ENS 51460
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ENS Event | |
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01:47 Oct 8, 2015 | |
Title | High Energy Line Break Door Found Unlatched |
Event Description | At approximately 2147 EDT on October 7, 2015, a high energy line break (HELB) door between the Turbine Building (TB) and the safety related Emergency Switchgear Room (ESGR) was determined to be unlatched. The door was immediately closed (latched). Investigation determined the door was unlatched for approximately 47 minutes. At 1617 EDT on October 8, 2015, it was determined the Unit 2 ESGR was outside of the design analysis for a Unit 1 HELB. A high energy line break in the TB with the door open could result in equipment in the Unit 2 ESGR experiencing high temperature, pressure, or humidity beyond conditions analyzed for equipment qualification which has the potential to render redundant safety-related equipment inoperable.
This condition is reportable in accordance with 10 CFR 50.72(b)(3)(ii)(B) as an unanalyzed condition and in accordance with 10 CFR 50.72(b)(3)(v)(A) & (B) & (D) as a condition that could have prevented the fulfillment of safety functions to shutdown the reactor and maintain it in a safe shutdown condition, remove residual heat, and mitigate the consequences of an accident. The NRC Senior Resident Inspector has been notified. |
Where | |
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North Anna Virginia (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
Time - Person (Reporting Time:+16.6 h0.692 days <br />0.0988 weeks <br />0.0227 months <br />) | |
Opened: | Michael Whalen 18:23 Oct 8, 2015 |
NRC Officer: | Donald Norwood |
Last Updated: | Oct 8, 2015 |
51460 - NRC Website
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Unit 2 | |
---|---|
Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
North Anna with 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
WEEKMONTHYEARENS 553752021-07-22T21:51:00022 July 2021 21:51:00
[Table view]10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition of Fire Safe Shutdown Equipment ENS 514602015-10-08T01:47:0008 October 2015 01:47:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition High Energy Line Break Door Found Unlatched ENS 506662014-12-10T18:44:00010 December 2014 18:44:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Inadvertent Loss of Vital Indication During Maintenance ENS 495712013-11-21T21:41:00021 November 2013 21:41:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Low Casing Cooling System Tank Level Potentially Causes Loss of Npsh to Outside Recirculation Spray Pumps ENS 472012011-08-26T17:00:00026 August 2011 17:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Based on Seismic Activity That Potentially Exceeded Design Basis Earthquake Magnitude ENS 445812008-10-18T15:25:00018 October 2008 15:25:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Both Boron Injection Tank Inlet Valves Inoperable. ENS 407392004-05-10T00:05:00010 May 2004 00:05:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Both Unit 2 Emergency Diesels Declared Inoperable Due to Shims/Supports Found to Be Either Missing or Not Properly Fastened. 2021-07-22T21:51:00 | |
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