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ENS 49698
Show incoming properties
Category
ENS Notification  and Power Reactor
CFR
10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation +, 10 CFR 50.72(b)(3)(iv)(A), System Actuation +, 10 CFR 50.72#b2ivB +  and 10 CFR 50.72#b3ivA +
Current power
0  +
Current reactor mode
Hot Standby +
Description
On January 6th, 2014 at 2115 EST Indian Po … On January 6th, 2014 at 2115 EST Indian Point Unit 3 experienced an Automatic Reactor Trip due to '33 Steam Generator Steam flow/Feed flow Mismatch.' Operators entered emergency procedure E-0, Reactor Trip or Safety Injection. All control rods fully inserted, all safety systems responded as expected, and off-site power remained in-service. No primary or secondary safety valves actuated due to the trip. This is reportable under 10CFR50.72(b)(2)(iv)(B). The main condenser is being used for heat sink. Unit 2 remains stable at 100% power.</br>The Auxiliary Feedwater System actuated following the automatic trip as expected. This is reportable under 10CFR50.72(b)(3)(iv)(A).</br>Investigation is underway to determine the cause of the 33 Steam Generator Mismatch condition.</br>The licensee will inform local and other government agencies and issue a press release. The licensee has informed the State of New York and the NRC Resident Inspector.f New York and the NRC Resident Inspector.  +
Discovered date
02:15:00, 7 January 2014  +
ENS id number
49,698  +
Emergency class
Non Emergency +
Entered date
21:55:00, 6 January 2014  +
Equipment trip
Reactor Trip +
Event date
02:15:00, 7 January 2014  +
Event description
On January 6th, 2014 at 2115 EST Indian Po … On January 6th, 2014 at 2115 EST Indian Point Unit 3 experienced an Automatic Reactor Trip due to '33 Steam Generator Steam flow/Feed flow Mismatch.' Operators entered emergency procedure E-0, Reactor Trip or Safety Injection. All control rods fully inserted, all safety systems responded as expected, and off-site power remained in-service. No primary or secondary safety valves actuated due to the trip. This is reportable under 10CFR50.72(b)(2)(iv)(B). The main condenser is being used for heat sink. Unit 2 remains stable at 100% power.</br>The Auxiliary Feedwater System actuated following the automatic trip as expected. This is reportable under 10CFR50.72(b)(3)(iv)(A).</br>Investigation is underway to determine the cause of the 33 Steam Generator Mismatch condition.</br>The licensee will inform local and other government agencies and issue a press release. The licensee has informed the State of New York and the NRC Resident Inspector.f New York and the NRC Resident Inspector.  +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
ENS 49698 +, ENS 49698 +, ENS 49698 +, ENS 49698 +, ENS 49698 +, ENS 49698 +, ENS 49698 +, ENS 49698 +, ENS 49698 +, ENS 49698 +, ENS 49698 +, ENS 49698 +, ENS 49698 +, ENS 49698 +  and ENS 49698 +
Initial power
100  +
Initial reactor mode
Power Operation +
Last update date
00:00:00, 6 January 2014  +
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>.
01:52:09, 2 March 2018  +
NRC officer
Steve Sandin +
Notification date
21:55:00, 6 January 2014  +
Originated by
George Keller +
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
-0.18 d (-4.33 hours, -0.0258 weeks, -0.00593 months)  +
Scram
Automatic Scram +
Site
Indian Point +
Start date
02:15:00, 7 January 2014  +
State
New York +
System
Steam Generator +, Feedwater +, Auxiliary Feedwater +, Main Condenser +  and Control Rod +
Title
Automatic Reactor Trip on Low Steam Generator Water Level Due to a Failed Main Feedwater Reg Valve  +
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/2014/20140107en.html#en49698  +
Unit
3  +
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