IR 05000324/2023011
| ML23355A057 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/26/2023 |
| From: | Daniel Bacon NRC/RGN-II/DRS/EB2 |
| To: | Krakuszeski J Duke Energy Progress |
| References | |
| IR 2023011 | |
| Download: ML23355A057 (10) | |
Text
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT - NRC FIRE PROTECTION TEAM INSPECTION (FPTI) REPORT 05000324/2023011 AND 05000325/2023011
Dear John A. Krakuszeski:
On December 14, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Brunswick Steam Electric Plant and discussed the results of this inspection with Mr. Jay Ratliff, Plant General Manager, 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. 05000324 and 05000325 License Nos. DPR-62 and DPR-71
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000324 and 05000325
License Numbers:
Report Numbers:
05000324/2023011 and 05000325/2023011
Enterprise Identifier:
I-2023-011-0014
Licensee:
Duke Energy Progress, LLC
Facility:
Brunswick Steam Electric Plant
Location:
Southport, NC
Inspection Dates:
November 27, 2023, to December 14, 2023
Inspectors:
W. Monk, Senior Reactor Inspector (Team Lead)
J. Montgomery, Senior Reactor Inspector
D. Strickland, Reactor Inspector
M. Carothers, Reactor Inspector (Observing)
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 Brunswick Steam Electric 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 industry 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).
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.
- (2) SSC #2 (Detection/Suppression) - U1 & U2 High Pressure Coolant Injection (HPCI)
High Pressure CO2 Fire Suppression System
- (3) SSC #3 (Safe Shutdown) - U1 & U2 Emergency Diesel Generator (EDG) System and Emergency Electrical Buses
- (4) SSC #4 (Safe Shutdown) - U1 & U2 Low Pressure Coolant Injection and Residual Heat Removal (LPCI / RHR) 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 Administration Program #1 - NFPA 805 Monitoring Program
- (2) Fire Protection Administration Program #2 - Fire Brigade Drills and Training 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) Fire Protection Program Change #1: EC 421458 - U1 HPCI Room CO2 Panel Replacement Modification
- (2) Fire Protection Program Change #2: EC 420076 - Temporary Fire Protection Water Supply
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained nor documented in this report.
- On December 14, 2023, the inspectors presented the NFPA 805 Fire Protection Team Inspection (FPTI) Exit Meeting results to Mr. Jay Ratliff, Plant General Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
BNP NFPA 805 Monitoring Target Value Calculation
Rev. 5
Evaluation of MOV Pressure Boundaries for IN 92-18 Hot-
Short Events
Rev. 6
NFPA 805 Transition - Fire Area RB1-1 Fire Safety
Analysis for Unit 1
Rev. 2
NFPA 805 Transition - Fire Area RB1-6 Fire Safety
Analysis for Unit 1
Rev. 0
BNP-E-9.007
ASSD Recovery Action Feasibility
Rev. 2
Calculations
BNP-E-9.010
NFPA 805 Nuclear Safety Capability Assessment (NSCA)
Rev. 4
AD-EG-ALL-1501 Fire Protection Program / Plant Impact
Review Form - Alternate Compensatory Actions
associated with the Non-Functional Diesel Building
Basement Halon System
Rev. 0
NCR 2318122
20 NRC Fire Protection Inspection QFPI 2-VA-DG-
FDMP-101
2/26/2020
Corrective Action
Documents
NCR 2492653
Diesel Generator Basement Halon Non-Functional Longer
than 0PLP-01.2 Allowance
10/31/2023
NCR 2496053
NRC TFPI - Walkdown Findings
11/29/2023
NCR 2498085
Enhancement Identified for ASSD Procedure
Implementation
2/14/2023
NCR 2498142
23 NRC FPTI - NSCA (BNP-E-9.010) Discrepancy
2/14/2023
NTM 2496744
BNP-E-9.010 Update for RB1-N
2/05/2023
PRR 2495999
1PT-34.10.1.0 (Remove PM Frequency from Procedure)
11/29/2023
PRR 2496001
2PT-34.10.1.0 (Remove PM Frequency from Procedure)
11/29/2023
PRR 2496740
Update ASSD-05 Phone Jack Location
2/05/2023
PRR 2497373
0PT-48.4 Procedure Updates
2/11/2023
PRR 2498077
0ASSD-00 Procedure Update
2/14/2023
Corrective Action
Documents
Resulting from
Inspection
2-FP-LIS-1431 GAUGE NUMBERS WORN OFF
11/30/2023
LL-92037 Sheet
Unit No. 1 - Motor Control Center "1XB" & "1XB-2" Switch
Development
Rev. 8
71111.21N.05
Drawings
LL-92037 Sheet
Unit No. 1 - MCC 1XB and 1XB-2 Switch Development
Rev. 7
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
17A
LL-92037 Sheet
17B
Unit No. 1 - MCC 1XB and 1XB-2 Switch Development
Rev. 7
LL-92037 Sheet
Unit No. 1 - MCC "1XB-2" Compt. "1-DL7" RHR Inboard
Inj. Vlv. 1-E11-F015B Control Wiring Diagram
Rev. 7
LL-92037 Sheet
Unit No. 1 - MCC "1XB-2" Compt. "1-DL7" RHR Inboard
Inj. Vlv. 1-E11-F015B Cable Diagram
Rev. 14
LL-92037 Sheet
Unit No. 1 - MCC "1XB-2" Compt. "1-DL7" RHR Inboard
Inj. Vlv. 1-E11-F017B Control Wiring Diagram
LL-92037 Sheet
Unit No. 1 - MCC "1XB-2" Compt. "1-DL7" RHR Inboard
Inj. Vlv. 1-E11-F017B Cable Diagram
Temporary Fire Protection Water Supply
Rev. 5
U1 HPCI Room CO2 Panel Replacement
Rev. 0
Engineering
Changes
Documentation of RIS 2005-007 Evaluation for Diesel
Generator Building Basement Halon System Non-
Functional
Rev. 0
AD-OP-BNP-
205
Time Re-validation for Action to Begin to Depressurize the
Reactor Pressure Vessel for Fire in The North U2 Reactor
Building
07/20/2022
AD-OP-BNP-
205
Start Suppression Pool Cooling Time Critical Action/ Time
Sensitive Action Validation
07/20/2022
AD-OP-BNP-
205
Emergency 4KV Busses Re-energized Time Critical
Action/Time Sensitive Action Validation
07/17/2022
BNP-LR-300
Electrical Integrated Plant Assessment (IPA)
Rev. 3
BNP-LR-315
License Renewal Aging Management Review - Residual
Heat Removal System (2045)
Rev. 2
Engineering
Evaluations
BNP-LR-336
License Renewal Aging Management Review - Diesel
Generator System (5095)
Rev. 0
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Docket
Nos. 50-325, 50-324 License Amendment Request to
Adopt NFPA 805 Performance-Based Standard for Fire
Protection for Light Water Reactor Electric Generating
Plants (2001 Edition)
09/25/2012
Miscellaneous
Gaseous Suppression System - Brunswick Units 1 & 2
Rev. 3
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
FIRE PROTECTION PROGRAM MANUAL
Rev. 27
Alternative Safe Shutdown User's Guide Procedure
Rev. 51
Alternate Safe Shutdown Procedure Index
Rev. 42
Control Building Alternative Safe Shutdown Procedure
Rev. 65
E6 SWITCHGEAR ROOM
Rev. 2
Fire Protection Semiannual Inspection
Rev. 72
0PLP-01.2
FIRE PROTECTION SYSTEM FUNCTIONALITY,
ACTION, AND SURVEILLANCE REQUIREMENTS
Rev. 60
Reactor Building North Fire Safe Shutdown Procedure
Rev. 35
Reactor Building South Alternative Safe Shutdown
Procedure
Rev. 26
AD-EG-ALL-1503
Fire Protection Performance Monitoring and Other
Program Elements
Rev. 5
AD-EG-ALL-1650
License Renewal Aging Management
Rev. 5
AD-FP-ALL-1520
TRANSIENT COMBUSTIBLE CONTROL
Rev. 0
AD-FP-ALL-1523
TEMPORARY IGNITION SOURCE CONTROL
Rev. 0
AD-HU-ALL-0004
Procedure and Work Instruction Use and Adherence
Rev. 15
AD-OP-ALL-0207
Fire Brigade Administrative Controls
Rev. 5
AD-OP-ALL-1000
Conduct of Operations
Rev. 22
AD-OP-BNP-
205
BNP Time Critical Actions/Time Sensitive Actions
Supplement
Rev. 2
AD-PI-ALL-0100
CORRECTIVE ACTION PROGRAM
Rev. 30
CSD-BNP-FPF-
1RB
Reactor Building Pre-fire Plans
Rev. 2
Procedures
PD-FP-ALL-1500
FLEET FIRE PROTECTION PROGRAM MANUAL
Rev. 1
20589223
LPCI/RHR System Operability Test - LOOP A
06/04/2023
20593855/01
LPCI/RHR System Operability Test - LOOP B
06/29/2023
20598236-01
ASSD Sound-Powered Phone System Functional Test
07/29/2023
20614455/
205311618
Core Spray System Operability Test - LOOP B
10/24/2023
20615611
ASSD Sound-Powered Phone System Functional Test
10/28/2023
20621548
LPCI/RHR System Component Test-LOOP A
09/27/2023
Work Orders
20627177/01
LPCI/RHR System Component Test-LOOP A
10/26/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
OPT-34.5.6.0 - Diesel Generator Building Halon System
Functional Test
09/02/20221
1PT-34.10.1.0 Plant High Pressure CO2 Fire
Extinguishing System Inspection
04/19/2022
OPT-34.5.6.0 - Diesel Generator Building Halon System
Functional Test
09/20/2022
2PT-34.10.1.0 Plant High Pressure CO2 Fire
Extinguishing System Inspection
11/30/2022
1PT-34.10.1.0 Plant High Pressure CO2 Fire
Extinguishing System Inspection
11/04/2022
OFPP-008 Fire Protection Equipment Semiannual
Inspection
01/25/2023
2PT-34.10.1.0 Plant High Pressure CO2 Fire
Extinguishing System Inspection
03/30/2023
OPT-34.4.2.1 - Diesel Generator Building Halon Fire
Extinguishing Systems
05/08/2023
1PT-34.10.1.0 Plant High Pressure CO2 Fire
Extinguishing System Inspection
05/15/2023
2PT-34.10.1.0 Plant High Pressure CO2 Fire
Extinguishing System Inspection
06/16/2023
OFPP-008 Fire Protection Equipment Semiannual
Inspection
07/27/2023
OPT-34.4.2.1 - Diesel Generator Building Halon Fire
Extinguishing Systems
09/26/2023
1PT-34.10.1.0 Plant High Pressure CO2 Fire
Extinguishing System Inspection
10/16/2023