IR 05000369/2020012

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NRC Post-Approval Site Inspection for License Renewal, Inspection Report 05000369/2020012 and 05000370/2020012
ML20213B223
Person / Time
Site: Mcguire, McGuire  Duke energy icon.png
Issue date: 07/31/2020
From: Binoy Desai
NRC/RGN-II/DRS/EB3
To: Teresa Ray
Duke Energy Carolinas
References
IR 2020012
Download: ML20213B223 (24)
v • d • e


Text

July 31, 2020

SUBJECT:

MCGUIRE NUCLEAR STATION UNITS 1 AND 2 - NRC POST-APPROVAL SITE INSPECTION FOR LICENSE RENEWAL, INSPECTION REPORT 05000369/2020012 AND 05000370/2020012

Dear Mr. Ray:

On June 19, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed a Post-Approval Site Inspection for License Renewal at McGuire Nuclear Station. On June 18, 2020, 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/

Binoy B. Desai, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 05000369 and 05000370 License Nos. NPF-17 and NPF-9

Enclosure:

Inspection Report

Docket Numbers: 05000369 and 05000370 License Numbers: NPF-9 and NPF-17 Report Numbers: 05000369/2020012 and 05000370/2020012 Enterprise Identifier: I-2020-012-0020 Licensee: Duke Energy Carolinas, LLC Facility: McGuire Nuclear Station Location: Huntersville, NC Inspection Dates: June 1, 2020 to June 19, 2020 Inspectors: A. Butcavage, Reactor Inspector B. Collins, Senior Reactor Inspector (Lead)

P. Cooper, Reactor Inspector S. Downey, Senior Reactor Inspector S. Makor, Reactor Inspector M. Tobin, Senior Resident Inspector Pwr/Tl Approved By: Binoy B. Desai, Chief Engineering Branch 3 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a NRC 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.

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.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

===71003 - Post-Approval Site Inspection for License Renewal From June 1, 2020 to June 19, 2020, the NRC continued monitoring Duke Energy's performance at McGuire by conducting a Post-Approval Site Inspection for License Renewal -

Phase II in accordance with the license renewal inspection program (LRIP). This inspection took place prior to the period of extended operation (PEO) for Units 1 and 2, which will begin on June 13, 2021 and March 4, 2023, respectively. Per Inspection Manual Chapter 2516, the LRIP is the process used by NRC staff to verify the adequacy of aging management programs (AMPs), Time Limited Aging Analyses (TLAAs), and other activities associated with an applicants request to renew an operating license of a commercial nuclear power plant beyond the initial licensing period under 10 CFR Part 54, Requirements for the Renewal of Operating Licenses for Nuclear Power Plants.

Post-Approval Site Inspection for License Renewal ===

Main article: IP 71003
(1) License Conditions and Commitments for License Renewal, Implementation of Aging Management Programs and Time-Limited Aging Analyses There are a total of 62 license renewal action items linked to the renewed operating license for McGuire Nuclear Plant Units 1 and 2, issued in December 2003, which include the following: 2 conditions required directly by the renewed operating license; 21 commitments to enhance existing AMPs; 34 commitments to implement AMPs; and 5 TLAAs. The inspectors reviewed a majority (greater than 70%) of regulatory commitments and associated AMPs and TLAAs in order to assess the adequacy and effectiveness of the license renewal program. For each item selected in the sample, the inspectors also reviewed the applicable license renewal program documents and conducted interviews with licensee staff to verify that the licensee completed the actions necessary to comply with the conditions listed in the renewed facility operating license. For those license renewal action items that were not completed at the time of this inspection, the inspectors verified, where possible, that there was reasonable assurance that such action items were on track for completion prior to the PEO or in accordance with an established implementation schedule consistent with the license renewal application (LRA), the NRC safety evaluation report (SER), and the Updated Final Safety Analysis Report (UFSAR) supplement.

The items selected for the inspection sample are listed below along with the completion status of the item at the time of the inspection. The full description of each item is available in the UFSAR supplement for license renewal, as revised, the Integrated Technical Specifications (ITS), and Appendix A of the NRC SER issued in 5 parts as NUREG-1772 (ML030830181, ML030850152, ML030850164, ML030380218, ML030850237).

Conditions:

  • Condition 1: Analysis of Pressure-Temperature Limit Curves at 34 Effective Full-Power Years for McGuire Unit 1 Reactor Vessel (License Amendment
  1. 269). Status: Complete.
  • Condition 2: Analysis of Pressure-Temperature Limit Curves at 34 Effective Full-Power Years for McGuire Unit 2 Reactor Vessel (License Amendment
  1. 249). Status: Complete.

Commitments:

  • Commitment Item 1a - d: Enhancements to the Alloy 600 Program and In-service Inspection Plan. Status: Complete.
  • Commitment Item 2: Complete the Borated Water Systems Stainless Steel Inspection. Status: Complete.
  • Commitment Item 3a - b: Implement Control Rod Drive and Other Vessel Closure Head Inspections. Status: Complete.

Complete.

  • Commitment Item 5: Complete the Galvanic Susceptibility Inspection. Status:

Complete.

  • Commitment Item 6: Enhancements to the Heat Exchanger Preventative Maintenance Activities. Status: Incomplete. Replacement activities are scheduled and are expected to be completed prior to entering the PEO. Based on the review of the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet Commitment Item 6. Therefore, no follow-up inspection is warranted.
  • Commitment Item 7: Implement the Inaccessible Non-EQ Medium Voltage Cables Aging Management Program. Status: Complete.
  • Commitment Item 8: Implement Enhancements to the In-service Inspection Plan. Status: Complete.
  • Commitment Item 9: Enhancements to the Inspection Program for Civil Engineering Structures and Components. Status: Complete.
  • Commitment Item 10: Complete the Liquid Waste System Inspection. Status:

Complete.

  • Commitment Item 11: Enhancement to Thermal Fatigue Management Program for Environmentally-Assisted Fatigue. Status: Complete.
  • Commitment Item 12: Enhancements to Non-EQ Insulated Cables and Connections. Status: Complete.
  • Commitment Item 13a - b: Pressurizer Spray Head Inspection. Status:

Complete.

  • Commitment Item 14a - c: Enhancements to the Reactor Vessel Internals Program. Status: Complete.
  • Commitment Item 15: Complete the Selective Leaching Inspection. Status:

Complete.

  • Commitment Item 16: Complete the Sump Pump Systems Inspection. Status:

Complete.

  • Commitment Item 17: Complete the Treated Water Systems Stainless Steel Inspection. Status: Complete.
  • Commitment Item 18: Enhancements to Ventilation Pressure Boundary Sealants Inspection. Status. Complete.
  • Commitment Item 19: Complete the Waste Gas System Inspection. Status:

Complete.

  • Commitment Item 20: Complete the Visual Inspections of the Interior Surfaces of the Auxiliary Feedwater System and Main Feedwater System components.

Status: Complete.

  • Commitment Item 21: Enhancements to Fuse Holder Inspection Program.

Status. Complete.

AMPs:

  • ITS SR 3.6.14.2/.4/.5: Divider Barrier Seal Inspection and Testing Program.

Status: Complete.

Status: Complete.

Complete.

  • ITS SR 3.8.4.3: Battery Rack Inspections. Status: Complete.
  • UFSAR 18.2.2: Borated Water Stainless Steel Inspection. Status: Complete.
  • UFSAR 18.2.3: Bottom-Mounted Instrumentation (BMI) Thimble Tube Inspection Program. Status: Incomplete. Some pre-PEO license renewal activities have not been completed. Specifically, based on current wear rate calculations, eddy current testing of the BMI thimble tubes in Unit 2 is required once more prior to the PEO. In addition, preventative maintenance task orders to track the performance of the BMI thimble tube inspections and associated follow up actions for both units during the PEO have not been developed yet. Based on the review of the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions in accordance with the AMP. Therefore, no follow-up inspection is warranted.
  • UFSAR 18.2.4: Chemistry Control Program. Status: Complete.
  • UFSAR 18.2.5: Containment In-service Inspection Plan - IWE. Status.

Complete.

  • UFSAR 18.2.7: Crane Inspection Program. Status: Complete.
  • UFSAR 18.2.8: Fire Protection Program. Status: Incomplete. Some license renewal activities have not been completed. Specifically, the preventative maintenance task order to perform periodic selective leaching inspections of cast iron components in the Fire Protection system during the PEO has not been developed yet. Based on the review of the administrative controls in place to track the pending action, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet Commitment Item 4. Therefore, no follow-up inspection is warranted.
  • UFSAR 18.2.9: Flood Barrier Inspection. Status: Complete.
  • UFSAR 18.2.10: Flow-Accelerated Corrosion Program. Status: Complete.
  • UFSAR 18.2.12: Galvanic Susceptibility Inspection. Status: Complete.
  • UFSAR 18.2.13: Heat Exchanger Activities (Pump Motor Air Handling Units, Pump Oil Coolers). Status: Complete.
  • UFSAR 18.2.14: Ice Condenser Inspections. Status: Complete.
  • UFSAR 18.2.16: In-service Inspection Plan. Status: Complete.
  • UFSAR 18.2.17: Inspection Program for Civil Engineering Structures and Components. Status: Complete. The inspectors identified two observations associated with this AMP, described in detail in the Inspection Results section of this report. However, no follow-up NRC inspection activities are needed to close out these observations.
  • UFSAR 18.2.18: Liquid Waste System Inspection. Status: Complete.
  • UFSAR 18.2.19: Non-EQ Insulated Cables and Connections. Status.

Complete.

  • UFSAR 18.2.21: Preventative Maintenance Activities. Status. Complete.
  • UFSAR 18.2.22: Reactor Vessel Integrity Program. Status: Complete.
  • UFSAR 18.2.23: Reactor Vessel Internals Inspection. Status: Complete.
  • UFSAR 18.2.24: Selective Leaching Inspection. Status: Complete.
  • UFSAR 18.2.26: Sump Pump Systems Inspection. Status: Complete.
  • UFSAR 18.2.27: Treated Water Systems Stainless Steel Inspection. Status:

Complete.

Status: Complete.

  • UFSAR 18.2.30: Waste Gas System Inspection. Status: Complete.
  • UFSAR 18.2.34: Fuse Holder Program. Status: Complete.

TLAAs:

  • UFSAR 3.9.2/5.2.1: Metal Fatigue (Thermal Fatigue, Environmentally-Assisted Fatigue). Status: Complete.
  • UFSAR 3.11: Environmental Qualification (EQ) of Electrical Equipment.

Status: Complete.

  • UFSAR 5.4.3: Reactor Vessel Neutron Embrittlement (Upper Shelf Energy, Pressurized Thermal Shock, Pressure-Temperature Limit Curves). Status:

Complete.

(2) Newly Identified Structures, Systems, and Components (SSCs)

Since the renewed license was issued, the licensee has performed an assessment to identify any structures, systems and components (SSCs) that would have been subject to an aging management review or evaluation as a time-limited aging analysis in accordance with 10 CFR 54.21. The inspectors reviewed the licensees assessment and noted that the following SSCs were identified as being within the scope of license renewal and subject to aging management review:

  • Liquid Waste System - Control Room Air Handling Drains
  • Boral Spent Fuel Rack Neutron Attenuation Material
  • Earthen Dike on the North Perimeter of the McGuire Nuclear Station Site
  • Auxiliary Feedwater Storage Tanks For each newly identified SSC, the inspectors determined that the licensee took appropriate actions in accordance with 10 CFR 54.37(b). Specifically, the inspectors verified that the SSCs have been included in the FSAR update required by 10 CFR 50.71(e), and that the FSAR update described how the effects of aging are managed such that the intended function(s) in 10 CFR 54.4(b) will be effectively maintained during the period of extended operation. The inspectors also reviewed a list of plant modifications performed from the time the LRA was submitted to the time the renewed operating license was issued, to identify any potentially new SSCs that would have been subject to aging management review at the time the NRC was reviewing the LRA. Based on this review, the inspectors did not identify any new SSCs that were subject to the provisions of 10 CFR 54.37(b).
(3) Description of Aging Management Programs in the UFSAR Supplement As part of the review of implementation activities for the selected AMPs, the inspectors reviewed the corresponding UFSAR sections to verify that the program descriptions were consistent with the license renewal application and the corresponding section of the NRC safety evaluation report. The inspectors reviewed three versions of the UFSAR supplement for license renewal as follows:
  • The inspectors reviewed the UFSAR supplement submitted with the LRA, as revised, to identify the program attributes and future inspection activities that were originally relied upon for the approval of the renewed operating license.
  • The inspectors reviewed the revision of the UFSAR submitted to the NRC pursuant to the requirements in 10 CFR 50.71(e)(4) following the issuance of the renewed operating license to verify that the UFSAR supplement for license renewal was included as required by the condition of the renewed operating license.
  • The inspectors reviewed the latest revision of the UFSAR supplement for license renewal (Revision 21) to verify that the program attributes and inspection activities were consistent with the AMPs as originally approved by the NRC and subsequent revisions performed under the provisions of 10 CFR 50.59. The inspectors also verified that any changes caused by the inclusion of newly identified SSCs were included in the UFSAR supplement.
(4) Changes to license renewal commitments and the UFSAR supplement for license renewal As part of the review of license renewal conditions, commitments, AMPs, and TLAAs described in this report, the inspectors reviewed a sample of license renewal commitment change documents to verify the licensee followed the guidance in NEI 99-04, Guidelines for Managing NRC Commitment Changes, for any change to the commitments, including their elimination. Except as identified in the Inspection Results section of the report, the inspectors verified that the licensee properly evaluated, reported, and approved where necessary, changes to license renewal commitments listed in the UFSAR in accordance with 10 CFR 50.59, as required by the Renewed Operating License (Section 2.C.(31))

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

  • On June 18, 2020, the inspectors presented the NRC inspection results to Mr. Tom Ray, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71003 Calculations 0801613.303 Structural Integrity File: Degradation Mechanism Evaluation 6/25/13

for McGuire Unit 2

DPC-1274.00-00- MNS and CNS Pressurizer Spray Head License Renewal Rev. 0

0005 Scoping Impacts Arising from NFPA-805

MCC-1201.01-00- Thermal Sleeve Metrology analysis results from M1R2 Rev. 01

0075

MCC-1252.00-00- Risk Informed lnservice Inspection Program, Degradation Rev. 0

0047 Mechanism Evaluation

for McGuire Unit 1

MCC-1553.03-00- Incore Instrumentation Thimble Tube Wear Review Rev. 7

0014

MCM 1201.01- STRESS REPORT FOR MCGUIRE RV, UPFLOW 5/3/18

0570.001 CONVERSION, (CORE BRL & FORMERS), 60 Year Life

MCM 1201.01- FLAW TOLERANCE EVALUATION FOR LOOP TWO COLD 8/21/17

1352.001 LEG ELBOW AT MCGUIRE NUCLEAR STATION, UNIT 1

Corrective Action 01456914, Condition Reports (various)

Documents 01593605,

01603829,

01606689-28,

01615456-12,

01622607,

01624455,

01636063,

01637337,

01638153,

01650601,

01654080,

01661965,

01667394,

01668900,

01673097,

01685394,

Inspection Type Designation Description or Title Revision or

Procedure Date

01903712,

01903766,

01904065,

01929436,

01955812,

01956970,

01998744,

2012795,

2038505,

2049571,

2055070,

2055850,

2055850,

216723,

223811,

233506,

233854,

234037,

265766,

292574,

298345,

2315252,

1993550-33,

2015273-60,

2142532

Corrective Action 02334437, Condition Reports (various)

Documents 02335756,

Resulting from 02335760,

Inspection 02335765

Drawings MCFD-1574-02.00 Flow Diagram of Nuclear Service Water System (RN) Rev. 35

Engineering EC405225 MNS Selective Leaching Inspection Program Implementation Rev. 0

Changes EC412897 MNS U2 RVCH Thermal Sleeve Replacement Rev. 002

EC415379 License Renewal 10 CFR 54.37(b) Review for MNS Fuel Rev. 0

Cycle 26

Inspection Type Designation Description or Title Revision or

Procedure Date

EC415384 License Renewal Service Water Piping Corrosion Program Rev. 0

Review for MNS Fuel Cycle 26

EC416846 MNS Selective Leaching Inspection Evaluation and Rev. 0

Disposition

EC416847 MNS Galvanic Susceptibility Inspection Evaluation and Rev. 0

Disposition

NTM02015273 Evaluate Update to MNS Chemistry Control AMP Basis 07/31/2020

Document for Tie to Steam Generator Program AMP Basis

Document

NTM02290941 Update MISI-1462.10-0040AUGISI-U1&U2 for License 09/10/2019

Renewal

Engineering 02200826-01 MRP 2018-010, Notification of Recent PWR CRDM Thermal 4/4/18

Evaluations Sleeve Flange Wear and Control Rod Motion Stoppage,

Operating Experience and Recommended Plant Actions

ANP-3658 Framatome Evaluation of the McGuire Units 1 and 2 Upflow Rev. 0

Modification for 60 Years

LCAMP-RVI Life Cycle Aging Management Plan: PWR Reactor Vessel 8/8/17

Integrity Catawba Nuclear Station, Units 1 & 2

H.B. Robinson Nuclear Plant, Unit 2 McGuire Nuclear Station,

Units 1 & 2

Oconee Nuclear Station, Units 1, 2, & 3 Shearon Harris

Nuclear Plant, Unit 1

WCAP-17096-NP Reactor Internals Acceptance Criteria Methodology Rev. 2

'A'

WCAP-17455-NP McGuire Unit 1 and Unit 2 Measurement Uncertainty Rev 0

Recapture (MUR) Power Uprate: Reactor Vessel Integrity and

Neutron Fluence Evaluations.

WCAP-18265-NP Aging Management Program and Inspection Plan for the Rev. 0

McGuire Nuclear Station

Units 1 and 2 Reactor Vessel Internals

WCAP-18412-P McGuire Unit 2 - Upper Internals 17x17A Guide Tube - Guide Dec. 2018

Card Wear Evaluation

WCAP-18454-P McGuire Unit 1 - Upper Internals 17x17 Standard Guide Tube July 2019

- Guide Card Wear

Inspection Type Designation Description or Title Revision or

Procedure Date

Miscellaneous Letter from Steven

D. Capps to U.S. Nuclear Regulatory March 7,

Commission, Restatement of License Condition Proposed in 2013

August 15, 2012 Response to Request for Additional

Information Related to License Amendment Request for

Measurement Uncertainty Recapture Power Uprate (TAC

Nos. ME8213 and ME 8214)"

McGuire Nuclear Station Units 1 and 2, Reactor Vessel Rev. 1

MNS-LR-029 Integrity Historical Implementation Plan

Letter from S.D. Capps to U.S. Nuclear Regulatory 5/14/14

Commission, "McGuire Units 1 and 2 Pressure - Temperature

Limit Curve (Beyond Belt-Line) Analyses Required by License

Conditions Issued as Part of Measurement Uncertainty

Recapture License Amendments"

1462.00 Memo to File: Flow Accelerated Corrosion Program 1EOC24 June 30,

Post Outage Report 2016

DPS-1274.00-00- Programmatic requirements for License Renewal Rev. 0

0005

DPS-1274.00-00- Electrical Components Integrated Plant Assessment and Rev. 3

0006 Evaluation of Time-Limited Aging Analyses for License

Renewal

DPS-1274.000-00- License Renewal Aging Management Programs and Activities Rev. 2

0005

FHG-SLA-NA-0015 Service Level Agreement (SLA) Between Fossil Hydro 11/17/17

Operations Hydro Fleet and McGuire Nuclear Station for DAM

Safety Related Services

LRI-1274.00-0001 License Renewal Cable and Connections Inspection Pre-PEO Rev. 000

Walkdown Report

MC-1462.00 2015 Inspection Report for Civil Engineering Structures and 12/17/15

Components per EDM-410

MC-ISIC3-1042- Third Interval Containment Inservice Inspection Plan Rev. 7

0001

ML003717179 NRC Letter to Mr. Douglas

J. Walters, "License Renewal 5/19/2000

Issue 98-0030, Thermal Aging Embrittlement of Cast

Inspection Type Designation Description or Title Revision or

Procedure Date

Austenitic Stainless Steel Components"

MNS-2019-02-25- Unit-1, Augmented Examination, 1B Cold Leg Elbow Rev. 00

MNS-LR-004 Chemistry Control Program Rev. 2

MNS-LR-005A MNS License Renewal Preventative Maintenance Activities - Rev. 2

Condenser Circulating Water System Internal Coating

Inspection Aging Management Program RC System Internal

Surfaces

MNS-LR-006 Containment Inservice Inspection Plan - IWE Aging Rev. 1

Management Program Implementation Plan

MNS-LR-010 Environmental Qualification Rev. 1

MNS-LR-013 Flow Accelerated Corrosion Program Rev. 0

MNS-LR-016 MNS License Renewal Ice Condenser Inspections Program Rev. 1

Implementation Plan

MNS-LR-017 Inservice Inspection Program Implementation Plan Rev. 2

MNS-LR-026 MNS License Renewal - Underwater Inspection of Nuclear Rev. 2

Service Water Structures Aging Management Program

Implementation Plan

MNS-LR-031 MNS License Renewal Refueling Water Storage Tank Internal Rev. 2

Coating Inspection Program Implementation Plan

MNS-LR-033 MNS License Renewal Borated Water Systems Stainless Rev. 0

Steel Inspection Program Aging Management Program

Implementation Plan

MNS-LR-041 Galvanic Susceptibility Inspection Implementation Plan Rev. 3

MNS-LR-043 License Renewal Heat Exchanger Preventative Maintenance Rev. 2

Activities - Pump Oil Coolers Implementation Plan

MNS-LR-044 Inaccessible Non-EQ Medium-Voltage Cables Aging Rev. 2

Management Program Implementation Plan

MNS-LR-046 MNS Inspection Program for Civil Engineering Structures and Rev. 1

Components Aging Management Program Implementation

Plan

MNS-LR-046 MNS License Renewal Inspection Program for Civil Rev. 1

Engineering Structures and Components Aging Management

Program Implementation Plan

Inspection Type Designation Description or Title Revision or

Procedure Date

MNS-LR-046 MNS License Renewal Inspection Program for Civil Rev. 1

Engineering Structures and Components Aging Management

Program Implementation Plan

MNS-LR-047 MNS License Renewal Liquid Waste System Inspection Aging Rev. 1

Management Program Implementation Plan

MNS-LR-048 Thermal Fatigue Management Program Incorporating Rev. 2

Environmentally-Assisted Fatigue

MNS-LR-049 MNS Non-EQ Insulated Cables and Connections Aging Rev. 2

Management Program Implementation Plan

MNS-LR-052 MNS License Renewal Selective Leaching Inspection Aging Rev. 2

Management Program

MNS-LR-053 MNS License Renewal Sump Pump Systems Inspection Rev. 2

Implementation Plan

MNS-LR-054 MNS License Renewal Treated Water Systems Stainless Rev. 1

Steel Inspection Program Aging Management Program

Implementation Plan

MNS-LR-055 MNS License Renewal Ventilation Area Pressure Boundary Rev. 1

Sealants Inspection Aging Management Program

Implementation Plan

MNS-LR-056 MNS License Renewal Gas System Inspection Aging Rev. 1

Management Program Implementation Plan

MNS-LR-057 MNS License Renewal Additional Chemistry Control Program Rev. 1

(AFW/FW Internal Inspection) Aging Management

Implementation Plan

MNS-LR-058 MNS Fuse Holder Inspection Program Implementation Rev. 1

MNS-LR-060 MNS License Renewal Steam Generator Surveillance Rev. 2

Program Aging Management Program Implementation Plan

MNS-LR-064 MNS License Renewal Auxiliary Feedwater Storage Tank Rev. 1

Internal Coating Inspection Aging Management Program

Implementation Plan

MNS-LR-065 MNS License Renewal Boral Monitoring Aging Management Rev. 2

Program Implementation Plan

MNS-LR-066 MNS License Renewal Nuclear Service Water System Rev. 1

Strainer Elements Inspection Aging Management Program

Inspection Type Designation Description or Title Revision or

Procedure Date

Implementation Plan

MNS-LR-073 Fire Protection Program - Turbine Building Strainer Rev. 1

Inspections Implementation Plan

MNS-LR-074 MNS License Renewal Reactor Makeup Water Storage Tank Rev. 0

Internal Coating Inspection Aging Management

Implementation Plan

MP/0/A/7700/096 Quarterly/ Annual Inspection and Servicing of Overhead and Rev. 20

Gantry Cranes

MP/0/B/7650/007 Annual Inspection of Electric, Air Operated and Hand Rev. 20

Operated Hoists

PD-EG-ALL-1615 Cable Management Program Rev. 2

PMCH 02262585 Change PM frequency to 10A from 6Y - Rev. 0

1RF502 cable

PMCH 02262588 Change PM frequency to 10A from 6Y - Rev. 0

1RF804 cable

PMCH 02317483 Change PMID 2000349-03 to 3Y Rev. 0

PP 11 Historical Pressurizer Spray Head Examination Binder 3/11/2020

PP 38 Historical Inservice Inspection Program 5/6/20

PP 44 Historical Alloy 600 Program 5/7/20

PP 45 Historical Reactor Vessel Integrity Binder 5/12/20

PP 46 Historical Reactor Vessel Internals Program 5/13/20

PP 60 Historical Operating Experience Review 3/23/20

RA-19-0425 Letter from Thomas

D. Ray,
P.E. to US Nuclear Regulatory May 17,

Commission, License Renewal Surge Line and Safety 2020

Injection Nozzle Inspection"

NDE Reports 180-9296414-000 McGuire, Unit 1 M1R26 Reactor Vessel Closure Head 5/24/19

(RVCH) Penetration Ultrasonic Examination

180-9308218-000 McGuire, Unit 2 2R26 Reactor Vessel Closure Head (RVCH) 5/13/20

Penetration Ultrasonic Examination

5646 Metallurgy File: MNS RF Jockey Pump Strainer Inspection January 23,

2017

5760 Metallurgy File: MNS FP-AHU-1A Air Handling Unit January 31,

2018

5794 Metallurgy File: NI Check Valve Socket Welds 2/22/18

Inspection Type Designation Description or Title Revision or

Procedure Date

5999 Metallurgy File: MNS 1 Piping at Valve 1RV-362 Galvanic October 2,

Corrosion Assessment 2019

6031 Metallurgy File: Analysis of 1RF-256 Valve January 15,

20

6054 Metallurgy File: Analysis of MNS 1RF-124-3 Valve February 20,

20

UT-18-001 Unit-2, Crossover Leg 2A Nozzle 1-6 Ultrasonic Examination 9/17/18

UT-19-001 McGuire Unit 1, Cross Over Leg 1A Nozzle 1-6, UT 3/26/19

Examination Results

VT-17-100 RPV Closure Head Outer Surface U-1, 1RPV-Head, Visual 10/2/17

Examination for Boric Acid Detection

VT-18-065 RPV Closure Head, 2RPV-Head, Visual Examination for 9/30/18

Boric Acid Detection

VT-19-059 1 B COLD LEG-ELBOW, Reactor Vessel Cold Leg Loop B, 3/26/19

Leakage Examination

VT-19-060 Visual Inspection (VT-1),1 B COLD LEG-ELBOW, Reactor 3/26/19

Vessel Cold Leg Loop B

Procedures AD-EG-ALL-1132 Preparation and Control of Design Change Engineering Rev. 15

Changes, Attachment 3

AD-EG-ALL-1214 Condition Monitoring of Structures Rev. 0

AD-EG-ALL-1610 Flow Accelerated Corrosion Implementation Rev. 5

AD-EG-ALL-1612 Environmental Qualification (EQ) Program Rev. 5

AD-EG-ALL-1615 Cable Aging Management Program - Implementation Rev. 2

AD-EG-ALL-1615 Cable Aging Management Program - Implementation Rev. 2

AD-EG-ALL-1630 ALLOY 600 PROGRAM IMPLEMENTATION Rev. 2

AD-EG-ALL-1632 Integrated Fatigue Management Rev. 2

AD-EG-ALL-1650 License Renewal Aging Management Rev. 3

Inspection Type Designation Description or Title Revision or

Procedure Date

AD-EG-ALL-1910 Reactor Internals Program Implementation Rev.2

AD-EG-MNS-1214 Condition Monitoring of Structures Rev. 004

AD-EG-MNS-1214 Condition Monitoring Structures Rev. 003

AD-EG-PWR-1813 Steam Generator Degradation Assessments Rev. 3

AD-EG-PWR-1814 Steam Generator Condition Monitoring Rev. 2

AD-EG-PWR-1815 Steam Generator Operational Assessments Rev. 2

AD-NF-ALL-0807 Reload Design Process ,Materials Integrity Review Questions Rev. 6

AD-OP-ALL-0109 Operator Rounds Rev. 2

CSD-AISI-ALL- Augmented Inservice Inspection Program Workplace Rev. 0

1704.01 Processes and Instructions (Alloy 600)

CSD-EG-MNS- MNS License Renewal Mechanical Fire Protection Rev. 001

1650-02 Component Tests and Inspections Basis Document

CSD-EG-MNS- MNS License Renewal Non-EQ Insulated Cables and Rev. 000

1650-04 Connections Basis Document

CSD-EG-MNS- MNS License Renewal Service Water Piping Corrosion Rev. 000

1650-05 Program Basis Document

CSD-EG-MNS- MNS License Renewal Rev. 000

1650-06

CSD-EG-MNS- MNS License Renewal Inspection Program for Civil Rev. 000

1650-06 Engineering Structures and Components Basis Document

CSD-EG-MNS- MNS License Renewal Containment Leak Rate Testing Rev. 000

1650-07 Program Basis Document

CSD-EG-MNS- Chemistry Control Program Basis Document Rev. 0

1650-07

CSD-EG-MNS- MNS License Renewal Heat Exchanger Activities Basis Rev. 0

1650-13 Document

CSD-EG-MNS- MNS License Renewal Inservice Inspection Plan Aging Rev. 000

1650-15 Management Program

CSD-EG-MNS- MNS License Renewal Piping and Tank Internal Coatings Rev. 000

1650-16 Inspection Program Basis Document

CSD-EG-MNS- MNS License Renewal Alloy 600 Program Basis Document Rev. 0

1650-18

CSD-EG-MNS- MNS License Renewal Reactor Vessel Internals Inspection Rev. 000

1650-19 Program Aging Management Program

Inspection Type Designation Description or Title Revision or

Procedure Date

CSD-EG-MNS- MNS License Renewal Piping and Tank Internal Coatings Rev. 000

1650-20 Inspection Program Basis Document

CSD-EG-MNS- MNS License Renewal Thermal Fatigue Management Rev. 000

1650-25 Program Basis Document

CSD-EG-MNS- MNS License Renewal Bottom Mounted Instrumentation Rev. 000

1650-30 Thimble Tube Inspection Program Basis Document

CSD-FAC-MNS- U1 & U2 McGuire Flow Accelerated Corrosion Program Rev. 000

1610.001 System Susceptibility Analysis

IP/0/A/3061/007 125 Volt Vital Battery Terminal Post Inspection And Rev. 29

Maintenance

IP/0/B/3061/007 A SSF Auxiliary 125/250 VDC Battery And Terminal Post Rev. 19

Inspection

IP/0/B/3061/020 Standby Shutdown Facility Diesel Generator NiCd Battery Rev. 36

And Charger Maintenance

MCC-1274.00-00- MNS Initial Review for License Renewal Newly Identified Rev. 000

0009 SSCs

MCM 3.2 Secondary Systems Analytical Requirements and Corrective Rev. 057

Actions

MCM/0/A/8600/049 Secondary System Data Review and Interpretation Rev. 13

MISI-1462.10- Augmented Inservice Inspection Plan and Schedule Rev. 4

0040AUGISI-

U1&U2

MNS-LR-001 Battery Rack Inspections Rev. 1

MNS-LR-009 MNS License Renewal Divider Barrier Seals Inspection and Rev. 1

Testing Program Implementation Plan

MNS-LR-012 Flood Barrier Inspection Aging Management Program Rev. 2

Implementation Plan

MNS-LR-014 MNS License Renewal Fluid Leak Management Program Rev. 1

MNS-LR-028 Reactor Coolant System Operational Leakage Monitoring Rev. 0

Program

MNS-LR-032 Alloy 600 Implementation Plan Rev. 0

MNS-LR-063 Technical Specification SR 3.6.16.3 Visual Inspection Rev. 2

Implementation Plan

MP/0/A/7700/080 Inspection, Assessment and Cleanup of Boric Acid on Plant Rev. 23

Inspection Type Designation Description or Title Revision or

Procedure Date

Materials

MP/0/A/7700/093 Trenching and Excavation Rev. 014

MP/0/A/7700/118 Inspection And Adjustment Of Flood Doors Rev. 3

MP/0/A/7700/134 Internal Flood Barrier Periodic Inspection Rev. 3

NE-18-12-01 Non-EQ Insulated Cables and Connections Inspection Rev. 0

Program

NE-19-04-1 Cable and Connection Inspection Report Rev. 0

PD-EG-ALL-1615 Cable Aging Management Program Rev. 2

PD-EG-ALL-1632 Integrated Fatigue Management Program Rev. 1

PD-EG-PWR-1611 Boric Acid Corrosion Control Program Rev. 1

PD-EG-PWR-1801 Steam Generator Management Program Rev. 7

PT/0/A/4200/005 Divider Barrier Seal Inspection Rev. 14

PT/0/A/4400/004 Standby Nuclear Service Water Pond Inspection Rev. 10

PT/0/B/4700/063 Periodic Inspection of Service Water Piping for Corrosion Rev. 006

Induced Thinning

PT/0/B/4700/063, , Periodic Inspection of Service Water Piping for Corrosion Rev. 006

Induced Thinning

PT/1/A/4200/044 Containment Structural Integrity Inspection Rev. 010

PT/2/A/4200/044 Containment Structural Integrity Rev. 011

SM/0/A/8510/002 Ice Basket Inspection Rev. 7

Self-Assessments 01985578 Environmental Qualification (EQ) Program Focused Self- 08/26/2016

Assessment

Work Orders 00401194, Work Orders (various)

00401195,

00438704,

00445443,

00478431,

00478696,

00525857-04,

00528002,

00538726,

00588872-01,

00590786-07,

01872743,

Inspection Type Designation Description or Title Revision or

Procedure Date

01972570,

01972571,

2043611,

2045560,

2087222,

2172051,

2199100-01,

206472,

216723,

20223220,

20257785,

20048329,

20059913-01,

20059914-01,

20084836-05,

20106367,

20124224,

20161401-09,

20161401-17,

20174523-48,

20174523-49,

20177205,

20184644,

20194594,

20194613,

207626,

215358-01,

223753-01,

229713,

230875,

257205,

257211,

257597-01,

257597-07,

Inspection Type Designation Description or Title Revision or

Procedure Date

257905,

275864,

275868,

20308206,

20308768,

20316937,

20317441-01,

20327482,

20327486,

20327487,

20361495-01,

20378130

00405427-01, Model Work Orders (various)

00405428-01,

00438704-01,

00438705-01,

2087222-01,

220821-01,

236443,

236731,

393627-01,

394264-01,

401961-01

2

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