ENS 52597
ENS Event | |
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13:30 Mar 7, 2017 | |
Title | Breach in Auxiliary Building Secondary Containment |
Event Description | At 0830 [EST] on March 7, 2017, operators discovered that on March 3, 2017 at 2046 a door was blocked open creating a breach of the auxiliary building secondary containment enclosure (ABSCE) boundary that exceeded the allowed ABSCE breach margin. As a result, both Unit 1 and Unit 2 entered Technical Specification Limiting Condition of Operation (LCO) 3.7.12 Condition B for two trains of Auxiliary Building Gas Treatment System (ABGTS) inoperable due to an inoperable ABSCE boundary in MODE 1, 2, 3, or 4. The condition has been corrected and ABGTS was restored to operable as of 0949 March 7, 2017.
In MODES 1, 2, 3, and 4, the analysis of the loss of coolant accident (LOCA) assumes that radioactive materials leaked from the Emergency Core Cooling System are filtered and adsorbed by the ABGTS. For the fuel handling accident, the analysis assumes that the ABSCE boundary is capable of being established to ensure releases from the auxiliary and containment buildings are consistent with the dose consequence analysis. The event is reportable in accordance with 10 CFR 50.72(b)(3)(v) as an event or condition that could have prevented fulfillment of a safety function of structures or systems that are needed to: (C) control the release of radioactive material and (D) mitigate the consequences of an accident. No actual LOCA or fuel handling accident occurred while both trains of ABGTS were inoperable. The condition had no impact on the health and safety of the public. The NRC Resident Inspector has been notified. |
Where | |
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Sequoyah ![]() Tennessee (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
LER: | 05000327/LER-2017-001 |
Time - Person (Reporting Time:+1.15 h0.0479 days <br />0.00685 weeks <br />0.00158 months <br />) | |
Opened: | Jonathan Redner 14:39 Mar 7, 2017 |
NRC Officer: | Jeff Rotton |
Last Updated: | Mar 7, 2017 |
52597 - NRC Website
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Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
Unit 2 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |