IR 05000369/2023001

Integrated Inspection Report 05000369/2023001 and 05000370/2023001

ML23118A014
Person / Time
Site:	McGuire, Mcguire
Issue date:	05/01/2023
From:	Eric Stamm Division Reactor Projects II
To:	Pigott E Duke Energy Carolinas
References
IR 2023001
Download: ML23118A014 (12)

Text

SUBJECT:

MCGUIRE NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000369/2023001 AND 05000370/2023001

Dear Edward Pigott:

On March 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at McGuire Nuclear Station. On April 12, 2023, the NRC inspectors 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, Eric J. Stamm, Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos. 05000369 and 05000370 License Nos. NPF-9 and NPF-17

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000369 and 05000370

License Numbers:

NPF-9 and NPF-17

Report Numbers:

05000369/2023001 and 05000370/2023001

Licensee:

Duke Energy Carolinas, LLC

Facility:

McGuire Nuclear Station

Location:

Huntersville, North Carolina

Inspection Dates:

January 1, 2023, to March 31, 2023

Inspectors:

C. Safouri, Senior Resident Inspector

F. Young, Resident Inspector

D. Ray, Reactor Inspector

M. Schwieg, Senior Reactor Inspector

Approved By:

Eric J. Stamm, Chief

Reactor Projects Branch 1

Division of Reactor Projects

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at McGuire 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 findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 operated at or near 100 percent rated thermal power (RTP) for the entire inspection period.

Unit 2 began the inspection period at or near 100 percent RTP. On February 18, 2023, the unit was shut down for the remainder of the inspection period for a scheduled refueling outage (M2R28).

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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk-significant activities, and completed on-site portions of IPs. 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.

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather tornado watch, tornado warning, and severe thunderstorm warning, on January 12, 2023.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 2 train B emergency diesel generator (EDG) while Unit 2 train A EDG was out of service for planned maintenance, on January 10, 2023

(2) Unit 2 train A and train B spent fuel cooling system, on March 6, 2023

(3) Unit 1 train A nuclear service water system (RN), on March 14, 2023

(4) Unit 2 low temperature overpressure protection system while Unit 2 was in mode 4, on March 29, 2023

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 train A and train B residual heat removal (ND) system while the reactor coolant system was in lowered inventory, on February 23, 2023.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Standby shutdown facility, on January 30, 2023

(2) Unit 2 safety-related emergency switchgear and associated HVAC rooms, on February 1, 2023

(3) Units 1 and 2 auxiliary building elevation 733' vital battery area, on March 8, 2023

(4) Unit 1 train A and train B EDG rooms, on March 17, 2023

(5) Unit 2 upper containment building, on March 28, 2023

(6) Unit 2 lower containment building, on March 28, 2023

Fire Brigade Drill Performance Sample (IP Section 03.02) (2 Samples)

(1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill, on January 8, 2023. The fire scenario involved a fire in the Unit 1 lube oil purifier in the Unit 1 turbine building basement.

(2) The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill, on January 12, 2023. The fire scenario involved a fire in the Unit 2 generator seal oil pump system.

71111.07A - Heat Exchanger/Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) PT/2/A/4403/007, "RN Train A Flow Balance," on March 9, 2023

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)

The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:

(1) Ultrasonic Examination

reactor head thermal sleeve inspection Visual Examination

reactor head bare metal inspection Welding Activities

cold leg check valves 2NI-21 and 2NI-349 PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection

Activities (IP Section 03.02) (1 Sample)

The inspectors verified that the license conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:

(1) reactor head bare metal inspection

reactor head thermal sleeve inspection PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)

The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:

(1) threaded fittings associated with flow transmitter 2-NI-FT-5450, action request (AR) 2419116

threaded fitting associated with flow transmitter 2-FW-FT-5250, AR 2424371

packing gland associated with valve 2-NV-VA-0060, AR 2437743

containment boric acid walkdown

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the control room during reactor shutdown and plant cooldown for Unit 2 refueling outage, on February 18, 2023.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated just in time training associated with refueling outage preparations, specifically on startup and zero power physics testing, on February 9, 2023.

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1) Emergent work and protected equipment plan associated with the failure of the 120VAC nonsafety-related auxiliary control power panelboard inverter (KXA), on January 4, 2023

(2) Equipment protection plan for Unit 1 train A component cooling water (KC) during preventive maintenance on Unit 1 train B KC auxiliary building non-essential header isolation valve (1KC-53B), on January 5, 2023

(3) Equipment protection plan for Unit 2 while in yellow shutdown risk for decay heat removal and inventory control due to lowered inventory, on February 23, 2023

(4) Unit 2 high risk evolution associated with core fuel offload during the refueling outage, on February 26, 2023

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Nuclear condition report (NCR) 02454406, Unit 2 upper airlock volumetrics failure - Airlock Operability Test (PT/2/A/4200/020A) failed acceptance criteria, on January 18, 2023

(2) NCR 02458167, oil leak on the isolation valve for Unit 2 train B steam generator power operated relief valve (2SV-28), on January 24, 2023

(3) NCR 02457570, water found in Unit 1 train B diesel fuel oil storage tank, on January 26, 2023

(4) NCR 02462518, several ice condenser baskets weighed less than expected during end of cycle surveillance, on February 27, 2023

(5) NCR 02463633, thermal sleeve wear discovered on locations F06 and K10, on March 6, 2023

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)

The inspectors evaluated the following temporary or permanent modifications:

(1) Engineering change 101501, implementation of an alternative wiring method for the close torque bypass switch on Rotork actuators for Unit 2 train A ND reactor coolant system (NC) isolation valve (2ND-19A), on January 17, 2023

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)

(1)

(Partial)

The inspectors evaluated Unit 2 refueling outage (M2R28) activities from February 18, 2023, to March 31, 2023. The inspectors completed inspection procedure Sections 03.01.a through 03.01.c

71111.24 - Testing and Maintenance of Equipment Important to Risk

The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:

Post-Maintenance Testing (PMT) (IP Section 03.01) (3 Samples)

(1) PT/1/A/4350/002B, "Diesel Generator 1B Operability Test," following Unit 1 train B EDG governor booster servomotor replacement, on January 3, 2023

(2) PT/0/A/4350/030, "Nordberg Diesel Engine 6 year Periodic Maintenance," on Unit 2 train B EDG, on March 14, 2023

(3) PT/2/A/4200/008B, "NC Pressure Isolation Valve Test," following repairs on safety injection to Unit 2 train A cold leg check valve (2NI-171), on March 31, 2023

Surveillance Testing (IP Section 03.01) (4 Samples)

(1) IP/1/A/3000/006C, "OTDT Channel Calibration Protection III," on January 11, 2023

(2) PT/1/A/4201/001A, "RWST Level Auto-Switchover Analog Channel Operational Test,"

on January 24, 2023

(3) PT/2/A/4200/009A, Engineered Safety Features Actuation Periodic Test Train A, Section 12.3, Unit 2 train A EDG load testing and engineered safety features valve stroking upon safety injection, phase A isolation, phase B isolation, and blackout signals, on February 19, 2023

(4) PT/2/A/4200/009A, Engineered Safety Features Actuation Periodic Test Train A, Section 12.4, Unit 2 train A EDG response testing with offsite power available upon safety injection signal, on February 19, 2023

Inservice Testing (IST) (IP Section 03.01) (2 Samples)

(1) PT/0/A/4250/037, "Main Steam Safety Valve Setpoint Test Using Set Pressure Verification Device (SPVD)," on Unit 2 valves 2SV-8, 2SV-9, 2SV-10, 2SV-11, and 2SV-12, on February 15, 2023

(2) PT/2/A/4204/004C, "A and B ND Pump Head Curve Verification," on February 27, 2023

Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)

(1) PT/2/A/4200/001C, "Isolation Valve Leak Rate Test," Enclosure 13.11, "Test Sheet for Penetration M-278 (NI)," for Unit 2 train B emergency core cooling system sump piping drain reservoir and associated isolation valves, on February 28, 2023

Reactor Coolant System Leakage Detection Testing (IP Section 03.01) (1 Sample)

(1) PT/1/A/4150/001B, "Reactor Coolant Leakage Calculation," due to Unit 1 elevated NC unidentified leakage, on January 6, 2023

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (2 Samples)

The inspectors evaluated:

(1) A simulator exam consisting of a failure of an intermediate range instrumentation; inadvertent start of the turbine driven auxiliary feedwater pump; and steam generator tube rupture requiring a reactor trip and safety injection, on January 20, 2023

(2) A technical support center qualification tabletop drill consisting of a failure of all three fission product barriers, on January 23,

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===

(1) Unit 1 (January 1, 2022, through December 31, 2022)

(2) Unit 2 (January 1, 2022, through December 31, 2022)

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)

(1) Unit 1 (January 1, 2022, through December 31, 2022)

(2) Unit 2 (January 1, 2022, through December 31, 2022)

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)

(1) Unit 1 (January 1, 2022, through December 31, 2022)

(2) Unit 2 (January 1, 2022, through December 31, 2022)

71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)

(1) NCR 02462518, several ice condenser baskets weighed less than expected during end of cycle surveillance, on February 27,

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On March 6, 2023, the inspectors presented the Unit 2 inservice inspection results to Edward Pigott and other members of the licensee staff.

On April 12, 2023, the inspectors presented the integrated inspection results to Edward Pigott and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

RP/0/A/5700/006

Natural Disasters

71111.01

Procedures

RP/0/B/5700/027

Severe Weather Preparation

MCFD-2551-

2.00

Flow Diagram of Chemical and Volume Control System (NV)

MCFD-2554-

01.02

Flow Diagram of Chemical and Volume Control System (NV)

MCFD-2554-

03.00

Flow Diagram of Chemical and Volume Control System (NV)

MCFD-2554-

03.01

Flow Diagram of Chemical and Volume Control System (NV)

Drawings

MCFD-2561-

01.00

Flow Diagram of Residual Heat Removal (ND)

OP/2/A/6200/004

Residual Heat Removal System

2

71111.04

Procedures

OP/2/A/6350/002

Diesel Generator

119

Corrective Action

Documents

Resulting from

Inspection

Nuclear Condition

Report(s)

2456811

Fire Plans

CSD-MNS-PFP-

AB-0733-001

Auxiliary Building Elevation 733 Pre-Fire Plan

71111.05

Procedures

AD-OP-ALL-0207

Fire Brigade Administrative Controls

71111.07A

Procedures

PT/2/A/4403/007

RN Train 2A Flow Balance

2

NDE-NE-ALL-

7301

VT-3 VISUAL EXAMINATION

71111.08P

Procedures

TE-MN-PWR-

0006

INSPECTION, ASSESSMENT, AND CLEANUP OF BORIC

ACID ON PLANT MATERIALS

Licensed Operator - Just in Time Training - Startup -

Simulator Exercise Guide

2/24/2021

Miscellaneous

Licensed Operator - Just in Time Training - Simulator

Exercise Guide - Initial Criticality and Zero Power Physics

Testing

09/01/2020

71111.11Q

Procedures

OP/2/A/6100/003

Controlling Procedure for Unit Operation

203

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Corrective Action

Documents

Nuclear Condition

Report(s)

2454401, 02467113

Corrective Action

Documents

Resulting from

Inspection

Nuclear Condition

Report(s)

2462559

AD-OP-ALL-0201

Protected Equipment

71111.13

Procedures

AP/1/A/5500/15

Loss of Vital of Aux Control Power

Corrective Action

Documents

Nuclear Condition

Report(s)

2457570, 02406930, 02401057, 02458167

MCS-1593.SM-

00-0001

Design Basis Specification for the SM, SV and SB Systems

71111.15

Miscellaneous

MCTC-1593-

SM.V006-01

SG PORV Isolation 1/2SV-25, -26, -27 and -28, Testing and

Acceptance Criteria, Units 1 & 2

2NI-201

MCSRD - NI System Reactor building

Drawings

2NI-211

MCSRD - NI System Reactor Building (Sh. 3 of 3)

Miscellaneous

AD-OP-ALL-0106

2NI-171 Repair - Freeze Seal - Conduct of Infrequently

Performed Tests of Evolutions

03/30/2023

AD-OP-ALL-0200

Clearance and Tagging

IP/1/A/3000/006C

OTDT Channel Calibration Protection III

PT/0/A/4250/037

Main Steam Safety Valve Setpoint Test Using Set Pressure

Verification Device (SPVD)

PT/0/A/4350/030

Nordberg Diesel Engine 6 Year Periodic Maintenance

PT/1/A/4150/001B

Reactor Coolant Leakage Calculation

105

PT/1/A/4150/055

NC System Unidentified Leakage OAC Point Determination

PT/2/A/4200/008B

NC Pressure Isolation Valve Leak Test

PT/2/A/4204/004C

2B ND Pump Comprehensive Test

71111.24

Procedures

TE-MN-ALL-0410

Freeze Seals

71114.06

Procedures

CSD-EP-MNS-

0101-01

EAL Technical Basis Document

71152A

Corrective Action

Documents

Resulting from

Inspection

Nuclear Condition

Report(s)

2457706