ENS Event | |
|---|---|
15:35 Mar 28, 2005 | |
| Title | Rcs Through Wall Leakage Identified At Welded Piping Junction |
| Event Description | At 1035 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.938175e-4 months <br /> on the morning of 3/28/05, investigation into a previously reported leak (Event #41530) identified an approximate 3 inch through wall flaw at the welded junction of the 4 inch diameter decon port and the 28 inch diameter 'B' Reactor Recirculation Systems pump suction piping. The identification of the indication required the removal of insulation in order to complete the inspection. The unidentified leakage rate is below Tech Spec limits and the leak location is within the isolable boundary of the 'B' Reactor Recirculation Pump. This failure constitutes a welding or material defect in the primary coolant system that is not acceptable under ASME Section XI for ASME Code Class 1 piping.
This report is being made under Hope Creek Event Classification Guide RAL# 11.2.1 in accordance with 10CFR50.72(b)(3)(ii). At the time of this notification, the Hope Creek Generating Station is in OPCON 4 at 150 degrees reactor coolant temperature to support piping repairs. The licensee informed the Lower Alloways Creek Township and NRC Resident Inspector. |
| Where | |
|---|---|
Hope Creek  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+0.28 h0.0117 days <br />0.00167 weeks <br />3.83544e-4 months <br />) | |
| Opened: | Clyde Bauer 15:52 Mar 28, 2005 |
| NRC Officer: | Steve Sandin |
| Last Updated: | Mar 28, 2005 |
| 41536 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
WEEKMONTHYEARENS 571032024-05-03T08:11:0003 May 2024 08:11:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Primary Containment Degraded ENS 564942023-04-30T05:00:00030 April 2023 05:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Primary Containment Integrity Degraded ENS 491102013-06-13T06:52:00013 June 2013 06:52:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Discovery of Pressure Boundary Leakage ENS 415362005-03-28T15:35:00028 March 2005 15:35:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Rcs Through Wall Leakage Identified at Welded Piping Junction 2024-05-03T08:11:00 | |