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ENS 56813
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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 2159 on 10/24/2023, with Unit 3 in Mode 1 at 100 percent power, the reactor was automatically tripped due to an actuation signal into the Unit 3 reactor protection system protection rack during maintenance. The trip was uncomplicated with all systems responding normally post trip. Decay heat is being removed via auxiliary feed water system and the steam dump system. Unit 4 is not affected.</br>This event is being reported pursuant to 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A). The NRC Resident Inspector has been notified.</br>The cause of the automatic reactor trip will be investigated by the licensee.trip will be investigated by the licensee.  +
Discovered date
01:59:00, 25 October 2023  +
Emergency class
Non Emergency +
Entered date
01:12:00, 25 October 2023  +
Equipment trip
Reactor Trip +
Event date
01:59:00, 25 October 2023  +
Event description
The following information was provided by … The following information was provided by the licensee via email:</br>At 2159 on 10/24/2023, with Unit 3 in Mode 1 at 100 percent power, the reactor was automatically tripped due to an actuation signal into the Unit 3 reactor protection system protection rack during maintenance. The trip was uncomplicated with all systems responding normally post trip. Decay heat is being removed via auxiliary feed water system and the steam dump system. Unit 4 is not affected.</br>This event is being reported pursuant to 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A). The NRC Resident Inspector has been notified.</br>The cause of the automatic reactor trip will be investigated by the licensee.trip will be investigated by the licensee.  +
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ENS 56813 +, ENS 56813 +, ENS 56813 +, ENS 56813 +, ENS 56813 +, ENS 56813 +, ENS 56813 +, ENS 56813 +, ENS 56813 +, ENS 56813 +, ENS 56813 +, ENS 56813 +, ENS 56813 +, ENS 56813 +  and ENS 56813 +
Initial power
100  +
Initial reactor mode
Power Operation +
Last update date
00:00:00, 25 October 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>.
19:56:34, 4 January 2024  +
NRC officer
Michael Bloodgood +
Notification date
01:12:00, 25 October 2023  +
Originated by
Richard Jackson +
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
-0.0325 d (-0.78 hours, -0.00464 weeks, -0.00107 months)  +
Scram
Automatic Scram +
Site
Turkey Point +
Start date
01:59:00, 25 October 2023  +
State
Florida +
System
Reactor Protection System +  and Auxiliary Feedwater +
Title
Automatic Reactor Trip  +
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/2023/20231027en.html#en56813  +
Unit
3  +
 
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