ENS 54794: Difference between revisions

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| unit = 1, 2, 3
| unit = 1, 2, 3
| utype = GE-4, GE-4, GE-4
| utype = GE-4, GE-4, GE-4
| cfr = 10 CFR 50.72(b)(2)(iv)(B), 10 CFR 50.72(b)(3)(iv)(A)
| cfr = 10 CFR 50.72(b)(2)(iv)(B)
| emergency class = Non Emergency  
| emergency class = Non Emergency
| notification date = 07/20/2020 18:11
| notification date = 07/20/2020 18:11
| notification by = Todd Christensen
| notification by = Todd Christensen
Line 16: Line 16:
| event date = 07/20/2020 13:25 CDT
| event date = 07/20/2020 13:25 CDT
| last update date = 07/20/2020
| last update date = 07/20/2020
| title = Biofouling of Intake Structure Leads to Manual Reactor Scram of Unit 2 and Downpower of Units 1 & 3  
| title = Biofouling of Intake Structure Leads to Manual Reactor Scram of Unit 2 and Downpower of Units 1 & 3
| event text = On July 20, 2020, at 1325 hours Central Daylight Time, Brown's Ferry Unit 2 inserted a manual reactor scram due to degrading main condenser vacuum from marine biofouling at the intake structure. Brown's Ferry Unit 1 performed a down power to 43% and Unit 3 down powered to 76%. Conditions are stable on both Unit 1 and 3 following unit down power.
| event text = On July 20, 2020, at 1325 hours Central Daylight Time, Brown's Ferry Unit 2 inserted a manual reactor scram due to degrading main condenser vacuum from marine biofouling at the intake structure. Brown's Ferry Unit 1 performed a down power to 43% and Unit 3 down powered to 76%. Conditions are stable on both Unit 1 and 3 following unit down power.
Primary Containment Isolations Systems received an actuation signal for groups 2, 3, 6, and 8 on reactor water level below +2". All Primary Containment Isolations System groups that received an actuation signal performed as designed. Additionally, all other systems functioned as designed.
Primary Containment Isolations Systems received an actuation signal for groups 2, 3, 6, and 8 on reactor water level below +2". All Primary Containment Isolations System groups that received an actuation signal performed as designed. Additionally, all other systems functioned as designed.  
This event is reportable within 4 hours per 10CFR50.72(b)(2)(iv)(B) - Any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.
This event is reportable within 4 hours per 10CFR50.72(b)(2)(iv)(B) - Any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.
This event also requires an 8 hour report per 10CFR 50.72(b)(3)(iv)(A), "Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B), (1) Reactor protection system (RPS) including: reactor scram or reactor trip, except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation and (2) General containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs).
This event also requires an 8 hour report per 10CFR 50.72(b)(3)(iv)(A), "Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B), (1) Reactor protection system (RPS) including: reactor scram or reactor trip, except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation and (2) General containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs).  
The NRC Resident Inspector has been notified.
The NRC Resident Inspector has been notified.
All control rods fully inserted and decay heat is being removed via normal feedwater and condenser.
All control rods fully inserted and decay heat is being removed via normal feedwater and condenser.
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2020/20200721en.html#en54794
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2020/20200721en.html#en54794
}}{{unit info
| Unit =  1
| type =
| Scram code =  N
| Reactor critical =  Y
| Initial power =  100
| Initial reactor mode =  Power Operation
| Current power =  43
| Current reactor mode =  Power Operation
}}{{unit info
| Unit =  2
| type =
| Scram code =  M/R
| Reactor critical =  Y
| Initial power =  100
| Initial reactor mode =  Power Operation
| Current power =  0
| Current reactor mode = 
}}{{unit info
| Unit =  3
| type =
| Scram code =  N
| Reactor critical =  Y
| Initial power =  100
| Initial reactor mode =  Power Operation
| Current power =  76
| Current reactor mode =  Power Operation
}}
}}


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

Latest revision as of 11:31, 15 January 2021

ENS 54794 +/-
Where
Browns Ferry Tennessee Valley Authority icon.png
Alabama (NRC Region 2)
Reporting
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation
Time - Person (Reporting Time:+-0.23 h-0.00958 days <br />-0.00137 weeks <br />-3.15054e-4 months <br />)
Opened: Todd Christensen
18:11 Jul 20, 2020
NRC Officer: Thomas Kendzia
Last Updated: Jul 20, 2020
54794 - NRC Website
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