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ENS 54289
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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
At 1106 CDT Braidwood Unit 1 experienced a … At 1106 CDT Braidwood Unit 1 experienced an automatic reactor trip due to lowering steam generator water levels following closure of the 1B steam generator feed water regulating valve.</br> </br>The cause of the 1B steam generator feedwater regulating valve failing closed is unknown at this time and is under investigation.</br> </br>Both trains of auxiliary feedwater started automatically following the reactor trip to maintain steam generator water levels.</br> </br>All systems responded as expected with the exception of intermediate range nuclear instrument N-36 which was identified as being undercompensated following the reactor trip. Both source range nuclear instruments were manually energized in accordance with station procedures. Steam generator power operated relief valves lifted momentarily and reseated as designed in response to the secondary transient due to the reactor trip. The main steam dump valves are in service to the main condenser to provide heat sink cooling. The plant is being maintained at normal operating pressure and temperature. AC power is being provided by offsite power with the diesel generators in stand by and all safety systems available. There is no impact to Unit 2. </br>This report is being made per 10 CFR 50.72(b)(2)(iv)(B) for a RPS actuation, 4 hour notification, and per 10 CFR 50.72(b)(3)(iv)(A) for an automatic actuation of the auxiliary feedwater system, 8 hour notification.</br>The NRC Resident Inspector has been informed. NRC Resident Inspector has been informed.  +
Discovered date
16:06:00, 23 September 2019  +
ENS id number
54,289  +
Emergency class
Non Emergency +
Entered date
14:15:00, 23 September 2019  +
Equipment trip
Reactor Trip +
Event date
16:06:00, 23 September 2019  +
Event description
At 1106 CDT Braidwood Unit 1 experienced a … At 1106 CDT Braidwood Unit 1 experienced an automatic reactor trip due to lowering steam generator water levels following closure of the 1B steam generator feed water regulating valve.</br> </br>The cause of the 1B steam generator feedwater regulating valve failing closed is unknown at this time and is under investigation.</br> </br>Both trains of auxiliary feedwater started automatically following the reactor trip to maintain steam generator water levels.</br> </br>All systems responded as expected with the exception of intermediate range nuclear instrument N-36 which was identified as being undercompensated following the reactor trip. Both source range nuclear instruments were manually energized in accordance with station procedures. Steam generator power operated relief valves lifted momentarily and reseated as designed in response to the secondary transient due to the reactor trip. The main steam dump valves are in service to the main condenser to provide heat sink cooling. The plant is being maintained at normal operating pressure and temperature. AC power is being provided by offsite power with the diesel generators in stand by and all safety systems available. There is no impact to Unit 2. </br>This report is being made per 10 CFR 50.72(b)(2)(iv)(B) for a RPS actuation, 4 hour notification, and per 10 CFR 50.72(b)(3)(iv)(A) for an automatic actuation of the auxiliary feedwater system, 8 hour notification.</br>The NRC Resident Inspector has been informed. NRC Resident Inspector has been informed.  +
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ENS 54289 +, ENS 54289 +, ENS 54289 +, ENS 54289 +, ENS 54289 +, ENS 54289 +, ENS 54289 +, ENS 54289 +, ENS 54289 +, ENS 54289 +, ENS 54289 +, ENS 54289 +, ENS 54289 +, ENS 54289 +  and ENS 54289 +
Hours
4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 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, 23 September 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>.
04:43:01, 24 February 2020  +
NRC officer
Caty Nolan +
Notification date
14:15:00, 23 September 2019  +
Originated by
Richard Rowe +
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
-0.0771 d (-1.85 hours, -0.011 weeks, -0.00253 months)  +
Scram
Automatic Scram +
Site
Braidwood +
Start date
16:06:00, 23 September 2019  +
State
Illinois +
System
Steam Generator +, Feedwater +, Auxiliary Feedwater +, Main Condenser +  and Main Steam +
Title
Automatic Reactor Trip Due to Lowering Steam Generator Levels  +
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/2019/20190924en.html#en54289  +
Unit
1  +
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