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ENS 50012
Show incoming properties 
Category
ENS Notification  and Power Reactor
Agency
Lower Alloways Creek Township +
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
This 4 and 8 hour notification is being ma … This 4 and 8 hour notification is being made to report that Salem Unit 1 has performed an unplanned manual reactor trip and subsequent Auxiliary Feedwater system actuation. The trip was initiated due to loss of Steam Generator water level (SGWL) following the loss of one of the running SGFPs (#11 Steam Generator Feed Pump). The reactor was manually tripped prior to reaching the automatic SGWL low setpoints. #11/12/13 Aux Feedwater Pumps automatically started following the reactor trip on low Steam Generator water level.</br>Salem Unit 1 is currently in Mode 3. Reactor Coolant system pressure is at 2235 PSIG and temperature is 547 degrees Fahrenheit with decay heat removal via the Main Steam Dumps and Auxiliary Feedwater Systems. Unit 1 has no active shutdown technical specification action statements in effect. All control rods inserted on the reactor trip. All ECCS (Emergency Core Cooling System) and ESF (Engineered Safety Feature) systems functioned as expected.</br>There was no major primary or secondary equipment tagged for maintenance prior to this event. No personnel were injured during this event.</br>The licensee will inform the Lower Alloways Creek Township and the NRC Resident Inspector.k Township and the NRC Resident Inspector.  +
Discovered date
01:14:00, 9 April 2014  +
ENS id number
50,012  +
Emergency class
Non Emergency +
Entered date
23:13:00, 8 April 2014  +
Equipment trip
Reactor Trip +
Event date
01:14:00, 9 April 2014  +
Event description
This 4 and 8 hour notification is being ma … This 4 and 8 hour notification is being made to report that Salem Unit 1 has performed an unplanned manual reactor trip and subsequent Auxiliary Feedwater system actuation. The trip was initiated due to loss of Steam Generator water level (SGWL) following the loss of one of the running SGFPs (#11 Steam Generator Feed Pump). The reactor was manually tripped prior to reaching the automatic SGWL low setpoints. #11/12/13 Aux Feedwater Pumps automatically started following the reactor trip on low Steam Generator water level.</br>Salem Unit 1 is currently in Mode 3. Reactor Coolant system pressure is at 2235 PSIG and temperature is 547 degrees Fahrenheit with decay heat removal via the Main Steam Dumps and Auxiliary Feedwater Systems. Unit 1 has no active shutdown technical specification action statements in effect. All control rods inserted on the reactor trip. All ECCS (Emergency Core Cooling System) and ESF (Engineered Safety Feature) systems functioned as expected.</br>There was no major primary or secondary equipment tagged for maintenance prior to this event. No personnel were injured during this event.</br>The licensee will inform the Lower Alloways Creek Township and the NRC Resident Inspector.k Township and the NRC Resident Inspector.  +
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ENS 50012 +, ENS 50012 +, ENS 50012 +, ENS 50012 +, ENS 50012 +, ENS 50012 +, ENS 50012 +, ENS 50012 +, ENS 50012 +, ENS 50012 +, ENS 50012 +, ENS 50012 +, ENS 50012 +, ENS 50012 +  and ENS 50012 +
Hours
9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +
Initial power
100  +
Initial reactor mode
Power Operation +
Last update date
00:00:00, 8 April 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>.
01:51:09, 2 March 2018  +
NRC officer
Steve Sandin +
Notification date
23:13:00, 8 April 2014  +
Originated by
William Muffley +
Reactor critical
true  +
Reactor scram
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
-0.0842 d (-2.02 hours, -0.012 weeks, -0.00277 months)  +
Scram
Manual Scram +
Site
Salem +
Start date
01:14:00, 9 April 2014  +
State
New Jersey +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Decay Heat Removal +, Control Rod +  and Main Steam +
Title
Unit 1 Manually Tripped Following the Loss of an Operating Steam Generator Feed Pump (Sgfp)  +
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/2014/20140409en.html#en50012  +
Unit
1  +
 
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