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ENS 52137
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Category
ENS Notification  and Power Reactor
CFR
10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown +, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded +, 10 CFR 50.72#b3iiA +  and 10 CFR 50.72#b2 +
Current power
35  +
Current reactor mode
Power Operation +
Description
On July 30, 2016 at 1152 hours (EDT) follo … On July 30, 2016 at 1152 hours (EDT) following a containment walkdown to investigate an increase in RCS unidentified leakage to 0.15 gpm, a leak was identified on the seal return line from 2-RC-P-1C, 'C' Reactor Coolant Pump. The source of the leakage cannot be isolated and is considered RCS pressure boundary leakage. (Technical Specification) LCO 3.4.13, RCS Operational Leakage, Condition B for the existence of pressure boundary leakage was entered. Technical Requirement TR 3.4.6, ASME Code Class 1, 2, and 3 Components is also applicable. Unit 2 is projected to be taken to Mode 5 for repair.</br>This event is reportable in accordance with 10 CFR 50.72(b)(2) for 'the initiation of any nuclear plant shutdown required by the plant's Technical Specifications' and 10 CFR 50.72(b)(3)(ii)(A) for 'any event or condition that results in the condition of the nuclear plant including its principal safety barriers, being seriously degraded.'</br>The licensee will be notifying the Louisa County Administrator and has notified the NRC Resident Inspector.d has notified the NRC Resident Inspector.  +
Discovered date
15:52:00, 30 July 2016  +
ENS id number
52,137  +
Emergency class
Non Emergency +
Entered date
15:17:00, 30 July 2016  +
Event date
15:52:00, 30 July 2016  +
Event description
On July 30, 2016 at 1152 hours (EDT) follo … On July 30, 2016 at 1152 hours (EDT) following a containment walkdown to investigate an increase in RCS unidentified leakage to 0.15 gpm, a leak was identified on the seal return line from 2-RC-P-1C, 'C' Reactor Coolant Pump. The source of the leakage cannot be isolated and is considered RCS pressure boundary leakage. (Technical Specification) LCO 3.4.13, RCS Operational Leakage, Condition B for the existence of pressure boundary leakage was entered. Technical Requirement TR 3.4.6, ASME Code Class 1, 2, and 3 Components is also applicable. Unit 2 is projected to be taken to Mode 5 for repair.</br>This event is reportable in accordance with 10 CFR 50.72(b)(2) for 'the initiation of any nuclear plant shutdown required by the plant's Technical Specifications' and 10 CFR 50.72(b)(3)(ii)(A) for 'any event or condition that results in the condition of the nuclear plant including its principal safety barriers, being seriously degraded.'</br>The licensee will be notifying the Louisa County Administrator and has notified the NRC Resident Inspector.d has notified the NRC Resident Inspector.  +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
ENS 52137 +, ENS 52137 +, ENS 52137 +, ENS 52137 +, ENS 52137 +, ENS 52137 +, ENS 52137 +, ENS 52137 +, ENS 52137 +, ENS 52137 +, ENS 52137 +, ENS 52137 +, ENS 52137 +, ENS 52137 +  and ENS 52137 +
Hours
0.0133 d (0.32 hours, 0.0019 weeks, 4.38336e-4 months)  +
Initial power
100  +
Initial reactor mode
Power Operation +
Last update date
00:00:00, 30 July 2016  +
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>.
01:44:33, 2 March 2018  +
NRC officer
Howie Crouch +
Notification date
15:17:00, 30 July 2016  +
Originated by
Don Taylor +
Reactor critical
true  +
Reactor scram
false  +
Reactor type
Westinghouse PWR 3-Loop +
Region
NRC Region 2 +
Reporting criterion
10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown +  and 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded +
Reporting time
-0.0242 d (-0.58 hours, -0.00345 weeks, -7.94484e-4 months)  +
Site
North Anna +
Start date
15:52:00, 30 July 2016  +
State
Virginia +
System
Reactor Coolant System +
TS
TS-3.4.13 +
Title
Technical Specification Required Shutdown Due to Unisolable Reactor Coolant System Boundary Leakage  +
Topic
Pressure Boundary Leakage +, Unidentified leakage +  and Operational leakage +
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/2016/20160801en.html#en52137  +
Unit
2  +
 
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