ENS 54652: Difference between revisions

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| unit = 2
| unit = 2
| utype = W-3-LP, W-3-LP, M-4-LP
| utype = W-3-LP, W-3-LP, M-4-LP
| cfr = 10 CFR 50.72(b)(2)(i), 10 CFR 50.72(b)(3)(ii)(A)
| cfr = 10 CFR 50.72(b)(2)(i)
| emergency class = Non Emergency  
| emergency class = Non Emergency
| notification date = 04/09/2020 03:37
| notification date = 04/09/2020 03:37
| notification by = Neil Turner
| notification by = Neil Turner
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| last update date = 04/09/2020
| last update date = 04/09/2020
| title = Technical Specification Required Shutdown Due to Reactor Coolant System Pressure Boundary Leakage
| title = Technical Specification Required Shutdown Due to Reactor Coolant System Pressure Boundary Leakage
| event text = On April 9, 2020 at 0100 EDT, while performing a containment walkdown due to a small increased RCS unidentified leakage, a leak was identified on the 'A' Reactor Coolant Pump (RCP) seal injection piping. The source of the leakage cannot be isolated and is considered Reactor Coolant System (RCS) pressure boundary leakage. At that time, Condition B of Technical Specification (TS) LCO 3.4.13, 'RCS Operational Leakage' was entered due to pressure boundary leakage. TS 3.4.4 'RCS Loops - Mode 1 and 2' and Technical Requirement (TR) 3.4.6 'ASME Code Class 1, 2, and 3 Components' are also applicable. Unit 2 is projected to be taken to Mode 5 for repairs.
| event text = On April 9, 2020 at 0100 EDT, while performing a containment walkdown due to a small increased Reactor Coolant System (RCS) unidentified leakage, a leak was identified on the 'A' Reactor Coolant Pump (RCP) seal injection piping. The source of the leakage cannot be isolated and is considered RCS pressure boundary leakage. At that time, Condition B of Technical Specification (TS) LCO 3.4.13, 'RCS Operational Leakage' was entered due to pressure boundary leakage. TS 3.4.4 'RCS Loops - Mode 1 and 2' and Technical Requirement (TR) 3.4.6 'ASME Code Class 1, 2, and 3 Components' are also applicable. Unit 2 is projected to be taken to Mode 5 for repairs.
This event is reportable in accordance with 10 CFR 50.72(b)(2) for 'Initiation of plant shutdown required by Technical Specifications' and 10 CFR 50.72(b)(3)(ii)(A) for 'Any event or condition that results in the condition of the nuclear power plant, including its principle safety barriers, being seriously degraded.'
This event is reportable in accordance with 10 CFR 50.72(b)(2) for 'Initiation of plant shutdown required by Technical Specifications' and 10 CFR 50.72(b)(3)(ii)(A) for 'Any event or condition that results in the condition of the nuclear power plant, including its principle safety barriers, being seriously degraded.'
The licensee notified the NRC Resident Inspector. There is no effect on Unit 1
The licensee notified the NRC Resident Inspector. There is no effect on Unit 1
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2020/20200409en.html#en54652
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2020/20200410en.html#en54652
}}{{unit info
| Unit =  2
| type =
| Scram code =  N
| Reactor critical =  Y
| Initial power =  100
| Initial reactor mode =  Power Operation
| Current power =  35
| Current reactor mode =  Power Operation
}}
}}


{{ENS-Nav}}[[Category:Power Reactor]]
{{ENS-Nav}}[[Category:Power Reactor]]

Latest revision as of 12:44, 15 January 2021

ENS 54652 +/-
Where
North Anna Dominion icon.png
Virginia (NRC Region 2)
Reporting
10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown
Time - Person (Reporting Time:+-1.38 h-0.0575 days <br />-0.00821 weeks <br />-0.00189 months <br />)
Opened: Neil Turner
03:37 Apr 9, 2020
NRC Officer: Donald Norwood
Last Updated: Apr 9, 2020
54652 - NRC Website
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