ENS 52738
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ENS Event | |
---|---|
13:25 May 8, 2017 | |
Title | Through-Wall Leakage Identified on Reactor Coolant System Pressure Boundary During Testing |
Event Description | On May 8th, 2017 at 0925 [EDT], during the performance of LGS [Limerick Generating Station] leakage testing of the reactor pressure vessel and associated piping, a through-wall leak was identified on an instrument line connected to the N16D nozzle.
The reactor will be maintained shutdown until pipe repairs and testing are complete. The licensee informed the NRC Resident Inspector. |
Where | |
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Limerick Pennsylvania (NRC Region 1) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
Time - Person (Reporting Time:+0.5 h0.0208 days <br />0.00298 weeks <br />6.849e-4 months <br />) | |
Opened: | John Harkins 13:55 May 8, 2017 |
NRC Officer: | Steve Sandin |
Last Updated: | May 8, 2017 |
52738 - NRC Website
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Unit 2 | |
---|---|
Reactor critical | Not Critical |
Scram | No |
Before | Cold Shutdown (0 %) |
After | Cold Shutdown (0 %) |
WEEKMONTHYEARENS 527382017-05-08T13:25:0008 May 2017 13:25:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Through-Wall Leakage Identified on Reactor Coolant System Pressure Boundary During Testing ENS 518092016-03-21T01:54:00021 March 2016 01:54:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification (Ts) Required Shutdown Due to Pressure Boundary Leakage ENS 483722012-10-03T20:00:0003 October 2012 20:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Fire Safe Shutdown Analysis Failed to Identify Unprotected Cable ENS 483342012-09-21T20:00:00021 September 2012 20:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Isolation Valves Could Fail to Fully Close 2017-05-08T13:25:00 | |
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