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ENS 53819
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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
At 1034 EST on January 9, 2019, with the r … At 1034 EST on January 9, 2019, with the reactor at 100% power, an automatic reactor trip was initiated. The trip occurred while Reactor Protection System testing was in progress. The trip was uncomplicated with all systems responding normally following the rip. Troubleshooting and investigation of the cause is ongoing. </br>All full-length control rods inserted fully. Auxiliary Feedwater System actuated as designed in response to low steam generator water levels. Operations stabilized the plant in Mode 3 (hot standby). Decay heat is being removed by the turbine bypass valve. </br>This condition has no impact to the health and safety of the public.</br>The licensee notified the NRC Resident Inspector.ensee notified the NRC Resident Inspector.  +
Discovered date
05:00:00, 9 January 2019  +
ENS id number
53,819  +
Emergency class
Non Emergency +
Entered date
13:23:00, 9 January 2019  +
Equipment trip
Reactor Trip +
Event date
05:00:00, 9 January 2019  +
Event description
At 1034 EST on January 9, 2019, with the r … At 1034 EST on January 9, 2019, with the reactor at 100% power, an automatic reactor trip was initiated. The trip occurred while Reactor Protection System testing was in progress. The trip was uncomplicated with all systems responding normally following the rip. Troubleshooting and investigation of the cause is ongoing. </br>All full-length control rods inserted fully. Auxiliary Feedwater System actuated as designed in response to low steam generator water levels. Operations stabilized the plant in Mode 3 (hot standby). Decay heat is being removed by the turbine bypass valve. </br>This condition has no impact to the health and safety of the public.</br>The licensee notified the NRC Resident Inspector.ensee notified the NRC Resident Inspector.  +
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ENS 53819 +, ENS 53819 +, ENS 53819 +, ENS 53819 +, ENS 53819 +, ENS 53819 +, ENS 53819 +, ENS 53819 +, ENS 53819 +, ENS 53819 +, ENS 53819 +, ENS 53819 +, ENS 53819 +  and ENS 53819 +
Initial power
100  +
Initial reactor mode
Power Operation +
LER
05000255/LER-2019-002, Automatic Reactor Trip and AFW System Actuation Due to the Loss of Power to the RPS Bd Matrix +  and Automatic Reactor Trip and AFW System Actuation Due to the Loss of Power to the RPS Bd Matrix +
Last update date
00:00:00, 9 January 2019  +
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>.
12:30:06, 10 January 2019  +
NRC officer
Karl Diederich +
Notification date
13:23:00, 9 January 2019  +
Originated by
Dan Geerlings +
Reactor critical
true  +
Region
NRC Region 3 +
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
0.349 d (8.38 hours, 0.0499 weeks, 0.0115 months)  +
Scram
Automatic Scram +
Site
Palisades +
Start date
05:00:00, 9 January 2019  +
State
Michigan +
System
Steam Generator +, Reactor Protection System +, Auxiliary Feedwater +  and Control Rod +
Title
Reactor Trip from Full Power Due to Rps Testing  +
Turbine component
Turbine bypass 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.
https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2019/20190110en.html#en53819  +
Unit
1  +
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