ENS 54603: Difference between revisions

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| unit = 1
| unit = 1
| utype = GE-4, GE-4
| utype = GE-4, GE-4
| cfr = 10 CFR 50.72(b)(2)(i), 10 CFR 50.72(b)(3)(iv)(A)
| cfr = 10 CFR 50.72(b)(2)(i)
| emergency class = Non Emergency  
| emergency class = Non Emergency
| notification date = 03/24/2020 16:02
| notification date = 03/24/2020 16:02
| notification by = William Roberts
| notification by = William Roberts
Line 17: Line 17:
| last update date = 03/24/2020
| last update date = 03/24/2020
| title = Technical Specification-Required Shutdown Due to Unidentified Leakage
| title = Technical Specification-Required Shutdown Due to Unidentified Leakage
| event text = At 1205 Eastern Daylight Time (EDT) on March 24, 2020, a Technical Specification-required shutdown was initiated on Unit 1 due to indication of a leak in the drywell. Technical Specification Action 3.4.4.A, Unidentified Reactor Coolant System (RCS) leakage increase not within limit, requires RCS leakage to be reduced to within limits within 8 hours.  
| event text = At 1205 Eastern Daylight Time (EDT) on March 24, 2020, a Technical Specification-required shutdown was initiated on Unit 1 due to indication of a leak in the drywell. Technical Specification Action 3.4.4.A, Unidentified Reactor Coolant System (RCS) leakage increase not within limit, requires RCS leakage to be reduced to within limits within 8 hours.
It was expected that the leakage would not have been reduced to within limits within the required Technical Specification completion time; therefore, this event is being reported in accordance with 10 CFR 50.72(b)(2)(i).
It was expected that the leakage would not have been reduced to within limits within the required Technical Specification completion time; therefore, this event is being reported in accordance with 10 CFR 50.72(b)(2)(i).
Reactor water level reached low level 1 (LL1) following the reactor shutdown. The LL1 signal causes Group 2 (i.e., floor and equipment drain isolation valves), Group 6 (i.e., monitoring and sampling isolation valves), and Group 8 (i.e., shutdown cooling isolation valves) isolations. The LL1 isolations occurred as designed; the Group 8 valves were closed at the time of the event. Due to the valid Primary Containment Isolation System (PCIS) actuation, this event is also being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A).
Reactor water level reached low level 1 (LL1) following the reactor shutdown. The LL1 signal causes Group 2 (i.e., floor and equipment drain isolation valves), Group 6 (i.e., monitoring and sampling isolation valves), and Group 8 (i.e., shutdown cooling isolation valves) isolations. The LL1 isolations occurred as designed; the Group 8 valves were closed at the time of the event. Due to the valid Primary Containment Isolation System (PCIS) actuation, this event is also being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A).
Unit 2 is not affected by this event.
Unit 2 is not affected by this event.
There was no impact on the health and safety of the public or plant personnel.
There was no impact on the health and safety of the public or plant personnel.
The NRC Resident Inspector has been notified.
The NRC Resident Inspector has been notified.
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2020/20200325en.html#en54603
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2020/20200325en.html#en54603
}}{{unit info
| Unit =  1
| type =
| Scram code =  M/R
| Reactor critical =  Y
| Initial power =  22
| Initial reactor mode =  Power Operation
| Current power =  0
| Current reactor mode =  Hot Shutdown
}}
}}


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

Latest revision as of 12:48, 15 January 2021

ENS 54603 +/-
Where
Brunswick Duke Energy icon.png
North Carolina (NRC Region 2)
Reporting
10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown
Time - Person (Reporting Time:+-0.05 h-0.00208 days <br />-2.97619e-4 weeks <br />-6.849e-5 months <br />)
Opened: William Roberts
16:02 Mar 24, 2020
NRC Officer: Bethany Cecere
Last Updated: Mar 24, 2020
54603 - NRC Website
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