IR 05000348/2024011

Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011

ML24100A808
Person / Time
Site:	Farley
Issue date:	04/12/2024
From:	Daniel Bacon NRC/RGN-II/DRS/EB2
To:	Coleman J Southern Nuclear Operating Co
References
IR 2024011
Preceding documents:	ML24026A053 (30 January 2024)
Download: ML24100A808 (8)

Text

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT - FIRE PROTECTION TEAM INSPECTION REPORT 05000348/2024011 AND 05000364/2024011

Dear Jamie Coleman:

On March 21, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Joseph M. Farley Nuclear Plant and discussed the results of this inspection with Edwin D.

Dean III (Sonny) and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Daniel M. Bacon, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos. 05000348 and 05000364 License Nos. NPF-2 and NPF-8

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000348 and 05000364 License Numbers:

NPF-2 and NPF-8 Report Numbers:

05000348/2024011 and 05000364/2024011 Enterprise Identifier:

I-2024-011-0018 Licensee:

Southern Nuclear Operating Co., Inc.

Facility:

Joseph M. Farley Nuclear Plant Location:

Columbia, AL Inspection Dates:

March 04, 2024 to March 22, 2024 Inspectors:

E. Coffman, Reactor Inspector L. Jones, Senior Reactor Inspector J. Montgomery, Senior Reactor Inspector Approved By:

Daniel M. Bacon, Chief Engineering Branch 2 Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a fire protection team inspection at Joseph M. Farley Nuclear Plant, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

71111.21N.05 - Fire Protection Team Inspection (FPTI) Structures, Systems, and Components (SSCs) Credited for Fire Prevention, Detection, Suppression, or Post-Fire Safe Shutdown Review (IP Section 03.01)

The inspectors verified that components and/or systems will function as required to support the credited functions stated for each sample. Additional inspection considerations are located in the fire hazards analysis (FHA) or safe shutdown analysis (SSA).

(1) Preaction sprinkler system 2A-43

(2) Preaction sprinkler system 2A-45

(3) Unit 2 Chemical Volume & Control System/High Head Safety Injection

(4) Unit 2 125VDC Electrical Distribution System

Fire Protection Program Administrative Controls (IP Section 03.02) (1 Sample)

The inspectors verified that the selected control or process is implemented in accordance with the licensees current licensing basis. If applicable, ensure that the licensees FPP contains adequate procedures to implement the selected administrative control. Verify that the selected administrative control meets the requirements of all committed industry standards.

(1) Radioactive Release Administrative Controls

Fire Protection Program Changes/Modifications (IP Section 03.03) (2 Samples)

The inspectors verified the following:

a. Changes to the approved FPP do not constitute an adverse effect on the ability to safely shutdown.

b. The adequacy of the design modification, if applicable.

c. Assumptions and performance capability stated in the SSA have not been degraded through changes or modifications.

d. The FPP documents, such as the Updated Final Safety Analysis Report, fire protection report, FHA, and SSA were updated consistent with the FPP or design change.

e. Post-fire SSD operating procedures, such as abnormal operating procedures, affected by the modification were updated.

(1) SNC 1495144 - Replacement of HSS Small Orifice Sprinkler Heads

(2) TE 1137363 - Evaluate Removal of Auxiliary Building Incipient Detection from FPP

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On March 21, 2024, the inspectors presented the fire protection team inspection results to Edwin D. Dean III (Sonny) and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

SE-C051326701-

010

Nuclear Safety Capability Assessment - Fire Area

Compliance Assessment

5.0

SE-C051326701-

011

Recovery Action Feasibility Evaluation

Revision 2.0

Calculations

SM-C051326701-

010

NFPA 805 Radiological Release Calculation

Revision 2.0

CR11057001

AOP Missing actions

03/06/2024

Corrective Action

Documents

Resulting from

Inspection

CR11060600

Remove CO2 signage

03/19/2024

A-181805

NFPA 805 Fire Protection Program Design Basis

Document

Version 9.0

D-207607

Elementary Diagram - HHSI to RCS Cold Leg Motor

Operated Valves - Sheet 1

Version 15.0

D-207607

Elementary Diagram - LHSI to RCS Cold Leg MOVs -

Sheet 2

Version 1.0

D-207608

Elementary Diagram - Charging/SI Pumps Isolation 575V

Motor Operated Valve - Sheet 1

Version 15.0

Drawings

SM-SNC901326-

005

HYDRAULIC NODE DRAWINGS ATTACHMENT 2

Engineering

Changes

SNC4559697

NFPA 805: U2 Circuit Protection and DC Shunt

3/3/2016

05354-RPT-01

Farley Incipient Detection Review

Rev. 2

F-RIE-FIREPRA-

U00-016

Resolution of CAR 2017-018 - Farley Nuclear Plant NSCA

Version 1

F-RIE-FIREPRA-

U00-017

NFPA 805 Transition Risk Results for Farley

Version 1

Engineering

Evaluations

SM84-2-2980-

206-5

ANALYSIS FOR COMPLIANCE IWTH SEISMIC

CATEGORY REQUIREMENTS

03/02/1985

Fire Plans

FNP-2-FPP-1.0

Unit 2 Auxiliary Building Pre-Fire Plan

Revision 4.1

71111.21N.05

Procedures

A181017

FUNCTIONAL SYSTEM DESCRIPTION

FIRE PROTECTION SYSTEM

VERSION

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

FNP-0-AOP-29.0

Abnormal Operating Procedure Plant Fire

07/26/2023

FNP-0-FPP-4.0

Radioactive Release Plan

Revision 1.0

FNP-0-SOP-0.4

FIRE PROTECTION PROGRAM ADMINISTRATION AND

FP IMPAIRMENT (FPIP) REQUIREMENTS

VERSION

29

FNP-2-SOP-62.0

Emergency Air Systems

Revision

30.0

NMP-ES-035-010

Fire Brigade

Revision 7.0

NMP-ES-05-006

FIRE PROTECTION PROGRAM IMPACT SCREEN AND

DETAILED REVIEWS

VERSION

Work Orders

SNC566099

NFPA 805: Ckt Protection & DC Shunt DCP-459697

11/5/2014