Beaver Valley Power Station Duquesne Light Company Docket No. 50-334 No further information is available or required to satisfy the reporting requirement.

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