ENS 51725
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ENS Event | |
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04:07 Feb 11, 2016 | |
Title | |
Event Description | This report is being made pursuant to 10CFR50.72(b)(3)(v)(C), event or condition that could have prevented fulfillment of a safety function needed to control the release of radioactive material and 10CFR50.72(b)(3)(v)(D), event or condition that could have prevented fulfillment of a safety function needed to mitigate the consequences of an accident. LaSalle Station's Unit 1 and Unit 2 were in Mode 1. At 2207 [CST] [on 2/10/16], Secondary Containment Differential Pressure dropped below the Technical Specification (TS) 3.6.4.1 minimum of 0.25 inches water vacuum. The initial indications are a failure of one Unit 1 Reactor Building Exhaust Isolation Damper, which resulted in a trip of the Unit 1 Reactor Building Exhaust Fans. At 2245, Secondary Containment Differential Pressure was restored to within the TS 3.6.4.1 limits by securing and isolating the Unit 1 Reactor Building Ventilation System. Troubleshooting plans are being developed to determine cause of the damper failure and to correct the deficient condition.
The licensee has notified the NRC Resident Inspector. |
Where | |
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Lasalle Illinois (NRC Region 3) | |
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: | 05000373/LER-2016-001 |
Time - Person (Reporting Time:+-2.78 h-0.116 days <br />-0.0165 weeks <br />-0.00381 months <br />) | |
Opened: | Mark Zickefoose 01:20 Feb 11, 2016 |
NRC Officer: | Howie Crouch |
Last Updated: | Feb 11, 2016 |
51725 - NRC Website
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Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (91 %) |
After | Power Operation (91 %) |
Unit 2 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
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