ENS 47306: Difference between revisions

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| event date = 09/29/2011 17:00 CDT
| event date = 09/29/2011 17:00 CDT
| last update date = 09/30/2011
| last update date = 09/30/2011
| title = Inadequate Surveillance Testing Of Emergency Diesel Generators
| title = Inadequate Surveillance Testing of Emergency Diesel Generators
| event text = Monticello has discovered that it has not met Technical Specification Surveillance Requirement (SR) 3.8.1.7 relating to the largest single post-accident load reject for the Emergency Diesel Generators (EDG).  Although the current test designated post-accident load is successfully load  rejected during the surveillance, the test load rejection must be higher to bound all post-accident load scenarios.  The capability of an EDG subsystem to recover from a reject of the largest single post-accident load testing has not met the requirements of SR 3.8.1.7.  Therefore, both EDGs have been declared inoperable.  Both EDGs are considered Functional and Available for use at this time.
| event text = Monticello has discovered that it has not met Technical Specification Surveillance Requirement (SR) 3.8.1.7 relating to the largest single post-accident load reject for the Emergency Diesel Generators (EDG).  Although the current test designated post-accident load is successfully load  rejected during the surveillance, the test load rejection must be higher to bound all post-accident load scenarios.  The capability of an EDG subsystem to recover from a reject of the largest single post-accident load testing has not met the requirements of SR 3.8.1.7.  Therefore, both EDGs have been declared inoperable.  Both EDGs are considered Functional and Available for use at this time.
There were no automatic EDG initiation signals associated with this event.
There were no automatic EDG initiation signals associated with this event.

Latest revision as of 21:05, 1 March 2018

ENS 47306 +/-
Where
Monticello Xcel Energy icon.png
Minnesota (NRC Region 3)
Reporting
10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor

10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat

10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material

10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
Time - Person (Reporting Time:+2.3 h0.0958 days <br />0.0137 weeks <br />0.00315 months <br />)
Opened: David Webster
00:18 Sep 30, 2011
NRC Officer: Vince Klco
Last Updated: Sep 30, 2011
47306 - NRC Website
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