ENS 48687
ENS Event | |
---|---|
21:51 Jan 21, 2013 | |
Title | Automatic Reactor Trip Due to Low Steam Generator Level |
Event Description | At 15:51 CST, Waterford 3 experienced an uncomplicated automatic reactor trip from 84.5% reactor power. The actuations of the Reactor Protection System (RPS) and the Emergency Feedwater Actuation System (EFAS) resulted from Steam Generator #1 Low Level, which is at a nominal 27.4% narrow range setpoint. Safety systems responded as expected.
All three (3) Emergency Feedwater Pumps started and injected into Steam Generator #1. Auxiliary Feedwater pump has been started, feeding both Steam Generators (#1 and #2) at levels above the EFAS low level setpoint. All control rods inserted by the automatic RPS actuation. Electrical power is being supplied from normal off-site power and condenser vacuum is available for Steam Generator heat removal via the Steam Dump Bypass Control system. There are no safety systems out of service or inoperable, nor any safety system TS [Technical Specification] LCO [Limiting Condition for Operation] actions entered. The cause of the Steam Generator #1 Low Level condition, and associated Reactor Trip, is under investigation. This event occurred during the initial power escalation from refuel outage RF18, after attempting to place C Heater Drain Pump (HDP), the first of three, into service. After starting, C HDP tripped for a reason not yet verified. Subsequently, based on initial Control Room operator observations, the Steam Generator #1 Main Feedwater control valve position was observed to be at 10-20% open, but with an open position demand signal of 100%. Main Feedwater response to the reactor trip (Reactor Trip Override) was as expected. The NRC Resident Inspector has been informed.
The original reactor power level stated in the report should be 91% in lieu of 84.5%. This information has been changed in the event heading. The licensee notified the NRC Resident Inspector. Notified R4DO (Werner). |
Where | |
---|---|
Waterford Louisiana (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:+-1.93 h-0.0804 days <br />-0.0115 weeks <br />-0.00264 months <br />) | |
Opened: | Joe Williams 19:55 Jan 21, 2013 |
NRC Officer: | Charles Teal |
Last Updated: | Mar 7, 2013 |
48687 - NRC Website | |
Unit 3 | |
---|---|
Reactor critical | Critical |
Scram | A/R |
Before | Power Operation (91 %) |
After | Hot Standby (0 %) |
Waterford with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 570322024-03-16T19:49:00016 March 2024 19:49:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Main Feedwater and Main Steam Isolations ENS 559632022-06-25T01:12:00025 June 2022 01:12:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Main Steam Isolation Valve Closure ENS 554362021-08-29T23:04:00029 August 2021 23:04:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Safety System Actuation ENS 549782020-11-02T10:19:0002 November 2020 10:19:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Control Element Drive Mechanism Control System Timer Failure ENS 540682019-05-16T18:48:00016 May 2019 18:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Turbine Trip ENS 528632017-07-17T21:17:00017 July 2017 21:17:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unusual Event Declared Due to Loss of Offsite Power ENS 514472015-10-04T04:07:0004 October 2015 04:07:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip ENS 511162015-06-03T22:05:0003 June 2015 22:05:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Loss of Main Feedwater Pump ENS 486872013-01-21T21:51:00021 January 2013 21:51:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Low Steam Generator Level ENS 454452009-10-19T14:44:00019 October 2009 14:44:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Following Stuck Open Moisture Separator Heater Relief Valve ENS 421382005-11-12T02:34:00012 November 2005 02:34:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip After Loss of All Condenser Circulating Water Pumps 2024-03-16T19:49:00 | |