IR 05000324/2022010
| ML22172A033 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/27/2022 |
| From: | James Baptist Division of Reactor Safety II |
| To: | Krakuszeski J Duke Energy Progress |
| References | |
| IR 2022010 | |
| Download: ML22172A033 (12) | |
Text
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000324/2022010 AND 05000325/2022010
Dear Mr. Krakuszeski:
On May 13, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Brunswick Steam Electric Plant 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, James B. Baptist, Chief Engineering Br 1 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:
05000324/2022010 and 05000325/2022010
Enterprise Identifier:
I-2022-010-0037
Licensee:
Duke Energy Progress, LLC
Facility:
Brunswick Steam Electric Plant
Location:
Southport, NC
Inspection Dates:
April 25, 2022 to May 13, 2022
Inspectors:
P. Braxton, Reactor Inspector
C. Franklin, Reactor Inspector
L. Haeg, Project Manager
T. Su, Reactor Inspector
Approved By:
James B. Baptist, Chief
Engineering Br 1
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) 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 standards.
REACTOR SAFETY
===71111.21M - Design Bases Assurance Inspection (Teams) The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:
Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (5 Samples)
- (1) Unit 2 Emergency Diesel Generator (EDG) Load Timing Relays 2-DG4-STR/2B-3/4
System transient requirements
Modification performed affecting Design Basis Functions
Operating Environment
Operating Procedures
Surveillance test procedures and performed procedures
System health reports
- (2) Unit 2 DC Battery/Battery Charger 2-2A-1-125VDC-CHRGR/BAT, 2-2A-2-125VDC-CHRGR/BAT
Compliance with Updated Final Safety Analysis (UFSAR) and Technical Specifications (TS), and Design Basis Document (DBD)
Material condition and configuration
Operating environment
Consistency between station documentation (e.g. procedures) and vendor specifications
Maintenance effectiveness
Designs requirements
Surveillance testing
- (3) Unit 1 Instrument Air N2 Solenoids 1-RNA-SV-5481/5482
System transient requirements
Modification performed affecting Design Basis Functions
Operating Environment
Operating Procedures
Backup Nitrogen Surveillance test procedures reviews
- (4) Unit 1 High Pressure Coolant Injection (HPCI), Reactor Core Isolation Cooling (RCIC)1-E41-C001, 1-E51-C001)
Material condition and configuration (e.g., visual inspection during a walkdown)
Operating environment
Design calculations (pump head, capacity, NPSH)
Consistency among design and licensing bases and other documents/procedures
Maintenance effectiveness and records, and corrective action history
Operating procedures
Surveillance testing and recent test results
Component health reports
- (5) Unit 2 Nuclear Service Water (NSW)/ Common Service Water (CSW) Pumps and Strainers 2-SW-2A-NUC-PMP, 2-SW-2B-NUC-PMP, 2-SW-2C-CONV-PMP
Material condition and configuration (e.g., visual inspection during a walkdown)
Operating environment
Design calculations (pump head, capacity, NPSH)
Consistency among design and licensing bases and other documents/procedures
Maintenance effectiveness and records, and corrective action history
Operating procedures
Surveillance testing and recent test results
Component health reports Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02)===
- (1) Unit 2 Residual Heat Removal (RHR) Heat Exchangers (HX) and Bypass Valve 2-E11-B00B1B, 2-E11-F048B
Material condition and configuration (e.g., visual inspection during a walkdown)
Operating environment
Design calculations
Consistency among design and licensing bases and other documents/procedures
Maintenance effectiveness and records, and corrective action history
Operating procedures
Surveillance testing and recent test results
Component health reports
Modification Review - Permanent Mods (IP Section 02.03) (6 Samples)
- (3) EC418443 -UAT Backfeed breaker Modification
- (4) EC295433 - NSW/CSW Pump Replacements
Review of Operating Experience Issues (IP Section 02.06) (2 Samples)
- (1) IN 2021-01 Lessons Learned from POV DBAI
- (2) IN 2010-25 Inadequate Electrical Connections
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On May 13, 2022, the inspectors presented the design basis assurance inspection (teams) inspection results to John A. Krakuszeski and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
89-068-2
HPCI Minimum Flow Calculation
Rev. 0
27-8-E41-06-F
NPSH Requirements - RCIC and HPSI
Rev. 0
BNP-E-6.079
Unit 1 & 2 - 125 V DC Battery Charger Sizing Calculation
Rev. 10
BNP-E-6.083
Unit 2 125/250 VDC Coordination Protection
Calculation
Rev. 10
BNP-E-6.085
Unit 2 125/250 V DC Coordination/Protection Calculation
Rev.8
BNP-E-6.087
Unit 2 124/250V DC Power Cable Ampacity
Rev. 12
BNP-E-6.120
25/250V DC System Battery Load Study
Rev.15
BNP-E-7.002
AC Auxiliary Electrical Distribution System Voltage/ Load
Flow/Fault Current Study
Rev. 16
DC Electrical System
Rev. 16
G0050A-12
BNP Unit No. 2 SWS Hydraulic Analysis
Rev. 13
G0050A-18
SW System Instrumentation and Control Setpoint Review
Rev.1
G0050A-20
Hydraulic Analysis of the Cooling Water Intake Canal and
Pump Intake Structure
Rev. 0
M-89-0021
HPCI/RCIC NPSH with Suction from the CST
Rev. 0
M-89-0021
HPCI/RCIC NPSH with Suction from the CST
Rev. 0
OSWB-0006
SW Intake Structure Heat Loads and Ventilation
Requirements
Rev.1
Calculations
PCN-G0050A-13
NSW and CSW Pressure Switch Setpoints for Pump Auto
Start,
Rev. 4
Corrective Action
Documents
717634,
258503,
259496,
261604,
277159,
287709,
2343684,
2349302,
2375869,
2380075,
2383437,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2391622,
2411224,
2421361, 96-
01675,
283394,
2337098,
2349404,
2349869,
2354643,
2359058,
2364279,
2396560, AR
106230-10, AR
00697175
25459
Typographical Error in Calculation PCN-G0050A-13
26668
Pipe Stress Calcs not Analyzed to Maximum Allowed
Temperature
27208
Inadequate Documentation - SW Shear Key Failure
Evaluations
Corrective Action
Documents
Resulting from
Inspection
NCR 1676661
Missing Documentation of scaled model testing of the CST
C24004
Inservice Inspection Isometric for Class II High Pressure
Coolant Injection System
Rev. 2
D-02041
Sht. 2, Piping Diagram, Service Water System
Rev. 67
D-02041
Sht. 1, Piping Diagram, Service Water System
Rev. 65
D-02529
Sht. 1, Piping Diagram, Reactor Core Isolation Cooling
System
Rev. 62
D-25023
Reactor Building High Pressure Coolant Injection System
Piping Diagram
Rev. 61
F-03026
Emergency Key One Line Diagram 4160V, 480V, 120/208V,
20/240V AC & 24/48V, 125/250V DC
Rev. 13
Drawings
F03006
Single Line Diagram 125/250V DC System Distribution
Switchboard 2A & 2B
Rev.39
416835
RWCU Valve 1-G31-F004 Replacement
Engineering
Changes
417289
Valve Data Sheet for 1-G31-F004
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
05/11/2007
Evaluate LL3 Avoidance with RCIC Operation Post Scram
Rev.1
RCIC Pump Performance Criteria Revision to OPT-10.1.1
Rev. 0
Jet Air Assist Upgrades
Rev. 56
Relay and Timing Upgrades
Rev. 62
Service Water Pump Replacement Master
Rev. 16
Replace CST Low Water Level Transmitters
Rev. 8
Service Water Pump Replacement Child EC
Rev. 5
Emergency Diesel Generator No. 1 Sync Check Relay
Rev. 0
Engineering
Evaluations
8001818-ER-1
Evaluation of the Flywheel 2301A Governor Upgrade on
Nordberg Model FS-1316-HSC EDG
2/08/2013
For Master EC 295433 - SW Pump Replacements
08/17/2017
BN-16.0.1
RCIC System
Rev. 5
CSD-EG-DEP-
0106
AC and DC Overcurrent Protection and Coordination
High Pressure Coolant Injection System
Rev. 27
Emergency Diesel Generator and Supplemental Diesel
Generator System
Rev. 28
Service Water System
Rev.18
Instrument Air & Service Air Systems
Rev. 19
Battery Charger Manual
Rev. H
Stationary Battery Manual
Rev. M
PGB005-PR-01
Diesel Generator Governor Replacement Study for the
Brunswick Nuclear Plant
8/13/2008
QCE 02061145-
1A NSW Pump Strainer Shear Pin Sheared
10/20/2016
SD-43
Service Water System
Rev. 27
Time Critical
Operator Action
Validation ASSD
RCIC In Service and Injecting into Reactor Pressure Vessel
11/25/2017
Miscellaneous
Time Critical
Operator Action
Battery Chargers are Re-Energized
09/25/2016
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Validation SBO 2
0AOP-18.0
NSW System Failure
Rev. 34
0AOP-19.0
Conventional Service Water System Failure
030
0AOP-19.0,
CSW System Failure
Rev. 30
0AOP-20.0
Pneumatic (Air/Nitrogen) System Failures
Rev. 52
0AOP-39.0
Loss of DC Power
2
Alternative Safe Shutdown Procedure Index
Control Building
000
Loss of All AC and DC Powered Injection
004
Battery Load Stripping
2
0PT-08.2.2B
LPCI/RHR System Operability Test Loop B
03/22/2022
0PT-09.2
HPCI System Operability Test
04/05/2022
0PT-09.8
HPCI System Coupled Overspeed Trip Test
2/17/2020
0PT-10.1.1
RCIC System Operability Test
04/05/2022
0PT-10.1.3
RCIC System Operability Test Flowrates at 150 psig
04/03/2022
0PT-10.1.8
RCIC System Valve Operability Test, Rev. 45,
01/12/2022
Governor Dynamic Tunning
Rev. 2
Station Blackout
004
RCIC System Operating Procedure
Rev. 93
SWS Operating Procedure
Rev. 175
2PT-24.1-2
SW Pump and Discharge Valve Operability Test, Rev. 89
03/17/22
2PT-24.1-2
SW Pump and Discharge Valve Operability Test, Rev. 89
03/17/2022
AD-OP-ALL-0205
Time Critical Actions/Time Sensitive Actions
AD-PI-ALL-0100
Corrective Action Program
Rev. 26
AD-PI-ALL-0400
Operating Experience Program
AS-OP-BNP-
205
BNP Time Critical Actions/Time Sensitive Actions
Supplement
Valves and operators
AG
Procedures
OPT-51.7
RCIC System EOP Component Functional Test, Rev. 4
03/16/2020
Work Orders
20066716-01,
20386029-02,
13527308-01,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
20410987-43,
20397484-05,
20397484-06,
20397581-05,
20411001-01,
20437889-03,
20465428-01,
20465428-02,
20483386-01,
20483386-02,
20495775-01,
20499261-01,
20499261-02,
20512084-01