ENS 40403: Difference between revisions

Latest revision as of 22:24, 1 March 2018

v t e ENS Event
14:49 Dec 20, 2003
Title	Rps Actuation Due to Loss of Turbine Generator Excitation
Event Description	On December 20, 2003, at 0949 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.610945e-4 months <br />, an automatic reactor trip occurred due to a loss of excitation of the turbine generator. All plant safety functions were maintained throughout the event. The plant was stabilized in Mode 3. All plant safety systems responded normally with the exception of the 2C Auxiliary Feedwater Pump (steam driven) which tripped on mechanical overspeed. The 2A and 2B Auxiliary Feedwater Pumps (electric driven) functioned normally to restore the 2A and 2B Steam Generator levels. Post trip system anomalies include RCS Letdown isolated, Steam Generator Blowdown isolation valves closed, Control Room ventilation system swapped to recirculation mode, and the Fuel Handling Building ventilation system swapped to the Shield Building. An Emergency Response Team has been formed to review these conditions prior to plant restart. This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) due to the automatic RPS Reactor Trip. All controls inserted properly. Decay heat is being removed using the turbine bypass valves. The Licensee notified the NRC Resident Inspector. * * UPDATE ON 1/08/04 @ 0625 B Y BRADY TO GOULD * * * This update is provided to include the 10CFR50.72(b)(3)(iv)(A) notification criterion for the auxiliary feedwater actuation. The NRC Resident Inspector was notified., Reg 2 RDO(Fredrickson) was informed.

ENS 40403 +/-
Where
Saint Lucie Florida (NRC Region 2)
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:+-1.82 h-0.0758 days <br />-0.0108 weeks <br />-0.00249 months <br />)
Opened:	Calvin Ward 13:00 Dec 20, 2003
NRC Officer:	Bill Gott
Last Updated:	Jan 8, 2004
40403 - 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 40403\u003C/a\u003E - \u003Ca href=\"/Saint_Lucie\" title=\"Saint Lucie\"\u003ESaint Lucie\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003ERps Actuation Due to Loss of Turbine Generator Excitation\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 40403 - Saint Lucie\n","link":"","lat":27.348672222222223,"lon":-80.24639722222223,"icon":"/w/images/9/9b/NextEra_Energy_icon.png"}],"imageoverlays":null}
v • d • e

v t e Emergency Notification System
Saint Lucie with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation
WEEKMONTHYEAR2024-06-04T17:52:00 [Table view]
[ENS list for Saint Lucie]

@@ Line 16: / Line 16: @@
 | event date = 12/20/2003 09:49 EST
 | last update date = 01/08/2004
-| title = Rps Actuation Due To Loss Of Turbine Generator Excitation
+| title = Rps Actuation Due to Loss of Turbine Generator Excitation
 | event text = On December 20, 2003, at 0949 hours, an automatic reactor trip occurred due to a loss of excitation of the turbine generator.  All plant safety functions were maintained throughout the event.  The plant was stabilized in Mode 3.  All plant safety systems responded normally with the exception of the 2C Auxiliary Feedwater Pump (steam driven) which tripped on mechanical overspeed.  The 2A and 2B Auxiliary Feedwater Pumps (electric driven) functioned normally to restore the 2A and 2B Steam Generator levels.  Post trip system anomalies include RCS Letdown isolated, Steam Generator Blowdown isolation valves closed, Control Room ventilation system swapped to recirculation mode, and the Fuel Handling Building ventilation system swapped to the Shield Building.  An Emergency Response Team has been formed to review these conditions prior to plant restart.  This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) due to the automatic RPS Reactor Trip.
 All controls inserted properly.  Decay heat is being removed using the turbine bypass valves.

v t e Unit 2
CE
Reactor critical	Critical
Scram	A/R
Before	Power Operation (100 %)
After	Hot Standby (0 %)

ENS 40403: Difference between revisions

Latest revision as of 22:24, 1 March 2018

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