IR 05000369/2020004

Integrated Inspection Report 05000369/2020004, 05000370/2020004, and 07200038/2020002

ML21026A254
Person / Time
Site:	McGuire, Mcguire
Issue date:	01/26/2021
From:	Tobin T NRC/RGN-II/DRP/RPB1
To:	Teresa Ray Duke Energy Carolinas
References
IR 2020002, IR 2020004
Download: ML21026A254 (21)

Text

January 26, 2021

SUBJECT:

MCGUIRE NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000369/2020004, 05000370/2020004, AND 07200038/2020002

Dear Mr. Ray:

On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at McGuire Nuclear Station. On January 14, 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.

No findings or violations of more than minor significance were identified during this inspection.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Margaret C. Tobin, Acting Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos. 05000369, 05000370, and 07200038 License Nos. NPF-17 and NPF-9

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000369, 05000370, and 07200038 License Numbers: NPF-9 and NPF-17 Report Numbers: 05000369/2020004, 05000370/2020004, and 07200038/2020002 Enterprise Identifier: I-2020-004-0047; I-2020-002-0073 Licensee: Duke Energy Carolinas, LLC Facility: McGuire Nuclear Station Location: Huntersville, North Carolina Inspection Dates: September 01, 2020 to December 31, 2020 Inspectors: A. Hutto, Senior Resident Inspector A. Butcavage, Reactor Inspector R. Cureton, Resident Inspector B. Griman, Project Engineer B. Kellner, Senior Health Physicist S. Sandal, Senior Risk Analyst Approved By: Margaret C. Tobin, Acting Chief Reactor Projects Branch 1 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at McGuire Nuclear Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 began the inspection period shutdown for a scheduled refueling outage. The unit was placed on line October 20, 2020 and was returned to 100 percent rated thermal power (RTP) on October 24, 2020. The unit operated 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 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 Disease 2019 (COVID-19), resident 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; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; 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 portions 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

External Flooding Sample (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding.

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) 1A train of spent fuel pool cooling system (KF), on October 6, 2020

(2) 1B train of auxiliary feedwater (CA) system, on November 12, 2020

(3) 2A diesel generator (EDG), on December 17, 2020

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

(1) The inspectors evaluated system configurations during a complete walkdown of the 2B nuclear service water system on November 9, 2020.

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 and 2 vital battery area, on October 11, 2020

(2) Turbine building basement instrument air compressor area, on December 21, 2020

(3) Unit 1 auxiliary building 750' ETA switchgear area, on December 28, 2020

(4) Unit 2 auxiliary building 733' ETB switchgear area, on December 30, 2020

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 live burn training on November 19, 2020.

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 03.01) (2 Samples)

The inspectors evaluated internal flooding mitigation protections in the:

(1) Unit 1 and 2 diesel generator rooms, on October 19, 2020

(2) Unit 1and 2 auxiliary building 695 level and component cooling pump areas, on November 3, 2020

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

(1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, 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 from 9/21/20 to 10/16/20:

03.01.a - Nondestructive Examination and Welding Activities.

• Ultrasonic Examination (UT) of ASME Class 1, Component ID. 1RPV1-446A, Closure Head Meridional Weld, Rpt. No.VE-20-003 (10 Year ISI Sample Review)

• UT, ASME Class 1, Component ID. 1RPV1-446A Reactor Vessel Closure Head Meridional Weld, Rpt. No. VE-20-005 (10 Year ISI Sample Review)

• Enhanced Visual Examination (EVT-1) of Reactor Vessel Core Barrel Upper Flange Weld (MRP-227 Primary Component Sample Review)

• EVT-1 of Reactor Vessel Core Barrel Lower Girth Weld (MRP-227 Primary Component Sample Review)

• VT-2 of ASME Class 1 Reactor Lower Head Penetrations IAW N722-1 BMI Penetrations, plus Lower Head Surface, and Nozzle Connections

• Work Order (WO) 20424739, Pre-Fab Welds, ASME Class 2, Valve 1-NI-IV-5010 Replacement 03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities

• VT -2 of ASME Class 1, Reactor Upper Closure Head IAW N729-4, Penetration Numbers 15, 25, 32, 62, and 75 (Video Review)

• WO 2036630, PM 1NC-RX-59, Perform Lower Canopy Seal Weld Leak Check Inspection (Reviewed)03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.

The inspectors evaluated the licensees boric acid corrosion control program performance, through field walk-downs inside containment and review of the boric acid program corrective actions and evaluations of reported leakage as listed in the documents reviewed section. This review included corrective actions planned to address refueling cavity seal leakage presented in CR-1557752.

03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities.

• No Sg EC Scheduled. Reviewed MNS 1E9C27, Skip Year Justification (Reviewed)

OE Sample: AR -02342522, Evaluation of IG-20-1, CRDM Latch Assembly Stationary Gripper Wear

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance

Requalification Examination Results (IP Section 03.03) (1 Sample)

(1) On July 21, 2020, the licensee completed the comprehensive biennial requalification written examinations and the annual requalification operating examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), Requalification Requirements, of the NRCs Operators Licenses. During the week of December 14, 2020, the inspectors performed an in-office review of the overall pass/fail results of the individual operating examinations and the crew simulator operating examinations in accordance with Inspection Procedure (IP) 71111.11, Licensed Operator Requalification Program. These results were compared to the thresholds established in Section 3.02, Requalification Examination Results, of IP 71111.11.

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 1 refueling outage, on October 15, 2020.

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

(1) The inspectors observed and evaluated a simulator refresher training dual unit exercise on November 3, 2020. The training scenario included a Unit 1 steam generator tube leak and rupture concurrent with a Unit 2 loss of the 2A busline and generator runback.

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) 2354739, Investigate/repair overload on 1WL-39A, on October 25, 2020

(2) NCR 2349944, 1VB-50 failed penetration test due to excessive leakage, on December 10, 2020

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)

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 EVCB vital battery out of service for maintenance and testing, on December 7, 2020

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 2349944, Penetration 1VB-50 failed leak test due to excessive leakage, on October 8, 2020

(2) NCR 2353723, MSD 585 evaluation for material remaining in lower containment through mode 4, on October 11, 2020

(3) NCR 2356006, 2D reactor coolant loop flow Channel 1 reading 111 percent, on November 3, 2020

(4) NCR 2357980, 1EMF-35L intermittent trip 2 alarm, on November 18, 2020

(5) NCR 2360561, PT/0/A/4150/041," RCCA Bank Reposition," could not be completed due to operator aid computer alarm, on December 8, 2020

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 (EC) 417467, Permanently bypass containment iodine detector 2EMF40

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)

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

(1) PT/1/A/4200/008 B, "NC Pressure Isolation Valve Leak Test," Enclosure 13.5, "Valve Leak Rate Test for 1NI-60," following 1NI-60 valve repair, on October 19, 2020

(2) PT/1/A/4400/105, "RCCA Drop Timing Using DRPI System," following M1R27 component shuffle and core reload, on October 19, 2020

(3) PT/0/A/4150/029, "Initial Approach to Criticality and Zero Power Physics Testing,"

following M1R27 core reload, on October 20, 2020

(4) PT/1/A/4350/002 A, "Diesel Generator 1A Operability Test," following 1A diesel generator preventive maintenance (PM) on October 27, 2020

(5) PT/1/A/4502/002 A, "WL Train A Valve Stroke Timing - Quarterly," following actuator replacement for 1WL-39A, on November 13, 2020

(6) PT/1/A/4401/014 B, "Train B KC/ND HX Valve Stroke Timing - Quarterly," following valve PMs on 1KC-81B, on December 10, 20020

(7) IP/0/A/3061/012, "Charging Site Lead-Acid Batteries," Enclosure 11.2, "Post Equalize Cell Readings," following performance test and equalize charge of vital battery EVCB, on December 14, 2020

71111.20 - Refueling and Other Outage Activities

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

(1) The inspectors evaluated refueling outage M1R27 activities from October 1, 2020 to October 21, 2020.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) PT/1/A/4350/002 A, "1A Diesel Generator Operability Test," on November 24, 2020

Inservice Testing (IP Section 03.01) (1 Sample)

(1) PT/2/A/4252/001 A, "2A CA Pump Performance Test," on December 29, 2020

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

(1) PT/1/A/4200/001 C, "Isolation Valve Leak Rate Test," on October 08, 2020

71114.06 - Drill Evaluation

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

(1) The inspectors evaluated the emergency preparedness drill conducted on October 28, 2020. The drill involved a steam generator tube rupture, followed by a failed open main steam relief valve, and loose parts induced fuel failure.

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 radiological protection-related instructions to plant workers.

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 licensee surveys of potentially contaminated material being removed through the Unit 1 equipment hatch during a refueling outage.

(2) Observed surveys to release material from the RCA during the Unit 1 refueling outage.

(3) Observed workers exiting the RCA during a Unit 1 refueling outage.

Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)

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

(1) Transfer Canal Blind Flange Removal - RWP #1951

(2) Rx head lift and move to the head stand - RWP #1728

(3) Rx core barrel lift and placement in the stand in the deep of the cavity - RWP #1384

(4) Rx core barrel 10 year ISI activities (underwater inspections) - RWP # 1040 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) Unit 1 incore thimble main access hatch (Grave Danger)

(2) Unit 1 incore thimble secondary access hatch (Grave Danger)

(3) Unit 1 transfer tube access hatch (Grave Danger)

(4) Unit 1 Lower Containment personnel hatch (High Radiation Area)

(5) Unit 1 Containment fuel transfer tube temporary fencing (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.

OTHER ACTIVITIES - BASELINE

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

BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) ===

(1) Unit 1 (October 1, 2019 through September 30, 2020)

(2) Unit 2 (October 1, 2019 through September 30, 2020)

BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)

(1) Unit 1 (October 1, 2019 through September 30, 2020)

(2) Unit 2 (October 1, 2019 through September 30, 2020)

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

(1) October 1, 2019 through June 30, 2020

71152 - Problem Identification and Resolution

Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in human performance that might be indicative of a more significant safety issue.

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 2334437, Internal flood barrier service life

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 2515/194 - Inspection of the Licensees Implementation of Industry Initiative Associated With the Open Phase Condition Design Vulnerabilities In Electric Power Systems (NRC Bulletin 2012-01)

Revision 0 of this TI was previously inspected, and closed, in Inspection Report 2019011 (ADAMS ML19330D480). However, a subsequent revision to the NEI Voluntary Initiative (Revision 3) provided plants the option of to leave the open phase protection (OPP) system in monitoring mode only in lieu of activating the automatic trip circuitry, provided it was supported by a risk evaluation. Revision 1 (and later Revision 2) of this TI was issued to provide inspection guidance for the new option.

The inspectors reviewed licensee analyses and procedures that demonstrated operator manual actions would successfully mitigate the impact of an open phase condition (OPC). The analyses were reviewed remotely, and the procedures were reviewed and walked down on site.

The inspectors completed Section 03.01c of TI 2515/194, Revision 2.

The inspectors verified that modeling used for the OPC reflected the as-designed and as-built plant, assumptions made by the licensee were reasonable, and licensee procedures were adequate to successfully respond to an OPC. The inspectors also verified that human reliability analysis and recovery evaluations were done in accordance with NEI and voluntary initiative guidance.

60855.1 - Operation of an Independent Spent Fuel Storage Installation at Operating Plants Operation of an Independent Spent Fuel Storage Installation at Operating Plants

(1) The inspectors evaluated the licensees activities related to long-term operation and monitoring of their independent spent fuel storage installation.

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On October 1, 2020, the inspectors presented the radiation safety inspection results to T. Ray, Site Vice President, and other members of the licensee staff.

• On January 14, 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

2515/194 Calculations MCC-1535.00-00- McGuire Nuclear Station PRA Analysis of Implementation 1

250 Options for Open Phase Condition Protection

Procedures EP/1/A/5000/E-0 Reactor Trip or Safety Injection 37

EP/1/A/5000/ES- Reactor Trip Response 49

0.1

OP/1/A/6100/010 Annunciator Response for Panel 1AD-11 90

L

71111.01 Procedures AD-WC-ALL-0230 Seasonal Readiness

AP/0/A/5500/044 Plant Flooding

PT/0/B/4700/038 Cold Weather Protection

PT/0/B/4700/070 On Demand Freeze Protection Verification Checklist

71111.04 Corrective Action NCR 02304934 ADJUST 2RN-25B VI ACCUMULATOR TANK PRESSURE November

Documents 28, 2019

NCR 02308418 2RNST0002: STRAINER HAS A PACKING LEAK December

GREATER THAN ALLOWED 21, 2019

NCR 02322379 2RNFS5780: 2B ND Pump Motor AHU RN Flow Low March 26,

20

Drawings MCFD-2574- Flow Diagram of Nuclear Service Water System (RN) 42

01.01

Procedures OP/2/A/6350/002 Diesel Generator 117

A

Work Orders 20368730 2RN-43A REPLACE CLUTCH RING ASSEMBLY June 25,

20

20388176 PM 2RNLP5010, RN PUMP STRAINER 2B PRESSURE March 10,

20

71111.05 Drawings MSFD-13 Vital Battery Room

Fire Plans CSD-MNS-PFP- Aux Bldg Elevation 733 Pre-Fire Plan 0

AB-0733-001

CSD-MNS-PFP- Aux Bldg Elevation 750 Pre-Fire Plan 0

AB-0750-001

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedures AD-EG-ALL-1520 Transient Combustible Control

71111.06 Procedures AP/0/A/5500/044 Plant Flooding

71111.08P Corrective Action Action Request - IG-20-1, CRDM Latch Assembly Stationary Gripper Wear 8/5/20

Documents 02342522 Operating Experience Evaluation

AR #01985576 Self-Assessment, Boric Acid Corrosion Control Program - 7/25/16

Implementation Procedure Effectiveness

AR - 02268666 Leakage identified during a VT-2 for Class A & B Walk-down 3/16/19

AR - 02314052 ISI Owner Proficiency, Program Health Report Indicator 2/03/20

Decline

AR - 02318485 Boric Acid Evaluation 2/28/20

AR - 02348773 M1R27 Scope Change - Thermal Fatigue Examinations 9/15/20

AR - 02349029 Recommendations from the Operating Experience, Dropped 9/16/20

Rod Event in 2019

AR - 02351528 ISI Visual Examination of 1-RPV-HEAD-PEN 10/1/20

AR 02350145 Boric Acid Corrosion Control Evaluation 10/7/20

AR- 02351608 ISI Visual Examination Limitation of 1-RPV-HEAD-Pen 10/3/20

AR-01935614 AR SUBJECT: G-ENG-SA-15-01-Augmented Inservice 7/8/15

Inspection - Focused SA

AR-02317305 Evaluation of 1-KF-VA-0014 Excessive Boron at Pipe 2/21/20

Cap/Nipple Connection

NCR 02349362 M1R27 Mode 3 Walkdown (Shutdown) 9/19/20

Drawings MCM-1201.01- Reactor Nozzle Details 10/1/1999

0148.001

MCM-1225.01- As Built Location of Weld Seams on Reactor Closure Head 8/1/1977

25.001

Engineering MNS 1E9C27 McGuire Unit 1 Steam Generator, M1R27 Skipped 0

Evaluations Skip Cycle Inspection Cycle Outage Review

Assessment Final

Miscellaneous AD-NE-ALL-1101, Visual Acuity Record for Company ID No. 472208 8/25/20

Rev.5, Att. 6

AD-NE-ALL-1101, Documentation of ASME Section XI, Appendix VII Annual 8/18/20

Inspection Type Designation Description or Title Revision or

Procedure Date

Rev.5, Att. 8 Training and 10 CFR 50.55a Hands on Practice, Candidate

ID 472208

Candidate ID No. NDE Examiner Written Certification Review, Direct and 9/9/20

288663 Remote VT-2 (with BACC)

Certificate of Visual Examination VT 1 and VT-3, Qualification Certification 8/11/20

Personnel

Qualification ID

No.: C2319

Certificate of Qualification Certification as VT Instructor and VT-1, 2 & 3 8/11/20

Personnel Examiner

Qualification ID

No.: L6868

Certificate of Visual Acuity Examination Certification 1/8/20

Personnel

Qualification ID

No.: L6868

NRC Safety Safety Evaluation by the Office of Nuclear Reactor 6/28/10

Evaluation for Regulation of Third 10-Year Interval Inservice Inspection

Relief Request Relief Request No. 09-MN-003, Duke Energy Carolinas LLC,

09-MN-003 McGuire Nuclear Station Unit 1, Docket No. 50-369

(ML101610306)

PDI Program Performance Demonstration Initiative Program, Manual 7/9/14

Qualification for Ultrasonic Examination Qualification Record for PDI-UT-12,

Candidate #1025 Rev. "D", Add. 0, Candidates #1025

PDI Program Performance Demonstration Initiative Program, Manual 8/30/19

Qualification for Ultrasonic Examination Qualification Record for PDI-UT-12,

Candidate #1037 Rev. "E", Add. 0, Candidates #1037

Relief Request McGuire 1, Relief Request For Extension of Reactor Vessel 6/28/10

09-MN-003 Inservice Inspection Date to 2020 +/- 1Year

Inspection Type Designation Description or Title Revision or

Procedure Date

Visual Sections Ill Certificate of Personnel Qualification, Candidate ID No.: 8/11/20

& XI, Ultrasonic L6868

Sections Ill & XI,

ASME Section XI

Appendix VIII,

PDI PDQS No.

23, with Special

Qualifications for

MRP-227/228

Endorsement and

VT-2 of Reactor

Heads

Visual VT-1 & 3 Certificate of Personnel Qualification, Candidate ID No.: 8/11/20

Section XI, with C2319

MRP-227 and

MRP 228

Endorsement

Welder ID D7468 Record of Welder Performance Qualification Test, ASME 11/25/08

Section IX, Groove Welds, GTAW Process, Manual, P-1 thru

P15F, P34 and all P3X, WPS No. GTSM0101-01, Rev. 4

NDE Reports A 51-9222850- Relief Request 09-MN-003, Verification of Oconee Unit-3, 10 7/24/14

000 Year Reactor ISI Inspection Completion in 2014, in

exchange for Extension of McGuire Unit-1,10 Year Reactor

Vessel ISI Inspection, "Oconee Nuclear Station, Unit- 3

EOC27 Reactor Vessel UT Examination Report

Certificate of Certification of Visual Acuity 1/20/20

Vision

Examination ID

No. C2319

NDE Examiner VT-2 Direct and Remote (with BACC)

Inspection Type Designation Description or Title Revision or

Procedure Date

Written Practice

Certification

Review, ID No.

288663

PT/ LA/4200/044 Containment Structural Integrity Inspection 4/25/19

VE-20-003 Ultrasonic Examination (UT) of ASME Class 1, Component 9/24/20

I

D. 1RPV1-446A, Reactor Vessel Closure Head Meridional

Weld

VE-20-004 Ultrasonic Examination (UT) of ASME Class 1, Component 9/24/20

I

D. 1RPV1-446B, Reactor vessel Closure Head Meridional

Weld

VT-20-079 Inconel Transition Weld to Stainless Steel Tube 9/28/20

VT-20-098 ASME Class 1, RPV Closure Head Outer Surface, Visual 10/3/20

Inspection (VT-2)

Procedures 54-ISl-370-007 Remote Underwater Visual Examination of PWR Reactor 2/8/18

Pressure Vessel

Internals in Accordance with MRP 227 & 228

AD-EG-PWR- Boric Acid Corrosion Control Program Implementation 3

1611 Program

AD-MN-ALL-0006 FLUID LEAK MANAGEMENT 2

AD-PI-ALL-0400 Operating Experience Program 9

NDE-NE-ALL- Utilization of PDI-UT-12 Procedure for Manual Phased Array 2

212 Ultrasonic Examination of Reactor Pressure Vessel Welds

NDE-NE-ALL- Visual Examination of PWR Reactor Pressure Vessel Upper 4

202 Head Penetrations

NDE-NE-ALL- Visual Examination of PWR Reactor Pressure Vessel 3

203 Bottom Mounted Instrument Penetrations

Inspection Type Designation Description or Title Revision or

Procedure Date

PD-EG-PWR- BORIC ACID CORROSION CONTROL PROGRAM 1

1611

PDI-UT-12 Procedure for Manual Phased Array Ultrasonic Examination E

of Reactor Pressure Vessel Welds

SM 0-A-8140-001 Welding Of QA And Non-QA Piping, Valves And 9/30/20

Components, Valve ID No. 1-NI-IV-5010

TE-MN-PWR- INSPECTION, ASSESSMENT, AND CLEANUP OF BORIC 0

0006 ACID ON PLANT MATERIALS

Work Orders WO 20424739 Weld Document Instruction, Weld ID 201037, Replace 9/26/20

Isolation Valve, 1-NI-IV-5010

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

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

Notebooks

AD-EG-ALL-1210 Maintenance Rule Program

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

71111.13 Procedures AD-OP-ALL-0201 Protected Equipment

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 Engineering EC 417467 Permanently Bypass Containment Iodine Detector 2EMF40

Evaluations

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

71111.20 Procedures OP/1/A/6100/003 Controlling Procedure for Unit Operation

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

PT/1/A/4600/003 Containment Cleanliness and ECCS Operability Inspection

F

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

Administration

Inspection Type Designation Description or Title Revision or

Procedure Date

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

AD-WC-ALL-0250 Work Implementation and Completion

PT/1/A/4200/001 Isolation Valve Leak Rate Test 130

C

PT/2/A/4252/001 2A CA Pump Performance Test 097

A

71124.01 Corrective Action Nuclear Condition 02266623, 02291246, 02339071, 02342263, 02345554, and Various

Documents Report 02345729

Miscellaneous Radioactive Air Sample Log Results, 10/1/2019 through 9/28/20

9/28/2020

RP# 604962 Intake Assessment - Ingestion [DRAFT] 9/27/20

TEDE-ALARA RWP # 1840, Task 6 [Unit 1 Cavity, deep end decon] 9/28/20

Evaluation

Worksheet

Procedures AD-PI-ALL-0100 Corrective Action Program 22

AD-RP-ALL-0003 Radiological Air Sampling 4

AD-RP-ALL-0005 Access Controls for High and Locked High Radiation Areas 1

AD-RP-ALL-0007 Control of Radioactive Material 0

AD-RP-ALL-0010 Radiological Job Coverage 0

AD-RP-ALL-2008 Remote Monitoring 4

AD-RP-ALL-2014 Work in Alpha Environments 7

AD-RP-ALL-2017 Access Controls to Very High Radiation Areas and 7

Supplemental Access Controls for HRA and LHRA

AD-RP-ALL-2019 TEDE-ALARA Evaluations and DAC-Hour Tracking 3

RPMP 7-1 Radiological Key Control 15

RPMP 7-11 Contamination Controls 16

RPMP 7-15 Supplemental Guidelines for Establishing High, Locked High 12

and Very High Radiation Areas

Radiation MNS-M- Unit 1 Blind flange removal [transfer canal] 9/22/20

Surveys 20200922-21

MNS-M- Unit 1 Post Rx Head move 9/24/20

200924-7

MNS-M- Unit 1 Core Barrel removal and move to stand in lower cavity 9/27/20

200927-12

Inspection Type Designation Description or Title Revision or

Procedure Date

MNS-M- Unit 1 Core Barrel removal and move to stand in lower cavity 9/27/20

200928-13

MNS-M- Unit 1 Core Barrel removal and move to stand in lower cavity

200928-14

Radiation Work RWP # 1040 U-1 Rx Bldg: 10 year ISI Reactor Vessel and Core Barrel 1

Permits (RWPs) RWP # 1384 Unit 1 Rx Bldg: Remove and Replace Core Barrel 2

RWP # 1728 Unit 1 Rx Bldg: R & R Rx head, vessel flange cleaning and 13

cleaning and replace Rx head O-rings

RWP # 1730 Unit 1 Rx Bldg: Remove and Replace "A" NCP Seals 10

RWP # 1902 Unit 1 Rx Bldg/Aux Bldg: Misc Surveillance (management, 12

safety tours, etc.)

Shipping Records Shipment ID 20-4- McGuire Incoming Radioactive Material Shipment 9/15/20

086 Documentation [including equipment radiation surveys] used

in basis for Intake Assessment

71151 Corrective Action Nuclear Condition Various

Documents Report 02270402,

293248, and

2348855

Miscellaneous Electronic Dosimeter (ED) Dose / Dose Rate Alarm Logs - Various

10/01/2019 through 09/29/2020

Procedures AD-LS-ALL-0004 NRC Performance Indicators and Monthly Operating Report

AD-PI-ALL-0100 Corrective Action Program

AD-PI-ALL-0100 Corrective Action Program 22

AD-PI-ALL-0700 Performance Indicators 3

71152 Procedures AD-LS-ALL-0006 Notification/Reportability Evaluation

AD-PI-ALL-0100 Corrective Action Program

AD-PI-ALL-0105 Effectiveness Reviews

19