IR 05000324/2022010

Design Basis Assurance Inspection (Teams) Inspection Report 05000324 2022010 and 05000325 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

June 27, 2022

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, Signed by Baptist, James on 06/27/22 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: DPR-62 and DPR-71 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 Enclosure

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)

(1) EC297884 - 885 - Replace Unit 1/2 CST Lo Level Transmitter

(2) EC408563 - 565 - Replace EDG Sync Check Relays

(3) EC418443 -UAT Backfeed breaker Modification

(4) EC295433 - NSW/CSW Pump Replacements

(5) EC296462, 65, 74 - 1C, 2B, 4C EDG Governor Replacement

(6) EC416835 - RWCU Valve 1-G31-F004 Replacement

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 Type Designation Description or Title Revision or

Procedure Date

71111.21M Calculations 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 Rev. 10

Calculation

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-6.120 125/250V DC System Battery Load Study Rev.15

BNP-E-7.002 AC Auxiliary Electrical Distribution System Voltage/ Load Rev. 16

Flow/Fault Current Study

DBD-51 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 Rev. 0

Pump Intake Structure

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 Rev.1

Requirements

PCN-G0050A-13 NSW and CSW Pressure Switch Setpoints for Pump Auto Rev. 4

Start,

Corrective Action 717634,

Documents 02258503,

259496,

261604,

277159,

287709,

2343684,

2349302,

2375869,

2380075,

2383437,

Inspection Type Designation Description or Title Revision or

Procedure Date

2391622,

2411224,

2421361, 96-

01675,

283394,

2337098,

2349404,

2349869,

2354643,

2359058,

2364279,

2396560, AR

106230-10, AR

00697175

Corrective Action 2425459 Typographical Error in Calculation PCN-G0050A-13

Documents 2426668 Pipe Stress Calcs not Analyzed to Maximum Allowed

Resulting from Temperature

Inspection 2427208 Inadequate Documentation - SW Shear Key Failure

Evaluations

NCR 1676661 Missing Documentation of scaled model testing of the CST

Drawings C24004 Inservice Inspection Isometric for Class II High Pressure Rev. 2

Coolant Injection System

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 Rev. 62

System

D-25023 Reactor Building High Pressure Coolant Injection System Rev. 61

Piping Diagram

F-03026 Emergency Key One Line Diagram 4160V, 480V, 120/208V, Rev. 13

20/240V AC & 24/48V, 125/250V DC

F03006 Single Line Diagram 125/250V DC System Distribution Rev.39

Switchboard 2A & 2B

Engineering 416835 RWCU Valve 1-G31-F004 Replacement 7

Changes 417289 Valve Data Sheet for 1-G31-F004 0

Inspection Type Designation Description or Title Revision or

Procedure Date

EC 054587 HPCI CST Vortexing Update 05/11/2007

EC 055880 Evaluate LL3 Avoidance with RCIC Operation Post Scram Rev.1

EC 074364 RCIC Pump Performance Criteria Revision to OPT-10.1.1 Rev. 0

EC 286411 Jet Air Assist Upgrades Rev. 56

EC 286413 Relay and Timing Upgrades Rev. 62

EC 295433, Service Water Pump Replacement Master Rev. 16

EC 296794 Replace CST Low Water Level Transmitters Rev. 8

EC 400469 Service Water Pump Replacement Child EC Rev. 5

EC 408563 Emergency Diesel Generator No. 1 Sync Check Relay Rev. 0

Engineering 8001818-ER-1 Evaluation of the Flywheel 2301A Governor Upgrade on 02/08/2013

Evaluations Nordberg Model FS-1316-HSC EDG

Miscellaneous AR 02144470 For Master EC 295433 - SW Pump Replacements 08/17/2017

BN-16.0.1 RCIC System Rev. 5

CSD-EG-DEP- AC and DC Overcurrent Protection and Coordination 0

0106

DBD-19 High Pressure Coolant Injection System Rev. 27

DBD-39 Emergency Diesel Generator and Supplemental Diesel Rev. 28

Generator System

DBD-43 Service Water System Rev.18

DBD-46 Instrument Air & Service Air Systems Rev. 19

FP-3808 Battery Charger Manual Rev. H

FP-3902 Stationary Battery Manual Rev. M

PGB005-PR-01 Diesel Generator Governor Replacement Study for the 8/13/2008

Brunswick Nuclear Plant

QCE 02061145- 1A NSW Pump Strainer Shear Pin Sheared 10/20/2016

SD-43 Service Water System Rev. 27

Time Critical RCIC In Service and Injecting into Reactor Pressure Vessel 11/25/2017

Operator Action

Validation ASSD

Time Critical Battery Chargers are Re-Energized 09/25/2016

Operator Action

Inspection Type Designation Description or Title Revision or

Procedure Date

Validation SBO 2

Procedures 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 052

0ASSD-01 Alternative Safe Shutdown Procedure Index 41

0ASSD-02 Control Building 60

0EOP-01-ATWS ATWS 000

0EOP-01-FSG-16 Loss of All AC and DC Powered Injection 004

0EOP-01-SBO-10 Battery Load Stripping 002

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 02/17/2020

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

0SMP-GOV001 Governor Dynamic Tunning Rev. 2

1EOP-01-SBO Station Blackout 004

1OP-16 RCIC System Operating Procedure Rev. 93

2OP-43 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 2

AD-PI-ALL-0100 Corrective Action Program Rev. 26

AD-PI-ALL-0400 Operating Experience Program 11

AS-OP-BNP- BNP Time Critical Actions/Time Sensitive Actions 0

205 Supplement

FP-61761 Valves and operators AG

OPT-51.7 RCIC System EOP Component Functional Test, Rev. 4 03/16/2020

Work Orders 20066716-01,

20386029-02,

13527308-01,

Inspection Type Designation Description or Title Revision or

Procedure 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

10