ML24262A223

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Part Event Notification 57330. Part 21 - Control Relay Defect
ML24262A223
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 09/18/2024
From: Murrell W
Point Beach
To: Hoc H
Document Control Desk, Office of Nuclear Reactor Regulation
References
57330
Download: ML24262A223 (1)


Text

From: Murrell, Bob To: Hoc, HOO X

Subject:

[External_Sender] Point Beach Part Event Notification#57330 Date: Wednesday, September 18, 2024 1:35:52 PM

Here is the wording from the EN for Point Beach.

Part 21 - CONTROL RELAY DEFECT

NextEra Energy Point Beach, LLC (NextEra) makes the following notification under 10 CFR 21.21(d)(3)(i) of a defect found in a Westinghouse relay, model NBFD31S, during pre-installation bench testing. Specifically, the relay was found to not function as required due to its internal plunger not operating properly. This malfunctioning caused the plunger to not fully extend and cause the normally open contacts to remain closed. Investigations completed by Westinghouse determined that the plunger would not function properly because its kickout spring was misaligned due to human error. This relay was procured from Westinghouse for safety related nuclear applications.

NextEra has concluded that this defect constitutes a Substantial Safety Hazard (SSH). An SSH exists because of the nature of the defect was such that the relay would not be able to perform its safety function, if installed, and would result in a loss of redundancy in a safety related system, in this case, the Reactor Protection System.

On September 17, 2024, the Point Beach Site Vice President was notified of the requirement to report this event under 10 CFR 21.21. This is a non-emergency notification required by 10 CFR 21.21(d)(3)(i). A written notification in accordance with 10 CFR 21.21(d)(3(ii) will be provided within 30 days.

Since this defect was discovered prior to installation, in accordance with station requirements for bench testing, and the vendor has concluded that this event is an isolated case, there were no actual impacts on Safety Related equipment.

The NRC Resident Inspector has been notified.