ENS 43613: Difference between revisions

v t e ENS Event
07:14 Sep 3, 2007
Title	Manual Reactor Scram Due to Electro-Hydraulic Control (Ehc) System Leak
Event Description	At 0214 [CDT] on 09/03/2007 with Unit 1 at 100% power a core flow runback and manual reactor scram were initiated due to a Electro-Hydraulic Control (EHC) System leak. Units 2 and 3 were also at 100% power and were unaffected by the event. As expected reactor water level momentarily lowered below +2 inches (Reactor Low Water Level) and all appropriate PCIS [Primary Containment Isolation System] isolations, Group 2 (RHR Shutdown Cooling). Group 3 (RWCU), Group 6 (Ventilation), and Group 8 (TIP) were received along with the auto start of CREVs [Control Room Emergency Ventilation] and 3 SBGT trains. This event is reportable as a 4-hour and 8-hour non-emergency notification along with a 60-day written report in accordance with 10 CFR 50.72(b)(2)(iv)(B), 10 CFR 50 72(b)(3)(iv)(A) and 10 CFR 50.73(a)(2)(iv)(A) as 'any event or condition that results in valid actuation of RPS or PCIS.' All control rods fully inserted, the electrical grid is stable, the EDGs and ESF systems remain available, and decay heat is being removed via the Turbine Bypass Valves and reactor water level is being controlled by the Reactor Feedwater System. The licensee notified the NRC Resident Inspector. Investigation into the cause of the leak is ongoing. * * UPDATE FROM DON SMITH TO HUFFMAN AT 1357 EDT ON 9/05/07 * * * The Unit 2 Refuel Zone Inboard Exhaust Damper, 2-FCO-64-10, failed to indicate closed in the Control Room at Panel 2-9-25 in response to the Group 6 isolation signal received during the Unit 1 Reactor SCRAM on 09/03/2007 at 0214 CDT as required by the plant design. The damper was physically verified to be open. The Unit 2 Refuel Zone Outboard Exhaust Damper, 2-FCO-64-09 automatically isolated as designed in response to the Group 6 isolation signal fulfilling its Safety Function, was verified closed and was later tagged closed as required by Technical Specifications. Investigation into the cause of the failure of the 2-FCO-64-10 is ongoing. The licensee notified the NRC Resident Inspector. R2DO ( Ernstes) notified.

ENS 43613 +/-
Where
Browns Ferry Alabama (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:+-2.15 h-0.0896 days <br />-0.0128 weeks <br />-0.00295 months <br />)
Opened:	Matthew Rasmussen 05:05 Sep 3, 2007
NRC Officer:	Jason Kozal
Last Updated:	Sep 5, 2007
43613 - 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 43613\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\u003EManual Reactor Scram Due to Electro-Hydraulic Control (Ehc) System Leak\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 43613 - 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)(2)(iv)(B), RPS System Actuation, 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 = 09/03/2007 02:14 CDT
 | last update date = 09/05/2007
-| title = Manual Reactor Scram Due To Electro-Hydraulic Control (Ehc) System Leak
+| title = Manual Reactor Scram Due to Electro-Hydraulic Control (Ehc) System Leak
 | event text = At 0214 [CDT] on 09/03/2007 with Unit 1 at 100% power a core flow runback and manual reactor scram were initiated due to a Electro-Hydraulic Control (EHC) System leak. Units 2 and 3 were also at 100% power and were unaffected by the event. As expected reactor water level momentarily lowered below +2 inches (Reactor Low Water Level) and all appropriate PCIS [Primary Containment Isolation System] isolations, Group 2 (RHR Shutdown Cooling). Group 3 (RWCU), Group 6 (Ventilation), and Group 8 (TIP) were received along with the auto start of CREVs [Control Room Emergency Ventilation] and 3 SBGT trains.
 This event is reportable as a 4-hour and 8-hour non-emergency notification along with a 60-day written report in accordance with 10 CFR 50.72(b)(2)(iv)(B), 10 CFR 50 72(b)(3)(iv)(A) and 10 CFR 50.73(a)(2)(iv)(A) as 'any event or condition that results in valid actuation of RPS or PCIS.'

v t e Unit 1
GE-4
Reactor critical	Critical
Scram	Yes, Manual Scram
Before	Power Operation (100 %)
After	Hot Shutdown (0 %)

ENS 43613: Difference between revisions

Latest revision as of 22:16, 1 March 2018

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ENS 43613: Difference between revisions

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