05000364/LER-2024-002, For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel

For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel

ML24106A162
Person / Time
Site:	Farley
Issue date:	04/15/2024
From:	Dean E Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
NL-24-0123 LER 2024-002-00
Download: ML24106A162 (1)

LER-2024-002, For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv)(B), System Actuation
3642024002R00 - NRC Website

text

A Southern Nuclear Edwin Dean Ill Joseph M. Farley Nuclear Plant Vice President - Farley 7388 North State Hwy 95 Columbia. Alabama 36319 334.661.2100 tel 334.661.2512 fax

EDDEANll@southemco.com

April 15, 2024

Docket No.: 50-364 NL-24-0123

U.S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, D. C. 20555-0001

Joseph M. Farley Nuclear Plant - Unit 2 Licensee Event Report 2024-002-00 Manual Reactor Trip due to Loss of Power to the 2A 125 Volt DC Distribution Panel

Ladies and Gentlemen:

In accordance with the requirements of 10 CFR 21.2(c) and 10 CFR 50.73(a)(2)(iv)(A),

Southern Nuclear Company is submitting the enclosed Licensee Event Report for Unit 2.

This letter contains no NRC commitments. If you have any questions regarding this submittal, please contact Gene Surber, Licensing Manager, at (334) 661-2265.

Respectfully submitted,

Vice President - Farley

ED/rgs/cbg

Enclosure: Unit 2 Licensee Event Report 2024-002-00

Cc: Regional Administrator, Region II NRR Project Manager - Farley Nuclear Plant Senior Resident Inspector-Farley Nuclear Plant RTYPE: CFA04.054 Joseph M. Farley Nuclear Plant - Unit 2 Licensee Event Report 2024-002-00 Manual Reactor Trip due to Loss of Power to the 2A 125 Volt DC Distribution Panel

Enclosure

Unit 2 Licensee Event Report 2024-002-00

Abstract

On February 16, 2024, at 00:48 CDT while in Mode 1 and at 100% power, Farley Nuclear Plant (FNP) operators manually tripped Unit 2 following a loss of control of critical air-operated valves due to a partial loss of A-train DC power. LA08-2, the feeder breaker to the 2A 125VDC Distribution Panel, was found tripped open. This event resulted in a loss of letdown and the reactor makeup system. With volume control tank (VCT) makeup capability lost, operators made the decision to trip the reactor prior to charging pump suction rollover to the refueling water storage tank (RWST).

The cause of the breaker opening was due to a short between wires on the A phase current transformer (CT) / sensor wiring harness in breaker LA08-2 because of poor workmanship. Immediate corrective action included replacing breaker LA08-2 with a spare breaker to restore plant equipment to operation and stabilize the plant.

This event is reportable under 10 CFR 50.73(a)(2)(iv)(A) due to the automatic actuation of multiple systems listed in 10 CFR 50.73(a)(2)(iv)(B). FNP Unit 1 was not affected during this event.

EVENT DESCRIPTION

On February 16, 2024, at 00:48 CDT, with reactor power at 100% and in Mode 1, Farley Nuclear Plant (FNP) operators manually tripped Unit 2 following a partial loss of A-train 125V DC power which affected critical air-operated valves.

Breaker LA08-2 [EIIS: EJ/BKR] the supply breaker to the 2A 125VDC Distribution Panel, was found tripped open. Loss of power to the 2A 125VDC Distribution Panel resulted in a loss of letdown and the reactor makeup system. With the volume control tank (VCT) [EIIS: CB / TK] makeup capability lost operators made the decision to trip the reactor prior to the charging pump suction rollover to the refueling water storage tank (RWST).

Operating events and actions occurred in the following timeline on February 16, 2024:

00:35 Multiple Main Control Room Alarms are received.

00:35 Breaker LA08-02 Tripped (Entry into TS 3.8.9) 00:35 Entry into Abnormal Operating Procedure for CVCS Malfunction 00:36 Entry into Abnormal Operating Procedure of Loss of Instrument Air 00:36 Letdown confirmed isolated and loss of makeup capability.

00:48 Operators Manually Trip Reactor based on VCT level.

01 :42 Reactor Coolant Pump 2B secured due to low seal leak off.

01 :45 Pressurizer (PZR) level rises to Technical Specification {TS) high value of 63.5%. (Entry into TS 3.4.9) 02:09 Instrument Air realigned to Containment.

03:08 Commenced Reactor Coolant System (RCS) Cooldown 04:20 Following troubleshooting and breaker replacement, closed Breaker LA08-02 and restored Letdown (Exit TS 3.8.9) 04:34 NRC notified per 10 CFR 50. 72 (EN 56971) 04:54 PZR level restored (Exit TS 3.4.9)

Following the reactor trip, main feedwater [EIIS: JB] continued to be available. An actuation of the Auxiliary Feedwater System [EIIS: BA] occurred following the manual reactor trip as designed due to low level in the steam generators [EIIS:

SB/SG].

BASIS FOR REPORTABILITY AND SAFETY ASSESSMENT

The safety consequences of this event were low. Although the component failure had downstream interrelation system effects on letdown and makeup, the operating crew appropriately mitigated the transient with abnormal and emergency operating procedures. Additionally, all TS required actions were met and parameters restored well within required action times. The operating crew responded appropriately to the event. This event was within the analysis of the UFSAR Chapter

15. This event is reportable per 10 CFR 50. 73(a)(2)(iv)(A) due to the automatic actuation of the Reactor Protection System

[EIIS: AA] and AFW system as listed in 10 CFR 50.73(a)(2)(iv)(B). FNP Unit 1 was not affected during this event.

CAUSE

The 125 Volt DC AKW breaker was built by Siemens and equipped with SIGMATRIP DC Analog Trip Unit built by SURE-TRIP. Framatome was the vendor used to qualify the safety related breakers and trip units. The analysis determined that the vendor QA/QC program was not sufficient to identify poor practices when interfacing with third party products. It was determined that during installation of the SIGMATRIP DC Analog Trip Unit that the stranded wires that were terminated in the harness protruded in such a manner they were able to short to an adjacent wire in the harness. The short occurred in breaker LA08-2 (Serial Number R-300950258102B-001) on the A phase current transformer {CT)/sensor harness. For the SIGMA TRIP DC Analog Trip Unit, Siemens and Framatome do not currently have a verification step/QA/QC check or any instruction for inspecting the wires connected in the wiring harnesses mounted to the CTs/sensors or the trip unit/logic box.

CORRECTIVE ACTIONS

The associated breaker was immediately replaced by a spare breaker during the event. A systematic plan has been developed to inspect all AKW Series breakers which are installed or will be installed in the plant. Additionally, site actions have been created to monitor the changes by SURE-TRIP, Siemens, and Framatome associated with wire stripping, installation, inspection, and QC/QA checks.

Additionally, Framatome has notified SNC by letter dated March 26, 2024 (L TR24010) that their evaluation has determined that this results in a Part 21 Deviation because the potential failure to inadvertently trip Siemens Low Voltage {LV) AKW circuit breakers is a departure from the technical requirements included in the Procurement Document.

Farley has begun a substantial safety hazard evaluation to determine if the deviation could constitute a defect in this application or if the deviation exists on other breakers delivered under affected Purchase Orders but notes that per 10 CFR 21.2{c) {and Information Notice 2011-19), evaluation and appropriate reporting under 10 CFR 50.73 {as completed herein) satisfies Farley's evaluation, notification, and reporting obligation to report defects under 10 CFR Part 21 for this particular application.

Basic Component: Siemens Low Voltage AKW Circuit Breaker

Serial Number: R-300950258102B-001

Supplying/Dedicating Entity: Framatome Inc.

PREVIOUS SIMILAR EVENTS

No similar events or failure of AKW breakers were identified.