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ENS 49538
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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
On November 14, 2013, at 1313 Eastern Stan … On November 14, 2013, at 1313 Eastern Standard Time, Unit 1 was manually tripped from 100% power due to indications of (four) dropped control rods. This manual reactor protection system actuation is reportable per 10 CFR 50.72(b)(2)(iv)(B). The cause of the dropped rods is not confirmed at this time, but may be related to maintenance in a Rod Control Power Cabinet ongoing at the time of the event.</br>The Operations crew entered the reactor trip procedure and stabilized Unit 1 in Mode 3 at normal operating temperature and pressure. All control rods fully inserted into the core following the reactor trip and all plant systems operated as designed.</br>The Auxiliary Feedwater (AFW) system (1A and 1B motor-driven pumps) was manually started for steam generator level control following reactor trip. The start of the AFW system is reportable per 10 CFR 50.72 (b)(3)(iv)(A) for a valid system actuation.</br>Decay heat is being removed via the steam generators (via steam dumps to the main condenser). This event does not impact public health and safety.</br>Unit 2 was not affected by this event.</br>The licensee notified the NRC Resident Inspector.</br>* * * UPDATE FROM WARREN MOORE TO DANIEL MILLS ON 11/18/13 AT 0950 EST * * *</br> A subsequent licensee evaluation determined that there were ten dropped control rods. </br>Notified the R1DO (Desai). control rods. Notified the R1DO (Desai).  +
Discovered date
18:13:00, 14 November 2013  +
ENS id number
49,538  +
Emergency class
Non Emergency +
Entered date
16:03:00, 14 November 2013  +
Equipment trip
Reactor Trip +
Event date
18:13:00, 14 November 2013  +
Event description
On November 14, 2013, at 1313 Eastern Stan … On November 14, 2013, at 1313 Eastern Standard Time, Unit 1 was manually tripped from 100% power due to indications of (four) dropped control rods. This manual reactor protection system actuation is reportable per 10 CFR 50.72(b)(2)(iv)(B). The cause of the dropped rods is not confirmed at this time, but may be related to maintenance in a Rod Control Power Cabinet ongoing at the time of the event.</br>The Operations crew entered the reactor trip procedure and stabilized Unit 1 in Mode 3 at normal operating temperature and pressure. All control rods fully inserted into the core following the reactor trip and all plant systems operated as designed.</br>The Auxiliary Feedwater (AFW) system (1A and 1B motor-driven pumps) was manually started for steam generator level control following reactor trip. The start of the AFW system is reportable per 10 CFR 50.72 (b)(3)(iv)(A) for a valid system actuation.</br>Decay heat is being removed via the steam generators (via steam dumps to the main condenser). This event does not impact public health and safety.</br>Unit 2 was not affected by this event.</br>The licensee notified the NRC Resident Inspector.</br>* * * UPDATE FROM WARREN MOORE TO DANIEL MILLS ON 11/18/13 AT 0950 EST * * *</br> A subsequent licensee evaluation determined that there were ten dropped control rods. </br>Notified the R1DO (Desai). control rods. Notified the R1DO (Desai).  +
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ENS 49538 +, ENS 49538 +, ENS 49538 +, ENS 49538 +, ENS 49538 +, ENS 49538 +, ENS 49538 +, ENS 49538 +, ENS 49538 +, ENS 49538 +, ENS 49538 +, ENS 49538 +, ENS 49538 +, ENS 49538 +, ENS 49538 +  and ENS 49538 +
Initial power
100  +
Initial reactor mode
Power Operation +
Last update date
00:00:00, 18 November 2013  +
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>.
01:52:36, 2 March 2018  +
NRC officer
Nestor Makris +
Notification date
16:03:00, 14 November 2013  +
Originated by
Scott Fortin +
Person
Daniel Mills +
Reactor critical
true  +
Reactor scram
true  +
Reactor type
Westinghouse PWR 4-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
-0.0904 d (-2.17 hours, -0.0129 weeks, -0.00297 months)  +
Scram
Manual Scram +
Site
McGuire +
Start date
18:13:00, 14 November 2013  +
State
North Carolina +
System
Steam Generator +, Reactor Protection System +, Auxiliary Feedwater +  and Control Rod +
Title
Manual Reactor Trip Due to Indication of Dropped Control Rods  +
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.
http://www.nrc.gov/reading-rm/doc-collections/event-status/event/2013/20131119en.html#en49538  +
Unit
1  +
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