IR 05000413/2024010
| ML25044A484 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/14/2025 |
| From: | Daniel Bacon NRC/RGN-II/DORS/EB2 |
| To: | Flippin N Duke Energy Carolinas |
| References | |
| I-2024-010-0043 IR 2024010 | |
| Download: ML25044A484 (1) | |
Text
SUBJECT:
CATAWBA NUCLEAR STATION - FIRE PROTECTION TEAM INSPECTION REPORT 05000413/2024010 AND 05000414/2024010
Dear Nicole Flippin:
On January 16, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Catawba Nuclear Station and discussed the results of this inspection with you 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 Operating Reactor Safety Docket Nos. 05000413 and 05000414 License Nos. NPF-35 and NPF-52
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000413 and 05000414
License Numbers:
Report Numbers:
05000413/2024010 and 05000414/2024010
Enterprise Identifier:
I-2024-010-0043
Licensee:
Duke Energy Carolinas, LLC
Facility:
Catawba Nuclear Station
Location:
York, SC
Inspection Dates:
November 18, 2024 to January 16, 2025
Inspectors:
J. Alamudun, Reactor Inspector
P. Braaten, Senior Reactor Inspector
J. Montgomery, Senior Reactor Inspector
Approved By:
Daniel M. Bacon, Chief
Engineering Branch 2
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a fire protection team inspection at Catawba Nuclear Station, 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).
- (3) Unit 2 RN (Service Water) System
- (4) Unit 2 CA (Auxiliary Feedwater) 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) NFPA 805 Monitoring Program
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) CNS 2024-001, Limiting detectors credit in proximity to fire rated assembly based upon UL spacing
- (2) EC 417257, EC 418258, Addition of auxiliary lube oil pumps to 1A, 1B, 2A, and 2B Emergency Diesel Generators
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 16, 2025, the inspectors presented the fire protection team inspection results to Nicole Flippin and other members of the licensee staff.
- On December 12, 2024, the inspectors presented the initial inspection results to Nicole Flippin and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CNC-1435.00-00-
0039
Evaluation of Auxiliary Feedwater Pump Pit CO2 System
Pilot Valve Inlet Stem
Rev. 00
CNC-1435.00-00-
0044
Fire Protection Nuclear Safety Capability Assessment
Rev. 004
CNC-1435.00-00-
0053
NFPA 12, High Pressure Carbon Dioxide System, Code
Conformance Review for NFPA 805 Transition
Rev. 02
CNC-1435.00-00-
0067
NFPA 805 Transition - Fire Risk Evaluation (FRE)
Rev. 004
Calculations
CNM-1206.08-
0083
High Pressure Carbon Dioxide Flow Calculations, AFWP
1A Calc
Rev. a
24 NRC TFPI: Out of date references in fire safe
shutdown calc
11/19/2024
24 NRC TFPI: 2CA VA0174 Normal Position is
11/21/2024
CNS 2024 NRC FPTI: 2 questions concerning NFPA 805
Monitoring Program
2/9/2024
24 NRC TFPI: Fire PRA Non-Suppression Probability
CO2 system
2/11/2024
Corrective Action
Documents
Resulting from
Inspection
24 NRC TFPI: Observation on NSCA supporting
information
2/12/2024
CN-1574-01.01
Flow Diagram of Nuclear Service Water System (RN)
Rev. 63
CN-1574-01.02
Flow Diagram of Nuclear Service Water System (RN)
Rev. 56
CN-1762-02.20
Connection Diagram Fire Detection System (EFA) CO2
Fire Suppression Aux FDWP Pits
Rev. 13
CN-2574-02.01
Flow Diagram of Nuclear Service Water System (RN)
Rev. 48
CN-2574-02.05
Flow Diagram of Nuclear Service Water System (RN)
Rev. 53
CN-2592-01.00
Flow Diagram of Auxiliary Feedwater System (CA)
Rev. 32
CN-2592-01.01
Flow Diagram Auxiliary Feedwater System (CA)
Rev. 34
CN-2592-01.02
Flow Diagram of Auxiliary Feedwater System (CA)
Rev. 1
CN-2713-31.01
Connection Diagram Left Front Half Input Cabinet 2IC31
Rev. 10
71111.21N.05
Drawings
CN-2716-03.05-
Connection Diagram Standby Shutdown Facility Auxiliary
Relay Interface Cabinet 2ELCC0034 EOC System
Rev. 37
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CN-2779-02.15
Connection Diagram Aux Feedwater Sys (CA) RC to CA
Suct Isol Vlv 2CA174
Rev. 0
CNEE-0215-
01.33-01
Elementary Diagram 4160V Switchgear 2ETB Unit #13
Auxiliary Feedwater Pmp. Mtr. 2B
Rev. 7
CNEE-0247-
01.04
Elementary Diagram Auxiliary Feedwater System (CA,
SA) Auxiliary Fdw Turbine Driven Pump Ind. Lights &
Rev. 6
CNEE-0247-
2.02
Elementary Diagram Auxiliary Feedwater Sys (CA) Driven
& Motor Pmps A&B Loss of Suction
Rev. 7
CNEE-0247-
03.03
Elementary Diagram Auxiliary Feedwater Sys. (CA) CA to
Nuclear Service Wtr Alignment and CA Pmp B Autio Start
Circuitry
Rev. 5
CNWT-2717-
2.17
Wiring Tabulations Area Terminal Cabinet 2ATC17
Rev. 031
CNWT-2779-
01.01
Wiring Tabulations Aux Fdw Pmp Turb Control Panel
2AFWPTCP
Rev. 043
Engineering
Changes
Install Aux Lube Oil Pumps on the 1A and 1B EDGs
Engineering
Evaluations
CNC-1435.00-00-
0084
Catawba NFPA 805 Monitoring Program
Rev. 002
AD-EG-ALL-1501
Fire Protection Change Process
Rev. 5
AD-EG-ALL-1503
FIRE PROTECTION PERFORMANCE MONITORING
AND OTHER PROGRAM ELEMENTS
Rev. 5
Procedures
AP/0/A/5500/045
Plant Fire
Rev. 20
Unit 2 Aux FDWP CO2 System Test (18 month)
08/22/2021
Unit 2 Aux FDWP CO2 Annual Test
08/21/2022
Unit 2 Aux FDWP CO2 System Test (18 Month)
05/17/2023
Unit 2 Aux FDWP CO2 System Annual Test
08/20/2023
Unit 2 Aux Feedwater Pump Room CO2 Test
04/09/2024
Work Orders
Unit 2 Aux Feedwater Pump Room CO2 Test
07/24/2024