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ENS 40286
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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
Automatic Reactor Trip due to low Steam Ge … Automatic Reactor Trip due to low Steam Generator levels. All systems responded normally. Plant is stable at NOT/NOP (normal operating temperature and pressure) in Mode 3. Emergency Feedwater system actuated as designed due to reactor trip.</br>Lowest Steam Generator level reached was just below the trip setpoint of 25%. Low level caused by trip of one of two Main Feed Pumps. All control rods fully inserted. No primary or secondary relief valves lifted. The electrical system is stable and the EDG's remain in standby. Decay heat is being removed via steam dumps. </br>The licensee has notified the NRC Resident Inspector.e has notified the NRC Resident Inspector.  +
Discovered date
00:48:00, 1 November 2003  +
ENS id number
40,286  +
Emergency class
Non Emergency +
Entered date
21:15:00, 31 October 2003  +
Equipment trip
Reactor Trip +
Event date
00:48:00, 1 November 2003  +
Event description
Automatic Reactor Trip due to low Steam Ge … Automatic Reactor Trip due to low Steam Generator levels. All systems responded normally. Plant is stable at NOT/NOP (normal operating temperature and pressure) in Mode 3. Emergency Feedwater system actuated as designed due to reactor trip.</br>Lowest Steam Generator level reached was just below the trip setpoint of 25%. Low level caused by trip of one of two Main Feed Pumps. All control rods fully inserted. No primary or secondary relief valves lifted. The electrical system is stable and the EDG's remain in standby. Decay heat is being removed via steam dumps. </br>The licensee has notified the NRC Resident Inspector.e has notified the NRC Resident Inspector.  +
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ENS 40286 +, ENS 40286 +, ENS 40286 +, ENS 40286 +, ENS 40286 +, ENS 40286 +, ENS 40286 +, ENS 40286 +, ENS 40286 +, ENS 40286 +, ENS 40286 +, ENS 40286 +, ENS 40286 +  and ENS 40286 +
Initial power
100  +
Initial reactor mode
Power Operation +
LER
05000443/LER-2003-002, Regarding Reactor Trip Following the Loss of a Main Feed Pump +  and Regarding Reactor Trip Following the Loss of a Main Feed Pump +
Last update date
00:00:00, 31 October 2003  +
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>.
02:24:52, 2 March 2018  +
NRC officer
Mike Ripley +
Notification date
21:15:00, 31 October 2003  +
Originated by
Tom Waechter +
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
-0.148 d (-3.55 hours, -0.0211 weeks, -0.00486 months)  +
Scram
Automatic Scram +
Site
Seabrook +
Start date
00:48:00, 1 November 2003  +
State
New Hampshire +
System
Steam Generator +, Control Rod +  and Emergency Feedwater System +
Title
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/2003/20031103en.html#en40286  +
Unit
1  +
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