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ENS 50711
Show incoming properties 
Category
ENS Notification  and Power Reactor
CFR
10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat +  and 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident +
Current power
0  +
Current reactor mode
Hot Standby +
Description
At 1105 PST, plant personnel identified th … At 1105 PST, plant personnel identified through-wall seepage in a Diablo Canyon Power Plant Unit 1 socket weld inside containment that provides a flow path to a relief valve protecting a common portion of both trains of the Residual Heat Removal (RHR) System. The as-found condition falls under the requirements of the ASME acceptance criteria. Unit 1 was already in Mode 3, or offline, due to a planned maintenance outage. PG&E accordingly declared both Unit 1 trains of RHR inoperable and has initiated a transition from Mode 3 to Mode 4 in accordance with requirements of Technical Specification 3.0.3. </br>The licensee notified the NRC Resident Inspector. licensee notified the NRC Resident Inspector.  +
Discovered date
18:05:00, 31 December 2014  +
Emergency class
Non Emergency +
Entered date
20:44:00, 31 December 2014  +
Event date
18:05:00, 31 December 2014  +
Event description
At 1105 PST, plant personnel identified th … At 1105 PST, plant personnel identified through-wall seepage in a Diablo Canyon Power Plant Unit 1 socket weld inside containment that provides a flow path to a relief valve protecting a common portion of both trains of the Residual Heat Removal (RHR) System. The as-found condition falls under the requirements of the ASME acceptance criteria. Unit 1 was already in Mode 3, or offline, due to a planned maintenance outage. PG&E accordingly declared both Unit 1 trains of RHR inoperable and has initiated a transition from Mode 3 to Mode 4 in accordance with requirements of Technical Specification 3.0.3. </br>The licensee notified the NRC Resident Inspector. licensee notified the NRC Resident Inspector.  +
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ENS 50711 +, ENS 50711 +, ENS 50711 +, ENS 50711 +, ENS 50711 +, ENS 50711 +, ENS 50711 +, ENS 50711 +, ENS 50711 +, ENS 50711 +, ENS 50711 +, ENS 50711 +, ENS 50711 +  and ENS 50711 +
Initial power
0  +
Initial reactor mode
Hot Standby +
LER
Both Trains of Residual Heat Removal Inoperable Due to Circumferential Crack on a Socket Weld +, Regarding Both Trains of Residual Heat Removal Inoperable Due to Circumferential Crack on a Socket Weld +  and 05000275/LER-2015-001, Regarding Both Trains of Residual Heat Removal Inoperable Due to Circumferential Crack on a Socket Weld +
Last update date
00:00:00, 31 December 2014  +
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>.
22:18:36, 24 September 2017  +
NRC officer
Daniel Mills +
Notification date
20:44:00, 31 December 2014  +
Originated by
Jeremy Cobbs +
Reactor critical
false  +
Reactor scram
false  +
Reactor type
Westinghouse PWR 4-Loop +
Region
NRC Region 4 +
Reporting criterion
10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat +  and 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident +
Reporting time
0.11 d (2.65 hours, 0.0158 weeks, 0.00363 months)  +
Site
Diablo Canyon +
Start date
18:05:00, 31 December 2014  +
State
California +
System
Residual Heat Removal +
TS
TS-3.0.3 +
Title
Through Wall Seepage Affecting Rhr System  +
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/2015/20150102en.html#en50711  +
Unit
1  +
 
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