ENS Event | |
|---|---|
14:30 Oct 29, 2020 | |
| Title | Through-Wall Leakage Identified on Reactor Coolant System Pressure Boundary During Testing |
| Event Description | At 1030 EDT on Thursday, October 29, 2020, during the performance of Peach Bottom Atomic Power Station leakage testing of the reactor pressure vessel and associated piping, a through-wall leak [non-isolable] was identified on an instrument line connected to the N16A nozzle.
The reactor will be maintained shutdown until pipe repairs and testing are complete. The NRC resident inspector has been informed. |
| Where | |
|---|---|
Peach Bottom  Pennsylvania (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+0.7 h0.0292 days <br />0.00417 weeks <br />9.5886e-4 months <br />) | |
| Opened: | Paul Bokus 15:12 Oct 29, 2020 |
| NRC Officer: | Thomas Kendzia |
| Last Updated: | Oct 29, 2020 |
| 54971 - NRC Website
Loading map... | |
Unit 2 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
WEEKMONTHYEARENS 549712020-10-29T14:30:00029 October 2020 14:30:00
[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 536172018-09-21T04:00:00021 September 2018 04:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded High Pressure Coolant Injection System Inoperable ENS 530312017-10-23T08:00:00023 October 2017 08:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Leakage Identified on One Inch Line Socket Weld for the B Recirculation Pump ENS 505712014-10-29T15:20:00029 October 2014 15:20:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Maximum Allowable Primary Containment Leakage Rate Exceeded ENS 428892006-10-07T21:50:0007 October 2006 21:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 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 Technical Specification Required Shutdown Due to Loss of Primary Containment Integrity ENS 420032005-09-20T09:00:00020 September 2005 09:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition - Small Leak on Rhr Injection Drain Line 2020-10-29T14:30:00 | |