ENS 46801: Difference between revisions

v t e ENS Event
04:38 Apr 29, 2011
Title	Primary Containment Isolation System Actuation Due to Loss of Power from a Diesel Generator
Event Description	At 2338 [CDT] on 04/28/2011, with Browns Ferry Nuclear Unit 1 and Unit 2 in Mode 4, Browns Ferry Nuclear Plant, performed a shutdown of the Unit 1/2 Emergency Diesel Generator 'C,' due to an oil leak coming from its governor causing voltage and frequency fluctuations. Following securing of the Unit 1/2 Diesel Generator 'C,' the 4kV Shutdown Board 'C,' which was being powered by DG 'C,' de-energized. This resulted in a loss of power to the 1B RPS, causing a Primary Containment Isolation System (PCIS) actuation and the automatic initiation of the three trains of Standby Gas and 1 train of CREV [Control Room Emergency Ventilation System]. The PCIS isolation (Group 2) also caused a loss of Shutdown Cooling on Unit 1 which was restored at 0025 [CDT] 04/29/2011 . In addition, the loss of power to the 4kV Shutdown Board 'C.' also caused the loss of 2B RHR Pump, leading to a momentary suspension of shutdown cooling to Unit 2. Shutdown cooling was immediately restored to Unit 2 using the 2D RHR Pump at 2342 [CDT]. 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)(A), 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.' There were no new Technical Specification LCO's entered as a result of this event. This is also reportable as 60 day written report lAW 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 SR# 361382.

ENS 46801 +/-
Where
Browns Ferry Alabama (NRC Region 2)
Reporting

10 CFR 50.72(b)(3)(iv)(A), System Actuation
Time - Person (Reporting Time:+2.8 h0.117 days <br />0.0167 weeks <br />0.00384 months <br />)
Opened:	William Baker 07:26 Apr 29, 2011
NRC Officer:	Dong Park
Last Updated:	Apr 29, 2011
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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 = 04/28/2011 23:38 CDT
 | last update date = 04/29/2011
-| title = Primary Containment Isolation System Actuation Due To Loss Of Power From A Diesel Generator
+| title = Primary Containment Isolation System Actuation Due to Loss of Power from a Diesel Generator
 | event text = At 2338 [CDT] on 04/28/2011, with Browns Ferry Nuclear Unit 1 and Unit 2 in Mode 4, Browns Ferry Nuclear Plant, performed a shutdown of the Unit 1/2 Emergency Diesel Generator 'C,' due to an oil leak coming from its governor causing voltage and frequency fluctuations. Following securing of the Unit 1/2 Diesel Generator 'C,' the 4kV Shutdown Board 'C,' which was being powered by DG 'C,' de-energized. This resulted in a loss of power to the 1B RPS, causing a Primary Containment Isolation System (PCIS) actuation and the automatic initiation of the three trains of Standby Gas and 1 train of CREV [Control Room Emergency Ventilation System]. The PCIS isolation (Group 2) also caused a loss of Shutdown Cooling on Unit 1 which was restored at 0025 [CDT] 04/29/2011 .
 In addition, the loss of power to the 4kV Shutdown Board 'C.' also caused the loss of 2B RHR Pump, leading to a momentary suspension of shutdown cooling to Unit 2. Shutdown cooling was immediately restored to Unit 2 using the 2D RHR Pump at 2342 [CDT].

v t e Unit 1
GE-4
Reactor critical	Not Critical
Scram	No
Before	Cold Shutdown (0 %)
After	Cold Shutdown (0 %)

ENS 46801: Difference between revisions

Latest revision as of 22:07, 1 March 2018

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ENS 46801: Difference between revisions

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