ENS Event | |
|---|---|
14:40 Oct 8, 2014 | |
| Title | Potential Leak from a Pipe Could Result in Damage to Both Trains of Electrical Power Systems |
| Event Description | This is a non-emergency notification.
At approximately 10:40 AM on October 8, 2014, with the Harris Nuclear Plant operating at 100% power, a condition was discovered where a potential leak from a pipe supplying water to the fire suppression system in the diesel fuel oil storage tank building could result in damage to equipment in both trains of the onsite electrical power system. Neither the leak from the piping nor the damage to equipment actually occurred, so there are no actual safety consequences and no impact to public health and safety or the environment due to this condition. The condition was discovered during a Harris staff evaluation in the corrective action program. The condition will be fully investigated, including the extent of condition, and corrective actions taken to resolve the issue. Compensatory actions have been taken as interim actions to ensure safety systems are not impacted by the potential pipe leak. This event is reportable per 10 CFR 50.72(b)(3)(v). The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
Harris  North Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor | |
| Time - Person (Reporting Time:+3.23 h0.135 days <br />0.0192 weeks <br />0.00442 months <br />) | |
| Opened: | Louis Parente 17:54 Oct 8, 2014 |
| NRC Officer: | Dong Park |
| Last Updated: | Oct 8, 2014 |
| 50520 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 543782019-11-09T11:35:0009 November 2019 11:35:00
[Table view]10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Both Source Range Instruments Found Inoperable ENS 510112015-04-04T15:20:0004 April 2015 15:20:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Power Lost to Control Room Normal Outside Air Intake Dampers During Testing ENS 505202014-10-08T14:40:0008 October 2014 14:40:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Potential Leak from a Pipe Could Result in Damage to Both Trains of Electrical Power Systems 2019-11-09T11:35:00 | |