ENS 46618
ENS Event | |
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16:25 Feb 16, 2011 | |
Title | Steam Leak on High Pressure Coolant Injection System |
Event Description | During system startup of [High Pressure Coolant Injection] HPCI for quarterly surveillance, audible and visual indications of steam leakage were observed. The system was secured and subsequently isolated (with outboard valve de-energized for configuration control). As a result of the steam leakage, a local fire alarm was received in the Control Room. HPCI is currently isolated and will not perform its safety function.
Operators were dispatched to the Reactor Building fire panel to verify that the fire alarm was due solely to the steam leak. As a precautionary measure, personnel were evacuated from the Reactor Building. Operators entered [Off Normal Procedure] ON 3158, Reactor Building High Area Temperature/Water Level, and verified that room temperatures were decreasing after the steam line was isolated. No EOP-4, Secondary Containment Control, entry conditions were exceeded. The steam leak was isolated when HPCI was secured. Associated fire alarms were verified to be caused by the steam leak. There was no impact on other plant equipment or personnel safety. The source of the steam leak is suspected to be from a steam trap but this has not been confirmed. The licensee notified the NRC Resident Inspector and the State of Vermont Department of Public Service Nuclear Engineer. Notified R1DO (Ferdas) |
Where | |
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Vermont Yankee File:NorthStar Vermont Yankee icon.png Vermont (NRC Region 1) | |
Reporting | |
10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
Time - Person (Reporting Time:+-0.93 h-0.0388 days <br />-0.00554 weeks <br />-0.00127 months <br />) | |
Opened: | Andrew Wisniewski 15:29 Feb 16, 2011 |
NRC Officer: | John Shoemaker |
Last Updated: | Feb 16, 2011 |
46618 - NRC Website
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Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |