ENS 46352: Difference between revisions

v t e ENS Event
10:36 Oct 22, 2010
Title	Manual Reactor Trip During Physics Testing Due to Problems with the Rod Control in Hold Out Switch
Event Description	On 10/22/2010 at 0636 hours0.00736 days <br />0.177 hours <br />0.00105 weeks <br />2.41998e-4 months <br />, North Anna Unit-1 reactor was manually tripped during physics testing and 1-E-0 was entered due to problems with the Rod Control In Hold Out Switch. The out direction of the switch was not functioning properly and the reactor was tripped to put the plant in a condition to perform maintenance. All control rods fully inserted into the reactor core. This was an uncomplicated reactor trip with no automatic ESF actuation required. Unit 1 is currently stable at normal operating temperature and pressure in MODE 3 (Hot Standby). The plant electrical line-up is normal. Decay heat removal is via the steam dumps. Notification will be made to the local county administrator's office. The NRC Resident Inspector has been notified.

ENS 46352 +/-
Where
North Anna Virginia (NRC Region 2)
Reporting

10 CFR 50.72(b)(2)(iv)(B), RPS Actuation
Time - Person (Reporting Time:+-0.83 h-0.0346 days <br />-0.00494 weeks <br />-0.00114 months <br />)
Opened:	Don Taylor 09:46 Oct 22, 2010
NRC Officer:	Eric Simpson
Last Updated:	Oct 22, 2010
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v • d • e

v t e Emergency Notification System
North Anna with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation
WEEKMONTHYEAR2024-05-29T10:24:00 [Table view]
[ENS list for North Anna]

@@ Line 16: / Line 16: @@
 | event date = 10/22/2010 06:36 EDT
 | last update date = 10/22/2010
-| title = Manual Reactor Trip During Physics Testing Due To Problems With The Rod Control In Hold Out Switch
+| title = Manual Reactor Trip During Physics Testing Due to Problems with the Rod Control in Hold Out Switch
 | event text = On 10/22/2010 at 0636 hours, North Anna Unit-1 reactor was manually tripped during physics testing and 1-E-0 was entered due to problems with the Rod Control In Hold Out Switch.  The out direction of the switch was not functioning properly and the reactor was tripped to put the plant in a condition to perform maintenance.  All control rods fully inserted into the reactor core.  This was an uncomplicated reactor trip with no automatic ESF actuation required.
 Unit 1 is currently stable at normal operating temperature and pressure in MODE 3 (Hot Standby).

Latest revision as of 22:08, 1 March 2018