ML25206A042
| ML25206A042 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 07/31/2025 |
| From: | Robert Williams NRC/RGN-II/DORS/PB1 |
| To: | Pigott E Duke Energy Carolinas |
| References | |
| IR 2025002 | |
| Download: ML25206A042 (1) | |
Text
Edward Pigott Site Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078
SUBJECT:
MCGUIRE NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000369/2025002 AND 05000370/2025002
Dear Edward Pigott:
On June 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at McGuire Nuclear Station. On July 23, 2025, the NRC inspectors discussed the results of this inspection with Michael Tate, Plant Manager, and other members of your staff. The results of this inspection are documented in the enclosed report.
No NRC-identified or self-revealing findings were identified during this inspection.
A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation 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.
July 31, 2025
E. Pigott 2
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, Robert E. Williams, Jr., Branch Chief Projects Branch 1 Division of Operating Reactor Safety Docket Nos. 05000369 and 05000370 License Nos. NPF-9 and NPF-17
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Williams, Robert on 07/31/25
SUNSI Review X
Non-Sensitive
Sensitive X
Publicly Available
Non-Publicly Available OFFICE RII/DORS RII/DORS RII/DORS NAME C. Safouri D. Jackson R. Williams Jr.
DATE 7/30/2025 7/30/2025 7/31/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05000369 and 05000370 License Numbers:
NPF-9 and NPF-17 Report Numbers:
05000369/2025002 and 05000370/2025002 Enterprise Identifier:
I-2025-002-0014 Licensee:
Duke Energy Carolinas, LLC Facility:
McGuire Nuclear Station Location:
Huntersville, North Carolina Inspection Dates:
April 1, 2025, to June 30, 2025 Inspectors:
C. Safouri, Senior Resident Inspector F. Young, Resident Inspector J. Diaz-Velez, Senior Health Physicist D. Neal, Health Physicist J. Quinones-Navarro, Senior Project Engineer D. Restrepo, Health Physicist N. Smalley, Senior Resident Inspector J. Vasquez, Construction Project Inspector Approved By:
Robert E. Williams, Jr., Chief Projects Branch 1 Division of Operating Reactor Safety
2
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. A licensee-identified non-cited violation is documented in report section: 71111.15.
List of Findings and Violations No findings or violations of more than minor significance were identified.
Additional Tracking Items None.
3 PLANT STATUS Unit 1 began the inspection period at or near 100 percent rated thermal power (RTP). On April 2, 2025, the unit was shut down for a scheduled refueling outage (M1R30). The unit was returned to 100 percent RTP on April 23, 2025, and remained at or near 100 percent RTP for the remainder of the inspection period.
Unit 2 operated at or near 100 percent RTP for the entire 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.
REACTOR SAFETY 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 seasonal hot temperatures for the following systems:
Main power distribution system Ice condenser cooling system 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 1 train B nuclear service water (RN) pump and suction strainer, on April 15, 2025 (2)
Unit 2 train A and B centrifugal charging pumps and suction flow paths, on May 9, 2025 (3)
Unit 1 train B auxiliary feedwater (CA) system, on May 20, 2025 Complete Walkdown Sample (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated system configurations during a complete walkdown of the Unit 1 train A and B residual heat removal (ND) system, on April 4, 2025.
4 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 reactor building lower containment area, on April 17, 2025 (2)
Unit 1 reactor building upper containment area, on April 18, 2025 (3)
Unit 1 and Unit 2 shared main control room, on May 1, 2025 (4)
Unit 1 and Unit 2 service building basement and cable spread room shared areas, on May 1, 2025 71111.07A - Heat Exchanger/Sink Performance Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
(1)
Unit 1 train B component cooling water heat exchanger, on April 8, 2025 71111.08P - Inservice Inspection Activities (PWR)
The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities at Unit 1 during refueling outage M1R30 from April 7, 2025, to April 10, 2025.
PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01) (1 Sample)
The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:
(1)
Ultrasonic Examination Reactor cooling system, cold leg loop 1D, nozzle 4-1, 1.5" boron injection line PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection Activities (IP Section 03.02) (1 Sample)
The inspectors verified that the licensee conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:
(1) 1RPV-head, bare metal visual examination of the reactor pressure vessel head, ASME, Class 1
5 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)
Boric acid walkdown date - April 19, 2025 TE-MN-PWR-0006 Reviewed corrective actions performed for evidence of boric acid leaks that were identified Action request (AR) 02551497 71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
(1)
The inspectors observed and evaluated licensed operator performance in the control room during reactor coolant system (NC) cooldown from 400°F to 160°F, establishment of low temperature overpressure protection, and initiation of the ND system to support refueling outage M1R30, on April 2, 2025.
(2)
The inspectors observed and evaluated licensed operator performance in the control room during activities preceding reactor startup following refueling outage M1R30, such as control rod drop timing surveillance, turbine driven CA pump surveillance, and NC dilution for reactivity control, on April 19, 2025.
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)
Nuclear condition report (NCR) 02542279, failure of diesel powered 'G' instrument air compressor to start, on May 1, 2025 (2)
NCR 02536748, licensee self-assessment identified missed maintenance rule (a)(1) evaluations for Unit 2 main feedwater piping vibrations and loss of power to auxiliary DC power supply (KXA), on May 27, 2025 Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
(1)
Work order (WO) 02179101, commercial grade dedication and first-time replacement of control relay (2ETP-CA-0022), on May 2, 2025
6 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)
Unit 1 yellow shutdown risk for decay heat removal and inventory control key safety functions during lowered NC inventory to support reactor head removal, on April 5, 2025 (2)
NCR 02548200, Unit 1 and Unit 2 auxiliary instrumentation and control power system bus, CXB, ground troubleshoot and repair, on May 28, 2025 (3)
Unit 1 train B emergency diesel generator planned implementation of risk-informed completion time, on June 2, 2025 (4)
NCR 02557420, Unit 1 train A main feedwater pump inboard bearing elevated vibration emergent issue, on June 10, 2025 71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01) (2 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)
NCR 02551500, Unit 1 Limiting Condition for Operation 3.0.3 entry for cold leg accumulator sample valve alignment, on April 19, 2025 (2)
NCR 02550257, Unit 1 train B electric power distribution power board, 1ETB, ground fault detector current transformers degraded epoxy, on June 16, 2025 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 423787, Unit 1 train B RN pump motor replacement, on April 28, 2025 71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated Unit 1 refueling outage (M1R30) activities from April 2, 2025, to April 20, 2025.
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:
7 Post-Maintenance Testing (PMT) (IP Section 03.01) (6 Samples)
(1)
WO 20634033, characterization testing of Unit 1 source range ex-core nuclear instrument cables following removal of containment penetration jumper connections, on April 5, 2025 (2)
PT/1/A/4403/008, "Nuclear Service Water Train 1B Flow Balance," and PT/1/A/4403/001B, "1B Nuclear Service Water Pump Performance Test," following Unit 1 train B RN pump motor replacement, on April 15, 2025 (3)
PT/1/A/4600/105, "Rod Cluster Control Assembly Drop Timing Using Digital Rod Position Indication System," following troubleshooting and repair of rod cluster control assembly F14 indication anomalies, on April 19, 2025 (4)
WO 02006844, Unit 1 turbine driven CA to loop C steam generator control valve controller, 1CA-SS-0480, repair and associated functional testing, on April 29, 2025 (5)
PT/2/A/4204/005B, "Residual Heat Removal Train B Valve Stroke Timing," and pump operational test per OP/2/A/6200/004, "Residual Heat Removal System," following inspections of Unit 2 train B ND pump and suction valve from refueling water storage tank, 2ND-4B, on May 29, 2025 (6)
PT/1/A/4350/002B, "Diesel Generator 1B Operability Test," following six-year periodic maintenance inspection of Unit 1 train B emergency diesel generator, on June 9, 2025 Surveillance Testing (IP Section 03.01) (2 Samples)
(1)
PT/1/A/4200/009B, Engineered Safety Features Actuation Periodic Test Train B, Section 12.3, Train B SI (Safety Injection), Phase A, Phase B, and BO (Blackout)
Signals Actuated Concurrently, Followed by Manual SI, on April 3, 2025 (2)
PT/1/A/4200/009B, Engineered Safety Features Actuation Periodic Test Train B, Section 12.4, Train B BO Event Actuation," on April 3, 2025 Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)
PT/1/A/4252/001C, "Unit 1 Turbine Driven Auxiliary Feedwater Pump Opening Valve 1SA-49 First," on April 19, 2025 Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
(1)
PT/1/A/2400/001C, "Isolation Valve Leak Rate Test," for penetration M-348, post accident liquid sampling line, on April 11, 2025 Ice Condenser Testing (IP Section 03.01) (1 Sample)
(1)
SM/0/A/8510/001, "Inspection and Cleaning of Ice Condenser Flow Passages," on Unit 1 ice condenser during refueling outage M1R30, on April 8, 2025 71114.06 - Drill Evaluation Required Emergency Preparedness Drill (1 Sample)
(1)
The inspectors evaluated an emergency preparedness drill that consisted of an earthquake and loss of spent fuel pool level, on May 21, 2025.
8 RADIATION SAFETY 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)
(1)
The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
(1)
Workers exiting the radiologically controlled area during a Unit 1 refueling outage (2)
Workers exiting the contaminated area in the Unit 1 lower containment (3)
Workers exiting the contaminated area in the Unit 1 upper containment Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
(1)
Unit 1 baffle bolt inspection (2)
Unit 1 reactor head mirror insulation removal (3)
Valve work performed during Unit 1 outage 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 (HRAs) and very high radiation areas (VHRAs):
(1)
Unit 1 spent fuel pool demineralizer, room 816A, locked high radiation area (LHRA)
(2)
Spent resin sluice pump, room 610, LHRA (3)
Waste drain tank, room 640, LHRA (4)
Laundry/hot shower, grit, floor drain tanks, room 606, LHRA (5)
Unit 1 incore sump room, VHRA 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.
9 71124.06 - Radioactive Gaseous and Liquid Effluent Treatment Walkdowns and Observations (IP Section 03.01) (4 Samples)
The inspectors evaluated the following radioactive effluent systems during walkdowns:
(1)
Liquid radioactive waste effluent monitoring system from containment ventilation unit condensate drain tank Unit 1 (1-EMF-44)
(2)
Liquid radioactive waste effluent monitoring system from waste monitoring tanks (WMT) A and B (0-EMF-44)
(3)
Auxiliary building ventilation system discharge to Unit 1 vent stack (4)
Unit 1, spent fuel pool ventilation filtration system Sampling and Analysis (IP Section 03.02) (3 Samples)
Inspectors evaluated the following effluent samples, sampling processes and compensatory samples:
(1)
Compensatory sampling for out-of-service (OOS) liquid radwaste effluent line monitor 0-EMF-49, for liquid waste release permit L20221121 from WMT A (2)
Compensatory sampling for OOS liquid radwaste effluent line monitor 0-EMF-49, for liquid waste release permit L20221124 from WMT B (3)
Unit 2 vent stack non-routine every 12-hour tritium and noble gas grab samples due to OOS 2-EMF-36L, 9/8-10/2024 Dose Calculations (IP Section 03.03) (2 Samples)
The inspectors evaluated the following dose calculations:
(1)
Gaseous radioactive waste release permit # G2025700 [including dose calculation for the maximum individual receptor], dated March 31, 2025 (2)
Liquid radioactive waste release permit # L20251800 [including dose calculation for the maximum individual receptor], dated June 10, 2025 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.
10 71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation Radioactive Material Storage (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensees performance in controlling, labeling and securing the following radioactive materials:
(1)
Auxiliary building: room 1010 (2)
Warehouse 7 (3)
Auxiliary building: room 12-02 Radioactive Waste System Walkdown (IP Section 03.02) (3 Samples)
The inspectors walked down the following accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:
(1) 760 elevation: solidification pad area, typical activity transfer of resins to the liner/high integrity container in preparation of shipment (2) 750 elevation: room 806 A/B, activity radwaste transfer/dewatering (pump), and evaporator condensate storage tanks (3) 750 elevation: room 818, observed from outside HRA. This room leads to rooms 818A and 818B, resin batching tank (room 818A) and evaporate condensate batching tank (818B)
Waste Characterization and Classification (IP Section 03.03) (2 Samples)
The inspectors evaluated the following characterization and classification of radioactive waste:
(1) 10 CFR Part 61 primary resin sample associated with radioactive shipping record (RSR) MNS 24-0009 waste shipment (2) 10 CFR Part 61 dry active waste (DAW) sample associated with RSR MNS 25-0001 waste shipment Shipment Preparation (IP Section 03.04) (1 Sample)
(1)
The inspectors observed the preparation of radioactive shipment RSR MNS 25-0002, including two sealand containers of DAW (shipped as low specific activity (LSA)), on April 9, 2025.
Shipping Records (IP Section 03.05) (5 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
(1)
RSR MNS 24-0007, Primary Resin, Type B package (8-120B Cask, LSA-II),
reportable quantity (RQ), shipped June 14, 2024 (2)
RSR MNS 24-0008, Primary Resin, Type B package (8-120B Cask, LSA-II, RQ),
shipped June 27, 2024 (3)
RSR MNS 24-0009, Primary Resin, Type B package (8-120B Cask, LSA-II, RQ),
shipped July 11, 2024
11 (4)
RSR MNS 25-0001, DAW, included two sealand containers, LSA-I waste, shipped January 22, 2025 (5)
RSR MNS 24-0015, DAW, including two sealand containers, LSA-I and LSA-II waste, shipped September 19, 2024 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) (2 Samples)
(1)
Unit 1 (April 1, 2024, through March 31, 2025)
(2)
Unit 2 (April 1, 2024, through March 31, 2025)
MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)
(1)
Unit 1 (April 1, 2024, through March 31, 2025)
(2)
Unit 2 (April 1, 2024, through March 31, 2025)
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
(1)
Unit 1 (April 1, 2024, through March 31, 2025)
(2)
Unit 2 (April 1, 2024, through March 31, 2025)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
(1)
September 14, 2024, through April 11, 2025 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)
May 31, 2024, through April 30, 2025 71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)
NCR 02551500, Unit 1 Limiting Condition for Operation 3.0.3 entry due to all Unit 1 cold leg accumulator sample valves open, on April 19, 2025
12 INSPECTION RESULTS Licensee-Identified Non-Cited Violation 71111.15 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation:
Technical Specification 5.4.1 requires, in part, Written procedures shall be established, implemented, and maintained covering the following activities: The applicable procedures recommended in Regulatory Guide (RG) 1.33, Revision 2, Appendix, A, February 1978.
RG 1.33, Appendix A, references a list of, typical safety-related activities that should be covered by written procedures, including, instructions for energizing, filling, venting, draining, startup, shutdown, and changing modes of operationfor the following systems:
Emergency Core Cooling System (ECCS).
Contrary to the above, on April 19, 2025, licensee procedure OP/1/A/6200/009, Accumulator Operation, Attachment 10, Alignment to Pressurize Nuclear Sampling System Sample Line for Visual Examination, was not adequately established or maintained and allowed operators to place the ECCS system into an alternate alignment that challenged cold leg accumulator (CLA) operability and ECCS safety function. The alternate alignment connected the liquid volumes of all four CLAs via sampling piping. If a loss of coolant accident were to occur, some water stored in the CLAs may not inject into the reactor core but instead flow into the adjacent CLA and not fulfill its safety function.
Significance/Severity: Green. The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Using Exhibit 2, Section A, the inspectors determined the finding of very low safety significance, Green, because it did not represent a loss of operability or probabilistic risk assessment function of the CLAs. The licensee demonstrated operability of the cold leg accumulators was maintained during the inappropriate alignment by performing additional analysis after discovery.
Corrective Action Reference: NCR 02551500 EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On April 10, 2025, the inspectors presented the inservice inspection results to Edward Pigott, Site Vice President (VP), and other members of the licensee staff.
On April 10, 2025, the inspectors presented the radiation protection (RP) occupational radiation safety and transportation baseline inspection results to Edward Pigott, Site VP, and other members of the licensee staff.
On June 12, 2025, the inspectors presented the RP public radiation safety baseline inspection results to Michael Tate, Plant Manager, and other members of the licensee staff.
On July 23, 2025, the inspectors presented the integrated inspection results to Michael Tate, Plant Manager, and other members of the licensee staff.
13 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date Miscellaneous AD-WC-ALL-0230 Seasonal Readiness: Certification for Summer Peak Period 04/29/2025 AD-WC-ALL-0240 On-line Risk Management Process 6
71111.01 Procedures AD-WC-ALL-0260 Nuclear Generation Response to High or Low Grid System Load 6
MCFD-1561-01.00 Flow Diagram of Residual Heat Removal System (ND) 24 MCFD-1574-01.00 Flow Diagram of Nuclear Service Water System (RN) 36 MCFD-1574-01.01 Flow Diagram of Nuclear Service Water System (RN) 41 MCFD-1592-01.00 Flow Diagram of Auxiliary Feedwater System (CA) 10 MCFD-1592-01.01 Flow Diagram of Auxiliary Feedwater System (CA) 34 71111.04 Drawings MCFD-2554-03.01 Flow Diagram of Chemical and Volume Control System (NV) 32 Corrective Action Documents Resulting from Inspection Nuclear Condition Report(s) 02556945 CSD-MN-PFP-SRV-0750-001 Service Building Elevation 750 Pre-Fire Plan 1
CSD-MNS-PFP-AB-0767-001 Auxiliary Building Elevation 767 Pre-Fire Plan 3
CSD-MNS-PFP-RB1-0000-001 U1 Reactor Building Elevation All Pre-Fire Plan 1
Fire Plans CSD-MNS-PFP-SRV-0739-001 Service Building Elevation 739 Pre-Fire Plan 1
71111.05 Miscellaneous Preventative Maintenance Change Request(s) 02286560
14 Inspection Procedure Type Designation Description or Title Revision or Date Procedures MP/0/A/7700/013 Component Cooling System (KC) HX Maintenance 23 71111.07A Work Orders 20673956 NDE Reports 180-9348166-000 McGuire Unit-1(M1R29) RVCH and AHA NDE Final Report 12/14/2023 AD-EG-PWR-1611 Boric Acid Corrosion Control Program - Implementation 6
71111.08P Procedures NDE-NE-ALL-6106 Ultrasonic Examination of mid or large Diameter Piping Welds and Base Materials for Thermal Fatigue Damage 5
OP/1/A/6100/SD-2 Cooldown to 400°F 65 OP/1/A/6100/SD-4 Cooldown to 240°F 80 OP/1/A/6100/SD-6A Placing Train A ND in Service 59 OP/1/A/6100/SD-8 Water Solid Operations 39 OP/1/A/6150/009 Boron Concentration Control 145 PT/1/A/4252/001C
- 1 TD CA Pump Performance Test Opening 1SA-49 First 24 71111.11Q Procedures PT/1/A/4600/106 RCCA Drop Timing Using DRPI System 12 Corrective Action Documents Nuclear Condition Report(s) 02459941, 02542279, 02454401 Corrective Action Documents Resulting from Inspection Nuclear Condition Report(s) 02555667 Drawings MC -2717-22.01-02 C/D Area Term Cab No. 2ATC22 (Train A) Left Half 33 AD-EG-ALL-1210 Maintenance Rule Program 5
DPM 1393.01-0002.001 Environmental Qualification Pkg for Cutler-Hammer D26 Ser Type M 2
DPM 1393.01-0002.002 Environmental Qualification Package for Eaton Corporation (Cutler-Hammer) D26 Series Type M Relays and Accessories Volume 2 0
71111.12 Procedures DPM 1393.01-0002.003 Seismic Testing of Eaton D26 Relays 0
15 Inspection Procedure Type Designation Description or Title Revision or Date MCC-51535.00-00-0006 PRA Risk Significant SSCs for the Maintenance Rule 5
Defense in Depth Data Sheet - Mode 5 LSHS, 1A Busline Work Window 04/04/2025 Defense in Depth Data Sheet - Mode 6 Begin De-tensioning
> Lowered Inventory 04/05/2025 Conditional Vulnerability Preparation Plan: CXB Ground Search 05/28/2025 AD-OP-ALL-0102 Operational Decision Making: 1A CF Pump Inboard Bearing Eevated Vibration 06/17/2025 Miscellaneous AD-OP-ALL-1000 Adverse Condition Monitoring Plan for 1A CF Pump Inboard Bearing Vibration 2
AD-OP-ALL-0212 Risk Informed Completion Time Program Calculations 2
AD-WC-ALL-0420 Shutdown Risk Management 9
AD-WC-MNS-0420 Shutdown Risk Management 15 Procedures OP/1/A/6100/SD-20 Draining the NC System 74 20725181 71111.13 Work Orders Work Request(s) 20285149 OP/1/A/6200/009 Accumulator Operation 126 Procedures OP/1/A/6200/009 Accumulator Operation 124 20673915 71111.15 Work Orders Work Request(s) 20286237 Calculations MCM 2318.20-0033.001 N.S.W.P. Motor Final Test Report, 1S-75 75L 10936 0
71111.18 Work Orders 20652712 Calculations MCM-1205.19-0039.001 Electric Motor Operator GL89-10 Set-up Information 91 Corrective Action Documents Nuclear Condition Report(s) 2551623 IP/0/A/3066/013H Testing Motor Operated Gate Diaphragm or Non-Kerotest Globe Valves Using Teledyne QUIKLOOK System 5
71111.24 Procedures IP/0/B/3203/005A Moore Products Model 528PM and Special Transfer Station 6
16 Inspection Procedure Type Designation Description or Title Revision or Date 528PM (M-383) Selector Station Calibration and Check-out IP/A/3190/005 Inspection and Testing of Motors 50 Work Orders 20719887, 20673972, 20673826, 20715356, 20703933, 20703934, 20652712, 20673280, 20673822 Corrective Action Documents Nuclear Condition Report(s) 02555641, 02555639, 02555642 71114.06 Miscellaneous Emergency Preparedness Critique Report: MNS Drill 25-01 on 5/21/25 06/19/2025 Corrective Action Documents AR-02550871 Miscellaneous PIRT (CR 02543473)
AD-RP-ALL-0010 Radiological Job Coverage Procedures PD-RP-ALL-0001 Radiation Worker Responsibilities 15 71124.01 Radiation Work Permits (RWPs)
RWP 73 02411069 02427036 02470159 02472222 02476377 02479195 02511416 02532917 Corrective Action Documents 02542786 02557904 71124.06 Corrective Action Documents Resulting from Inspection 02557909 71124.07 Corrective Action Documents ARs 02392960,
- 02416930, 02429448,
- 02453792, 02490607, and 02547094 Various
17 Inspection Procedure Type Designation Description or Title Revision or Date 71124.08 Miscellaneous Procedure AD-RP-ALL-5002 10 CFR 61 RADIOACTIVE WASTE CLASSIFICATION REPORT 08/28/2024 MSPI Derivation Report - McGuire Unit 1 - MSPI Emergency AC Power System - Performance Limit Exceeded (PLE) 05/14/2025 MSPI Derivation Report - McGuire Unit 2 - MSPI Emergency AC Power System - Performance Limit Exceeded (PLE) 05/14/2025 MSPI Derivation Report - McGuire Unit 1 - MSPI Emergency AC Power System - Unavailability Index (UAI) 05/14/2025 MSPI Derivation Report - McGuire Unit 2 - MSPI Emergency AC Power System - Unavailability Index (UAI) 05/14/2025 MSPI Derivation Report - McGuire Unit 1 - MSPI Emergency AC Power System - Unreliability Index (URI) 05/14/2025 MSPI Derivation Report - McGuire Unit 2 - MSPI Emergency AC Power System - Unreliability Index (URI) 05/14/2025 MSPI Derivation Report - McGuire Unit 1 - High Pressure Injection System - Performance Limit Exceeded (PLE) 05/14/2025 MSPI Derivation Report - McGuire Unit 2 - High Pressure Injection System - Performance Limit Exceeded (PLE) 05/14/2025 MSPI Derivation Report - McGuire Unit 1 - High Pressure Injection System - Unavailability Index (UAI) 05/14/2025 MSPI Derivation Report - McGuire Unit 2 - High Pressure Injection System - Unavailability Index (UAI) 05/14/2025 MSPI Derivation Report - McGuire Unit 1 - High Pressure Injection System - Unreliability Index (URI) 05/14/2025 71151 Miscellaneous MSPI Derivation Report - McGuire Unit 2 - High Pressure Injection System - Unreliability Index (URI) 05/14/2025 AD-PI-ALL-0106 Cause Investigation Checklists 10 OP/1/A/6200/009 Accumulator Operation 124 71152A Procedures OP/1/A/6200/009 Accumulator Operation 126