ENS 49608
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ENS Event | |
|---|---|
08:25 Dec 5, 2013 | |
| Title | Automatic Reactor Scram Following Turbine Trip on High Moisture Separator Level |
| Event Description | While operating at 76% power on 12/5/13 at 0325 EST, the main turbine tripped on moisture separator hi level. The reactor scrammed along with the main turbine trip. All safety systems responded as designed and expected. There was no radiological release. There were no injuries.
During the scram, all rods inserted into the core. Plant is stable in Mode 3 in its normal S/D [shutdown] electrical line up. Decay heat is being removed via the turbine bypass valves dumping steam to the main condenser. At 0505 EST while securing from cooldown in an attempt to start a recirc pump, BPVs [Bypass Valve] opened causing reactor level swell and subsequent shrink. During this time, RPV [Reactor Pressure Vessel] level lowered to below RPV level 3 and caused a RPS [Reactor Protection System] actuation. RPV level was recovered and is now stable in normal band. The licensee has notified the NRC Resident Inspector.
This update to ENS #49608 adds reporting criterion 10CFR50.72(b)(3)(iv)(A) for the RPS actuation at 0505 EST during post-scram recovery. The licensee notified the NRC Resident Inspector and the Lower Alloways Creek township. The licensee will be making a press release. Notified R1DO (Cook). |
| 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 | |
| LER: | 05000354/LER-2013-009 |
| Time - Person (Reporting Time:+-2.75 h-0.115 days <br />-0.0164 weeks <br />-0.00377 months <br />) | |
| Opened: | Thomas Agster 05:40 Dec 5, 2013 |
| NRC Officer: | Dong Park |
| Last Updated: | Dec 5, 2013 |
| 49608 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (76 %) |
| 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 | |
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