ENS 44399
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ENS Event | |
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16:30 Aug 7, 2008 | |
Title | Degraded Principal Safety Barrier |
Event Description | This is a late non-emergency notification to the NRC Operations Center in accordance with 10 CFR 50.72(b)(3)(ii)(A) due to the degradation of a principal safety barrier.
A flaw in a weld in a 3/4 inch test connection off the seal water injection line for the 4B reactor coolant pump was identified at approximately 1230 during a containment entry on August 7, 2008. The flaw is leaking at the rate of approximately 0.14 gpm (current total), it [the leak] is isolable, and the leakage is currently considered as unidentified leakage from the reactor coolant system. The Technical Specification limit for unidentified leakage is 1.0 gpm. Currently, the leak is being monitored while repair options are evaluated. The licensee notified the NRC Resident Inspector. |
Where | |
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Turkey Point Florida (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
Time - Person (Reporting Time:+23.52 h0.98 days <br />0.14 weeks <br />0.0322 months <br />) | |
Opened: | Micheal Coen 16:01 Aug 8, 2008 |
NRC Officer: | Jason Kozal |
Last Updated: | Aug 8, 2008 |
44399 - NRC Website
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Unit 4 | |
---|---|
Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
WEEKMONTHYEARENS 564742023-04-15T15:12:00015 April 2023 15:12:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded RCS Pressure Boundary Degraded ENS 555742021-11-12T21:05:00012 November 2021 21:05:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 499332014-03-20T02:02:00020 March 2014 02:02:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Potential Leak Discovered Around Pressurizer Heater Bank ENS 463622010-10-26T02:00:00026 October 2010 02:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Containment Liner Corrosion Degradation ENS 443992008-08-07T16:30:0007 August 2008 16:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Principal Safety Barrier ENS 436412007-09-14T03:04:00014 September 2007 03:04:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Potential Reactor Pressure Boundary Leakage ENS 436272007-09-08T16:28:0008 September 2007 16:28:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Pressure Boundary Leakage 2023-04-15T15:12:00 | |
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