ENS 56411: Difference between revisions
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| NRC officer = Kerby Scales | | NRC officer = Kerby Scales | ||
| event date = 03/14/2023 22:57 CDT | | event date = 03/14/2023 22:57 CDT | ||
| last update date = | | last update date = 05/04/2023 | ||
| title = Reactor Coolant System (RCS) Boundary Degraded Condition | | title = Reactor Coolant System (RCS) Boundary Degraded Condition | ||
| event text = The following information was provided by the licensee via email: | | event text = The following information was provided by the licensee via email: | ||
| Line 24: | Line 24: | ||
The following information was provided by the licensee via email: | The following information was provided by the licensee via email: | ||
The purpose of this notification is to retract a previous Event Notification, EN 56411 reported on 3/14/23. | The purpose of this notification is to retract a previous Event Notification, EN 56411 reported on 3/14/23. | ||
Following the initial notification, further analysis of the condition was performed. It was determined that the leaking pipe weld was ASME Section XI Code Class 2 piping which falls under the requirements of ASME Section XI Subsection IWC and not Subsection IWB. Therefore, this condition does not represent a serious degradation of the nuclear power plant | Following the initial notification, further analysis of the condition was performed. It was determined that the leaking pipe weld was ASME Section XI Code Class 2 piping which falls under the requirements of ASME Section XI Subsection IWC and not Subsection IWB. Therefore, this condition does not represent a serious degradation of the nuclear power plant, including its principle safety barriers. Based upon the above, the leaks identified on the ASME Section XI Code Class 2 equivalent Main Steam sense lines are not reportable under 10 CFR 50.72(b)(3)(ii). | ||
Therefore, the NRC non-emergency 10 CFR 50.72(b)(3)(ii) report was not required and the NRC report 56411 can be retracted and no Licensee Event Report under 10 CFR 50.73(a)(2)(ii) is required to be submitted. | Therefore, the NRC non-emergency 10 CFR 50.72(b)(3)(ii) report was not required and the NRC report 56411 can be retracted and no Licensee Event Report under 10 CFR 50.73(a)(2)(ii) is required to be submitted. | ||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2023/ | Notified R2DO (Miller) | ||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2023/20230505en.html#en56411 | |||
}}{{unit info | }}{{unit info | ||
| Unit = 2 | | Unit = 2 | ||
Latest revision as of 07:31, 5 May 2023
| Where | |
|---|---|
Browns Ferry  Alabama (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+0.5 h0.0208 days <br />0.00298 weeks <br />6.849e-4 months <br />) | |
| Opened: | Courtney Rose 04:27 Mar 15, 2023 |
| NRC Officer: | Kerby Scales |
| Last Updated: | May 4, 2023 |
| 56411 - NRC Website
| |