ENS 56411: Difference between revisions
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| emergency class = Non Emergency | | emergency class = Non Emergency | ||
| notification date = 03/15/2023 04:27 | | notification date = 03/15/2023 04:27 | ||
| retracted = Yes | |||
| notification by = Courtney Rose | | notification by = Courtney Rose | ||
| 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 = 03/ | | last update date = 03/28/2023 | ||
| 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: | ||
At 2257 [CDT] on 3/14/2023 during the 2R22 refueling outage on Browns Ferry Nuclear Plant Unit 2, it was determined there was RCS boundary leakage from five of eight sensing lines that pass through containment penetrations X-30 and X-34 that did not meet the requirements of Section XI, of the ASME Boiler and Pressure Vessel Code. The condition will be resolved prior to plant startup. This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A). | At 2257 [CDT] on 3/14/2023 during the 2R22 refueling outage on Browns Ferry Nuclear Plant Unit 2, it was determined there was RCS boundary leakage from five of eight sensing lines that pass through containment penetrations X-30 and X-34 that did not meet the requirements of Section XI, of the ASME Boiler and Pressure Vessel Code. The condition will be resolved prior to plant startup. This event is being reported as an eight-hour, non-emergency notification per 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. | There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. | ||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2023/ | * * * RETRACTION ON 03/28/2023 AT 1059 EST FROM CASEY CARTWRIGHT TO THOMAS HERRITY * * * | ||
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. | |||
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. | |||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2023/20230329en.html#en56411 | |||
}}{{unit info | }}{{unit info | ||
| Unit = 2 | | Unit = 2 | ||
Revision as of 07:30, 29 March 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: | Mar 28, 2023 |
| 56411 - NRC Website
| |