IR 05000269/2026010

From kanterella
Jump to navigation Jump to search
Fire Protection Team Inspection FPTI Report 05000269/2026010, 05000270/2026010 and 05000287/2026010
ML26035A177
Person / Time
Site: Oconee  
Issue date: 02/04/2026
From: Daniel Bacon
NRC/RGN-II/DORS
To: Snider S
Duke Energy Carolinas
References
IR 2026010
Download: ML26035A177 (0)


Text

SUBJECT:

OCONEE NUCLEAR STATION - FIRE PROTECTION TEAM INSPECTION (FPTI) REPORT 05000269/2026010 AND 05000270/2026010 AND 05000287/2026010

Dear Steven M. Snider:

On January 29, 2026, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Oconee Nuclear Station and discussed the results of this inspection with Mr. Todd Grant, Site Engineering General Manager and other members of your staff. The results of this inspection are documented in the enclosed report.

One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at Oconee Nuclear Station.

February 4, 2026 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. 05000269 and 05000270 and 05000287 License Nos. DPR-38 and DPR-47 and DPR-55

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000269, 05000270 and 05000287

License Numbers:

DPR-38, DPR-47 and DPR-55

Report Numbers:

05000269/2026010, 05000270/2026010 and 05000287/2026010

Enterprise Identifier:

I-2026-010-0030

Licensee:

Duke Energy Carolinas, LLC

Facility:

Oconee Nuclear Station

Location:

Seneca, SC

Inspection Dates:

January 12, 2026 to January 29, 2026

Inspectors:

J. Alamudun, Reactor Inspector

D. Dang, Resident Inspector

W. Monk, Senior Reactor Inspector (Team Lead)

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 (FPTI) at Oconee 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 Semi-Annual Visual Turbine Building Deluge Systems Grinnell Heat Detector Inspections as Required by NFPA 72-2013 Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000269,05000270,05000287/2026010-01 Closed None (NPP)71111.21N.05 The NRC identified a Green Non-Cited Violation (NCV) of Oconee Nuclear Station (ONS) Units 1, 2, & 3 RFOL, 3.D, Fire Protection, for the licensees failure to complete semi-annual visual inspections of Turbine Building Grinnell thermostat heat detectors as required by NFPA 72, Fire Alarm / Detection System, Code of Record 2013 Section 10.3, Inspection.

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) (3 Samples)

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)a. Review deficiencies or open fire protection impairments for the selected system, including any temporary modifications, operator workarounds, or compensatory measures.

b. Verify that operator actions can be accomplished as assumed in the licensees FHA, or as assumed in the licensees fire probabilistic risk assessment (FPRA) analysis and SSA.

c. Review repetitive or similar maintenance work requests, which could be an indicator of a design deficiency and could affect the ability of the components to perform their functions when needed.

d. Ensure that post-maintenance and/or surveillance activities are performed as scheduled.

e. Perform a walkdown inspection to identify equipment alignment discrepancies. Inspect for deficient conditions such as corrosion, missing fasteners, cracks, and degraded insulation.

f. Ensure the selected SSCs that are subject to aging management review (AMR) pursuant to 10 CFR Part 54 are being managed for aging (e.g., loss of material, cracking, reduction of heat transfer) in accordance with appropriate aging management programs. Verify that the licensees aging management program activities (such as Fuel Oil Analysis or Selective Leaching Aging Management Program) associated with FP equipment are being implemented.

g. If a review of operating experience issues will be completed for the selected inspection sample, verify that the licensee adequately reviewed and dispositioned the operating experience in accordance with their processes.

SSC #1 (Fire Prevention) - Transient Combustible Controls Program

(2) SSC #2 (Detection / Suppression) - U1/U2/U3 Main Feedwater Pump Suppression Systems
(3) SSC #3 (Safe Shutdown) - U1/U2/U3 Emergency Feedwater Systems

Fire Protection Program Administrative Controls (IP Section 03.02) (2 Samples)

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) Fire Protection Admin Program #1 - Hot Work Program
(2) Fire Protection Admin Program #2 - Fire Brigade Drills and Training Program

Fire Protection Program Changes/Modifications (IP Section 03.03) (1 Sample)

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 consistently with the FPP or design change.

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

(1) FPP Change #1 - EC 421928 (ONS-2023-007) - Standby Shutdown Facility (SSF)

Fire Detection System Replacement

INSPECTION RESULTS

No Semi-Annual Visual Turbine Building Deluge Systems Grinnell Heat Detector Inspections as Required by NFPA 72-2013 Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000269,05000270,05000287/2026010-01 Closed None (NPP)71111.21N.05 The NRC identified a Green Non-Cited Violation (NCV) of Oconee Nuclear Station (ONS) Units 1, 2, & 3 RFOL, 3.D, Fire Protection, for the licensees failure to complete semi-annual visual inspections of Turbine Building Grinnell thermostat heat detectors as required by NFPA 72, Fire Alarm / Detection System, Code of Record 2013 Section 10.3, Inspection.

Description:

When the inspection team was walking down the Main Feedwater Pump Fire Water Suppression systems, it was noted that a few of the associated Grinnell quartzoid thermostat heat detectors had accumulated debris/loading around the thermal element which could cause an insulating thermal effect resulting in the heat detectors to not activate at their rated design temperature. The inspectors asked for the surveillance inspection history of the fire suppressions detection system, and it was determined that these heat detectors were not visually inspected as required by NFPA 72-2013, Fire Alarm / Detection System.

Additionally, the licensee conducted an extent of condition and determined that all the Turbine Building deluge fire suppression systems quartzoid thermostat heat detectors were not being visually inspected on a semi-annual basis. Each of the three ONS Units have two Main Feedwater Pump, one Turbine-driven Emergency Feedwater and one Main Turbine Lube Oil Conditioning fire suppression deluge systems.

Corrective Actions:

  • Action was needed to identify all required heat detectors not currently being visually inspected on site.
  • Additionally, action was needed to develop procedures and preventative maintenance (PMs) to perform semi-annual visual inspections as required by NFPA 72-2013.

Corrective Action References: This issue is tracked in the licensees CAP under NCR 2582298 - 2026 ONS NRC FPTI: Fire Detection Visual Inspections Not Performed as Required, 01/14/2026 and NCR 2582270, 2026 ONS NRC FPTI: Replace Quartzoid Detector at Front of the 1B Feedwater Turbine, 01/14/2026.

Performance Assessment:

Performance Deficiency:

The licensees failure to complete visual inspections of the sites quartzoid thermostat heat detectors was a performance deficiency (PD). Specifically, NFPA 72, Fire Alarm / Detection System, COR 2013 Section 10.3.1, states visual inspection shall be performed IAW the schedules in Table 10.3.1 (Heat Detectors - Semiannually).

Screening:

The inspectors determined that the performance deficiency (PD) was more-than-minor because if left uncorrected it would have the potential to lead to a more significant safety concern. Specifically, the lack of periodic visual inspections of the heat detectors precludes the licensees ability to detect material deficiency conditions which could lead to the thermal heat detectors failing to activate their associated water suppression system at their design/rated temperature.

Significance:

The inspectors assessed the significance of the finding using Appendix F, Fire Protection and Post - Fire Safe Shutdown SDP. Using IMC 0609, Appendix F, Attachment 1, the NRC team determined that the finding screened to Green (very low safety significance)because the fire finding adversely affected an area with adequate automatic detection and suppression (Question 1.4.1-B). Therefore, the issued screened to Green, and no further analysis was required.

Cross-Cutting Aspect:

Not Present Performance. No cross-cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.

Enforcement:

Violation:

ONS license condition 3.D requires in part, that the licensee shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), NFPA Standard 805, 2001 Edition. NFPA 805, Section 3.2.3, Procedures, states Procedures shall be established for implementation of the fire protection program. In addition to procedures that could be required by other sections of the standard, the procedures to accomplish inspection, testing, and maintenance for fire protection systems and features credited by the fire protection program.

The licensees fire protection program is committed to NFPA-72 for heat detectors. NFPA 72-2013, Fire Alarm / Detection System, Section 10.3.1, states visual inspection shall be performed in accordance with the schedules in Table 10.3.1 (Heat Detectors - Semiannually).

Contrary to the above, since the sites Turbine Building deluge fire suppression systems (i.e.,

Main Feed Pump, Lube Oil Conditioning, and TDEFW Pump fire water suppression systems)commissioning (1973) the license failed to perform the required semiannual visual inspections of these systems heat detector initiating devices.

Enforcement Action:

This violation is being treated as a non-cited violation (NCV), consistent with Section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained nor documented in this report.

On January 29, 2026, the inspectors presented the FPTI

Exit Meeting

inspection results to Mr.

Todd Grant, Site Engineering General Manager and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

OSC-8837

Unit 1 Feedwater Pump A NFPA 15 Code Compliance

07/25/2006

OSC-8838

Unit 1 Feedwater Pump B NFPA 15 Code Compliance

07/25/2006

Calculations

OSC-9659

Oconee Nuclear Safety Capability Assessment For Units 1,

2, and 3

Rev. 12

AR 02518117

SSF Pump Room Zone 11 Beam Detector

06/03/2024

Corrective Action

Documents

NCR 2580376

Fire Detector TROUBLE Alarm

2/25/2025

AR 2581969

AD-TQ-ALL-0086 Procedure Revise Request

01/13/2026

AR 2582302

26 ONS NRC FPTI: Remove Transient Combustibles and

Close Storage Locker

01/14/2026

AR 2582303

26 ONS NRC FPTI: Remove Transient Material within 8

of Front of Heater

01/14/2026

NCR 2582270

26 ONS NRC FPTI: Replace Quartzoid Detector at Front

of the 1B Feedwater Turb

01/14/2026

Corrective Action

Documents

Resulting from

Inspection

NCR 2582298

26 ONS NRC FPTI: Fire Detection Visual Inspections Not

Performed as Required

01/14/2026

O-0310-L-001

TURBINE BUILDING - UNIT 1 FIRE PROTECTION PLAN

Rev. 11

OFD-121D-1.1

Emergency Feedwater System

Rev. 40

Drawings

OFD-124C-1.2

FLOW DIAGRAM OF HIGH-PRESSURE SERVICE WATER

SYSTEM TURBINE BUILDING

Rev. 43

Fire Plans

CSD-ONS-PFP-

1TB-0775

Pre-Fire Plan for U1 Turbine Building Elevation 775

Rev. 1

Grinnell Quartzoid Thermostat Model F910 Spec Sheet

Rev. 0

25 Annual Fire Department Site Access Training

Rev. 1

ADM-NFPA805

Fire Protection Program

Rev. 0

ONS USFAR

Section 9.5.1

Fire Protection

Rev. 30

71111.21N.05

Miscellaneous

ONS-25-010390

Fire Protection Impairment Form - Fire Hydrant 23 Broken

2/23/2025

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

AD-FP-ALL-1520

TRANSIENT COMBUSTIBLE CONTROL

Rev. 4

AD-FP-ALL-1521

HOT WORK PERMITS

Rev. 4

AD-FP-ALL-1523

TEMPORARY IGNITION SOURCE CONTROL

Rev. 0

AD-OP-ALL-0207

FIRE BRIGADE ADMINISTRATIVE CONTROLS

Rev. 8

AD-TQ-ALL-0086

FIRE BRIGADE AND HAZMAT TRAINING

REV. 8

IP/0/A/0250/005 H

Periodic Test/Replacement of Mulsifyre Heat Detectors

REV 010

IP/0/B/0385/002 B

STANDBY SHUTDOWN FACILITY FIRE DETECTION

SYSTEM VISUAL INSPECTION

REV 012

MP/0/A/1705/019

Fire Protection - SLC-Related Fire Doors - HELB Doors -

Annual And Bi-Monthly Inspections

Rev. 31

OSS-0072.0A-00-

0004

FIRE PROTECTION ACCEPTANCE SPECIFICATION

Rev. 21

OSS-0254.00-00-

1000

Design Basis Specification for the Emergency Feedwater

System

Rev. 61

OSS-0254.00-00-

4008

Design Basis Specification for Fire Protection

Rev. 53

PD-FP-ALL-1500

Fleet Fire Protection Program Manual

Rev. 3

PT/0/B/0250/003

SSF FIRE DETECTION CONTROL PANEL TEST

Rev. 0

PT/1/A/0250/010

Fire Suppression Systems Dry Pipe Test

Rev. 23

Procedures

PT/1/A/250/10B

Fire Suppression Systems Test

Rev. 22

WO 02164719

IP/0/A/250/5H - RANDOMLY REPLACE MULSIFYRE FIRE

DETECTORS

06/08/2015

WO 20294601

IP/0/A/250/5H - RANDOMLY REPLACE MULSIFYRE FIRE

DETECTORS

06/30/2021

WO 20491045-51

EC 421928 SSF FIRE DETECTION POWER FAILURE

TESTING

04/28/2025

WO 20491045-52

EC 421928 Fire Detection Verify FACU #PL0007 Factory

Wiring

2/31/2024

Work Orders

WO 20493300

PT/1/A/0250/010B - Fire Suppression Systems Test

04/15/2023

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

WO 20629208

PT/1/A/0250/010B - Fire Suppression Systems Test

05/26/2025

WO 20661864

SEMI/ANNUAL INSPECTION OF FIRE DETECTOR

2/02/2024

WO 20697005

SEMI/ANNUAL INSPECTION OF FIRE DETECTOR

07/30/2025

WO 20711504

SSF FIRE DETECTION VISUAL INSPECTION

REV 01

WR 20270102

SSF PUMP ROOM ZONE 11 BEAM DETECTOR

06/03/2024