IR 05000369/2023002

Integrated Inspection Report 05000369/2023002 and 05000370/2023002

ML23208A327
Person / Time
Site:	McGuire, Mcguire
Issue date:	07/28/2023
From:	Eric Stamm NRC/RGN-II/DRP/RPB1
To:	Pigott E Duke Energy Carolinas
References
IR 2023002
Download: ML23208A327 (14)

Text

July 28, 2023

SUBJECT:

MCGUIRE NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000369/2023002 AND 05000370/2023002

Dear Edward Pigott:

On June 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at McGuire Nuclear Station. On July 24, 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, Signed by Stamm, Eric on 07/28/23 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: 05000369/2023002 and 05000370/2023002 Enterprise Identifier: I-2023-002-0019 Licensee: Duke Energy Carolinas, LLC Facility: McGuire Nuclear Station Location: Huntersville, North Carolina Inspection Dates: April 1, 2023, to June 30, 2023 Inspectors: C. Safouri, Senior Resident Inspector F. Young, Resident Inspector J. Diaz-Velez, Senior Health Physicist B. Kellner, Senior Health Physicist 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

Type Issue Number Title Report Section Status URI 05000369,05000370/ Technical basis for changes 71124.05 Closed 2022002-02 to calibration frequency of radiation monitors EMF-36,

EMF-44, and EMF-49 LOW and HIGH channels and SLC respective update/

clarification

PLANT STATUS

Unit 1 began the inspection period at 100 percent rated thermal power (RTP) and remained at or near 100 percent RTP for the remainder of the inspection period.

Unit 2 began the inspection period in mode 3 as part of refueling outage M2R28 and returned to 96 percent RTP on April 6, 2023. On April 6, 2023, the unit experienced a turbine runback to approximately 57 percent RTP in response to a loss of 'B' busline and 2B generator circuit breaker lockout. On April 8, 2023, the unit was down powered to 36 percent RTP to secure isophase duct cooling to perform troubleshooting. On April 9, 2023, the unit was raised to 55 percent RTP but closure of the 2B generator circuit breaker was unsuccessful and resulted in a 2B generator circuit breaker lockout. On April 9, 2023, the unit was returned to 36 percent RTP to perform additional troubleshooting and conduct repairs. The unit was returned to 100 percent RTP on April 12, 2023, and remained at or near 100 percent RTP for the remainder of the inspection period.

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

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of hot weather for the following systems:

Auxiliary building ventilation Units 1/2 containment ventilation systems

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (3 Samples)

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

(1) Unit 2 train A and train B motor driven auxiliary feed water pumps and discharge flow paths, on April 5, 2023

(2) Unit 1 main steam isolation and power operated relief valves for 1A, 1B, 1C, and 1D steam generators, on May 2, 2023

(3) Unit 2 train A nuclear service water system while standby nuclear service water pond remote level indication was unavailable, on May 4, 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) Auxiliary building 716' elevation, on April 14, 2023

(2) Auxiliary building 767' elevation, including the main control room, on April 26, 2023

(3) Auxiliary and service building cable spreading rooms, on May 11, 2023

(4) Unit 1 auxiliary feedwater pump room, on May 16, 2023

(5) Unit 1 emergency diesel generator rooms, on May 25, 2023

(6) Unit 1 emergency switchgear and electrical penetration rooms, on June 15, 2023

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 main control room during Unit 2 mode 4 to mode 3 heat up activities, on April 1, 2023, as well as Unit 2 zero power physics testing following refueling outage M2R28, on April 3, 2023.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (3 Samples)

(1) The inspectors observed and evaluated an active simulator exam on May 23, 2023.

The first scenario involved a steam generator power operated relief valve failing open and a loss of all AC power. The second scenario involved an unexpected turbine driven auxiliary feedwater pump start, followed by a failure of the running charging pump, followed by a non-isolable steam line rupture inside containment.

(2) The inspectors observed and evaluated an active simulator exam on May 30, 2023.

The first scenario involved a failure of power range N-42, 1A steam generator power operated relief valve failing open, and an inadvertent turbine trip with an anticipated transient without scram followed by a steam line break outside containment. The second scenario involved a digital electrohydraulic turbine runback due to loss of a 1B busline with a stuck control rod, followed by a loss of coolant accident caused by a control rod ejection event.

(3) The inspectors observed and evaluated an active simulator exam on June 13, 2023. The first scenario involved a failure of intermediate range N-35 and source range N-31, excessive reactor coolant pump vibration requiring a manual reactor trip, and a loss of coolant accident inside containment with subsequent engineered safety features actuation failures. The second scenario involved a loss of component cooling water, loss of spent fuel pool cooling, and a steam generator fault inside containment with a stuck open main steam isolation valve.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (3 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) Nuclear condition report (NCR) 02463522, loss of power on 6.9kV switchgear, 2TA, on March 8, 2023

(2) NCR 02416694, Unit 2 turbine control system plant level event, on May 12, 2023

(3) NCR 02474389, Unit 1 train A emergency diesel generator indication anomaly, on June 15, 2023

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (6 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 on safety injection to Unit 2 train A cold leg check valve reactor coolant pressure isolation valve, 2NI-171, repair/rebuild with a freeze seal application, on March 30, 2023

(2) Emergent work and condition monitoring plan for steam leak on main feedwater drain valve, 2CF-88, on April 25, 2023

(3) Equipment protection plan during Unit 1/2 train B chilled water system planned maintenance outage, on May 8, 2023

(4) Equipment protection plan during Unit 2 spent fuel pool time to 200 degrees Fahrenheit being less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, on May 11, 2023

(5) Equipment protection plan during Unit 2 train A component cooling water system planned maintenance outage, on June 12, 2023

(6) Emergent work and operational risk mitigation plan for loss of the backup power supply for Unit 1 protection channel 2, on June 28, 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) NCR 02470033, Unit 2 non-isolable feedwater drain valve, 2CF-88, leaking through pipe cap, on April 25, 2023

(2) NCR 02471954, Unit 2 train B emergency diesel generator fuel oil piping contact with barring gear motor, on May 8, 2023

(3) NCR 02472536, Unit 1 train B component cooling water motor cooler heat exchanger water leak, on May 16, 2023

(4) NCR 02474839, Unit 1 train A emergency diesel generator time delay relay anomaly, on June 20, 2023

(5) NCR 02477449, Unit 1 loss of backup power supply to protection cabinet channel 2, on June 28, 2023

71111.20 - Refueling and Other Outage Activities

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

(1) The inspectors evaluated Unit 2 refueling outage (M2R28) activities from April 1, 2023, to April 4, 2023. The inspectors completed inspection procedure Sections 03.01.d through 03.01.e.

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)

(1) Work order (WO) 20246240, post maintenance testing following resolution of Unit 2 main turbine throttle valve #3 suspect indications, on April 5, 2023

(2) WO 20543966, Unit 1 train A nuclear service water system flow discharge calibration, on April 18, 2023

(3) WO 20472030, low level intake supply to nuclear service water system isolation valve, 1RN-1, electrical and mechanical inspection of Limitorque actuator, on April 19, 2023

(4) PT/2/A/4350/002B, "Diesel Generator B Operability Test," on Unit 2 train B emergency diesel generator following cylinder fluid checks, on May 3, 2023

(5) PT/0/A/4457/001A, "A Chilled Water System Pump Performance Test," on Unit 1/2 train A chilled water pump following motor replacement and pump rebuild, on May 19, 2023

(6) WO 20542923, Unit 2 train B auxiliary feedwater pump discharge to Unit 2 loop C steam generator isolation valve diagnostic test and lubrication, on May 31, 2023

(7) WO 20383899, Unit 2 train A component cooling water pump #1 breaker and auxiliary switches replacement, on June 12, 2023

Surveillance Testing (IP Section 03.01) (2 Samples)

(1) PT/2/A/4200/001A, Containment Integrated Leak Rate Test, on March 26, 2023

(2) PT/2/A/4350/004, 4kV Loss of Voltage Trip Actuating Device Operational Test, on

June 1, 2023 Ice Condenser Testing (IP Section 03.01) (1 Sample)

(1) PT/0/A/4200/032, Periodic Inspection of Ice Condenser Lower Inlet Doors, during Unit 2 refueling outage M2R28, on March 31,

OTHER ACTIVITIES - BASELINE

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

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) ===

(1) Unit 1 (April 1, 2022, through March 31, 2023)

(2) Unit 2 (April 1, 2022, through March 31, 2023)

MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)

(1) Unit 1 (April 1, 2022, through March 31, 2023)

(2) Unit 2 (April 1, 2022, through March 31, 2023)

MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)

(1) Unit 1 (April 1, 2022, through March 31, 2023)

(2) Unit 2 (April 1, 2022, through March 31, 2023)

71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends associated with water leakage in auxiliary building elevation 767', near the Unit 2 fuel building ventilation air handling unit, that might be indicative of a more significant safety issue.

71153 - Follow Up of Events and Notices of Enforcement Discretion Personnel Performance (IP Section 03.03)

(1) The inspectors evaluated the turbine runback transient associated with Unit 2 loss of bus line B and licensee's performance, on April 6,

INSPECTION RESULTS

Unresolved Item Technical basis for changes to calibration frequency of 71124.05 (Closed) radiation monitors EMF-36, EMF-44, and EMF-49 LOW and HIGH channels and SLC respective update/clarification. URI 05000369,05000370/2022002-02

Description:

Site Technical Specification (TS) 5.5, Programs and Manuals, Section 5.5.5 a.

Radioactive Effluent Controls Program, states, This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in Chapter 16 of the Updated Final Safety Analysis Report (UFSAR), shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1. Limitations on the functional capability of radioactive liquid and gaseous monitoring

instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM; Additionally, Section 5.5.5 b. states that licensee-initiated changes to the Radiological Effluent Controls of the UFSAR:

1. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and A determination that the change(s) maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations or a determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations Chapter 16 of the UFSAR, Selected Licensee Commitments (SLCs) states that, Changes to these Selected Licensee Commitments shall be considered a change in an NRC commitment and shall be made only in accordance with the approved Nuclear Operating Fleet Administrative Procedure for the Control of Selected Licensee Commitments and by use of the 10 CFR 50.59 Process. SLC section 16.11.2, Radioactive Liquid Effluent Monitoring Instrumentation, identified the surveillance frequency requirements and compensatory actions which included channel calibration Testing Requirement (TR) 16.11.2.7 on a 24-month periodicity. SLC section 16.11.7, Radioactive Gaseous Effluent Monitoring Instrumentation, identified the surveillance frequency requirements and compensatory actions which included channel calibration TR 16.11.7.7 on an 18-month periodicity.

The inspectors noted that calibration intervals of site effluent radiation monitors used for making decisions related to emergency action levels declarations in case of an event were changed from the expected frequencies described in Chapter 16 of the UFSAR. Specifically, effluent monitors EMF-36, EMF-44, and EMF-49 High channels were found calibrated at 6-year intervals. The inspectors opened an unresolved item (URI 05000269,270/2022002-02)to review the licensees technical basis/justification for the change in calibration frequency.

The inspectors reviewed the information provided by the licensee to address the URI. Based on review of historical licensing actions, the inspectors verified that the low range channels of EMF-36, EMF-44, and EMF-49 were removed from TSs, and relocated to the SLC manual, following NRC approval (ADAMS Accession Number ML013200186) of the license amendment request dated February 7, 1990, and its supplement dated May 7, 1990. Also, EMF-36 (High High range) was removed from TSs, and relocated to the SLC manual, following NRC approval (ADAMS Accession Number ML013230218) of the license amendment request dated February 25, 1994. There were no other TS requirements for High range channels. Inspectors noted that once removed from TSs, changes to the emergency plan radiation monitors can be made without prior NRC approval provided such changes do not reduce the effectiveness of the Emergency Plan, do not require a license amendment pursuant to 10 CFR 50.90, or do not otherwise satisfy requirements for prior NRC approval.

Also, NRC inspectors confirmed that the Low and High range channels of EMF-36, EMF-44, and EMF-49 do not meet any of the four criteria specified in 10 CFR 50.36 for inclusion in the TSs.

The licensee amended SLC sections 16.7.6, 16.11.2, and 16.11.7 to clarify that calibration frequencies stated therein are applicable to the specific instrument channels (e.g., Low Range, High Range, High High Range) and not for the entire set of channels available.

The NRC inspectors evaluated the 6-year calibration frequency for EMF-36, EMF-44, and EMF-49 High channels, in accordance with licensee's procedure AD-EG-ALL-1202, Preventive Maintenance [PM] and Surveillance Testing Administration, and the information described above, and no performance deficiency was identified. This URI is closed.

Corrective Action References: NCRs 02427036, 02452188,

EXIT MEETINGS AND DEBRIEFS

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

On July 24, 2023, the inspectors presented the integrated inspection results to Ed Pigott and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.04 Corrective Action Nuclear Condition 02468556

Documents Report(s)

Drawings MCFD-1574- Flow Diagram of Nuclear Service Water System (RN) 35

01.00

MCFD-2574- Flow Diagram of Nuclear Service Water System (RN) 44

01.01

MCFD-2574- Flow Diagram of Nuclear Service Water System (RN) 30

2.00

MCFD-2574- Flow Diagram of Nuclear Service Water System (RN) 13

2.01

MCFD-2574- Flow Diagram of Nuclear Service Water System (RN) 23

03.00

MCFD-2574- Flow Diagram of Nuclear Service Water System (RN) 13

03.01

MCFD-2574- Flow Diagram of Nuclear Service Water System (RN) 34

04.00

MCFD-2574- Flow Diagram of Nuclear Service Water System (RN) 7

05.00

Procedures OP/1/A/6400/006 Nuclear Service Water System 256

PT/1/A/4600/003B Daily Surveillance Items 183

71111.11Q Procedures PT/0/A/4150/021 Post Refueling Controlling Procedure for Criticality, Zero 124

Power Physics, and Power Escalation Testing

PT/0/A/4150/028 Initial Criticality and Zero Power Physics Testing 81

71111.13 Corrective Action Nuclear Condition 02477616, 02477449

Documents Report(s)

Corrective Action Nuclear Condition 02467389

Documents Report(s)

Resulting from Procedure 02467345

Inspection Revision

Request(s)

Training Request 02469205

Form(s)

Inspection Type Designation Description or Title Revision or

Procedure Date

Drawings 2NI-201 MCSRD - NI System Reactor Building (Sh. 2 of 2) 5

2NI-211 MCSRD - NI System Reactor Building (Sh. 3 of 3) 1

Procedures AD-OP-ALL-0106 Conduct of Infrequently Performed Tests or Evolutions: 2NI- 4

171

AD-OP-ALL-0200 Clearance and Tagging 21

TE-MN-ALL-0410 Freeze Seals 0

71111.15 Corrective Action NCR 02477616 Channel 2 of Unit 1 7300 reverted to test condition

Documents

71111.20 Miscellaneous Maintenance Outage Work Schedule, 2/13/2023 - 4/9/2023

Maintenance Outage Work Exceptions, 2/13/2023 - 4/9/2023

Operations Outage Work Schedule, 2/13/2023 - 4/9/2023

Operations Outage Work Exceptions, 2/13/2023 - 4/9/2023

Chemistry Outage Work Schedule, 2/13/2023 - 4/9/2023

Chemistry Outage Work Exceptions, 2/13/2023 - 4/9/2023

71111.24 Corrective Action Procedure 02467956

Documents Revision

Request(s)

Drawings MC-1760-01.03 Connection Diagram - Nuclear Service Water - Motor 21

Operated Valves

MCEE-138-00.01 Elementary Diagram - Low Level Intake Isolation - Valve 4

1RN1

MCFD-1574- Flow Diagram of Nuclear Service Water System (RN) 35

01.00

Procedures IP/0/A/3066/002D Rotork Actuator Preventative Maintenance 47

IP/0/A/3066/013 Using Crane VIPER to Obtain Data for Trending Valve 9

Performance

IP/0/A/4971/007 ITE 27N and Time Delay Relay Calibration 22

IP/0/A/4971/010 Brown Boveri ITE27D Relay Calibration 14

PT/2/A/4252/002B CA Valve Stroke Timing - Quarterly 2B Motor Driven Pump 38

Flowpath

PT/2/A/4350/004 4 kV Loss of Voltage Trip Actuating Device Operational Test 20

Work Orders 20246240

Miscellaneous Selected Licensee Commitment Manual 200

Inspection Type Designation Description or Title Revision or

Procedure Date

71151 Corrective Action Nuclear Condition 02479658

Documents Report(s)

Resulting from

Inspection

71152S Corrective Action Nuclear Condition 02471224

Documents Report(s)

Work Orders Work Request(s) 20245243, 20247792, 20247965

71153 Corrective Action Nuclear Condition 02468097

Documents Report(s)

Miscellaneous MCS-1465.00-00- Design Basis Specification for Plant and Offsite Power 29

23 Protective Relaying

2