ENS 43457: Difference between revisions

From kanterella

Latest revision as of 22:16, 1 March 2018

v t e ENS Event
00:17 Jun 29, 2007
Title	Reactor Trip Due to Condensate Pump Trip
Event Description	Reactor trip at 1717 hrs PDT due to [condensate pump] COND-P-2B trip. Reactor power was at 70% with [condensate pump] COND-P-2A secured. Reactor vessel level reached -50 inches and was restored with High Pressure Core Spray and Reactor Core Isolation Cooling. Main Steam Isolation Valves closed as expected due to the reaching -50 inches. All systems operated as expected. Further investigation into COND-P-2B trip is underway. Plant is stable in mode three, heat removal is being maintained by RHR-P-2B and Safety Relief Valves. All rods fully inserted on the automatic reactor scram. All safety systems were available at the time of the trip. The trip was considered uncomplicated. The reactor pressure is currently being maintained between 500 to 600 psi and water level between 60 to 80 inches. The licensee was at 70% power at the time of the trip due to maintenance of condensate pump P-2A. The licensee will notify the NRC Resident Inspector.

ENS 43457 +/-
Where
Columbia Generating Station Washington (NRC Region 4)
Reporting

10 CFR 50.72(b)(2)(iv)(B), RPS Actuation
LER:	05000397/LER-2007-004
Time - Person (Reporting Time:+-2.4 h-0.1 days <br />-0.0143 weeks <br />-0.00329 months <br />)
Opened:	Mike Ferry 21:53 Jun 28, 2007
NRC Officer:	Bill Huffman
Last Updated:	Jun 28, 2007
43457 - 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 43457\u003C/a\u003E - \u003Ca href=\"/Columbia\" title=\"Columbia\"\u003EColumbia\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003EReactor Trip Due to Condensate Pump Trip\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 43457 - Columbia\n","link":"","lat":46.55068333333333,"lon":-119.488975,"icon":"/w/images/7/7c/Energy_Northwest_icon.png"}],"imageoverlays":null}
v • d • e

v t e Emergency Notification System
Columbia with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation
WEEKMONTHYEAR2018-05-18T13:51:00 [Table view]
[ENS list for Columbia]

@@ Line 16: / Line 16: @@
 | event date = 06/28/2007 17:17 PDT
 | last update date = 06/28/2007
-| title = Reactor Trip Due To Condensate Pump Trip
+| title = Reactor Trip Due to Condensate Pump Trip
 | event text = Reactor trip at 1717 hrs PDT due to [condensate pump] COND-P-2B trip.  Reactor power was at 70% with [condensate pump] COND-P-2A secured.  Reactor vessel level reached -50 inches and was restored with High Pressure Core Spray and Reactor Core Isolation Cooling.   Main Steam Isolation Valves closed as expected due to the reaching -50 inches.  All systems operated as expected.  Further investigation into COND-P-2B trip is underway.  Plant is stable in mode three, heat removal is being maintained by RHR-P-2B and Safety Relief Valves.
 All rods fully inserted on the automatic reactor scram.  All safety systems were available at the time of the trip. The trip was considered uncomplicated.   The reactor pressure is currently being maintained between  500 to 600 psi  and water level between 60 to 80 inches.  The licensee was at 70% power at the time of the trip due to maintenance of condensate pump P-2A.