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ENS 55078
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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 +  and 10 CFR 50.72#b2ivB +
Current power
0  +
Current reactor mode
Hot Standby +
Description
On 1/20/2021 at 1822 EST, with Unit 2 in M … On 1/20/2021 at 1822 EST, with Unit 2 in Mode 1 at 100 percent power, the reactor automatically tripped due to a loss of Motor Control Center 2B2. The trip was uncomplicated with all systems responding normally post trip. Operations stabilized the plant in Mode 3. Auxiliary feed-water automatically actuated on the 2A Steam Generator post trip. Current decay heat removal is the 2B main feedwater pump to both steam generators and the Steam Bypass Control System to the main condenser.</br>Unit 1 is not affected.</br>This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B).</br>The NRC Resident Inspector has been notified. NRC Resident Inspector has been notified.  +
Discovered date
23:22:00, 20 January 2021  +
ENS id number
55,078  +
Emergency class
Non Emergency +
Entered date
21:48:00, 20 January 2021  +
Event date
23:22:00, 20 January 2021  +
Event description
On 1/20/2021 at 1822 EST, with Unit 2 in M … On 1/20/2021 at 1822 EST, with Unit 2 in Mode 1 at 100 percent power, the reactor automatically tripped due to a loss of Motor Control Center 2B2. The trip was uncomplicated with all systems responding normally post trip. Operations stabilized the plant in Mode 3. Auxiliary feed-water automatically actuated on the 2A Steam Generator post trip. Current decay heat removal is the 2B main feedwater pump to both steam generators and the Steam Bypass Control System to the main condenser.</br>Unit 1 is not affected.</br>This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B).</br>The NRC Resident Inspector has been notified. NRC Resident Inspector has been notified.  +
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ENS 55078 +, ENS 55078 +, ENS 55078 +, ENS 55078 +, ENS 55078 +, ENS 55078 +, ENS 55078 +, ENS 55078 +, ENS 55078 +, ENS 55078 +, ENS 55078 +, ENS 55078 +, ENS 55078 +, ENS 55078 +  and ENS 55078 +
Initial power
100  +
Initial reactor mode
Power Operation +
Last update date
00:00:00, 20 January 2021  +
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>.
20:04:47, 4 January 2024  +
NRC officer
Donald Norwood +
Notification date
21:48:00, 20 January 2021  +
Originated by
Charlie Pike +
Reactor critical
true  +
Reactor type
CE +
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
-0.0654 d (-1.57 hours, -0.00935 weeks, -0.00215 months)  +
Scram
Automatic Scram +
Site
Saint Lucie +
Start date
23:22:00, 20 January 2021  +
State
Florida +
System
Steam Generator +, Feedwater +, Steam Bypass Control System +, Decay Heat Removal +  and Main Condenser +
Title
Automatic Reactor Trip Due to Trip of Motor Control Center  +
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/2021/20210121en.html#en55078  +
Unit
2  +
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