ENS 46618: Difference between revisions
Jump to navigation
Jump to search
StriderTol (talk | contribs) (Created page by program invented by Mark Hawes) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 16: | Line 16: | ||
| event date = 02/16/2011 11:25 EST | | event date = 02/16/2011 11:25 EST | ||
| last update date = 02/16/2011 | | last update date = 02/16/2011 | ||
| title = Steam Leak | | title = Steam Leak on High Pressure Coolant Injection System | ||
| event text = 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. | | event text = 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. | 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. | ||
Latest revision as of 22:07, 1 March 2018
| Where | |
|---|---|
Vermont Yankee  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
| |
Vermont Yankee with 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |