IR 05000443/2023010
| ML23291A356 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 10/19/2023 |
| From: | Glenn Dentel Division of Operating Reactors |
| To: | Coffey B Florida Power & Light Co |
| References | |
| IR 2023010 | |
| Download: ML23291A356 (1) | |
Text
October 19, 2023
SUBJECT:
SEABROOK STATION - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000443/2023010
Dear Bob Coffey:
On October 5, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Seabrook Station and discussed the results of this inspection with Brian Booth, Site Vice President, 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 (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Glenn T. Dentel, Chief Engineering Branch 2 Division of Operating Reactor Safety
Docket No. 05000443 License No. NPF-86
Enclosure:
As stated
Inspection Report
Docket Number:
05000443
License Number:
Report Number:
Enterprise Identifier: I-2023-010-0035
Licensee:
NextEra Energy Seabrook, LLC
Facility:
Seabrook Station
Location:
Seabrook, New Hampshire
Inspection Dates:
September 18, 2023 to October 5, 2023
Inspectors:
L. Cline, Senior Reactor Inspector
M. Patel, Senior Reactor Inspector
B. Pinson, Senior Reactor Inspector
Approved By:
Glenn T. Dentel, 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 triennial fire protection inspection at Seabrook 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
Structures, Systems, and Components 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) Fire Pumps and Tanks
- (3) Service Water System
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 Fire Protection Program (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 System Impairments
- (2) Fire Brigade Training, Drills, and Qualifications
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 (UFSAR),fire protection report, FHA, and SSA were updated consistent with the FPP or design change.
e. Post-fire safe shutdown operating procedures, such as abnormal operating procedures, affected by the modification were updated.
- (1) EC 296106 - Emergency Feedwater System Pump House Fire with A Loss of Offsite Power Incorporation Into UFSAR Appendix R Design Basis
- (2) EC290177-Fire Pump Skid and Controller Replacement
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 5, 2023, the inspectors presented the triennial fire protection inspection results to Brian Booth, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.05 Calculations
C-S-1-20801
Emergency Feedwater System Flow Study
Revision 1
C-S-1-80801
Appendix R Timing Calculations for Decay Heat Removal
Revision 2
C-S-1-84019
Appendix R Timing Calculations for Decay Heat Removal
Revision 1
C-S-1-84213
Appendix R Timing Calculations for Reactor Coolant
Inventory Control
Revision 2
C-S-1-84214
Appendix R Timing Calculations for Reactivity Control
Revision 0
Corrective Action
Documents
AR 024400009
Corrective Action
Documents
Resulting from
Inspection
Engineering
Changes
EFW Pump House Fire With A Loss Of Offsite Power
Incorporation Into UFSAR Appendix R Design Basis
Fire Pump Skid and Controller Replacement
Miscellaneous
Seabrook Station Evaluation and Comparison to BTP
APCSB 9.5-1, Appendix A
Revision 19
Seabrook Station Fire Protection of Safe Shutdown
Capability (10 CFR 50 Appendix R)
Revision 18
Procedures
Fire Protection Screening
Revision 14
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CFR Applicability and 10 CFR 50.59 Screening
Reviews
Revision 23
FPI.40
Fire Protection Instruction - Pre-fire Strategies/Brigade
Response Guidelines for Charcoal Filter Fire Alarms
Revision 2
ON0443.35
Fire Brigade Ready Area Inventory
Revision 13
OS1090.05
Component Configuration Control
Revision 84
OS1200.00
Response to Fire or Fire Alarm Actuation
Revision 28
OS1200.01
Safe Shutdown and Cooldown from the Main Control
Room
Revision 29
OS1200.02
Safe Shutdown and Cooldown from the Remote Safe
Shutdown Facilities
Revision 26
OS1200.02A
Remote Safe Shutdown Control - Train A
Revision 20
OS1200.02B
Remote Safe Shutdown Control - Train B
Revision 21
OS1200.05
Response to EFW Pump House Fire
Revision 0
OX0443.10
Fire Pumps' Annual Flow Capacity Test
Revision 16
SM7.20
Control of Time Critical Operator Actions and Time
Sensitive Actions
Revision 18