ENS 56411
ENS Event | |
|---|---|
03:57 Mar 15, 2023 | |
| Title | Reactor Coolant System (RCS) Boundary Degraded Condition |
| Event Description | 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). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
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. Notified R2DO (Miller) |
| 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
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Unit 2 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Shutdown (0 %) |
| After | Hot Shutdown (0 %) |
WEEKMONTHYEARENS 564112023-03-15T03:57:00015 March 2023 03:57:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System (RCS) Boundary Degraded Condition ENS 563712023-02-18T10:39:00018 February 2023 10:39:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition ENS 562572022-12-03T16:00:0003 December 2022 16:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Discovered on Shutdown Cooling Test Line ENS 557062022-01-16T05:20:00016 January 2022 05:20:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Discovered on Shutdown Cooling Test Line ENS 539592019-03-26T15:30:00026 March 2019 15:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Report of Degraded Condition Due to Leaking Valve ENS 451072009-05-31T18:30:00031 May 2009 18:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Discovery of Pressure Boundary Leakage ENS 446802008-11-23T18:00:00023 November 2008 18:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressure Boundary Leak ENS 436592007-09-22T17:45:00022 September 2007 17:45:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressure Boundary Leakage Discovered During Drywell Inspection 2023-03-15T03:57:00 | |