ENS 54252: Difference between revisions

v t e ENS Event
00:55 Sep 1, 2019
Title	Manual Trip Due to Loss of Steam Generator Level Control
Event Description	While operating at 100 percent power, the Watts Bar Unit 1 reactor was manually tripped at 2055 EDT on August 31, 2019 due to loss of steam generator #2 level control. The trip was not complex. All control and shutdown bank rods inserted properly in response to the manual reactor trip. All safety systems, including Auxiliary Feedwater, actuated as designed. Operations responded and stabilized the plant. Decay heat is being removed by the Auxiliary Feedwater and the Steam Dump System. Unit 2 is not affected. The cause of the loss of steam generator water level control is being investigated. The manual actuation of the Reactor Protection System (RPS) is being reported as a four hour report under 10 CFR 50.72 (b)(2)(iv)(B). The automatic actuation of the Auxiliary Feedwater System (an engineered safety feature) is being reported as an eight hour report under 10 CFR 50.72 (b)(3)(iv)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector was notified.

ENS 54252 +/-
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:+-0.77 h-0.0321 days <br />-0.00458 weeks <br />-0.00105 months <br />)
Opened:	David Allen 00:09 Sep 1, 2019
NRC Officer:	Ossy Font
Last Updated:	Sep 1, 2019
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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]

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 The cause of the loss of steam generator water level control is being investigated.
 The manual actuation of the Reactor Protection System (RPS) is being reported as a four hour report under 10 CFR 50.72 (b)(2)(iv)(B).  The automatic actuation of the Auxiliary Feedwater System (an engineered safety feature) is being reported as an eight hour report under 10 CFR 50.72 (b)(3)(iv)(A).
-There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector was notified."
+There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector was notified.
 | URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2019/20190903en.html#en54252
 }}{{unit info

Latest revision as of 23:44, 23 February 2020