ENS 45866: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by Mark Hawes)
 
(Created page by program invented by StriderTol)
 
Line 16: Line 16:
| event date = 04/22/2010 10:51 EDT
| event date = 04/22/2010 10:51 EDT
| last update date = 04/22/2010
| last update date = 04/22/2010
| title = Reactor Scram On Low Reactor Vessel Water Level During Feedwater Integrated Control System Testing
| title = Reactor Scram on Low Reactor Vessel Water Level During Feedwater Integrated Control System Testing
| event text = At 10:51 on 4/22/10, Susquehanna Unit 1 experienced an automatic reactor SCRAM on reactor low level, +13", during the initial testing of the Feedwater Integrated Control System.  Following the SCRAM, reactor water level dropped to approx. -30", and the Reactor Core Isolation Cooling system initiated and injected into the vessel.  Level was recovered by the Feedwater System and the RCIC system.  Division 2 Alternate Rod Insertion unexpectedly initiated during the level transient.  Due to scheduled maintenance activities, the 11B Aux Bus did not transfer to the off site power supply post SCRAM. The 11B Aux bus was restored at 12:17.  There were no ECCS initiations and no challenges to containment.
| event text = At 10:51 on 4/22/10, Susquehanna Unit 1 experienced an automatic reactor SCRAM on reactor low level, +13", during the initial testing of the Feedwater Integrated Control System.  Following the SCRAM, reactor water level dropped to approx. -30", and the Reactor Core Isolation Cooling system initiated and injected into the vessel.  Level was recovered by the Feedwater System and the RCIC system.  Division 2 Alternate Rod Insertion unexpectedly initiated during the level transient.  Due to scheduled maintenance activities, the 11B Aux Bus did not transfer to the off site power supply post SCRAM. The 11B Aux bus was restored at 12:17.  There were no ECCS initiations and no challenges to containment.
This event is a Reactor Protection System (RPS) actuation when the reactor is critical, and is reportable as a four hour ENS Notification under 10 CFR 50.72(b)(2)(iv)(B). This event is also an unplanned actuation of a system used to mitigate the consequences of a significant event and is reportable as an eight hour ENS notification under 10CFR50.72(b)(3)(iv)(A).
This event is a Reactor Protection System (RPS) actuation when the reactor is critical, and is reportable as a four hour ENS Notification under 10 CFR 50.72(b)(2)(iv)(B). This event is also an unplanned actuation of a system used to mitigate the consequences of a significant event and is reportable as an eight hour ENS notification under 10CFR50.72(b)(3)(iv)(A).

Latest revision as of 22:09, 1 March 2018

ENS 45866 +/-
Where
Susquehanna Talen Energy icon.png
Pennsylvania (NRC Region 1)
Reporting
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation

10 CFR 50.72(b)(3)(iv)(A), System Actuation
LER: 05000387/LER-2010-002
Time - Person (Reporting Time:+-1.52 h-0.0633 days <br />-0.00905 weeks <br />-0.00208 months <br />)
Opened: Darvin Duttry
13:20 Apr 22, 2010
NRC Officer: Bill Huffman
Last Updated: Apr 22, 2010
45866 - NRC Website
Loading map...