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ENS 49260
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Category
ENS Notification  and Power Reactor
CFR
10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation +  and 10 CFR 50.72(b)(3)(iv)(A), System Actuation +
Current power
0  +
Current reactor mode
Hot Standby +
Description
The loss of a non-vital 480v bus resulted … The loss of a non-vital 480v bus resulted in a feedwater transient that caused steam generator water level to lower below the automatic reactor trip setpoint. The reactor trip and plant response was uncomplicated with all rods being inserted into the core.</br>The auxiliary feedwater system automatically actuated and is currently being to used to feed the steam generators. Decay heat is being removed via the steam dumps to the condenser. No relief valves or safeties lifted during the transient. The plant is currently stable in Mode 3 at normal operating pressure and temperature and is in its normal shutdown electrical lineup. There was no impact on Unit 2 which is currently operating at 100% power.</br>The licensee has notified state and local authorities and the NRC Resident Inspector.uthorities and the NRC Resident Inspector.  +
Discovered date
01:19:00, 10 August 2013  +
ENS id number
49,260  +
Emergency class
Non Emergency +
Entered date
22:27:00, 9 August 2013  +
Equipment trip
Reactor Trip +
Event date
01:19:00, 10 August 2013  +
Event description
The loss of a non-vital 480v bus resulted … The loss of a non-vital 480v bus resulted in a feedwater transient that caused steam generator water level to lower below the automatic reactor trip setpoint. The reactor trip and plant response was uncomplicated with all rods being inserted into the core.</br>The auxiliary feedwater system automatically actuated and is currently being to used to feed the steam generators. Decay heat is being removed via the steam dumps to the condenser. No relief valves or safeties lifted during the transient. The plant is currently stable in Mode 3 at normal operating pressure and temperature and is in its normal shutdown electrical lineup. There was no impact on Unit 2 which is currently operating at 100% power.</br>The licensee has notified state and local authorities and the NRC Resident Inspector.uthorities and the NRC Resident Inspector.  +
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ENS 49260 +, ENS 49260 +, ENS 49260 +, ENS 49260 +, ENS 49260 +, ENS 49260 +, ENS 49260 +, ENS 49260 +, ENS 49260 +, ENS 49260 +, ENS 49260 +, ENS 49260 +, ENS 49260 +  and ENS 49260 +
Initial power
100  +
Initial reactor mode
Power Operation +
LER
05000423/LER-2013-007, Reactor Trip on Low-Low Steam Generator Level +  and Reactor Trip on Low-Low Steam Generator Level +
Last update date
00:00:00, 9 August 2013  +
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
02:00:19, 2 March 2018  +
NRC officer
Howie Crouch +
Notification date
22:27:00, 9 August 2013  +
Originated by
Michel Ciccone +
Reactor critical
true  +
Reactor type
Westinghouse PWR 4-Loop +
Region
NRC Region 1 +
Reporting criterion
10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation +  and 10 CFR 50.72(b)(3)(iv)(A), System Actuation +
Reporting time
-0.12 d (-2.87 hours, -0.0171 weeks, -0.00393 months)  +
Scram
Automatic Scram +
Site
Millstone +
Start date
01:19:00, 10 August 2013  +
State
Connecticut +
System
Steam Generator +, Feedwater +  and Auxiliary Feedwater +
Title
Automatic Reactor Trip on Low Steam Generator Water Level  +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://www.nrc.gov/reading-rm/doc-collections/event-status/event/2013/20130812en.html#en49260  +
Unit
3  +
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