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ENS 56585
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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
The following information was provided by … The following information was provided by the licensee via email:</br>At 1035, on June 22, 2023, with Unit 2 in Mode 1 at 100% power, the reactor automatically tripped due to `A' train reactor trip breaker and `B' train reactor trip bypass breaker opening during testing. The trip was not complex, with all systems responding normally post-trip. MST-021 (Reactor Protection Logic Train `B' At Power) testing was in progress at the time of trip. </br>Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves. </br>Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). </br>As a result of the reactor trip, emergency feedwater actuated; therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A).</br>There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. NRC Resident Inspector has been notified.  +
Discovered date
14:35:00, 22 June 2023  +
ENS id number
56,585  +
Emergency class
Non Emergency +
Entered date
13:50:00, 22 June 2023  +
Equipment trip
Reactor Trip +
Event date
14:35:00, 22 June 2023  +
Event description
The following information was provided by … The following information was provided by the licensee via email:</br>At 1035, on June 22, 2023, with Unit 2 in Mode 1 at 100% power, the reactor automatically tripped due to `A' train reactor trip breaker and `B' train reactor trip bypass breaker opening during testing. The trip was not complex, with all systems responding normally post-trip. MST-021 (Reactor Protection Logic Train `B' At Power) testing was in progress at the time of trip. </br>Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves. </br>Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). </br>As a result of the reactor trip, emergency feedwater actuated; therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A).</br>There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. NRC Resident Inspector has been notified.  +
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ENS 56585 +, ENS 56585 +, ENS 56585 +, ENS 56585 +, ENS 56585 +, ENS 56585 +, ENS 56585 +, ENS 56585 +, ENS 56585 +, ENS 56585 +, ENS 56585 +, ENS 56585 +, ENS 56585 +  and ENS 56585 +
Initial power
100  +
Initial reactor mode
Power Operation +
LER
05000261/LER-2023-002, Plant Trip During Reactor Protection System Testing +  and Plant Trip During Reactor Protection System Testing +
Last update date
00:00:00, 22 June 2023  +
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>.
19:57:54, 4 January 2024  +
NRC officer
Thomas Herrity +
Notification date
13:50:00, 22 June 2023  +
Originated by
Brant Sostak +
Procedure
MST-021 +
Reactor critical
true  +
Reactor type
Westinghouse PWR 3-Loop +
Region
NRC Region 2 +
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
-0.0313 d (-0.75 hours, -0.00446 weeks, -0.00103 months)  +
Scram
Automatic Scram +
Site
Robinson +
Start date
14:35:00, 22 June 2023  +
State
South Carolina +
System
Feedwater +, Reactor Protection System +  and Main Condenser +
Title
Automatic Reactor Trip Occured During Protection System 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/2023/20230626en.html#en56585  +
Unit
2  +
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