ENS 52663: Difference between revisions

v t e ENS Event
05:10 Apr 4, 2017
Title	Manual Reactor Scram Due to Condensate Leak
Event Description	At 0010 [CDT], 04/04/2017, the reactor was manually scrammed from approximately 75 [percent] core thermal power due Condensate Storage tank level lowering to 24 feet. All control rods fully inserted and all systems actuated and operated as designed. No safety relief valves actuated. Reactor level and pressure are currently being controlled within normal bands. RCIC [reactor core isolation cooling] was manually initiated for level control. This event is reportable under 10CFR50.72(b)(2)(iv)(B) for the reactor trip and 50.72(b)(3)(iv)(A) for the manual start of the reactor core isolation cooling system. The cause of lowering level was a condensate pipe leak. Decay heat is being removed via steam dumps to the condenser. The electrical grid is stable and supplying plant loads. The licensee has notified the NRC Resident Inspector.

ENS 52663 +/-
Where
Grand Gulf Mississippi (NRC Region 4)
Reporting

10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation
Time - Person (Reporting Time:+1.78 h0.0742 days <br />0.0106 weeks <br />0.00244 months <br />)
Opened:	David Burrus 06:57 Apr 4, 2017
NRC Officer:	Jeff Herrera
Last Updated:	Apr 4, 2017
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v • d • e

v t e Emergency Notification System
Grand Gulf with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation
WEEKMONTHYEAR2024-03-26T16:15:00 [Table view]
[ENS list for Grand Gulf]

@@ Line 16: / Line 16: @@
 | event date = 04/04/2017 00:10 CDT
 | last update date = 04/04/2017
-| title = Manual Reactor Scram Due To Condensate Leak
+| title = Manual Reactor Scram Due to Condensate Leak
 | event text = At 0010 [CDT], 04/04/2017, the reactor was manually scrammed from approximately 75 [percent] core thermal power due Condensate Storage tank level lowering to 24 feet.  All control rods fully inserted and all systems actuated and operated as designed.  No safety relief valves actuated.  Reactor level and pressure are currently being controlled within normal bands.  RCIC [reactor core isolation cooling] was manually initiated for level control.
 This event is reportable under 10CFR50.72(b)(2)(iv)(B) for the reactor trip and 50.72(b)(3)(iv)(A) for the manual start of the reactor core isolation cooling system.

Latest revision as of 21:43, 1 March 2018