ENS 46805: Difference between revisions

Latest revision as of 22:07, 1 March 2018

v t e ENS Event
11:26 May 2, 2011
Title	Specified System Actuation Due to a Emergency Diesel Generator Output Breaker Trip
Event Description	At 0626 [CDT] on 05/2/2011, with BFN U1 in Mode 4, Browns Ferry Nuclear Plant, received an 'A' Emergency Diesel Generator output breaker trip for unknown reasons that de-energized the 'A' 4kV Shutdown Board, resulting in a loss of power to RPS 'A' and a subsequent half scram, 'B' CREV and 'B/C' SGT automatic initiation, and Primary Containment isolation for Groups 2, 3, 6 and 8. The PCIS isolation (Group 2) also caused a loss of Shutdown Cooling on U1 which was restored at 0723 following restoration of power to the 'A' 4kV Shutdown Board from offsite 161kV power. The general containment isolation signals affecting containment isolation valves in more than one system is reportable as an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification to the NRC IAW 10CFR50.72(b)(3)(iv), as any event or condition that results in a valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B), except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation. This is also reportable as 60 day written report IAW 10CFR50.73(a)(2)(iv). The NRC Resident [Inspector] has been notified of this event. This event was entered into the licensee's Corrective Action Program as PER# 362340.

ENS 46805 +/-
Where
Browns Ferry Alabama (NRC Region 2)
Reporting

10 CFR 50.72(b)(3)(iv)(A), System Actuation
Time - Person (Reporting Time:+0.03 h0.00125 days <br />1.785714e-4 weeks <br />4.1094e-5 months <br />)
Opened:	David Renn 11:28 May 2, 2011
NRC Officer:	Vince Klco
Last Updated:	May 2, 2011
46805 - 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 46805\u003C/a\u003E - \u003Ca href=\"/Browns_Ferry\" title=\"Browns Ferry\"\u003EBrowns Ferry\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003ESpecified System Actuation Due to a Emergency Diesel Generator Output Breaker Trip\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 46805 - Browns Ferry\n","link":"","lat":34.70418333333333,"lon":-87.11844722222222,"icon":"/w/images/c/ce/Tennessee_Valley_Authority_icon.png"}],"imageoverlays":null}
v • d • e

v t e Emergency Notification System
Browns Ferry with 10 CFR 50.72(b)(3)(iv)(A), System Actuation
WEEKMONTHYEAR2024-04-25T03:15:00 [Table view]
[ENS list for Browns Ferry]

@@ Line 16: / Line 16: @@
 | event date = 05/02/2011 06:26 CDT
 | last update date = 05/02/2011
-| title = Specified System Actuation Due To A Emergency Diesel Generator Output Breaker Trip
+| title = Specified System Actuation Due to a Emergency Diesel Generator Output Breaker Trip
 | event text = At 0626 [CDT] on 05/2/2011, with BFN U1 in Mode 4, Browns Ferry Nuclear Plant, received an 'A' Emergency Diesel Generator output breaker trip for unknown reasons that de-energized the 'A' 4kV Shutdown Board, resulting in a loss of power to RPS 'A' and a subsequent half scram, 'B' CREV and 'B/C' SGT automatic initiation, and Primary Containment isolation for Groups  2, 3, 6 and 8.  The PCIS isolation (Group 2) also caused a loss of Shutdown Cooling on U1 which was restored at 0723 following restoration of power to the 'A' 4kV Shutdown Board from offsite 161kV power.
 The general containment isolation signals affecting containment isolation valves in more than one system is reportable as an 8 hour notification to the NRC IAW 10CFR50.72(b)(3)(iv), as any event or condition that results in a valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B), except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.

Latest revision as of 22:07, 1 March 2018