ENS Event | |
|---|---|
15:30 Oct 23, 2022 | |
| Title | Reactor Coolant System (RCS) Pressure Boundary Degradation |
| Event Description | The following information was provided by the licensee via email:
At 0830 PDT on 10/23/2022, during routine outage inspections on Unit 2, it was determined that the RCS Pressure Boundary did not meet ASME Section XI acceptance criteria on a 2-inch vacuum refill connection line. This event is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
Diablo Canyon  California (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+3.58 h0.149 days <br />0.0213 weeks <br />0.0049 months <br />) | |
| Opened: | Brian Engleton 19:05 Oct 23, 2022 |
| NRC Officer: | Adam Koziol |
| Last Updated: | Oct 23, 2022 |
| 56176 - NRC Website
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WEEKMONTHYEARENS 561762022-10-23T15:30:00023 October 2022 15:30:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System (RCS) Pressure Boundary Degradation ENS 425472006-05-03T09:14:0003 May 2006 09:14:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition ENS 421362005-11-11T20:00:00011 November 2005 20:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Report of Degraded Condition Due to Defective Steam Generator Tubes ENS 406892004-04-21T01:10:00021 April 2004 01:10:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition - Greater than One Percent of Steam Generator Tubes Defective ENS 406592004-04-08T20:00:0008 April 2004 20:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition - Greater than One Percent of Steam Generator Tubes Defective 2022-10-23T15:30:00 | |