ENS 53374
From kanterella
Jump to navigation
Jump to search
ENS Event | |
---|---|
20:51 May 1, 2018 | |
Title | Plant Received Division One Reactor Pressure Vessel Level 1 Signal |
Event Description | At 1551 hrs [CDT] on 5/1/2018, with the plant in Mode 5, a division one Reactor Pressure Vessel (RPV) Level 1 signal was received; however there was no actual change in RPV level. RPV Level remained at High Water Level supporting refuel operations. This caused an actuation of division one Load Shed and Sequencing system that shed and then re-energized the 15 bus. Division one diesel generator started from standby. Residual Heat Removal pump 'A', which was in shutdown cooling mode, was lost during the bus shed, and was re-sequenced upon re-energization of the 15 bus. Upon restoration of shutdown cooling, the RHR pump discharged into the RPV. RCS temperature increased approximately 5 degrees Fahrenheit as a result of the loss of shutdown cooling. The cause of the actuation signal is under investigation.
In accordance with NUREG 1022, Event Reporting Guidelines, this event is conservatively reported under 10 CFR 50.72(b)(2)(iv)(A) as an event that results in emergency core cooling system discharge into the RCS as a result of a valid signal, under 10 CFR 50.72(b)(3)(iv)(B)(8) as an event that results in the actuation of emergency ac electrical power systems, and under 10 CFR 50.72(b)(3)(v)(B) as an event or condition that at the time of discovery could have prevented the fulfillment of a safety function (remove residual heat). The licensee notified the NRC Resident Inspector. |
Where | |
---|---|
Grand Gulf ![]() Mississippi (NRC Region 4) | |
Reporting | |
10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge 10 CFR 50.72(b)(3)(iv)(A), System Actuation 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat | |
Time - Person (Reporting Time:+-0.15 h-0.00625 days <br />-8.928571e-4 weeks <br />-2.0547e-4 months <br />) | |
Opened: | Brandon Starnes 20:42 May 1, 2018 |
NRC Officer: | Dong Park |
Last Updated: | May 1, 2018 |
53374 - NRC Website
Loading map... {"minzoom":false,"maxzoom":false,"mappingservice":"leaflet","width":"350px","height":"250px","centre":false,"title":"","label":"","icon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"zoom":6,"defzoom":14,"layers":["OpenStreetMap"],"image layers":[],"overlays":[],"resizable":false,"fullscreen":false,"scrollwheelzoom":true,"cluster":false,"clustermaxzoom":20,"clusterzoomonclick":true,"clustermaxradius":80,"clusterspiderfy":true,"geojson":"","clicktarget":"","imageLayers":[],"locations":[{"text":"\u003Cb\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003E\u003Ca class=\"mw-selflink selflink\"\u003EENS 53374\u003C/a\u003E - \u003Ca href=\"/Grand_Gulf\" title=\"Grand Gulf\"\u003EGrand Gulf\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003EPlant Received Division One Reactor Pressure Vessel Level 1 Signal\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 53374 - Grand Gulf\n","link":"","lat":32.009233333333334,"lon":-91.04695833333334,"icon":"/w/images/7/79/Entergy_icon.png"}],"imageoverlays":null} | |
Grand Gulf ![]() | |
WEEKMONTHYEARENS 570532024-03-26T16:15:00026 March 2024 16:15:00
[Table view]10 CFR 50.72(b)(3)(iv)(A), System Actuation Actuation of Reactor Protection System ENS 568942023-12-16T09:50:00016 December 2023 09:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Scram Due to Turbine Trip ENS 562822022-12-20T03:01:00020 December 2022 03:01:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Scram Due to Loss of Feedwater Pump ENS 559732022-06-30T19:45:00030 June 2022 19:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Scram Due to Loss of Transformer ENS 540622019-05-12T15:39:00012 May 2019 15:39:00 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)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Reactor Scram Due to Partial Loss of Service Water ENS 538942019-02-23T20:58:00023 February 2019 20:58:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram After Turbine Control Valve Fast Closure ENS 537882018-12-12T06:00:00012 December 2018 06:00:00 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 En Revision Imported Date 12/17/2018 ENS 533992018-05-12T04:27:00012 May 2018 04:27:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertent Actuation of the Emergency Diesel Generator ENS 533742018-05-01T20:51:0001 May 2018 20:51:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Plant Received Division One Reactor Pressure Vessel Level 1 Signal ENS 531882018-01-31T00:22:00031 January 2018 00:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Main Turbine Load Oscillations ENS 531152017-12-12T15:18:00012 December 2017 15:18:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start of Edg Due to Loss of Esf Transformer ENS 526632017-04-04T05:10:0004 April 2017 05:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Condensate Leak ENS 520572016-06-30T22:15:00030 June 2016 22:15:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Multiple Valid Specified System Actuations Due to Loss of Service Transformer 21 ENS 520442016-06-25T19:07:00025 June 2016 19:07:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to Turbine Trip ENS 520122016-06-17T07:57:00017 June 2016 07:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram During Testing ENS 518272016-03-29T16:23:00029 March 2016 16:23:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scram Due to Turbine Trip ENS 518002016-03-17T20:15:00017 March 2016 20:15:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Engineered Safety Feature System Actuation Due to Lightning Strike ENS 499202014-03-17T10:14:00017 March 2014 10:14:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Steam Leak in Low Pressure Turbine Line ENS 492252013-07-30T19:32:00030 July 2013 19:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scram Due to Turbine Generator Trip ENS 477982012-04-02T20:11:0002 April 2012 20:11:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Autostart of Division 3 Diesel Generator Following 4160 Volt Line Outage ENS 476792012-02-20T01:04:00020 February 2012 01:04:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram During Shutdown Due to Lowering Reactor Vessel Water Level (Rvwl) ENS 450442009-05-06T04:27:0006 May 2009 04:27:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Auto-Start and Loading of Emergency Diesel Generator to Safety Bus Due to Undervoltage Condition ENS 446012008-10-26T16:25:00026 October 2008 16:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram and Isolation Due to Turbine Trip ENS 445952008-10-23T12:20:00023 October 2008 12:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram with Manual Rcic Initiation ENS 438992008-01-12T22:26:00012 January 2008 22:26:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Degraded Cooling to Main Transformers ENS 433762007-05-19T16:27:00019 May 2007 16:27:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scram Due to Turbine Trip on Loss of Condenser Vacuum ENS 414052005-02-12T01:59:00012 February 2005 01:59:00 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 Rps Actuation 2024-03-26T16:15:00 | |
Retrieved from "https://kanterella.com/w/index.php?title=ENS_53374&oldid=621973"