ENS 54198
From kanterella
Revision as of 07:30, 6 August 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
ENS Event | |
|---|---|
23:47 Aug 3, 2019 | |
| Title | Manual Reactor Trip and Manual Actuation of Reactor Core Isolation Cooling |
| Event Description | At 1947 [EDT] on 8/3/19, with Hope Creek in Mode 1 at 37 percent power, the reactor was manually scrammed due to loss of condenser vacuum. All control rods fully inserted into the core. All safety systems responded as designed and expected. Reactor level was stabilized using Reactor Core Isolation Cooling (RCIC) and Reactor Feedwater Pumps.
Currently reactor water level is being maintained by the feedwater system and decay heat is being removed by the main condenser using the main turbine bypass valves. Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). Due to the manual actuation of RCIC, this event is also being reported as an eight-hour, non-emergency notification per 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 has been notified. The plant is in its normal shutdown electrical lineup with all safe shutdown equipment available. The licensee will be notifying the state of Delaware, state of New Jersey and the Lower Alloway Creek township. |
| Where | |
|---|---|
Hope Creek  New Jersey (NRC Region 1) | |
| 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:+-0.23 h-0.00958 days <br />-0.00137 weeks <br />-3.15054e-4 months <br />) | |
| Opened: | Steven Bier 23:33 Aug 3, 2019 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Aug 4, 2019 |
| 54198 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (37 %) |
| After | Hot Shutdown (0 %) |
Hope Creek with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 568892023-12-15T00:39:00015 December 2023 00:39:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram ENS 541982019-08-03T23:47:0003 August 2019 23:47:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip and Manual Actuation of Reactor Core Isolation Cooling ENS 523472016-11-05T08:04:0005 November 2016 08:04:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of Rps While Reactor Shutdown ENS 514302015-09-29T00:46:00029 September 2015 00:46:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Following Trip of Both Reactor Recirculation Pumps ENS 496082013-12-05T08:25:0005 December 2013 08:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Following Turbine Trip on High Moisture Separator Level ENS 495922013-12-01T11:13:0001 December 2013 11:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to Main Turbine Trip ENS 491082013-06-12T17:33:00012 June 2013 17:33:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Circulating Water Pump Trip Leads to Reactor Scram ENS 450742009-05-17T07:35:00017 May 2009 07:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Loss of Scram Air Header ENS 450162009-04-23T13:10:00023 April 2009 13:10:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Actuation of Auto Load Sequencer During Fast Bus Transfer Testing ENS 437532007-10-29T02:03:00029 October 2007 02:03:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Refuel Floor Exhaust Hi-Hi Radiation Alarms During Reactor Reassembly ENS 433952007-05-29T12:35:00029 May 2007 12:35:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Manual Reactor Scram Due to Loss of Feed Pumps After Electrical Transient ENS 431322007-01-30T04:10:00030 January 2007 04:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram on Low Reactor Pressure Vessel (Rpv) Water Level ENS 411102004-10-11T01:53:00011 October 2004 01:53:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation a Rps Actuation Signal Occurred Due to Low Reactor Water Level While in Mode 3 ENS 411092004-10-10T22:14:00010 October 2004 22:14:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Manual Reactor Scram Due to a Steam Leak in the Turbine Building ENS 410942004-10-05T17:34:0005 October 2004 17:34:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertent Undervoltage Condition Initated Diesel Load Sequencer, Etc. Diesel Did Not Start. ENS 404372004-01-12T15:48:00012 January 2004 15:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Scram Following Invalid Containment Isolation Signal ENS 403782003-12-06T04:49:0006 December 2003 04:49:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation a Level 3 Low Reactor Water Level Was Reached During a Reactor Water Level Transient ENS 402242003-10-04T21:13:0004 October 2003 21:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Rps Actuation While Critical 2023-12-15T00:39:00 | |
Retrieved from "https://kanterella.com/w/index.php?title=ENS_54198&oldid=1871152"