ENS 49710
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ENS Event | |
|---|---|
05:17 Jan 10, 2014 | |
| Title | Degraded Fittings Connected to Containment Penetration |
| Event Description | During an engineering walk down inside containment a minor leak from a pipe fitting was discovered on the primary sampling piping connected to penetration M-45. There was previously identified minor leakage from a fitting on this same penetration outside of containment in the auxiliary building. The containment isolation valves are currently tagged closed.
The licensee notified the NRC Resident Inspector.
Additional testing was performed on penetration M-45 which determined that the penetration met the required leakage limits. Therefore this issue does not represent a degraded condition for the containment and is not reportable. The previous notification is being retracted. The licensee has notified the NRC Resident Inspector. Notified the R4DO (Kellar). |
| Where | |
|---|---|
| Fort Calhoun Nebraska (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+1.37 h0.0571 days <br />0.00815 weeks <br />0.00188 months <br />) | |
| Opened: | Scott Moeck 06:39 Jan 10, 2014 |
| NRC Officer: | Dan Livermore |
| Last Updated: | Jan 16, 2014 |
| 49710 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Standby (0 %) |
| After | Hot Shutdown (0 %) |
WEEKMONTHYEARENS 512702015-07-22T18:30:00022 July 2015 18:30:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Reactor Coolant System Leak ENS 497102014-01-10T05:17:00010 January 2014 05:17:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Fittings Connected to Containment Penetration ENS 494522013-10-18T18:28:00018 October 2013 18:28:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Potential for High Energy Line Break on Letdown System Outside Containment ENS 481112012-07-17T15:00:00017 July 2012 15:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Charging Line Socket Welds Based on Thermal Fatigue Analysis ENS 479532012-05-23T21:00:00023 May 2012 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Crack Identified in Pressurizer Heater ENS 457242010-02-24T17:40:00024 February 2010 17:40:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Auxiliary Feedwater Pumps May Experience Runout at Low Steam Pressures 2015-07-22T18:30:00 | |
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