IR 05000369/2021003

Integrated Inspection Report 05000369/2021003 and 05000370/2021003

ML21301A069
Person / Time
Site:	Mcguire, McGuire
Issue date:	10/28/2021
From:	Eric Stamm NRC/RGN-II/DRP/RPB1
To:	Teresa Ray Duke Energy Carolinas
References
IR 2021003
Download: ML21301A069 (24)

Text

October 28, 2021

SUBJECT:

MCGUIRE NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000369/2021003 AND 05000370/2021003

Dear Mr. Ray:

On September 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at McGuire Nuclear Station. On October 27, 2021, 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.

One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at McGuire Nuclear Station.

If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC Resident Inspector at McGuire Nuclear Station. 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,

/RA/

Eric J. Stamm, Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos. 05000369 and 05000370 License Nos. NPF-17 and NPF-9

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000369 and 05000370 License Numbers: NPF-9 and NPF-17 Report Numbers: 05000369/2021003 and 05000370/2021003 Enterprise Identifier: I-2021-003-0015 Licensee: Duke Energy Carolinas, LLC Facility: McGuire Nuclear Station Location: Huntersville, North Carolina Inspection Dates: June 13, 2021 to September 30, 2021 Inspectors: A. Hutto, Senior Resident Inspector M. Toth, Senior Project Engineer J. Diaz-Velez, Senior Health Physicist S. Downey, Senior Reactor Inspector C. Fontana, Emergency Preparedness Inspector J. Rivera, Health Physicist S. Sanchez, Senior Emergency Preparedness Inspector J. Walker, Emergency Response 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

Inadequate design control during Unit 1 reciprocating charging pump abandonment Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.12] - Avoid 71111.12 Systems NCV 05000369/2021003-01 Complacency Open/Closed A green, self-revealing non-cited violation (NCV) of 10 CFR Part 50, Appendix B, Criterion III,

Design Control, was identified for the licensee's failure to translate the correct information from design drawings to their procedure for de-terminating electrical leads during the abandonment of the Unit 1 reciprocating charging (NV) pump. Specifically, six incorrect wires were included to be lifted in IP/0/A/3090/004, "Changes on Systems and Components."

When technicians performed the de-termination steps in the field, an operator aid computer (OAC) alarm for valve 1NI-9A was received that procedurally required operators to open the power supply to the valve, resulting in the unavailability of the "A" train flow path of high head safety injection for approximately two hours.

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 September 11, 2021, the unit was shut down for a scheduled refueling outage and ended the period in No Mode.

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.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week, increasing the amount of time on-site as local COVID-19 conditions permitted.

As part of their on-site activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution, observed risk significant activities; and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on-site. The inspections documented below met the objectives and requirements for completion of the IP.

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 from Tropical Storm Elsa on July 7, 2021.

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) 2B diesel generator, on July 15, 2021

(2) Standby shutdown facility, on August 10, 2021

(3) 2A spent fuel pool cooling, on September 20, 2021

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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) Unit 1 auxiliary feedwater (CA) pump room (fire area 2, 2A), on July 7, 2021

(2) Unit 2 CA pump room (fire area 3, 3A), on July 7, 2021

(3) Unit 1 4.16KV Blackout Auxiliary Power (ETB) electrical switchgear room and 733 elevation electrical penetration room (fire areas 9-11) on July 8, 2021

(4) Unit 2 ETB electrical switchgear room and 733 elevation electrical penetration room (fire areas 10-12) on July 8, 2021

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill on July 18, 2021. The fire scenario involve a fire in the 1ETA vital switchgear air conditioning equipment room.

===71111.07T - Heat Sink Performance The inspectors evaluated heat exchanger/sink performance on the following components from July 19, 2021 to July 23, 2021:

Heat Exchanger (Service Water Cooled) (IP Section 03.02) ===

(1) Component Cooling Pump Motor Coolers 1A2 and 1B2 (1RNHX0014, 1RNHX0016)

(2) Unit 2 Chemical and Volume Control Pump Bearing Oil Coolers (2RNHX0019, 2RNHX0020)

Heat Exchanger (Closed Loop) (IP Section 03.03) (2 Samples)

(1) Spent Fuel Pool Heat Exchanger 1A (1KFHX0003)

(2) Unit 2 Chemical and Volume Control Letdown Heat Exchanger (2NVHX0009)

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)

The inspectors evaluated pressurized water reactor non-destructive testing by reviewing the following examinations from September 13, to September 24, 2021:

(1)

• Eddy Current Examination a. Steam Generator 2A - ET for tubes R3C108, R85C74, R117C76 b. Steam Generator 2C - ET for tube R92C79 c. Steam Generator 2D - ET for tube R108C69

• Liquid Penetrant Examination a. Weld RN2FW38-20, flange to pipe weld, ASME Class 2. This included a review of associated welding activities.

b. Weld 2MCA-CF-H205, attachment to pipe weld, ASME Class 2.

• Radiographic Examination a. Weld RN2F1512, pipe to pipe weld, ASME Class 2. This included a review of associated welding activities.

• Magnetic Particle Examination a. Weld 2MCA-CF-H205, attachment to pipe weld, ASME Class 2.

• Ultrasonic Examination a. Weld 2NC2FW22-16, elbow to tee weld, ASME Class 1 b. Weld 2NC2FW22-14, pipe to elbow weld, ASME Class 1 c. Weld 2NC2FW61-NW4, nozzle to safe end weld overlay, ASME Class 1 d. Weld 2NC2FW45-8, pipe to coupling weld, ASME Class 1

• Visual Examination a. Bare metal visual examination of reactor pressure vessel head surface and penetrations, ASME Class 1 The inspectors also evaluated the licensees boric acid control program performance.

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 Unit 2 shutdown and cooldown for a refueling outage on September 11, 2021.

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

(1) The inspectors observed and evaluated operator crew performance during the emergency preparedness simulator scenario involving a loss of offsite power, a loss of cooling accident, followed by an extended loss of all power, on August 3, 2021.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 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) McGuire Maintenance Rule (a)(3) periodic assessment

(2) Nuclear condition report (NCR) 2383680, Investigate/repair 1NI-9A "Overload" OAC alarm

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (5 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) Equipment protection plan for the 2A diesel generator six-year preventive maintenance (PM) activity, on July 12, 2021

(2) Equipment protection plan and risk reduction measures for the 'C' main fire pump emergent failure, on July 21, 2021

(3) Equipment protection plan for the 'A' control room chiller annual PM, on July 26, 2021

(4) Unit 2 unplanned yellow risk condition due to a tornado watch established for the area while the Unit 2 standby makeup pump was unavailable for scheduled maintenance, on August 17, 2021

(5) Refueling outage M2R27 Risk Review Assessment, on September 8, 2021

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 2388753, Flow transmitter 2-FD-FT-5190 active leakage and excessive boron accumulation, on July 13, 2021

(2) NCR 2393729, 1AD-9 A-5 (Ice condenser lower inlet doors opened) - lit, on August 16, 2021

(3) NCR 2394558, Breaker trip times below minimum limit, on August 25, 2021

(4) NCR 2394727, 2D pressurizer heater PH2D-2E fuses blown and NCR 2394728, Unit 2 "C" pressurizer heater increased error demand, on September 2, 2021

(5) NCR 2397398, 2ETB blackout during engineered safety features testing restoration sequence, on September 23, 2021

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 419482, Evaluation of Unit 1 Containment Cooling (VL/RV)

Options

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:

(1) PT/2/A/4350/002 A, "Diesel Generator 2A Operability Test," following the 6-year PM diesel outage, on July 19, 2021

(2) PT/0/A/4457/003, "VC/YC Condenser A Delta P Performance Test," following annual PMs, on July 28, 2021

(3) PT/0/A/4400/010 C, "Main Fire Pump C Head Curve Test," following pump replacement, on August 12, 2021

(4) PT/0/A/4200/002, "Standby Shutdown Facility Operability Test," following fuel transfer PMs, on August 26, 2021

(5) PT/2/A/4350/002 B, "Diesel Generator 2B Operability Test," following output breaker repairs, on September 29, 2021

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 M2R27 activities from September 11, 2021, to September 30, 2021.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) PT/2/A/4200/043 D, "Reverse Flush of 2A RN to KD Assured Makeup Header," on July 20, 2021

(2) PT/2/A/4350/002 B, "Diesel Generator 2B Operability Test," on August 4, 2021

Inservice Testing (IP Section 03.01) (1 Sample)

(1) PT/1/A/4252/001 C, "#1 TD CA Pump Performance Test Opening 1SA-49 First," on

August 2, 2021 Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) PT/2/A/4200/001 C, "Isolation Valve Leak Rate Test," for penetration M-361, on

September 14, 2021 FLEX Testing (IP Section 03.02) (1 Sample)

(1) Flex Test Checklist, UHP 40/11700 D5-TC 40 (High Pressure Flex Hale Pump #8),

September 21, 2021

71114.01 - Exercise Evaluation

Inspection Review (IP Section 02.01-02.11) (1 Sample)

(1) The inspectors evaluated the biennial emergency plan exercise during the week of August 1, 2021. The simulated scenario began with a loss of offsite electrical power that caused an automatic reactor shutdown of both units, along with three control rods that failed to fully insert into the reactor core of Unit 1. This met the conditions for declaring an Alert. Subsequently, a loss of reactor coolant water occurred on Unit 1, along with an increase in containment pressure and radiation levels. When a Unit 1 containment purge penetration then failed, the conditions for declaring a Site Area Emergency were met. Once the only operating emergency diesel generator on Unit 1 failed and the site determined that power would not be restored within four hours, the conditions for a General Emergency were met, and the offsite response organizations were able to demonstrate their ability to implement emergency actions.

71114.04 - Emergency Action Level and Emergency Plan Changes

Inspection Review (IP Section 02.01-02.03) (1 Sample)

(1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of August 1, 2021. This evaluation does not constitute NRC approval.

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) McGuire emergency preparedness drill 21-04, on July 14, 2021. The drill involved a seismic event, followed by the failure of the Unit 1 spent fuel pool. Loss of spent fuel pool level progressed to the declaration of a General Emergency.

71114.08 - Exercise Evaluation Scenario Review

Inspection Review (IP Section 02.01 - 02.04) (1 Sample)

(1) The inspectors reviewed and evaluated in-office, the proposed scenario for the biennial emergency plan exercise at least 30 days prior to the day of the exercise.

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.

Instructions to Workers (IP Section 03.02) (1 Sample)

The inspectors evaluated instructions to workers including radiation work permits (RWPs)used to access high radiation areas (HRAs).

(1) The inspectors reviewed the following:

Radiation Work Packages

• RWP 2807, Unit 2 Reactor Building: Work on Electrically Operated Valves, HRA Entry

• RWP 2493, Unit 2 AWAW Set-up / Removal and Decon of S/G Equipment, HRA Entry

• RWP 2874, Unit 2 Reactor Building: Retract and Insert Incore Thimbles, HRA Entry Electronic Alarming Dosimeter (ED) Alarms

• 09/13/2021 ED Dose Rate Alarm

• 10/10/2020 ED Dose Alarm (Prompt Investigation Response Team (PIRT) #02352602, dated: 10/15/2020)

• 03/21/2020 ED Dose Alarm (PIRT #02321628, dated: 02/22/2020)

Labeling of Containers

• Containers in auxiliary building elevation 760'

Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)

The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.

(1) Observed workers exiting the radiologically controlled area (RCA) at Unit 2 during a refueling outage

(2) Observed radiation protection (RP) staff assisting a contaminated radiation worker (decontamination) after alarming RCA personnel contamination monitor

(3) Observed radiation workers performing small articles surveys prior leaving the RCA

Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)

The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.

(1) The inspectors reviewed RWP #2863, Unit-2 Rx Bldg: Inspect and Clean Tubes in 2A and 2D VL Air Handler Units for areas with possible airborne radioactivity

(2) The inspectors reviewed RWP #2751, Unit-2 Rx Bldg: Inservice Inspection (ISI) Weld Preps and Inspections for areas with possible airborne radioactivity

(3) The inspectors reviewed RWP #2977, Unit-2 Rx Bldg: Install and Remove Scaffolds for areas with possible airborne radioactivity High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (5 Samples)

The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:

(1) Room 809, 750' Elevation, Unit 1 Letdown Heat Exchanger, HRA

(2) Room 773, 733' Elevation, Recycle Holdup Tank "A", HRA

(3) Room 816A, Unit 1 Spent Fuel Cooling Demin Room, locked HRA (LHRA)

(4) Room 789, Unit 2 Letdown Filter Room, LHRA

(5) Room 818A, 750' Elevation, Resin Batch Tank, LHRA Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)

(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.

71124.02 - Occupational ALARA Planning and Controls

Radiological Work Planning (IP Section 03.01) (4 Samples)

The inspectors evaluated the licensees radiological work planning and reviewed the following activities:

(1) Installation/removal of temporary shielding, M1R27-20-01

(2) Steam generator work plans, M2R27-21-08

(3) Remove and replace reactor lower internals for M1R27-20-03

(4) Reactor head bottom mounted instruments with contingency for shroud removal, M2R27-27-06 Verification of Dose Estimates and Exposure Tracking Systems (IP Section 03.02) (3 Samples)

The inspectors evaluated dose estimates and exposure tracking by reviewing the following as low as reasonably achievable planning documents:

(1) Install/Remove temporary shielding complete package with as low as reasonably achievable (ALARA) Critique, M1R26-19-01

(2) Perform Reactor 10-year ISI ALARA Plan and ALARA Critique, M1R27-20-04

(3) Remove and Replace Reactor Lower Internals (Core Barrel), M1R27-20-03

Implementation of ALARA and Radiological Work Controls (IP Section 03.03) (2 Samples)

The inspectors reviewed as low as reasonably achievable practices and radiological work controls and observed the following activities:

(1) ALARA Briefings for RWP 2807, Unit 2 Reactor Building: Work on Electrically Operated Valves, HRA Entry

(2) ALARA Briefings for RWP 2874, Unit 2 Reactor Building: Retract and Insert Incore Thimbles, HRA Entry

Radiation Worker Performance (IP Section 03.04) (1 Sample)

The inspectors evaluated radiation worker and radiation protection technician performance through observing:

(1)

• workers performing fuel movement

• workers installing and removing scaffolding

• portions of the reactor head lift (as observed through recorded video)

• RP staff overseeing various jobs through remote monitoring

71124.06 - Radioactive Gaseous and Liquid Effluent Treatment

Walkdowns and Observations (IP Section 03.01) (5 Samples)

The inspectors evaluated the following radioactive effluent systems during walkdowns:

(1) Auxiliary building vent gaseous radiation monitor

(2) Containment ventilation unit condensate drain tank (CVUCDT) liquid radiation monitor

(3) Auxiliary building ventilation filtration system

(4) Unit 2 spent fuel pool ventilation filtration system

(5) Liquid waste discharge radiation monitor

Sampling and Analysis (IP Section 03.02) (1 Sample)

(1) Inspectors observed weekly composite sampling of the Units 1 and 2 CVUCDTs.

Dose Calculations (IP Section 03.03) (3 Samples)

The inspectors evaluated the following dose calculations:

(1) "A" waste gas decay tank gaseous release, 08/21/2019 (2) "A" waste monitor tank liquid release, 07/15/2021

(3) Unit 1 CVUCDT liquid release, 06/30/2021

Abnormal Discharges (IP Section 03.04) (1 Sample)

The inspectors evaluated the following abnormal discharges:

(1) Unit 2 gland seal secondary side steam leak, 02/20/2021

71124.07 - Radiological Environmental Monitoring Program

Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.

Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.

GPI Implementation (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative program to identify incomplete or discontinued program elements.

71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &

Transportation

Radioactive Material Storage (IP Section 03.01)

(1) Inspectors evaluated the licensees performance in controlling, labeling, and securing radioactive materials.

Radioactive Waste System Walkdown (IP Section 03.02) (1 Sample)

(1) Inspectors walked down accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality.

Waste Characterization and Classification (IP Section 03.03) (3 Samples)

(1) The inspectors evaluated the licensees characterization and classification of radioactive waste for dry active waste stream.

(2) The inspectors evaluated the licensees characterization and classification of radioactive waste for primary resin "A" waste stream.

(3) The inspectors evaluated the licensees characterization and classification of radioactive waste for Unit 1 fuel cleaning filters waste stream.

Shipping Records (IP Section 03.05) (3 Samples)

The inspectors evaluated the following non-excepted radioactive material shipments through a record review:

(1) Shipping record no. 19-0003, Primary Resin

(2) Shipping record no. 19-0005, Anion Radwaste Resin

(3) Shipping record no. 21-0010, Primary Resin

OTHER ACTIVITIES - BASELINE

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

MS08: Heat Removal Systems (IP Section 02.07) ===

(1) Unit 1 (July 1, 2020 - June 30, 2021)

(2) Unit 2 (July 1, 2020 - June 30, 2021)

MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)

(1) Unit 1 (July 1, 2020 - June 30, 2021)

(2) Unit 2 (July 1, 2020 - June 30, 2021)

MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)

(1) Unit 1 (July 1, 2020 - June 30, 2021)

(2) Unit 2 (July 1, 2020 - June 30, 2021)

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) October 2020 through August 9, 2021 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) October 2020 through August 9, 2021

EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)

(1) Unit 1 (July 1, 2020, through June 30, 2021)

Unit 2 (July 1, 2020, through June 30, 2021)

EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13)

(1 Sample)

(1) Unit 1 (July 1, 2020, through June 30, 2021)

Unit 2 (July 1, 2020, through June 30, 2021)

EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)

(1) Unit 1 (July 1, 2020, through June 30, 2021)

Unit 2 (July 1, 2020, through June 30, 2021)

71152 - Problem Identification and Resolution

Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) NCR 2383680, Investigate/repair 1NI-9A "Overload" OAC alarm

INSPECTION RESULTS

Inadequate design control during Unit 1 reciprocating charging pump abandonment Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.12] - Avoid 71111.12 Systems NCV 05000369/2021003-01 Complacency Open/Closed A green, self-revealing non-cited violation (NCV) of 10 CFR Part 50, Appendix B, Criterion III, Design Control, was identified for the licensee's failure to translate the correct information from design drawings to their procedure for de-terminating electrical leads during the abandonment of the Unit 1 reciprocating charging (NV) pump. Specifically, six incorrect wires were included to be lifted in IP/0/A/3090/004, "Changes on Systems and Components."

When technicians performed the de-termination steps in the field, an operator aid computer (OAC) alarm for valve 1NI-9A was received that procedurally required operators to open the power supply to the valve, resulting in the unavailability of the "A" train flow path of high head safety injection for approximately two hours.

Description:

On May 25, 2021, the operators received an "overload" alarm on the OAC for valve 1NI-9A, "NC cold leg injection from NV." In response to the alarm, the power supply breaker to the valve (1EMXA-F12D) was opened as directed by the alarm response procedure. Removing the power from 1NI-9A made the "A" train flow path of high head safety injection inoperable and unavailable. Approximately two hours after the breaker was opened, the alarm was determined to be from the on-going abandonment of the Unit 1 reciprocating NV pump and was an indication only condition. Consequently, the 1NI-9A power supply breaker was closed, restoring the "A" train flow path availability.

As a result of the event, the licensee established a Prompt Investigation Response Team (PIRT), and "Human Performance" and "Organizational and Programmatic" checklists were performed per licensee procedure AD-PI-ALL-0106, "Cause Investigation Checklists." The investigation determined that during the task preparation for the abandonment of the reciprocating NV pump, a technician highlighted three pairs of conductors on the design drawing MC-1790-08.00, "1NI-10," to be deleted that were not specified by the work instructions or the design drawing. These conductors were outside the bubble/shaded region designated for removal. The technician subsequently transferred the incorrect information to IP/0/A/3090/004, "Changes on Systems and Components," Enclosure 9.3, "Modifications of Equipment or Components Removal and Restoration Sheet." This procedure was used by the technicians in the field to complete the abandonment tasks. At the time, IP/0/A/3090/004 did not require independent verifications or peer checks when developing Enclosure 9.3 information. The de-terminating of two of the incorrect leads specified in Enclosure 9.3 resulted in the 1NI-9A OAC "overload" alarm. The remaining four incorrect conductors had no adverse impacts when they were de-terminated.

Corrective Actions: The operators restored power to 1NI-9A once it was determined the OAC alarm was a result of erroneous indications due to field activities and the conductors that were erroneously de-terminated were reconnected. Errors in IP/0/A/3090/004, "Changes on Systems and Components," Enclosure 9.3, "Modifications of Equipment or Components Removal and Restoration Sheet," for the reciprocating NV pump abandonment were corrected. Additionally, a requirement to perform an independent verification for information entered on Enclosure 9.3 was incorporated in IP/0/A/3090/004.

Corrective Action References: NCR 2383680, Investigate/repair 1NI-9A "Overload" OAC alarm

Performance Assessment:

Performance Deficiency: The inspectors determined that the licensees failure to translate the correct conductor de-termination information from design drawings to the procedures for implementing the Unit 1 reciprocating NV pump abandonment was a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the SSC Performance attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the licensee's failure to translate the correct conductor de-termination information from design drawings to the procedures for implementing the Unit 1 reciprocating NV pump abandonment resulted in the unavailability of the "A" train of the high head safety injection flow path for approximately two hours.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The finding was determined to be green, based on Inspection Manual Chapter 0609, Appendix A, Exhibit 2, dated November 30, 2020, as the degraded condition did not represent a loss of one train of a multi-train system for greater than its technical specification allowed outage time.

Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. Specifically, licensee personnel preparing work procedures for the abandonment of the Unit 1 reciprocating NV pump did not utilize error reduction tools such as peer checking or independent verification for correct translation of design drawing information into these procedures.

Enforcement:

Violation: 10 CFR Part 50, Appendix B, Criterion III, "Design Control," requires in part, that measures shall be established to assure that regulatory requirements and the design basis are correctly translated into specifications, drawings, procedures, and instructions. Contrary to the above, on May 25, 2021, the licensee failed to translate the correct conductor information from design drawings into their procedures for de-terminating conductors associated with the abandonment of the Unit 1 reciprocating NV pump.

Enforcement Action: This violation is being treated as an NCV, consistent with Section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

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

• On July 22, 2021, the inspectors presented the Triennial Heat Sink inspection results to Tom Ray and other members of the licensee staff.

• On July 22, 2021, the inspectors presented the RP Public Radiation Safety inspection results to Tom Ray and other members of the licensee staff.

• On August 5, 2021, the inspectors presented the Emergency Preparedness Exercise inspection results to Tom Ray and other members of the licensee staff.

• On September 17, 2021, the inspectors presented the RP Occupational Radiation Safety inspection results to Tom Ray and other members of the licensee staff.

• On September 24, 2021, the inspectors presented the Baseline ISI inspection results to Tom Ray and other members of the licensee staff.

• On October 27, 2021, the inspectors presented the integrated inspection results to Tom Ray and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Procedures RP/0/B/5700/027 Severe Weather Preparation

71111.04 Drawings MCFD-2570-01.00 Unit 2 Flow Diagram of Spent Fuel Cooling

System

Procedures OP/2/A/6350/002 Diesel Generator

71111.05 Fire Plans CSD-MNS-PFP-AB-0750-001 Auxiliary Building Elevation 750 Pre-Fire Plan

MFSD-002 Unit 1 CA Pump Room

MFSD-003 Unit 2 CA Pump Room

MFSD-009.011 1ETB/733 ELEC PEN

MFSD-010.012 2ETB/733 ELEC PEN ROOM

Miscellaneous MCS-1465.00-00-0008 Design Basis for Fire Protection

Procedures AD-EG-ALL-1520 Transient Combustible Control

71111.07T Calculations MCC-1223.20-00-0001 Fuel Pool Cooling Heat Exchanger Design Revision 1

Calculations

MCC-1223.20-00-0023 KF Heat Exchanger Tube Plugging Analysis Revision 0

MCC-1223.24-00-0073 RN Supplied Integral Essential Motor Cooler Revision 2

Tube Plugging Analysis

MCC-1223.24-00-0080 RN/NV Pump Oil Cooler Tube Plugging Analysis Revision 3

MCC-1223.24-00-0096 RN System Flow Balance Acceptance Criteria Revision 18

Calculations

MCC-1223.24-00-0126 Design Inputs for Raising RN Design Revision 1

Temperature

Miscellaneous MCS-1554.NV-00-0001 Design Basis Specification for the NV System Revision

041

MCS-1570.KF-00-0001 Design Basis Specification for the KF System Revision

015

MCS-1574.RN-00-0001 Design Basis Specification for the RN System Revision

061

Procedures MCM 3.6 Closed Cooling Systems Analytical Revision

Requirements and Corrective Actions 041

MP/0/A/7700/043 Westinghouse Larger Motor Cooler HX Revision

Maintenance 028

OP/1/A/6200/005 Spent Fuel Cooling System Revision

Inspection Type Designation Description or Title Revision or

Procedure Date

106

PT/2/A/4973/005 NV Pump 2A Oil Cooler Delta P Performance Revision

Test 014

71111.08P Corrective NCRs by Number 02351876, 02361708, 02388753, 02397334

Action

Documents

Miscellaneous McGuire Unit 2 M2R27 Degradation Revision 0

Assessment

CFR80 Steam Generator Site Technique Revision 3

Validation for Catawba Nuclear Station Unit 1

and McGuire Nuclear Station Units 1 and 2

Procedure Qualification Record L-109 Revision 1

Procedure Qualification Record L-128A Revision 1

NDE Reports MT-21-001 Magnetic Particle Examination of 2MCA-CF- 09/17/2021

H205

NDE Report # 53040 Liquid Penetrant Examination of RN2FW38-20 06/02/2020

NDE Report # Computed Radiography Examination Report for 03/19/2020

DE_M_2_RN2F1512_20200303 Weld RN2F1512

PT-21-003 Liquid Penetrant Examination of 2MCA-CF- 09/17/2021

H205

UT-21-004 Ultrasonic Examination of Weld 2NC2FW22-14 09/18/2021

UT-21-005 Ultrasonic Examination of Weld 2NC2FW22-16 09/18/2021

UT-21-018 Ultrasonic Examination of Weld 2NC2FW45-8 09/22/2021

VE-21-009 Ultrasonic Examination of Weld 2NC2FW61- 09/19/2021

NW4

VT-21-159 Visual Examination of the Unit 2 Reactor Vessel 09/23/2021

Head

Procedures AD-EG-PWR-1611 Boric Acid Corrosion Control Program - Revision 4

Implementation

NDE-NE-ALL-6106 Ultrasonic Examination of Mid or Large Revision

Diameter Piping Welds and Base Materials for 002

Thermal Fatigue Damage

NDE-NE-ALL-7202 Visual Examination of PWR Reactor Pressure Revision

Vessel Upper Head Penetrations 005

Inspection Type Designation Description or Title Revision or

Procedure Date

TE-MN-PWR-0006 Inspection, Assessment, and Cleanup of Boric Revision 1

Acid on Plant Materials

Work Orders Work Orders by Number 02184068-02, 02184068-12

Work Requests by Number 20188017, 20194197, 20194200, 20194201

71111.11Q Procedures AD-OP-ALL-1000 Conduct of Operations

OP/2/6100/003 Controlling Procedure for Unit Operation

OP/2/A/6100/002 Controlling Procedure for Unit Shutdown

OP/2/A/6100/SD-4 Cooldown to 240 Degrees F

OP/2/A/6100/SD-6A Placing Train A ND in Service

71111.12 Miscellaneous Duke Equipment Reliability Maintenance Rule

Database

Procedures AD-EG-ALL-1204 Single Point Vulnerability Identification,

Elimination and Mitigation

AD-EG-ALL-1206 Equipment Reliability Classification

AD-EG-ALL-1209 System, Component and Program Health

Reports and Programs

AD-EG-ALL-1210 Maintenance Rule Program

AD-EG-ALL-1211 System Performance Monitoring and Trending

71111.13 Corrective NCR 2394312 Unit 2 Yellow PRA risk entry

Action

Documents

Procedures AD-OP-ALL-0201 Protected Equipment

AD-OP-ALL-0204 Plant Status Control

AD-WC-ALL-0240 On-line Risk Management Process

RP/0/A/5700/006 Natural Disasters

RP/0/A/5700/026 Severe Weather Preparation

71111.15 Procedures AD-EG-ALL-1211 System Performance Monitoring and Trending

AD-OP-ALL-0102 Operability Decision Making

AD-OP-ALL-0105 Operability Determinations and Functionality

Assessment

71111.18 Procedures AD-EG-ALL-1139 Temporary Configuration Changes

MP/0/B/7650/154 RV Supplemental Cooling Chiller Installation

71111.19 Procedures AD-EG-ALL-1155 Post Modification Testing

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.20 Procedures OP/2/A/6100/SD-20 Draining the NC System

71111.22 Procedures AD-EG-ALL-1202 Preventive Maintenance and Surveillance

Testing Administration

AD-EG-ALL-1720 In-service Testing (IST) Program

Implementation

AD-WC-ALL-0250 Work Implementation and Completion

71124.01 Corrective CRs #02349409, 02350424, Corrective Action Reports Various

Action 02351088, 02351284,

Documents 02352910, 02353136,

2356013, 02349862, and

2386417

Procedures AD-RP-ALL-0002 RADIATION AND CONTAMINATION Revision 2

SURVEYS

AD-RP-ALL-0003 RADIOLOGICAL AIR SAMPLING Revision 4

AD-RP-ALL-0004 RADIOLOGICAL POSTING AND LABELING Revision 5

AD-RP-ALL-0005 ACCESS CONTROLS FOR HIGH AND Revision 1

LOCKED HIGH RADIATION AREAS

AD-RP-ALL-0006 PERSONNEL CONTAMINATION Revision 1

MONITORING

AD-RP-ALL-0007 CONTROL OF RADIOACTIVE MATERIAL Revision 2

AD-RP-ALL-0010 RADIOLOGICAL JOB COVERAGE Revision 0

AD-RP-ALL-2000 PREPARATION AND MANAGEMENT OF Revision 5

RADIATION WORK PERMITS (RWP)

AD-RP-ALL-2017 ACCESS CONTROLS TO VERY HIGH Revision 8

RADIATION AREAS AND SUPPLEMENTAL

ACCESS CONTROLS FOR HRA AND LHRA

AD-RP-ALL-9003 HOT SPOT TRACKING AND CONTROL Revision 1

RPMP7-9 Management's Expectations for Single Point Revision 8

Access (SPA) Duties and Investigation of Portal

and Whole Body Monitor Alarms

71124.02 ALARA Plans AD-RP-ALL-9000 Attachment 5 Long Range ALARA Plan 2021 McGuire 1/8/2021

Nuclear Station

Procedures AD-RP-ALL-9000 ALARA Program Revision 9

AD-RP-ALL-9001 ALARA Planning Revision 5

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.06 Corrective NCR 02291733 2EMF-46A and 2EMF-46B showing increased 09/13/2019

Action counts (U2 KC)

Documents NCR 02295184 Abnormal radio-isotopic activity in Unit 2 KC 10/02/2019

System

Miscellaneous HP/0/B/1003/004, Enclosure 5.1 CVUCDT Composite Sample Collection With 07/20/2021

Operable Composite Sampler

Procedures HP/0/B/1003/044 Containment Ventilation Unit Condensate Drain Revision 19

Tank (CVUCDT) Release to the RC System

71124.07 Calibration ISCO Model 3710 Portable ISCO Model 3710 Portable Sampler Calibration 05/18/2020

Records Sampler #01711 Record

ISCO Model 3710 Portable ISCO Model 3710 Portable Sampler Calibration 04/19/2021

Sampler #01711 Record

ISCO Model 3710 Portable ISCO Model 3710 Portable Sampler Calibration 06/15/2020

Sampler #01712 Record

ISCO Model 3710 Portable ISCO Model 3710 Portable Sampler Calibration 05/17/2021

Sampler #01712 Record

LV-1D Air Sampler #09097 LV-1D Air Sampler Calibration Record 05/13/2019

LV-1D Air Sampler #09097 LV-1D Air Sampler Calibration Record 09/09/2020

LV-1D Air Sampler #09387 LV-1D Air Sampler Calibration Record 09/18/2019

LV-1D Air Sampler #09387 LV-1D Air Sampler Calibration Record 02/09/2021

Corrective NCRs: 02302298, 02340178, Various

Action 02304178, 02319274,

Documents 02323506, 02350082,

2338345 and 02355096

Miscellaneous 2021 MNS Annual Land Use 2021 MNS Annual Land Use Census 06/22/2021

Census

Operability PE #6, LSC Serial 3H Background, 14C Background, 3H 07/21/2021

Evaluations #SGLO48170662 Efficiency, 14C Efficiency QC Control Charts

PE#3, LSC Serial 3H Background, 14C Background, 3H 07/21/2021

1. SGTC33140391 Efficiency, 14C Efficiency QC Control Charts

PE#4, LSC Serial 3H Background, 14C Background, 3H 07/21/2021

1. SGTC44140456 Efficiency, 14C Efficiency QC Control Charts

Procedures AD-NS-NGO-0003 CONDUCT OF ENRAD LABORATORIES Revision 5

Inspection Type Designation Description or Title Revision or

Procedure Date

EnRad Procedure #114 ROUTINE QUALITY CONTROL OF PERKIN Revision 5

ELMER LIQUID SCINTILLATION SYSTEMS

EnRad Procedure #336 OPERATION OF PERKIN ELMER LIQUID Revision 14

SCINTILLATION SYSTEMS

EnRad Procedure #62 PREPARATION OF TRITIUM SAMPLES Revision 14

IP/0/B/3260/023 METEOROLOGICAL MONITORING (EEB) Revision 36

SYSTEM WEEKLY CHANNEL VERIFICATION

Radiation 2019 Environmental TLD CY 2019 Environmental TLD Monitoring Report Various

Surveys Monitoring Report for1st for1st Quarter to 4th Quarter

Quarter to 4th Quarter

20 Environmental TLD CY 2020 Environmental TLD Monitoring Report Various

Monitoring Report for1st for1st Quarter to 4th Quarter

Quarter to 4th Quarter

21 Environmental TLD CY 2021 Environmental TLD Monitoring Report 04/13/2021

Monitoring Report for1st for1st Quarter (only)

Quarter (only)

Ground Water Protection Ground Water Protection Initiative Tritium 07/06/2021

Initiative Tritium Summary Summary Report (Since July 2019)

Report (Since July 2019)

Self- Self-Assessment Number: 2020 REMP Assessment 11/10/2020

Assessments 02332182-05

Work Orders Work Order #20463262 01 PT 1EEBCRXXXX / METEOROLOGICAL SYS 04/17/21

WEEKLY SURVEY

71124.08 Miscellaneous MC-764.05 (Revision 2) Memo to File, 10 CFR Part 37 Requirements 08/18/2021

71151 Procedures AD-LS-ALL-0004 NRC Performance Indicators and Monthly

Operating Report

AD-PI-ALL-0100 Corrective Action Program

21