ENS 42138
ENS Event | |
|---|---|
02:34 Nov 12, 2005 | |
| Title | Manual Reactor Trip After Loss of All Condenser Circulating Water Pumps |
| Event Description | Waterford 3 manually tripped the reactor at 20:34 [CST] on 11/11/05 due to lowering main condenser vacuum caused by a loss of all circ water pumps. Subsequently an Emergency Feedwater Actuation Signal (EFAS) was received due to low steam generator levels. The plant is currently being maintained in mode 3 with both Steam Generators being fed from the Auxiliary Feedwater system with Steam Generator levels in the normal operational band for mode 3. The EFAS has been reset. The plant will be maintained in Mode 3 while a Post Trip Review is performed. This report is submitted as required by 10CFR50.72.
All control rods fully inserted on the manual trip. The main steam isolation valves are shut and the heat sink is through the atmospheric dump valves. The electrical grid is stable and plant power is from the startup transformer. No primary or secondary relief valves or safety valves lifted. The site was able to restart the B & D circ water pumps. There is no significant steam generator tube leakage. The licensee notified the NRC Resident Inspector.
This notification is an update to an immediate notification that was called into the NRC Operations Center at 04:48 (eastern time) on November 12, 2005 (Event # 42138). The event was reported as an 8-hour event. This update to the original notification is to communicate that, based on further review, the event notification should have been made within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> since it was reportable within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> as well as the 8-hour reporting criteria and therefore the call should have been made within the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> period. The condition is reportable under four hour reporting criteria 50.72(b)(2)(iv)(B) for a manual trip of the plant in anticipation of receiving a RPS Trip with the Reactor critical. The condition is reportable within eight hour reporting criteria 50.72(b)(3)(iv)(A) for the automatic actuation of EFAS upon low steam generator levels. This update does not report a change to the event description reported. As mentioned in the original report, Waterford 3 manually tripped the reactor at 20:34 on November 11, 2005 due to lowering main condenser vacuum caused by a loss of all circulating water pumps. Subsequently an Emergency Feedwater Actuation Signal (EFAS) was received due to low steam generator levels. The plant was then maintained in Mode 3 with both steam generators being fed from the Auxiliary Feedwater System with steam generator levels in the normal operational band for Mode 3. The EFAS had been reset at the time of the original notification. The plant was maintained in Mode 3 while a Post Trip Review was performed. Further details of the event will be reported under the 60 day LER reporting criteria. The licensee notified the NRC Resident Inspector. R4DO (Clark) notified. |
| Where | |
|---|---|
Waterford  Louisiana (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+2.23 h0.0929 days <br />0.0133 weeks <br />0.00305 months <br />) | |
| Opened: | Paul Wood 04:48 Nov 12, 2005 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Nov 14, 2005 |
| 42138 - NRC Website | |
Unit 3 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (100 %) |
| 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 | |