IR 05000369/2025002
| 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
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 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
Inspection Report
Docket Numbers:
05000369 and 05000370
License Numbers:
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
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: 71111.1
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
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.
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)===
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 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
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:
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,
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.
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.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation
Radioactive Material Storage (IP Section 03.01)
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
- (5) RSR MNS 24-0015, DAW, including two sealand containers, LSA-I and LSA-II waste, shipped September 19,
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, 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)
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,
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
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.
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
Procedures
AD-WC-ALL-0260
Nuclear Generation Response to High or Low Grid System
Load
MCFD-1561-
01.00
Flow Diagram of Residual Heat Removal System (ND)
MCFD-1574-
01.00
Flow Diagram of Nuclear Service Water System (RN)
MCFD-1574-
01.01
Flow Diagram of Nuclear Service Water System (RN)
MCFD-1592-
01.00
Flow Diagram of Auxiliary Feedwater System (CA)
MCFD-1592-
01.01
Flow Diagram of Auxiliary Feedwater System (CA)
Drawings
MCFD-2554-
03.01
Flow Diagram of Chemical and Volume Control System (NV)
Corrective Action
Documents
Resulting from
Inspection
Nuclear Condition
Report(s)
2556945
CSD-MN-PFP-
SRV-0750-001
Service Building Elevation 750 Pre-Fire Plan
CSD-MNS-PFP-
AB-0767-001
Auxiliary Building Elevation 767 Pre-Fire Plan
CSD-MNS-PFP-
RB1-0000-001
U1 Reactor Building Elevation All Pre-Fire Plan
Fire Plans
CSD-MNS-PFP-
SRV-0739-001
Service Building Elevation 739 Pre-Fire Plan
Miscellaneous
Preventative
Maintenance
Change
Request(s)
286560
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
MP/0/A/7700/013
Component Cooling System (KC) HX Maintenance
Work Orders
20673956
NDE Reports
180-9348166-000
McGuire Unit-1(M1R29) RVCH and AHA NDE Final Report
2/14/2023
AD-EG-PWR-
1611
Boric Acid Corrosion Control Program - Implementation
Procedures
NDE-NE-ALL-
6106
Ultrasonic Examination of mid or large Diameter Piping
Welds and Base Materials for Thermal Fatigue Damage
OP/1/A/6100/SD-
Cooldown to 400°F
OP/1/A/6100/SD-
Cooldown to 240°F
OP/1/A/6100/SD-
6A
Placing Train A ND in Service
OP/1/A/6100/SD-
Water Solid Operations
OP/1/A/6150/009
Boron Concentration Control
145
PT/1/A/4252/001C
- 1 TD CA Pump Performance Test Opening 1SA-49 First
Procedures
PT/1/A/4600/106
RCCA Drop Timing Using DRPI System
Corrective Action
Documents
Nuclear Condition
Report(s)
2459941, 02542279, 02454401
Corrective Action
Documents
Resulting from
Inspection
Nuclear Condition
Report(s)
2555667
Drawings
MC -2717-22.01-
C/D Area Term Cab No. 2ATC22 (Train A) Left Half
AD-EG-ALL-1210
DPM 1393.01-
0002.001
Environmental Qualification Pkg for Cutler-Hammer D26 Ser
Type M
DPM 1393.01-
0002.002
Environmental Qualification Package for Eaton Corporation
(Cutler-Hammer) D26 Series Type M Relays and
Accessories Volume 2
Procedures
DPM 1393.01-
0002.003
Seismic Testing of Eaton D26 Relays
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
MCC-51535.00-
00-0006
PRA Risk Significant SSCs for the Maintenance Rule
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
AD-OP-ALL-0212
Risk Informed Completion Time Program Calculations
AD-WC-ALL-0420
Shutdown Risk Management
AD-WC-MNS-
20
Shutdown Risk Management
Procedures
OP/1/A/6100/SD-
Draining the NC System
20725181
Work Orders
Work Request(s)
285149
OP/1/A/6200/009
Accumulator Operation
26
Procedures
OP/1/A/6200/009
Accumulator Operation
24
20673915
Work Orders
Work Request(s)
286237
Calculations
MCM 2318.20-
0033.001
N.S.
- W.P. Motor Final Test Report, 1S-75 75L 10936
Work Orders
20652712
Calculations
MCM-1205.19-
0039.001
Electric Motor Operator GL89-10 Set-up Information
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
Procedures
IP/0/B/3203/005A
Moore Products Model 528PM and Special Transfer Station
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
28PM (M-383) Selector Station Calibration and Check-out
IP/A/3190/005
Inspection and Testing of Motors
Work Orders
20719887, 20673972, 20673826, 20715356, 20703933,
20703934, 20652712, 20673280, 20673822
Corrective Action
Documents
Nuclear Condition
Report(s)
2555641, 02555639, 02555642
Miscellaneous
Emergency Preparedness Critique Report: MNS Drill 25-01
on 5/21/25
06/19/2025
Corrective Action
Documents
Miscellaneous
PIRT (CR 02543473)
AD-RP-ALL-0010
Radiological Job Coverage
Procedures
PD-RP-ALL-0001
Radiation Worker Responsibilities
Radiation Work
Permits (RWPs)
RWP 73
2411069
2427036
2470159
2472222
2476377
2479195
2511416
2532917
Corrective Action
Documents
2542786
2557904
Corrective Action
Documents
Resulting from
Inspection
2557909
Corrective Action
Documents
ARs 02392960,
2416930,
2429448,
2453792,
2490607, and
2547094
Various
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Procedure AD-
RP-ALL-5002
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
OP/1/A/6200/009
Accumulator Operation
24
Procedures
OP/1/A/6200/009
Accumulator Operation
26