ENS 52898: Difference between revisions

Latest revision as of 21:42, 1 March 2018

v t e ENS Event
16:24 Aug 11, 2017
Title	Comanche Peak Automatic Turbine Trip from 10 Percent Power
Event Description	At 1124 CDT on 11 August 2017, CPNPP [Comanche Peak Nuclear Power Plant] Unit 2 experienced an automatic turbine trip and trip of both main feedwater pumps on high steam generator water level (P-14, 81.5 percent level) in steam generator 2-02. Following the turbine trip, the auxiliary feedwater system actuated as required. The plant was stabilized at 2-3 percent reactor power with auxiliary feedwater feeding all steam generators with all levels within their normal bands. The cause of the high steam generator level appears to be a mechanical malfunction of steam generator 2-02 flow control valve bypass valve 2-LV-2163 (SG 2-02 FW BYP CTRL VLV) to close when demanded. Troubleshooting and repair of 2-LV-2163 is in progress. This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) for an actuation of auxiliary feedwater. The NRC Resident Inspector has been notified.

ENS 52898 +/-
Where
Comanche Peak Texas (NRC Region 4)
Reporting

10 CFR 50.72(b)(3)(iv)(A), System Actuation
Time - Person (Reporting Time:+-0.2 h-0.00833 days <br />-0.00119 weeks <br />-2.7396e-4 months <br />)
Opened:	Jonathan Bain 16:12 Aug 11, 2017
NRC Officer:	Jeff Herrera
Last Updated:	Aug 11, 2017
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v • d • e

v t e Emergency Notification System
Comanche Peak with 10 CFR 50.72(b)(3)(iv)(A), System Actuation
WEEKMONTHYEAR2024-03-17T20:15:00 [Table view]
[ENS list for Comanche Peak]

@@ Line 16: / Line 16: @@
 | event date = 08/11/2017 11:24 CDT
 | last update date = 08/11/2017
-| title = Comanche Peak Automatic Turbine Trip From 10 Percent Power
+| title = Comanche Peak Automatic Turbine Trip from 10 Percent Power
 | event text = At 1124 CDT on 11 August 2017, CPNPP [Comanche Peak Nuclear Power Plant] Unit 2 experienced an automatic turbine trip and trip of both main feedwater pumps on high steam generator water level (P-14, 81.5 percent level) in steam generator 2-02. Following the turbine trip, the auxiliary feedwater system actuated as required. The plant was stabilized at 2-3 percent reactor power with auxiliary feedwater feeding all steam generators with all levels within their normal bands.
 The cause of the high steam generator level appears to be a mechanical malfunction of steam generator 2-02 flow control valve bypass valve 2-LV-2163 (SG 2-02 FW BYP CTRL VLV) to close when demanded. Troubleshooting and repair of 2-LV-2163 is in progress.

Latest revision as of 21:42, 1 March 2018