IR 05000348/2024011
| 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 | |
| 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:
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.
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