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

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

Enclosure

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 Type Designation Description or Title Revision or

Procedure Date

71111.21N.05 Calculations SE-C051326701-Nuclear Safety Capability Assessment - Fire Area 5.0

010 Compliance Assessment

SE-C051326701-Recovery Action Feasibility Evaluation Revision 2.0

011

SM-C051326701-NFPA 805 Radiological Release Calculation Revision 2.0

010

Corrective Action CR11057001 AOP Missing actions 03/06/2024

Documents CR11060600 Remove CO2 signage 03/19/2024

Resulting from

Inspection

Drawings A-181805 NFPA 805 Fire Protection Program Design Basis Version 9.0

Document

D-207607 Elementary Diagram - HHSI to RCS Cold Leg Motor Version 15.0

Operated Valves - Sheet 1

D-207607 Elementary Diagram - LHSI to RCS Cold Leg MOVs - Version 1.0

Sheet 2

D-207608 Elementary Diagram - Charging/SI Pumps Isolation 575V Version 15.0

Motor Operated Valve - Sheet 1

SM-SNC901326-HYDRAULIC NODE DRAWINGS ATTACHMENT 2

005

Engineering SNC4559697 NFPA 805: U2 Circuit Protection and DC Shunt 3/3/2016

Changes

Engineering 05354-RPT-01 Farley Incipient Detection Review Rev. 2

Evaluations F-RIE-FIREPRA-Resolution of CAR 2017-018 - Farley Nuclear Plant NSCAVersion 1

U00-016

F-RIE-FIREPRA-NFPA 805 Transition Risk Results for Farley Version 1

U00-017

SM84-2-2980- ANALYSIS FOR COMPLIANCE IWTH SEISMIC 03/02/1985

206-5 CATEGORY REQUIREMENTS

Fire Plans FNP-2-FPP-1.0 Unit 2 Auxiliary Building Pre-Fire Plan Revision 4.1

Procedures A181017 FUNCTIONAL SYSTEM DESCRIPTION VERSION

FIRE PROTECTION SYSTEM 45

Inspection Type Designation Description or Title Revision or

Procedure 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 VERSION

FP IMPAIRMENT (FPIP) REQUIREMENTS 129

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 VERSION

DETAILED REVIEWS 13

Work Orders SNC566099 NFPA 805: Ckt Protection & DC Shunt DCP-459697 11/5/2014

6