05000271/LER-1979-001-03, /03L-0 on 790110:during Normal Operation & Routine Maint,Leak Was Noted Adjacent to Flange on Reactor Water Cleanup Sys Suction Piping.Cause Unknown

/03L-0 on 790110:during Normal Operation & Routine Maint,Leak Was Noted Adjacent to Flange on Reactor Water Cleanup Sys Suction Piping.Cause Unknown

ML19263C277
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	02/08/1979
From:	Conway W VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19263C276	List: 05000271/LER-1979-001, Forwards LER 79-001/03L-0 05000271/LER-1979-001-03, /03L-0 on 790110:during Normal Operation & Routine Maint,Leak Was Noted Adjacent to Flange on Reactor Water Cleanup Sys Suction Piping.Cause Unknown
References
LER-79-001-03L, LER-79-1-3L, NUDOCS 7902130182
Download: ML19263C277 (2)

LER-1979-001, /03L-0 on 790110:during Normal Operation & Routine Maint,Leak Was Noted Adjacent to Flange on Reactor Water Cleanup Sys Suction Piping.Cause Unknown

Event date:
Report date:
2711979001R03 - NRC Website

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NA.VE OF PREPARER

LER 79-01/3L VTVYS1 05000271 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES During normal operation, while performing routine maintenance, leakage was observed adjacent to a 2" flange on the Reactor Water Cleanup System suction piping.

Investigation revealed a through wall leak near the piping weld between the 2" flange and the adjoining tee.

Further investigation revealed a through wall leak in the spare nozzle of the Electro Chemical Potential Autoclave located upstream of the 2" flange.

The Reactor Cleanup System was secured, the flange replaced, and the spare nozzle connection repair welded.

Conductivity monitoring of main coolant was shifted to the recirc-ulation loop sample point during the repairs.

The RWCU System was re-turned to service approximately 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> after the discovery. Reactor water chemistry was maintained within Tech. Spec. limits and there were no consequences to the health and safety of the public. A similar inci-dent was reported as RC 77-22/IP.