IR 05000369/2020012
| ML20213B223 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| 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) | |
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:
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
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===
- (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
- 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
- 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.
- Commitment Item 4: Enhancements to the Fire Protection Program. Status:
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 3.4.13/.15: Reactor Coolant System Operational Leakage Monitoring Program. Status: Complete.
Status: Complete.
- ITS SR 3.6.16.3: Technical Specifications SR 3.6.16.3 Visual Inspection.
Status: Complete.
- ITS SR 3.7.8.3: Standby Nuclear Service Water Pond Dam Inspection. Status:
Complete.
- UFSAR 18.2.1: Alloy 600 Aging Management Review. 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.
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 18.2.11: Boric Acid Corrosion Control. 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 18.2.15: Inaccessible Non-EQ Medium-Voltage Cables Aging Management Program. 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 18.2.25: Service Water Piping Corrosion Program. Status. Complete.
- UFSAR 18.2.27: Treated Water Systems Stainless Steel Inspection. Status:
Complete.
- UFSAR 18.2.28: Underwater Inspection of Nuclear Service Water Structures.
Status: Complete.
- UFSAR 18.2.30: Waste Gas System Inspection. Status: Complete.
- UFSAR 18.2.34: Fuse Holder Program. Status: Complete.
- UFSAR 18.3.2: Steam Generator Surveillance Program. Status: Complete.
- UFSAR 3.9.2/5.2.1: Metal Fatigue (Thermal Fatigue, Environmentally-Assisted Fatigue). Status: Complete.
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:
- Nuclear Service Water Strainer Elements
- 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
Procedure
Type
Designation
Description or Title
Revision or
Date
71003
Calculations
0801613.303
Structural Integrity File: Degradation Mechanism Evaluation
for McGuire Unit 2
6/25/13
DPC-1274.00-00-
0005
MNS and CNS Pressurizer Spray Head License Renewal
Scoping Impacts Arising from NFPA-805
Rev. 0
MCC-1201.01-00-
0075
Thermal Sleeve Metrology analysis results from M1R2
Rev. 01
MCC-1252.00-00-
0047
Risk Informed lnservice Inspection Program, Degradation
Mechanism Evaluation
for McGuire Unit 1
Rev. 0
MCC-1553.03-00-
0014
Incore Instrumentation Thimble Tube Wear Review
Rev. 7
MCM 1201.01-
0570.001
STRESS REPORT FOR MCGUIRE RV, UPFLOW
CONVERSION, (CORE BRL & FORMERS), 60 Year Life
5/3/18
MCM 1201.01-
1352.001
FLAW TOLERANCE EVALUATION FOR LOOP TWO COLD
LEG ELBOW AT MCGUIRE NUCLEAR STATION, UNIT 1
8/21/17
Corrective Action
Documents
01456914,
01593605,
01603829,
01606689-28,
01615456-12,
01622607,
01624455,
01636063,
01637337,
01638153,
01650601,
01654080,
01661965,
01667394,
01668900,
01673097,
01685394,
Condition Reports
(various)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Documents
Resulting from
Inspection
2334437,
2335756,
2335760,
2335765
Condition Reports
(various)
Drawings
MCFD-1574-02.00
Flow Diagram of Nuclear Service Water System (RN)
Rev. 35
Engineering
Changes
MNS Selective Leaching Inspection Program Implementation
Rev. 0
MNS U2 RVCH Thermal Sleeve Replacement
Rev. 002
License Renewal 10 CFR 54.37(b) Review for MNS Fuel
Cycle 26
Rev. 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
License Renewal Service Water Piping Corrosion Program
Review for MNS Fuel Cycle 26
Rev. 0
MNS Selective Leaching Inspection Evaluation and
Disposition
Rev. 0
MNS Galvanic Susceptibility Inspection Evaluation and
Disposition
Rev. 0
NTM02015273
Evaluate Update to MNS Chemistry Control AMP Basis
Document for Tie to Steam Generator Program AMP Basis
Document
07/31/2020
NTM02290941
Update MISI-1462.10-0040AUGISI-U1&U2 for License
Renewal
09/10/2019
Engineering
Evaluations
200826-01
MRP 2018-010, Notification of Recent PWR CRDM Thermal
Sleeve Flange Wear and Control Rod Motion Stoppage,
Operating Experience and Recommended Plant Actions
4/4/18
ANP-3658
Framatome Evaluation of the McGuire Units 1 and 2 Upflow
Modification for 60 Years
Rev. 0
LCAMP-RVI
Life Cycle Aging Management Plan: PWR Reactor Vessel
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
8/8/17
'A'
Reactor Internals Acceptance Criteria Methodology
Rev. 2
McGuire Unit 1 and Unit 2 Measurement Uncertainty
Recapture (MUR) Power Uprate: Reactor Vessel Integrity and
Neutron Fluence Evaluations.
Rev 0
Aging Management Program and Inspection Plan for the
McGuire Nuclear Station
Units 1 and 2 Reactor Vessel Internals
Rev. 0
McGuire Unit 2 - Upper Internals 17x17A Guide Tube - Guide
Card Wear Evaluation
Dec. 2018
McGuire Unit 1 - Upper Internals 17x17 Standard Guide Tube
- Guide Card Wear
July 2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Letter from Steven D. Capps to U.S. Nuclear Regulatory
Commission, Restatement of License Condition Proposed in
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)"
March 7,
2013
MNS-LR-029
McGuire Nuclear Station Units 1 and 2, Reactor Vessel
Integrity Historical Implementation Plan
Rev. 1
Letter from S.D. Capps to U.S. Nuclear Regulatory
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"
5/14/14
1462.00
Memo to File: Flow Accelerated Corrosion Program 1EOC24
Post Outage Report
June 30,
2016
DPS-1274.00-00-
0005
Programmatic requirements for License Renewal
Rev. 0
DPS-1274.00-00-
0006
Electrical Components Integrated Plant Assessment and
Evaluation of Time-Limited Aging Analyses for License
Renewal
Rev. 3
DPS-1274.000-00-
0005
License Renewal Aging Management Programs and Activities
Rev. 2
FHG-SLA-NA-0015 Service Level Agreement (SLA) Between Fossil Hydro
Operations Hydro Fleet and McGuire Nuclear Station for DAM
Safety Related Services
11/17/17
LRI-1274.00-0001
License Renewal Cable and Connections Inspection Pre-PEO
Walkdown Report
Rev. 000
MC-1462.00
2015 Inspection Report for Civil Engineering Structures and
Components per EDM-410
2/17/15
MC-ISIC3-1042-
0001
Third Interval Containment Inservice Inspection Plan
Rev. 7
NRC Letter to Mr. Douglas
Issue 98-0030, Thermal Aging Embrittlement of Cast
5/19/2000
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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 -
Condenser Circulating Water System Internal Coating
Inspection Aging Management Program RC System Internal
Surfaces
Rev. 2
MNS-LR-006
Containment Inservice Inspection Plan - IWE Aging
Management Program Implementation Plan
Rev. 1
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
Implementation Plan
Rev. 1
MNS-LR-017
Inservice Inspection Program Implementation Plan
Rev. 2
MNS-LR-026
MNS License Renewal - Underwater Inspection of Nuclear
Service Water Structures Aging Management Program
Implementation Plan
Rev. 2
MNS-LR-031
MNS License Renewal Refueling Water Storage Tank Internal
Coating Inspection Program Implementation Plan
Rev. 2
MNS-LR-033
MNS License Renewal Borated Water Systems Stainless
Steel Inspection Program Aging Management Program
Implementation Plan
Rev. 0
MNS-LR-041
Galvanic Susceptibility Inspection Implementation Plan
Rev. 3
MNS-LR-043
License Renewal Heat Exchanger Preventative Maintenance
Activities - Pump Oil Coolers Implementation Plan
Rev. 2
MNS-LR-044
Inaccessible Non-EQ Medium-Voltage Cables Aging
Management Program Implementation Plan
Rev. 2
MNS-LR-046
MNS Inspection Program for Civil Engineering Structures and
Components Aging Management Program Implementation
Plan
Rev. 1
MNS-LR-046
MNS License Renewal Inspection Program for Civil
Engineering Structures and Components Aging Management
Program Implementation Plan
Rev. 1
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
MNS-LR-046
MNS License Renewal Inspection Program for Civil
Engineering Structures and Components Aging Management
Program Implementation Plan
Rev. 1
MNS-LR-047
MNS License Renewal Liquid Waste System Inspection Aging
Management Program Implementation Plan
Rev. 1
MNS-LR-048
Thermal Fatigue Management Program Incorporating
Environmentally-Assisted Fatigue
Rev. 2
MNS-LR-049
MNS Non-EQ Insulated Cables and Connections Aging
Management Program Implementation Plan
Rev. 2
MNS-LR-052
MNS License Renewal Selective Leaching Inspection Aging
Management Program
Rev. 2
MNS-LR-053
MNS License Renewal Sump Pump Systems Inspection
Implementation Plan
Rev. 2
MNS-LR-054
MNS License Renewal Treated Water Systems Stainless
Steel Inspection Program Aging Management Program
Implementation Plan
Rev. 1
MNS-LR-055
MNS License Renewal Ventilation Area Pressure Boundary
Sealants Inspection Aging Management Program
Implementation Plan
Rev. 1
MNS-LR-056
MNS License Renewal Gas System Inspection Aging
Management Program Implementation Plan
Rev. 1
MNS-LR-057
MNS License Renewal Additional Chemistry Control Program
(AFW/FW Internal Inspection) Aging Management
Implementation Plan
Rev. 1
MNS-LR-058
MNS Fuse Holder Inspection Program Implementation
Rev. 1
MNS-LR-060
MNS License Renewal Steam Generator Surveillance
Program Aging Management Program Implementation Plan
Rev. 2
MNS-LR-064
MNS License Renewal Auxiliary Feedwater Storage Tank
Internal Coating Inspection Aging Management Program
Implementation Plan
Rev. 1
MNS-LR-065
MNS License Renewal Boral Monitoring Aging Management
Program Implementation Plan
Rev. 2
MNS-LR-066
MNS License Renewal Nuclear Service Water System
Strainer Elements Inspection Aging Management Program
Rev. 1
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Implementation Plan
MNS-LR-073
Fire Protection Program - Turbine Building Strainer
Inspections Implementation Plan
Rev. 1
MNS-LR-074
MNS License Renewal Reactor Makeup Water Storage Tank
Internal Coating Inspection Aging Management
Implementation Plan
Rev. 0
MP/0/A/7700/096
Quarterly/ Annual Inspection and Servicing of Overhead and
Gantry Cranes
Rev. 20
MP/0/B/7650/007
Annual Inspection of Electric, Air Operated and Hand
Operated Hoists
Rev. 20
PD-EG-ALL-1615
Cable Management Program
Rev. 2
PMCH 02262585
Change PM frequency to 10A from 6Y -
1RF502 cable
Rev. 0
PMCH 02262588
Change PM frequency to 10A from 6Y -
1RF804 cable
Rev. 0
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
Letter from Thomas
- D. Ray, P.E. to US Nuclear Regulatory
Commission, License Renewal Surge Line and Safety
Injection Nozzle Inspection"
May 17,
20
NDE Reports
180-9296414-000
McGuire, Unit 1 M1R26 Reactor Vessel Closure Head
(RVCH) Penetration Ultrasonic Examination
5/24/19
180-9308218-000
McGuire, Unit 2 2R26 Reactor Vessel Closure Head (RVCH)
Penetration Ultrasonic Examination
5/13/20
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
Procedure
Type
Designation
Description or Title
Revision or
Date
5999
Metallurgy File: MNS 1 Piping at Valve 1RV-362 Galvanic
Corrosion Assessment
October 2,
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
Examination Results
3/26/19
VT-17-100
RPV Closure Head Outer Surface U-1, 1RPV-Head, Visual
Examination for Boric Acid Detection
10/2/17
VT-18-065
RPV Closure Head, 2RPV-Head, Visual Examination for
Boric Acid Detection
9/30/18
VT-19-059
B COLD LEG-ELBOW, Reactor Vessel Cold Leg Loop B,
Leakage Examination
3/26/19
VT-19-060
Visual Inspection (VT-1),1 B COLD LEG-ELBOW, Reactor
Vessel Cold Leg Loop B
3/26/19
Procedures
AD-EG-ALL-1132
Preparation and Control of Design Change Engineering
Changes, Attachment 3
Rev. 15
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
Procedure
Type
Designation
Description or Title
Revision or
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-
1704.01
Augmented Inservice Inspection Program Workplace
Processes and Instructions (Alloy 600)
Rev. 0
CSD-EG-MNS-
1650-02
MNS License Renewal Mechanical Fire Protection
Component Tests and Inspections Basis Document
Rev. 001
CSD-EG-MNS-
1650-04
MNS License Renewal Non-EQ Insulated Cables and
Connections Basis Document
Rev. 000
CSD-EG-MNS-
1650-05
MNS License Renewal Service Water Piping Corrosion
Program Basis Document
Rev. 000
CSD-EG-MNS-
1650-06
Rev. 000
CSD-EG-MNS-
1650-06
MNS License Renewal Inspection Program for Civil
Engineering Structures and Components Basis Document
Rev. 000
CSD-EG-MNS-
1650-07
MNS License Renewal Containment Leak Rate Testing
Program Basis Document
Rev. 000
CSD-EG-MNS-
1650-07
Chemistry Control Program Basis Document
Rev. 0
CSD-EG-MNS-
1650-13
MNS License Renewal Heat Exchanger Activities Basis
Document
Rev. 0
CSD-EG-MNS-
1650-15
MNS License Renewal Inservice Inspection Plan Aging
Management Program
Rev. 000
CSD-EG-MNS-
1650-16
MNS License Renewal Piping and Tank Internal Coatings
Inspection Program Basis Document
Rev. 000
CSD-EG-MNS-
1650-18
MNS License Renewal Alloy 600 Program Basis Document
Rev. 0
CSD-EG-MNS-
1650-19
MNS License Renewal Reactor Vessel Internals Inspection
Program Aging Management Program
Rev. 000
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CSD-EG-MNS-
1650-20
MNS License Renewal Piping and Tank Internal Coatings
Inspection Program Basis Document
Rev. 000
CSD-EG-MNS-
1650-25
MNS License Renewal Thermal Fatigue Management
Program Basis Document
Rev. 000
CSD-EG-MNS-
1650-30
MNS License Renewal Bottom Mounted Instrumentation
Thimble Tube Inspection Program Basis Document
Rev. 000
CSD-FAC-MNS-
1610.001
U1 & U2 McGuire Flow Accelerated Corrosion Program
System Susceptibility Analysis
Rev. 000
IP/0/A/3061/007
25 Volt Vital Battery Terminal Post Inspection And
Maintenance
Rev. 29
IP/0/B/3061/007 A
SSF Auxiliary 125/250 VDC Battery And Terminal Post
Inspection
Rev. 19
IP/0/B/3061/020
Standby Shutdown Facility Diesel Generator NiCd Battery
And Charger Maintenance
Rev. 36
MCC-1274.00-00-
0009
MNS Initial Review for License Renewal Newly Identified
Rev. 000
MCM 3.2
Secondary Systems Analytical Requirements and Corrective
Actions
Rev. 057
MCM/0/A/8600/049 Secondary System Data Review and Interpretation
Rev. 13
MISI-1462.10-
0040AUGISI-
U1&U2
Augmented Inservice Inspection Plan and Schedule
Rev. 4
MNS-LR-001
Battery Rack Inspections
Rev. 1
MNS-LR-009
MNS License Renewal Divider Barrier Seals Inspection and
Testing Program Implementation Plan
Rev. 1
MNS-LR-012
Flood Barrier Inspection Aging Management Program
Implementation Plan
Rev. 2
MNS-LR-014
MNS License Renewal Fluid Leak Management Program
Rev. 1
MNS-LR-028
Reactor Coolant System Operational Leakage Monitoring
Program
Rev. 0
MNS-LR-032
Alloy 600 Implementation Plan
Rev. 0
MNS-LR-063
Technical Specification SR 3.6.16.3 Visual Inspection
Implementation Plan
Rev. 2
MP/0/A/7700/080
Inspection, Assessment and Cleanup of Boric Acid on Plant
Rev. 23
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Program
Rev. 0
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
Induced Thinning
Rev. 006
PT/0/B/4700/063,, Periodic Inspection of Service Water Piping for Corrosion
Induced Thinning
Rev. 006
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-
Assessment
08/26/2016
Work Orders
00401194,
00401195,
00438704,
00445443,
00478431,
00478696,
00525857-04,
00528002,
00538726,
00588872-01,
00590786-07,
01872743,
Work Orders
(various)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Procedure
Type
Designation
Description or Title
Revision or
Date
257905,
275864,
275868,
20308206,
20308768,
20316937,
20317441-01,
20327482,
20327486,
20327487,
20361495-01,
20378130
00405427-01,
00405428-01,
00438704-01,
00438705-01,
2087222-01,
220821-01,
236443,
236731,
393627-01,
394264-01,
401961-01
Model Work Orders
(various)