ENS 53697: Difference between revisions

v t e ENS Event
04:00 Oct 27, 2018
Title	Manual Reactor Trip Following Startup
Event Description	On October 27, 2018, at 1533 EDT, Watts Bar Nuclear (WBN) Plant Unit 1 reactor was manually tripped due to a failure of the #3 Reactor Coolant Pump normal feeder breaker to close during the planned power transfer to unit power following startup. Concurrent with the reactor trip, the Auxiliary Feedwater system actuated as designed. All Control and Shutdown rods fully inserted. [Main Steam Isolation Valves] MSIVs were required to be isolated due to cooldown. All safety systems responded as designed. The unit is currently stable in Mode 3, with decay heat removal via Auxiliary Feedwater and Steam Generator Atmospheric Dump Valves. Unit 1 is in a normal shutdown electrical alignment. This reactor trip and system actuation is being reported under 10CFR 50.72(b)(3)(iv)(A) and 10CFR 50.72 (b)(2)(iv)(B). There was no effect on WBN Unit 2. The NRC Senior Resident has been notified."

ENS 53697 +/-
Where
Watts Bar Tennessee (NRC Region 2)
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:+12.87 h0.536 days <br />0.0766 weeks <br />0.0176 months <br />)
Opened:	David Allen 16:52 Oct 27, 2018
NRC Officer:	Dong Park
Last Updated:	Oct 27, 2018
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v • d • e

v t e Emergency Notification System
Watts Bar with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation
WEEKMONTHYEAR2024-07-08T19:21:00 [Table view]
[ENS list for Watts Bar]

@@ Line 16: / Line 16: @@
 | event date = 10/27/2018 00:00 EDT
 | last update date = 10/27/2018
-| title =
+| title = Manual Reactor Trip Following Startup
-| event text =
+| event text = On October 27, 2018, at 1533 EDT, Watts Bar Nuclear (WBN) Plant Unit 1 reactor was manually tripped due to a failure of the #3 Reactor Coolant Pump normal feeder breaker to close during the planned power transfer to unit power following startup. Concurrent with the reactor trip, the Auxiliary Feedwater system actuated as designed.
+All Control and Shutdown rods fully inserted. [Main Steam Isolation Valves] MSIVs were required to be isolated due to cooldown. All safety systems responded as designed. The unit is currently stable in Mode 3, with decay heat removal via Auxiliary Feedwater and Steam Generator Atmospheric Dump Valves. Unit 1 is in a normal shutdown electrical alignment.
+This reactor trip and system actuation is being reported under 10CFR 50.72(b)(3)(iv)(A) and 10CFR 50.72 (b)(2)(iv)(B).
+There was no effect on WBN Unit 2.
+The NRC Senior Resident has been notified."
 | URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2018/20181029en.html#en53697
 }}{{unit info

Revision as of 13:17, 30 October 2018