ENS 53031
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ENS Event | |
|---|---|
08:00 Oct 23, 2017 | |
| Title | Leakage Identified on One Inch Line Socket Weld for the B Recirculation Pump |
| Event Description | On Monday, October 23, 2017, with PBAPS [Peach Bottom Atomic Power Station] Unit 3 in Mode 3 at the beginning of a refueling outage, personnel entered the drywell to perform an inspection. At approximately 0400 [EDT], leakage was identified on a one-inch diameter instrument line socket weld for the 'B' recirculation pump. Because the leak was misting, the leakage rate could not be quantified. However, Unit 3 reactor coolant unidentified leakage prior to plant shutdown was 0.18 gpm. This line is considered part of the primary coolant pressure boundary.
This event is being reported as an occurrence of an event or condition that results in the condition of the nuclear power plant, including its principal safety barriers being seriously degraded under 10 CFR 50.72(b)(3)(ii). The Station is preparing an evaluation and repair plan at this time. The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
Peach Bottom  Pennsylvania (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| LER: | 05000278/LER-2017-001 |
| Time - Person (Reporting Time:+1.58 h0.0658 days <br />0.0094 weeks <br />0.00216 months <br />) | |
| Opened: | Josh Smith 09:35 Oct 23, 2017 |
| NRC Officer: | Jeff Herrera |
| Last Updated: | Oct 23, 2017 |
| 53031 - NRC Website
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Unit 3 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Shutdown (0 %) |
| After | Hot 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 | |
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