ENS 43900
From kanterella
Jump to navigation
Jump to search
ENS Event | |
|---|---|
10:21 Jan 13, 2008 | |
| Title | Manual Reactor Trip After Loss of Main Feedwater Pump |
| Event Description | Palisades Operations staff manually tripped the reactor in accordance with their station's Off-Normal Operating Procedure, after an automatic trip of the "B" Main Feedwater Pump (MFP). The cause of the MFP auto-trip is unknown and being investigated. During the trip, all systems performed as designed.
During the transient resulting from the trip, the atmospheric steam dump valves did open momentarily and properly reseated. There is no known primary-to-secondary leakage therefore no release was known to have occurred. All control rods inserted fully as a result of the trip. Auxiliary feedwater pump [AFW] 8A started, as expected, in response to low steam generator water levels experienced during the transient and supplied both steam generators. Decay heat is being removed via the main steam isolation valves to the condenser with the 8A AFW pump supplying feedwater to the steam generators. The plant is at normal temperatures and pressures for this mode. The electrical grid is stable with the station start-up transformer supplying station loads. The licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
Palisades  Michigan (NRC Region 3) | |
| 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:+-1.17 h-0.0488 days <br />-0.00696 weeks <br />-0.0016 months <br />) | |
| Opened: | Mike Mlynarek 09:11 Jan 13, 2008 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Jan 13, 2008 |
| 43900 - 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 43900\u003C/a\u003E - \u003Ca href=\"/Palisades\" title=\"Palisades\"\u003EPalisades\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003EManual Reactor Trip After Loss of Main Feedwater Pump\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 43900 - Palisades\n","link":"","lat":42.32339722222222,"lon":-86.31451666666666,"icon":"/w/images/7/79/Entergy_icon.png"}],"imageoverlays":null} | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Palisades with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 538192019-01-09T05:00:0009 January 2019 05:00:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip from Full Power Due to Rps Testing ENS 538132019-01-03T05:00:0003 January 2019 05:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Cycling of Turbine Governor Valve ENS 527642017-05-19T06:06:00019 May 2017 06:06:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Reactor Protection System Actuation While Shutdown ENS 513972015-09-16T05:17:00016 September 2015 05:17:00 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 475232011-12-14T20:10:00014 December 2011 20:10:00 Other Unspec Reqmnt, 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 Both Main Feedpumps ENS 472902011-09-25T19:06:00025 September 2011 19:06:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Loss of Two 120 Volt Ac Instrument Busses ENS 465642011-01-22T22:35:00022 January 2011 22:35:00 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 Loss of Generator Load ENS 442372008-05-23T16:49:00023 May 2008 16:49:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Possible Generator Lockout ENS 439002008-01-13T10:21:00013 January 2008 10:21:00 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 Main Feedwater Pump ENS 433512007-05-08T17:22:0008 May 2007 17:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Low Steam Generator Water Level ENS 425692006-05-11T19:14:00011 May 2006 19:14:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Actuation of Reactor Protection System Due to Failure of Control Rod to Withdraw ENS 425552006-05-04T21:50:0004 May 2006 21:50:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unexpected Reactor Protection System (Rps) Actuation During Testing ENS 419672005-09-01T14:25:0001 September 2005 14:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Main Generator Hydrogen Leak ENS 413192005-01-09T16:27:0009 January 2005 16:27:00 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 Lowering Main Condenser Vacuum ENS 410022004-08-31T11:18:00031 August 2004 11:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Rps Actuation Due to Fire in 2B Condensate Pump 2019-01-09T05:00:00 | |
Retrieved from "https://kanterella.com/w/index.php?title=ENS_43900&oldid=426602"