Text

NRC Integrated Inspection Reports 05200025/2020004 and 05200026/2020004
	ML21041A051
Person / Time
Site:	Vogtle
Issue date:	02/10/2021
From:	Nicole Coovert; NRC/RGN-II
To:	Yox M; Southern Nuclear Operating Co
References
	IR 2020004
	Download: ML21041A051 (79)
	v • d • e

February 10, 2021 Mr. Michael Yox Regulatory Affairs Director Southern Nuclear Operating Company 7825 River Road, Bldg. 302, Vogtle 3&4 Waynesboro, GA 30830

SUBJECT:

VOGTLE ELECTRIC GENERATING PLANT, UNITS 3 AND 4 - NRC INTEGRATED INSPECTION REPORTS 05200025/2020004, 05200026/2020004

Dear Mr. Yox:

On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Vogtle Electric Generating Plant (VEGP), Units 3 and 4. The enclosed inspection report documents the inspection results, which the inspectors discussed on January 14, 2021, with Mr. Glen Chick, VEGP Units 3 and 4, Executive Vice President, and other licensee and contractor staff members.

The inspection examined a sample of construction activities conducted under your Combined License (COL) as it relates to safety and compliance with the Commissions rules and regulations and with the conditions of these documents. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

NRC inspectors documented two findings of very low safety significance (Green). Both of these findings involved violations of NRC requirements. The NRC is treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2.a of the Enforcement Policy.

If you contest the violations or significance of these NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC resident inspector at the VEGP Units 3 and 4.

If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC resident inspector at the VEGP Units 3 and 4.

M. Yox 2 This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Should you have any questions concerning this letter, please contact us.

Sincerely,

/RA/

Nicole Coovert, Branch Chief Construction Inspection Branch 1 Division of Construction Oversight Docket Nos. 05200025 and 05200026 License Nos. NPF-91, NPF-92

Enclosure:

NRC Inspection Reports (IR) 05200025/2020004 and 05200026/2020004 w/attachments: Supplemental Information

M. Yox 3 cc w/ encls:

Resident Manager Resident Inspector Oglethorpe Power Corporation Vogtle Plant Units 3 & 4 Alvin W. Vogtle Nuclear Plant 8805 River Road 7821 River Road Waynesboro, GA 30830 Waynesboro, GA 30830 Mr. Barty Simonton Office of the Attorney General Team Leader 40 Capitol Square, SW Environmental Radiation Program Atlanta, GA 30334 Air Protection Branch Environmental Protection Division Southern Nuclear Operating Company 4244 International Parkway, Suite 120 Document Control Coordinator Atlanta, GA 30354-3906 3535 Colonnade Parkway Birmingham, AL 35243 Brian H. Whitley Regulatory Affairs Director Anne F. Appleby Southern Nuclear Operating Company Olgethorpe Power Corporation 3535 Colonnade Parkway, BIN N-226-EC 2100 East Exchange Place Birmingham, AL 35243 Tucker, GA 30084 Mr. Michael Yox County Commissioner Site Regulatory Affairs Director Office of the County Commissioner Vogtle Units 3 & 4 Burke County Commission 7825 River. Road, Building 302 (ESB)

Waynesboro, GA 30830 Bin 6031 Waynesboro, GA 30830 Mr. Wayne Guilfoyle Commissioner District 8 Augusta-Richmond County Commission 4940 Windsor Spring Rd Hephzibah, GA 30815 Gwendolyn Jackson Burke County Library 130 Highway 24 South Waynesboro, GA 30830 Mr. Reece McAlister Executive Secretary Georgia Public Service Commission Atlanta, GA 30334

M. Yox 4 aagibson@southernco.com (Amanda Gibson) acchambe@southernco.com (Amy Chamberlian) awc@nei.org (Anne W. Cottingham) becky@georgiawand.org (Becky Rafter) bhwhitley@southernco.com (Brian Whitley)

Bill.Jacobs@gdsassociates.com (Bill Jacobs) corletmm@westinghouse.com (Michael M. Corletti) crpierce@southernco.com (C.R. Pierce) david.hinds@ge.com (David Hinds) david.lewis@pillsburylaw.com (David Lewis) dlfulton@southernco.com (Dale Fulton) ed.burns@earthlink.net (Ed Burns) edavis@pegasusgroup.us (Ed David)

G2NDRMDC@southernco.com (SNC Document Control)

George.Taylor@opc.com (George Taylor) harperzs@westinghouse.com (Zachary S. Harper) james1.beard@ge.com (James Beard)

JHaswell@southernco.com (Jeremiah Haswell) jim@ncwarn.org (Jim Warren)

Joseph_Hegner@dom.com (Joseph Hegner) karlg@att.net (Karl Gross) kmstacy@southernco.com (Kara Stacy) kroberts@southernco.com (Kelli Roberts)

KSutton@morganlewis.com (Kathryn M. Sutton) kwaugh@impact-net.org (Kenneth O. Waugh) markus.popa@hq.doe.gov (Markus Popa) mdmeier@southernco.com (Mike Meier) media@nei.org (Scott Peterson)

Melissa.Smith@Hq.Doe.Gov (Melissa Smith) mike.price@opc.com (M.W. Price)

MKWASHIN@southernco.com (MKWashington) mphumphr@southernco.com (Mark Humphrey)

MSF@nei.org (Marvin Fertel) nirsnet@nirs.org (Michael Mariotte)

Nuclaw@mindspring.com (Robert Temple)

Paul@beyondnuclear.org (Paul Gunter) pbessette@morganlewis.com (Paul Bessette) ppsena@southernco.com (Peter Sena,III) r.joshi15@comcast.net (Ravi Joshi) rwink@ameren.com (Roger Wink) sabinski@suddenlink.net (Steve A. Bennett) sara@cleanenergy.org (Sara Barczak)

M. Yox 5 Vogtle Mailing List sblanton@balch.com (Stanford Blanton)

Shiva.Granmayeh@hq.doe.gov (Shiva Granmayeh) sjackson@meagpower.org (Steven Jackson) sjones@psc.state.ga.us (Shemetha Jones) skauffman@mpr.com (Storm Kauffman) slieghty@southernco.com (Steve Leighty) sroetger@psc.state.ga.us (Steve Roetger) syagee@southernco.com (Stephanie Agee)

TomClements329@cs.com (Tom Clements)

Vanessa.quinn@dhs.gov (Vanessa Quinn) wayne.marquino@gmail.com (Wayne Marquino) weave1dw@westinghouse.com (Doug Weaver)

William.Birge@hq.doe.gov (William Birge)

X2edgran@southernco.com (Eddie R. Grant) x2gabeck@southernco.com (Gary Becker)

X2hagge@southern.com (Neil Haggerty)

X2wwill@southernco.com (Daniel Williamson)

M. Yox 6

SUBJECT:

VOGTLE ELECTRIC GENERATING PLANT, UNITS 3 AND 4 - NRC INTEGRATED INSPECTION REPORTS 05200025/2020004, 05200026/2020004 DATED: February 10, 2021 DISTRIBUTION:

Ho Nieh, NRR M. King, NRR V. Hall, NRR M. Webb, NRR T. Fredette, NRR G. Armstrong, NRR E. Duncan, NRR L. Dudes, RII J. Munday, RII M. Bailey, RII S. Rose, RII B. Davis, RII A. Blamey, RII N. Staples, RII M. Checkle, RII M. Keefe Forsyth, NRR A. Athar, RIV R. Taylor, RII A. Veil, NRR R2DCO PUBLIC ADAMS ACCESSION NUMBER: ML21041A051 OFFICE RII: DCO RII: DCO RII: DCO RII: DCO NAME G. Khouri B. Kemker J. Vasquez N. Coovert DATE 2/9/2021 2/9/2021 2/9/2021 2/10/2021

U.S. NUCLEAR REGULATORY COMMISSION Region II Docket Numbers: 5200025 5200026 License Numbers: NPF-91 NPF-92 Report Numbers: 05200025/2020004 05200026/2020004 Licensee: Southern Nuclear Operating Company, Inc.

Facility: Vogtle Unit 3 Combined License Vogtle Unit 4 Combined License Location: Waynesboro, GA Inspection Dates: October 1, 2020 through December 31, 2020 Inspectors: A. Artayet, Senior Construction Inspector, Division of Construction Oversight (DCO)

K. Carrington, Resident Inspector, DRP, Division of Reactor Projects G. Crespo, Senior Construction Inspector, DCO J. Eargle, Senior Resident Inspector - Testing, DCO B. Griman, Resident Inspector, DRP N. Karlovich, Resident Inspector, DCO B. Kemker, Senior Resident Inspector, DCO G. Khouri, Senior Project Manager, DCO J. Lizardi-Barreto, Construction Inspector, DCO R. Patel, Resident Inspector (Acting), DCO A. Ponko, Senior Construction Inspector, DCO J. Vasquez, Construction Inspector, DCO Approved by: Nicole Coovert, Branch Chief Construction Inspection Branch 1 Enclosure

SUMMARY

OF FINDINGS Inspection Report (IR) 05200025/2020004, 05200026/2020004; 10/01/2020 through 12/31/2020; Vogtle Unit 3 Combined License, Vogtle Unit 4 Combined License, Integrated Inspection Report.

This report covers a three-month period of inspection by regional and resident inspectors.

Two findings of very low safety significance (Green), each with an associated non-cited violation (NCV) of NRC requirements, were identified. The significance of most findings is indicated by their color (i.e., greater than Green, or Green, White, Yellow, Red) which is determined using Inspection Manual Chapter (IMC) 2519, Construction Significance Determination Process.

Cross-cutting aspects are determined using IMC 0613, Appendix F, Construction Cross-Cutting Areas and Aspects. All violations of NRC requirements are dispositioned in accordance with the NRCs Enforcement Policy. The NRCs program for overseeing the safe construction of commercial nuclear power reactors is described in IMC 2506, Construction Reactor Oversight Process General Guidance and Basis Document.

A. NRC-Identified and Self Revealed Findings (Green) The inspectors identified a construction finding of very low safety significance with an associated NCV of Title 10 of the Code of Federal Regulations Part 50 (10 CFR 50), Appendix B, Criterion III, "Design Control" for the licensee's failure to have design control measures for the 18-inch diameter carbon steel guard pipes for containment vessel penetrations P44 and P45. Specifically, the site previously performed a structural analysis that omitted the guard pipe portion of the penetrations and did not consider how the guard pipe exclusion would infringe upon the design margin for ensuring the requirement for American Society of Mechanical Engineers (ASME) Code Section III, Level C service limits were not exceeded, in accordance with the current licensing basis. The Licensee entered this issue into its corrective action program (CAP) as condition report (CR) 50053621 and updated its structural model calculations as part of the corrective action.

The performance deficiency was of more than minor safety significance, and thus a finding, because it represented an adverse condition that rendered the quality of a structure, system, and component (SSC), unacceptable or indeterminate, and required substantive corrective action. This finding was not associated with an inspection, test, analyses, and acceptance criteria (ITAAC); it was not associated with a security program; it was not associated with an IMC 2504 operational/construction program; and it was not associated with a repetitive, NRC-identified omission of a program critical attribute. This finding was of very low safety significance because the licensee was able to demonstrate the design function of the applicable structure or system (containment vessel) would not be impaired by the deficiency by successfully reperforming a structural model calculation. The inspectors determined the finding was indicative of present licensee performance and was associated with the cross-cutting aspect Documentation, in the area of Human Performance, in accordance with IMC 0613, Appendix F, Construction Cross-Cutting Areas and Aspects. Specifically, the licensee did not ensure its calculations were reflective of the ASME Level C service limit requirements for the P44 and P45 penetration guard pipes. [H.7] (Section 1A08) 2

(Green) The inspectors identified an ITAAC finding of very low safety significance with an associated NCV of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings. The licensee failed to construct and perform quality inspections on Unit 3 and Unit 4 Class 1E DC and uninterruptible power supply system (IDS) battery racks for the 250 Vdc 24-hour, 72-hour, and spare batteries in accordance with ITAAC 2.6.03.02.i and the approved design requirements for Vogtle Units 3 and 4. The licensee entered this finding into its CAP as CR 50066999, conducted engineering analysis of the nonconforming conditions, and performed rework on the battery racks to correct the nonconforming conditions.

This performance deficiency was of more than minor safety significance, and thus a finding, because it was material to the acceptance criteria of an ITAAC and invalidated the Inspection, Test, or Analyses described in the ITAAC 2.6.03.02.i. This finding was not associated with a security program; it was not associated with an IMC 2504 operational or construction program; and it was not associated with a repetitive, NRC-identified omission of a program critical attribute. This finding was a licensee performance deficiency of very low safety significance because it was associated with the IDS and there was reasonable assurance the design function of the system would not have been impaired by the deficiency based on engineering analysis of the nonconforming conditions identified. The inspectors determined this finding was indicative of present licensee performance and affected the cross-cutting area of human performance and the cross-cutting aspect of avoiding complacency. The proximate cause of the performance deficiency was primarily attributed to a failure to perform a thorough review of the work instructions and to plan the activity every time without relying on past successes and assumed conditions. [H.12] (Section 1A15)

B. Licensee-Identified Violations None 3

REPORT DETAILS Summary of Plant Construction Status Unit 3: The licensee completed shield building construction and was in the process of finalizing the as-built design. In the containment building, the licensee satisfactorily performed the American Society of Mechanical Engineers (ASME) required hydrostatic test on the reactor and reactor coolant systems. In the containment and auxiliary buildings, the licensee continued with installation of safety related instrumentation, electrical conduits and cables (safety and non-safety related), necessary to support hot functional testing. In the turbine building, the licensee established main condenser vacuum and placed the main turbine on the turning gear for the first time. The licensee received the first shipment of nuclear fuel at the site.

Unit 4: The licensee completed the shield building tension ring and set the conical roof. In the containment building, the licensee continued with installation of reactor coolant system (RCS) and passive core cooling system (PXS) small bore piping and was in the process of routing electrical raceways, cables, and terminations. In the auxiliary building, the licensee continued with construction of the building up to elevation 180-feet and continued with installation of electrical cabinets, raceways, conduits and cables (safety and non-safety related).

1. CONSTRUCTION REACTOR SAFETY Cornerstones: Design/Engineering, Procurement/Fabrication, Construction/Installation, Inspection/Testing IMC 2503, Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) - Related Work Inspections 1A01 (Unit 3) ITAAC Number 2.1.02.01 (12) / Family 14A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.1.02.01 (12). The inspectors used the following NRC inspection procedures (IPs)/sections to perform this inspection:

65001.14-02.01 - General Installation

65001.A.02.02 - Installation Records Review

65001.A.02.03 - Independent Assessment/Measurement Inspection The inspectors performed an inspection of the Unit 3 RCS functional arrangement to verify the as-built system piping and components conform to the system design description in Section 2.1.2 of Appendix C of the Vogtle Combined License (COL),

including Table 2.1.2-5 and Figure 2.1.2-1.

4

The inspectors performed independent field walkdowns and reviewed quality records including the principal closure document (PCD), piping and instrumentation diagrams, and functional arrangement sketches to verify the RCS piping and components (including steam generators, pressurizer, reactor coolant pumps, fourth-stage automatic depressurization system (ADS) valves, ASME Code relief and ADS stage 1-3 lines, valves, and instruments) were physically arranged consistent with Figure 2.1.2-1 and located as identified in Table 2.1.2-5 of Appendix C of the Vogtle Unit 3 COL, such that the piping and components will support system functions described in the design description of Section 2.1.2 of Appendix C of the COL and Section 5.1.2 of the Vogtle 3 and 4 Updated Final Safety Analysis Report (UFSAR). System installation attributes inspected included proper location, placement (such as relative elevation), quantity, physical orientation, flow direction, and alignment.

b. Findings No findings were identified.

1A02 (Unit 3) ITAAC Number 2.1.02.02a (13) / Family 06F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.1.02.02a (13). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.03-02.06 - Nondestructive Examination

65001.03-02.07 - Review of Records

65001.B-02.05 - Inspection

65001.B-02.06 - Records The inspectors reviewed nine work packages that were used to remove visible surface defects on the following piping systems prior to hydrostatic pressure testing to verify repairs were performed in accordance with the applicable requirements of the ASME Code Section III for Class 1, 2, and 3:

Chemical and Volume Control System;

PXS; and

RCS.

The inspectors verified if unacceptable dents, scratches, arc strikes, and tapered thickness transitions and indications identified during preservice inspections were eliminated by mechanical means (e.g. grinding, buffing) or repaired by welding and blended uniformly into the surrounding surface with subsequent final nondestructive examinations (NDE) in accordance with the applicable requirements of the ASME Code Sections III and V.

5

The inspectors reviewed weld data sheets (WDSs) to verify quality control (QC) inspection hold points were signed-off and dated for acceptance of final visual examination in accordance with NCA-4134.10. The inspectors also reviewed entries on the WDSs to determine whether the traceability of stainless steel weld filler metals and welders were maintained in accordance with the applicable code provisions of Articles NB/NC/ND-4122 and NB/NC/ND-4300.

The inspectors reviewed ultrasonic thickness survey reports to verify manual ultrasonic metal thickness measurements performed by Level II technicians with the use of calibration blocks were deemed acceptable and the results of the final thickness did not encroach on the minimum design thickness of the components in accordance with the applicable requirements of the ASME Code Section III, Articles NB/NC/ND-3000.

The inspector reviewed liquid penetrant examination reports to verify the removal of surface defects were deemed acceptable by SNT-TC-1A Level II examiners and were performed in accordance with the applicable requirements of the ASME Code Section III (Articles NB/NC/ND-5000) and Section V (Article 6).

The inspectors reviewed a computed radiography examination report to determine whether acceptance by the SNT-TC-1A Level III examiner was performed with no rejectable indication using the proper type of source, image quality indicator designation, exposure time, and geometric unsharpness in accordance with the applicable requirements of the ASME Code Section III (Article ND-5000) and Section V (Article 2).

b. Findings No findings were identified.

1A03 (Unit 3) ITAAC Number 2.1.02.02a (13) / Family 06F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.1.02.02a (13). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.07-02.01 - General Installation The inspectors reviewed documents associated with work package SV3-RCS-P0W-1057531 for installation of the 14-inch diameter fourth-stage ADS squib valve SV3-RCS-PL-V004D to determine if the bolted joint connections to the valve body and flange at the inlet side of the valve were assembled in accordance with the requirements of the ASME Code Section III, Subsection NB, for Class 1 components.

6

The inspectors reviewed Stone and Webster (S&W) valve installation data sheet to verify QC inspector hold points for identification/marking of the PV70 valve with serial number 0920-164451-3-4, material traceability (including studs/bolts/nuts), internal cleanliness, and torque wrench calibration were deemed satisfactory and signed-off in accordance with the requirements of the ASME Code Section III, Article NCA-3000 with final signature by the authorized nuclear inspector (ANI).

The inspectors reviewed the S&W bolted joint data sheet to verify QC inspector hold points for inlet side alignment/fit-up with gasket between the valve body and flange verified fasteners were sequentially torqued in gradual steps to the initial maximum torque value using 12 threaded stud and nut materials in accordance with the requirements of the ASME Code Section III, NB-2128, and Section II, Part D, Subpart 1, Table 4 with final signature by the ANI.

The inspectors reviewed the S&W special operations data sheet to verify hold points for hydraulic tensioning of 12 studs into the inlet side of the valve body and tightening of the nuts to the flange were deemed satisfactory and signed-off by QC inspectors and the ANI in accordance with the requirements of the ASME Code Section III, NB-4700 for mechanical joints and Article NCA-5000 for authorized inspection.

b. Findings No findings were identified.

1A04 (Unit 3) ITAAC Number 2.1.02.02a (13) / Family 06F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.1.02.02a (13). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.C - Inspection of the ITAAC-Related Construction Test Program

65001.C-02.01 - Program and Procedure Reviews

65001.C-02.02 - Construction Test Observation

65001.C-02.03 - Construction Test Record Review

65001.C-02.04 - General Quality Assurance Review

65001.C-A2 - Appendix 2 - Construction Test Inspection for Piping Systems and Components

65001.C-A2.03 - Piping The inspectors performed a direct inspection of ASME Code Section III hydrostatic testing activities associated with the Unit 3 RCS and connecting systems pressure boundary components and piping identified as ASME Code Section III in Tables 2.1.2-1 and 2.1.2-2 of Appendix C to the Vogtle Unit 3 COL to verify conformance with the requirements of the ASME Code Section III.

7

The inspectors reviewed the work package for the piping and components associated with ASME Code Section III hydrostatic test procedure 3-RCS-ITPP-503, Reactor Coolant System Cold Hydrostatic Test - Preoperational Test Procedure. The inspectors reviewed the work package instructions and the licensee's procedure for construction pressure testing to determine whether the following test attributes were included:

the system boundary included all pressure vessels, piping, pumps, and valves that were part of the piping system to be tested;

the system was vented during the filling operation;

water quality was specified as required by the latest licensee approved specifications for the temperatures to be present during the test;

temperature requirements were stated to ensure components were maintained above the nil-ductility transition temperature during hydrostatic pressure testing;

minimum hydrostatic test pressure was as specified in the applicable design and/or fabrication specification; maximum hydrostatic test pressure was less than the limits in the applicable design and/or fabrication specification; and

hydrostatic test pressure was maintained for a minimum of 10 minutes before initiation of the examination for leakage; and

examination for leakage included all joints, connections, and regions of high stress, such as openings, attachments, and thickness transition sections at a pressure equal to the design pressure or three-fourths of the test pressure, whichever was greater.

The inspectors conducted walkdowns prior to the test to verify valve positions and system boundaries were set up in accordance with the system boundary maps within the work package. The inspectors also verified the fill points and vent points were set up in accordance with the work package.

The inspectors observed the ASME Code Section III hydrostatic test to determine if the testing was conducted in accordance with the requirements of ASME Section III, Subsection NB-6000, the work package instructions, and the licensee's procedure 3-RCS-ITPP-503 for construction pressure testing. Specifically, the inspectors observed the test to determine if:

the latest revision of the test procedure was available and used;

test prerequisites were met;

joints, including welded joints, were left uninsulated and exposed for examination during the tests;

valve lineup/system checklists were completed;

water quality and temperature were as stated in the procedures;

calibrated pressure gauges of the required range were installed where required;

calibrated relief valves of the required set point and capacity were installed where required;

testing was performed as required by the approved procedure;

crew actions were correct and timely during the performance of the test and coordination existed among crew members to conduct the test; 8

temporary modifications such as jumpers, strainers, spool pieces, or blank flanges were installed and tracked per established administrative controls; and

overall test acceptance criteria were satisfied.

The inspectors also reviewed the results from the 3-RCS-ITPP-503 procedure for ASME Code Section III hydrostatic test to determine if the results conformed to the requirements of ASME Code Section III, Subsection NB-6000. Specifically, the inspectors reviewed the test results to determine if they were identifiable and retrievable evidence of activities affecting quality and were reviewed and verified to be complete per the licensees procedures.

b. Findings No findings were identified.

1A05 (Unit 3) ITAAC Number 2.1.02.12a.i (53) / Family 07E

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.1.02.12a.i (53). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.07-02.03 - Post Installation Activities

65001.E-02.04-Documentation The inspectors reviewed the equipment qualification reconciliation reports (EQRRs) for ADS motor-operated valves (MOV) RCS-PL-V001B, RCS-PL-V003A, and RCS-PL-V013B to determine whether the licensee assessed work packages, design changes, and nonconformances to verify the as-built configuration, including anchorage, were seismically bounded by the analyzed conditions in accordance with data sheets SV3-PV01-Z0D-131 and SV3-PV01-132 and design specification SV3-PV01-Z0-001.

The inspectors reviewed the licensee's methodology and selection of applicable work orders, data sheets, and design drawings, to determine whether the inspections and analyses demonstrated the as-built installed ADS MOVs were bounded by tests or type tests. The inspectors reviewed the equipment qualification summary reports (EQSRs) and equipment qualification data packages (EQDPs) to determine whether installation restrictions were translated, via the design process, to the drawings and EQRRs. The inspectors performed a review of as-installed electrical connections to determine whether the electrical connections were installed as tested so the valves would function during a design basis accident.

The inspector performed a walkdown of the ADS valve area (room 11603) and verified the as-built configuration of two second-stage ADS A & B MOVs, RCS-PL-V002A and RCS-PL-V002B, matched the analyzed configuration.

9

The inspectors also interviewed licensing personnel to determine how inspection and analysis were performed for applicable nonconformances and engineering and design coordination reports (E&DCRs) issued during fabrication, handling, installation, and testing to verify all deviations were bounded by the seismically analyzed conditions.

b. Findings No findings were identified.

1A06 (Unit 3) ITAAC Number 2.1.03.03 (72) / Family 05F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.1.03.03 (72). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.C - Inspection of the ITAAC-Related Construction Test Program

65001.C-02.04 - General Quality Assurance Review

65001.C-A2 - Appendix 2 - Construction Test Inspection for Piping Systems and Components

65001.C-A2.05 - Reactor Pressure Vessel & Internals The inspectors performed a direct inspection of ASME Code Section III hydrostatic testing activities associated with the Unit 3 reactor system (RXS) pressure boundary components identified as ASME Code Section III in Table 2.1.3-1 of Appendix C to the Vogtle Unit 3 COL (e.g., reactor vessel, control rod drive mechanisms, and in-core instrument QuickLoc assemblies) to verify conformance with the requirements of the ASME Code Section III.

The inspectors reviewed the work package for the RXS components associated with ASME Code Section III hydrostatic test procedure 3-RCS-ITPP-503, Reactor Coolant System Cold Hydrostatic Test - Preoperational Test Procedure. The inspectors reviewed the work package instructions and the licensee's procedure for construction pressure testing to determine whether the following test attributes were included:

the system boundary included the reactor vessel and all system components to be tested;

the system was vented during the filling operation;

water quality was specified as required by the latest licensee approved specifications for the temperatures to be present during the test;

temperature requirements were stated to ensure components were maintained above the nil-ductility transition temperature during hydrostatic pressure testing;

minimum hydrostatic test pressure was as specified in the applicable design and/or fabrication specification;

maximum hydrostatic test pressure was less than the limits in the applicable design and/or fabrication specification; 10

hydrostatic test pressure was maintained for a minimum of 10 minutes before initiation of the examination for leakage; and

examination for leakage included all joints, connections, and regions of high stress, such as openings, attachments, and thickness transition sections at a pressure equal to the design pressure or three-fourths of the test pressure, whichever was greater.

The inspectors conducted walkdowns prior to the test to verify valve positions and system boundaries were set up in accordance with the system boundary maps within the work package. The inspectors also verified the fill points and vent points were set up in accordance with the work package.

The inspectors observed the ASME Code Section III hydrostatic test to determine if the testing was conducted in accordance with the requirements of ASME Code Section III, Subsection NB-6000, the work package instructions, and the licensee's procedure 3-RCS-ITPP-503 for construction pressure testing. Specifically, the inspectors observed the test to determine if:

the latest revision of the test procedure was available and used;

test prerequisites were met;

joints, including welded joints, were left uninsulated and exposed for examination during the test;

valve lineup/system checklists were completed;

water quality and temperature were as stated in the procedure;

calibrated pressure gauges of the required range were installed where required;

calibrated relief valves of the required set point and capacity were installed where required;

testing was performed as required by the approved procedure;

crew actions were correct and timely during the performance of the test and coordination existed among crew members to conduct the test;

temporary modifications such as jumpers, strainers, spool pieces, or blank flanges were installed and tracked per established administrative controls; and

overall test acceptance criteria were satisfied.

The inspectors also reviewed the results from the 3-RCS-ITPP-503 procedure for ASME Code Section III hydrostatic test to determine if the results conformed to the requirements of ASME Code Section III, Subsection NB-6000. Specifically, the inspectors reviewed the test results to determine if they were identifiable and retrievable evidence of activities affecting quality and were reviewed and verified to be complete per the licensees procedures.

b. Findings No findings were identified.

11

1A07 (Unit 3) ITAAC Number 2.1.03.13 (88) / Family 05F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.1.03.13 (88). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.05 - Inspection of ITAAC-Related Installation of Reactor Pressure Vessel and Internals

65001.05-02.01 - Purchase and Receipt of Components

65001.F- Inspection of the ITAAC-Related Design and Fabrication Requirements

65001.F-02.02-Fabrication Records Review The inspectors performed an inspection to verify a report exists and concludes the fuel assemblies and rod cluster control assemblies (RCCA) intended for the initial core load and listed in Table 2.1.3-1 of Appendix C to the Vogtle Unit 3 COL, had been designed and constructed in accordance with the principal design requirements.

The inspectors reviewed APP-SSAR-F5-001, AP1000 Safety Analysis Checklist, Revision 1, which is specific to the Vogtle 3 first core design and additional changes made to the AP1000 fuel assembly, RCCA, and gray rod control assembly designs.

The inspectors reviewed the safety analysis checklist to verify if the first core safety analysis performed by Westinghouse for Cycle 1 met the principal design requirements listed in the UFSAR Section 4.1.1, and more broadly the UFSAR Chapter 4 requirements.

The inspectors also reviewed the Unit 3 Cycle 1 Core Operating Limits Report (COLR), which is specific to the Vogtle 3 Cycle 1 core design and provides the applicable core operating limits of the safety analysis (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, PXS limits, nuclear limits such as shutdown margin, transient analysis limits, and accident analysis limits). The inspectors reviewed the COLR to verify if the core operating limit results were consistent with those in the Safety Analysis Checklist and the UFSAR Chapter 4 requirements.

The inspectors reviewed selected quality records including the Unit 3 Cycle 1 Core Loading Plan and the letter documenting the verification and certification of the fuel assemblies and RCCA from the vendor to verify the components conformed with the design requirements.

b. Findings No findings were identified.

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1A08 (Unit 3) ITAAC Number 2.2.01.02a (91) / Family 06F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.01.02a (91). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.11-02.11 - Problem Identification and Resolution The inspectors reviewed the licensees corrective actions to address unresolved item (URI)05200025/2020003-02, ASME Section III Level C service Limits May Not Be Met for Containment Penetrations P44 and P45," which were captured in the corrective action program (CAP) as condition report (CR) 50063621 and Westinghouse Electric Company (WEC) CAP as issue report (IR) 2020-10571. The inspectors also reviewed E&DCR APP-ML10-GEF-046 (with attached APP-ML10-S3C-001 calculations) and finite element analysis (FEA) model files for containment penetration P44 and P45 guard pipes referenced in the E&DCR to verify loadings associated with the Vogtle Unit 3 containment design pressure and temperatures in combinations with a safe shutdown earthquake can be extracted from the model. The inspectors reviewed the results from the FEA model files against the Level C service limits of the ASME Code,Section III, Paragraph NE-3221.

The inspectors also reviewed proposed changes to the licensees calculation APP-ML10-S3C-001, AP1000 Containment Piping Penetrations with Flued Heads Analysis and Verification, to determine if the contents of the analysis included the penetration guard pipes and demonstrated the acceptance criteria of ITAAC 2.2.01.02a for Unit 3 was not impacted.

Based on the inspectors review, URI 05200025/2020003-02 is closed and NCV 05200025/2020004-01 is opened and closed in this report.

b. Findings Introduction The inspectors identified a construction finding of very low safety significance (Green) with an non-cited violation (NCV) of Title 10 of the Code of Federal Regulations Part 50 (10 CFR 50), Appendix B, Criterion III, "Design Control," for the licensees failure to have design control measures for the 18-inch diameter carbon steel guard pipes for containment vessel penetrations P44 and P45. Specifically, the site previously performed a structural analysis that omitted the guard pipe portion of the penetrations and did not consider how the guard pipe exclusion would infringe upon the design margin for ensuring the requirement for ASME Section III, Level C service limits were not exceeded, in accordance with the current licensing basis.

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Description In NRC inspection report 05200025/2020003, the inspectors opened URI 05200025/2020003-02, ASME Section III Level C service Limits May Not Be Met for Containment Penetrations P44 and P45" because the licensee had not performed an analysis for the guard pipes for penetrations P44 and P45, as required by the UFSAR, Revision 9.0, Subsection 3.6.2.1.1.4. The licensee entered this issue into its CAP as 50053621. The issue remained unresolved pending further analysis by the licensee and Westinghouse.

The Vogtle Unit 3 containment penetration P44 and P45 guard pipes are in the break exclusion area in the annulus region between the containment vessel and shield building (SB). The guard pipes internally contain the 6-inch diameter startup feedwater pipes that are routed from the turbine building through the auxiliary building to the corresponding steam generators. Subsection 3.6.2.1.1.4 of the Vogtle 3 and 4 UFSAR, High Energy Piping in Containment Penetration Areas, states, in part, that breaks are not postulated in the portions of ASME Code,Section III piping, defined as break exclusion piping, provided it meets the provision(s) that Level C service limits of ASME Code,Section III, Paragraph NE-3221 are not exceeded by the loadings associated with containment design pressure and temperature in combinations with a safe shutdown earthquake. However, the licensees structural and thermal analysis model omitted the guard pipe portion of the penetrations and did not consider how this exclusion might infringe upon the design margin for ensuring the requirement for ASME Section III, Level C service limits were not exceeded. The licensee documented this issue in its CAP as CR 50063621 and WEC CAP IR-2020-10571.

The inspectors reviewed the changes to the calculation addressed in E&DCR APP-ML10-GEF-046, Update for Penetrations 44 and 45, that included calculation APP-ML10-S3C-001, AP1000 Containment Piping Penetrations with Flued Heads Analysis and Verification, to determine if the contents of the analysis showed that UFSAR Subsection 3.6.2.1.1.4 criteria were met and the acceptance criteria of ITAAC 2.2.01.02a was not impacted. Specifically, the inspectors reviewed the structural model calculation to verify contents were in accordance with ASME Code Section III, Subsection NE design criteria described in Article NE-3000 for Class MC metal containment components. The inspectors reviewed the penetration design analysis against the requirements in ASME Section III requirements of subparagraphs NE-3221.1, General Primary Membrane Stress Intensity and NE-3221.4, Primary Plus Secondary Stress Intensity.

The inspectors evaluated the primary stress loading analysis results for the guard pipes associated with the containment design pressure and temperature in combination with a safe shutdown earthquake to verify the results did not exceed the Level C service limits of the ASME Code Section III, Paragraph NE-3221. Based on their review, the inspectors determined the information provided in the E&DCR provided reasonable assurance that containment penetrations P44 and P45 met the licensing requirement of the Vogtle UFSAR, Revision 9.0, Subsection 3.6.2.1.1.4.

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Analysis The inspectors determined the licensees failure to have design control measures for the 18-inch diameter carbon steel guard pipes for containment vessel penetrations P44 and P45 was a performance deficiency. The inspectors determined that the failure to ensure Level C service limits were not exceeded by the design loading conditions with a safe shutdown earthquake, as required in the licensing basis was contrary to the requirements of 10 CFR 50, Appendix B, Criterion III, Design Control, and resulted in a performance deficiency that required substantive corrective action.

Per the guidance in IMC 0613, Power Reactor Construction Inspection Reports, Appendix B, Issue Screening, dated November 4, 2020, the inspectors determined traditional enforcement or enforcement discretion would not apply to this performance deficiency. Per IMC 0613, Appendix E, Examples of Minor Construction Issues, dated November 4, 2020, the inspectors determined this performance deficiency was of more-than-minor safety significance, and thus a finding, because it represented an adverse condition that rendered the quality of an SSC unacceptable or indeterminate, and required substantive corrective action.

The inspectors determined this finding was related to the Design/Engineering cornerstone of the Construction Reactor Safety strategic performance area. This was a construction finding and it was not associated with an inspection, test, analyses, and acceptance criteria. This finding was not associated with a security program; it was not associated with an IMC 2504 operational/construction program; and it was not associated with a repetitive, NRC-identified omission of a program critical attribute.

The inspectors assessed the finding using IMC 2519, Appendix A, AP1000 Significance Determination Process, dated October 26, 2020, and determined the finding was a performance deficiency of very low safety significance (Green) because it was associated with the containment system (CNS), a structure assigned to the intermediate risk column of the AP1000 Construction Significance Determination Matrix. The inspectors determined this finding was a finding of very low safety significance because the licensee was able to demonstrate the design function of the applicable structure or system (containment vessel) would not be impaired by the deficiency by successfully reperforming a structural model calculation.

The inspectors determined the finding was indicative of present licensee performance and was associated with the cross-cutting aspect of Documentation in the area of Human Performance, in accordance with IMC 0613, Appendix F, Construction Cross-Cutting Areas and Aspects, dated November 4, 2020. The licensee did not ensure its calculations were reflective of the ASME Level C service limit requirements for the P44 and P45 penetration guard pipes. [H.7].

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Enforcement 10 CFR 50, Appendix B, Criterion III, Design Control, requires, in part, that design control measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews to items such as stress, thermal, and accident analyses. UFSAR Section 3.6.2.1.1.4, High Energy Piping in Containment Penetration Areas, states, in part, that breaks are not postulated in the portions of ASME Code,Section III, Class 2 or Class 3 piping, as break exclusion piping, provided the subject piping that meets the provisions to support the UFSAR for Level C service limits of ASME Code,Section III, Paragraph NE-3221 are not exceeded by the loadings associated with containment design pressure and temperature in combinations with a safe shutdown earthquake. The licensees postulation was based on ASME Section III Level C service limits not being exceeded.

Contrary to the above, on and before September 23, 2020, the licensee did not have design control measures for verifying or checking the adequacy of design of the 18-inch diameter carbon steel guard pipes for containment vessel penetrations P44 and P45. Specifically, the licensee previously performed a structural analysis that omitted the guard pipe portion of the penetrations and did not consider how the guard pipe exclusion would infringe upon the design margin for ensuring the requirement for ASME Section III, Level C service limits were not exceeded, in accordance with the current licensing basis. The licensee entered this issue into its CAP as CR 50063621 and updated the structural model calculations as part of the corrective action. Because this violation was not repetitive or willful, was of very low safety significance (Green), and was entered into the licensees CAP, it is being treated as an NCV consistent with Section 2.3.2.a of the NRC Enforcement Policy (NCV 05200025/2020004-01, Failure to verify ASME Code Section III Level C Service Limits in Accordance with License Basis and ASME Code Section III).

1A09 (Unit 3) ITAAC Number 2.2.01.02a (91) / Family 06F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.01.02a (91). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.11-02.03 - Installation and Welding

65001.B-02.03-Welder Qualification

65001.F-02.02-Fabrication Records Review

65001.F-02.03-Observation of Fabrication Activities

65001.F-02.04-General Quality Assurance (QA) Review 16

The inspectors performed a direct inspection of pressure retaining rings installed on the Unit 3 containment building electrical penetration assemblies (EPA). The epoxy coating to the containment vessel penetration sleeve weld joint was removed and two new halves of pressure retaining rings were welded to the outside of the EPA extension sleeve and containment vessel penetration sleeve. Specifically, the inspectors observed welding of pressure retaining rings on EPA 019 and EPA 022, and observed pre-heating of EPA 021 and EPA 024.

The inspectors reviewed welder performance qualification records to verify if the welders qualification records were current and met the requirements of the ASME Code,Section III Subsection NE, and Section IX. The inspectors reviewed records of heat treat contractors personnel to verify personnel were qualified and current. The inspectors reviewed calibration records of the weld machine and k-wire thermocouples to verify the equipment were calibrated within their full range, identified, and traceable to national standards. In addition, the inspectors reviewed material test reports of the weld rods used to verify the chemical and physical test records met the requirements of the ASME Code,Section II and Section III.

b. Findings No findings were identified.

1A10 (Unit 3) ITAAC Number 2.2.01.08 (109) / Family 08F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.01.08 (109). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.08-02.04 - Inspection of Containment Electrical Penetration Assemblies (EPAs) Yes

65001.08-02.05 - Inspection of Station Grounding and Surge Protection Yes

65001.F-02.02-Fabrication Records Review Yes

65001.F-02.04-General QA Review The inspectors reviewed documentation and conducted walkdowns of protection devices for the EPAs to verify the as-built containment EPAs were protected against currents which are greater than their continuous ratings as required by Appendix C to the Vogtle Unit 3 COL.

Specifically, for cables that originated from medium voltage switchgears, low voltage distribution panels and motor control centers feeding motors inside containment, the inspectors verified that overcurrent protection was provided for the cables. The inspectors reviewed reports and calculations to verify the design addressed protection from currents which were greater than the continuous ratings of the EPA cables.

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For medium voltage cables, the inspectors reviewed engineering studies that specified the overcurrent protection relay settings using time-current curves of the Schweitzer Engineering Laboratories 710 relays. As shown in the curves, these relays, as programmed, provided adequate level of protection for the cables running through the EPA. For low voltage cables, the inspectors conducted a walkdown of distribution panels and motor control centers to verify the size of fuses used to protect feeders and wiring routed through the EPAs were in accordance with the design.

b. Findings No findings were identified.

1A11 (Unit 3) ITAAC Number 2.2.01.11a.i (114) / Family 07E

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.01.11a.i (114). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.09-02.02 - Attributes of Electrical Cable installation

65001.09-02.03 - Documentation

65001.10-02.02.c - As Built Verification

65001.E-02.04-Documentation

65001.E-02.06-Problem Identification and Resolution The inspectors reviewed the EQRR for component cooling water system (CCS) containment isolation MOVs CCS-PL-V207 and CCS-PL-V208, to determine whether the licensee assessed work packages, design changes, and nonconformances to verify the as-built configuration, including anchorage, were seismically bounded by the analyzed conditions in accordance with data sheets SV3-PV11-Z0D-122 and SV3-PV11-124 and design specification SV3-PV11-Z0-001.

The inspectors reviewed the licensees methodology and selection of applicable work orders, data sheets, and design drawings, to determine whether the inspections and analyses demonstrated the as-built installed MOVs were bounded by tests or type tests.

The inspectors reviewed the EQSRs and EQDPs to determine whether installation restrictions were translated to the drawings and EQRRs. The inspectors performed a review of as-installed electrical connections to determine whether the electrical connections were installed as tested so the valves would function during a design basis accident.

The inspectors conducted a walkdown of the CNS to verify the satisfactory installation of the MOVs. The inspectors verified each valves make/model/serial number, mounting orientation and location. The inspectors also verified the mechanical and electrical connections were bounded by the tested conditions.

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The inspectors also interviewed licensing personnel to determine how inspection and analysis were performed for applicable nonconformances and E&DCRs issued during fabrication, handling, installation, and testing to verify all deviations were bounded by the seismically analyzed conditions.

b. Findings No findings were identified.

1A12 (Unit 3) ITAAC Number 2.2.02.02a (120) / Family 07F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.02.02a (120). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.03-02.03 - Installation and Welding

65001.03-02.06 - Nondestructive Examination

65001.07-02.02 - Component Welding

65001.B-02.03-Welder Qualification

65001.B-02.04-Production Controls

65001.B-02.05-Inspection The inspectors reviewed welding and NDE records associated with eight field welds on the inlet and outlet sides of four passive containment cooling system (PCS) gate valves: PCS-PL-V001C, -V002A, -V002B, and -V002C to four connecting line numbers: PCS-PL-L002 and -L005, and PCS-PL-L003A and -L003B to determine if the 6-inch diameter stainless steel motor operated valves were installed in accordance with the ASME Code Section III, Subsection ND, for Class 3 components.

The inspectors reviewed eight WDSs for three work packages to verify QC inspection hold points were signed-off and dated for acceptance of internal cleanliness, fit-up with alignment tack welds, and final visual examination in accordance with NCA-4134.10 and ND-4230.

The inspectors also reviewed the entries on the WDSs to determine whether the traceability of previously reviewed stainless steel weld filler metals and welders were maintained in accordance with ND-4122 and ND-4300. In addition, the inspectors reviewed certified material test reports (CMTRs) for 1/16-inch (heat-no. 1030L) and 1/8-inch (heat-no. 1408D) diameter ER308/308L solid rods to verify the chemical analysis and mechanical properties were in accordance with the ASME Code Section III (NB-2400) and ASME Code Section II, Part C, SFA-5.9 specification for stainless steel welding rods.

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The inspectors reviewed performance qualification records of welders to verify the welders were tested and certified for welding on this portion of the PCS piping in accordance with the requirements of the ASME Code Section IX, Article III for welding performance qualifications.

The inspectors reviewed six liquid penetration examination reports to determine whether acceptance by SNT-TC-1A Level II examiners were performed with no rejectable indications in accordance with the requirements of the ASME Code Section III (Article ND-5000) and Section V (Article 6) for liquid penetration examination.

b. Findings No findings were identified.

1A13 (Unit 3) ITAAC Number 2.2.03.02a (159) / Family 06F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.03.02a (159). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.07-02.01 - General Installation The inspectors observed and reviewed documents associated with work package SV3-PXS-P0W-1057547 for installation of the 8-inch diameter isolation MOV, SV3-PXS-PL-V125B for the in-containment refueling water storage tank injection B squib valve to determine if the mechanical joint connections at the inlet and outlet sides to the valve body and flanges were assembled in accordance with the requirements of the ASME Code Section III, Subsection NB, for Class 1 components.

The inspectors reviewed the Valve Installation Data Sheet to verify QC inspector hold points for identification/marking of the PV70 valve with serial number 0920-164451 3, material traceability for studs and nuts, internal cleanliness, and torque wrench calibration were deemed satisfactory and signed-off in accordance with the requirements of the ASME Code Section III, Article NCA-3000 with final signature by the ANI.

The inspectors reviewed Bolted Joint Data Sheets to verify QC inspector hold points for the inlet and outlet side alignment/fit-up with gaskets between the valve body and flanges were sequentially torqued in gradual steps to the initial maximum torque value using 12 threaded stud and nut materials on each side in accordance with the requirements of the ASME Code Section III, NB-2128, and Section II, Part D, Subpart 1, Table 4 with final signature by the ANI.

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The inspectors reviewed Special Operations Data Sheets to verify hold points for hydraulic tensioning of 12 studs into the inlet and outlet sides of the valve body and tightening of the nuts to the flanges were deemed satisfactory and signed-off by QC inspectors and the ANI in accordance with the requirements of the ASME Code Section III, NB-4700 for mechanical joints and Article NCA-5000 for authorized inspection.

b. Findings No findings were identified.

1A14 (Unit 3) ITAAC Number 2.2.03.02a (159) / Family 06F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.03.02a (159). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.06-02.01 - General Installation

65001.06-02.03 - Post Installation Activities

65001.F-02.01-Design Document Review

65001.F-02.02-Fabrication Records Review The inspectors reviewed the isometric construction drawings for the Vogtle Unit 3 PXS pipe supports located in the containment building to verify they were in accordance with the WEC fabrication and installation specification. The inspectors performed a walkdown in the containment building room 11206 to verify the pipe supports installed were of correct type, were in the correct location, restrained to the pipe and the anchorage point, and were aligned in accordance with the pipe support installation construction drawings and met the requirements of the WEC fabrication and installation specification. The inspectors examined the pipe supports to verify there was no structural damage, there was no oil leakage from the snubber, and the weld reinforcement to the pipe was in accordance with the QA program requirements and WEC fabrication and installation specification.

b. Findings No findings were identified.

1A15 (Unit 3) ITAAC Number 2.6.03.02.i (597) / Family 08A (Unit 4) ITAAC Number 2.6.03.02.i (597) / Family 08A 21

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.6.03.02.i (597). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.09-02.03 - Documentation

65001.A- As-Built Attributes for SSCs associated with ITAAC

65001.A.02.02 - Installation Records Review

65001.A.02.03 - Independent Assessment/Measurement Inspection

65001.A.02.04 - Review As-built Deviations/Nonconformance The inspectors reviewed the design and construction of battery racks for the Unit 3 Class 1E DC and uninterruptible power supply system (IDS) for the 24-hour, 72-hour, and spare batteries to determine whether the installation was in accordance with the ITAAC requirements. Specifically, the inspectors reviewed quality records, including the design specification, work packages, inspection records, engineering service requests (ESRs), CRs, procedures, vendor manuals, and drawings to verify:

the design was implemented in accordance with regulatory requirements, including applicable sections of the UFSAR and the Institute of Electrical and Electronic Engineers standards;

differences between the as-built configuration and the design were reconciled in the design report;

the design drawings were revised to reflect the as-built configuration by qualified personnel;

issues identified during the inspection were entered into the CAP in accordance with the CAP requirements;

design changes were evaluated and implemented in accordance with established site procedures; and

design deviations or nonconforming conditions were identified, documented, and dispositioned in accordance with site procedures.

The inspectors conducted a walkdown to determine whether the critical attributes of the as-built IDS battery racks conformed to the approved design. During the walkdown, the inspectors reviewed licensee actions to address similar or related problems that were previously identified, in order to check the extent of condition and verify the effectiveness of the licensees corrective measures.

b. Findings Introduction The inspectors identified an ITAAC finding of very low safety significance (Green) with an associated NCV of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, for the licensees failure to construct and perform quality inspections on Unit 3 and Unit 4 IDS battery racks for the 250 Vdc 24-hour, 72-hour, and spare batteries in accordance with ITAAC 2.6.03.02.i and the approved design requirements for Vogtle Units 3 and 4.

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Description ESR 50053212 was written to evaluate misaligned channel nuts, also known as misaligned spring nuts, on IDS battery racks in Unit 3 room 12102. The term misaligned spring nuts refers to spring or channel nuts that may not be seated on the Unistrut rail channel sections. Thus, the slots within the spring nuts may not be fully engaged with the rails folded edges in accordance with Section 7.3, Install Support Rails & Side Rails to Frame, of Vendor Manual APP-DB01-V8M-001. The licensee had captured this issue in its CAP on June 16, 2020 (ESR 50053212) and closed the issue without completing an evaluation. The Unit 3 IDS battery racks were fully assembled, hardware was torqued, and spring nuts had been QC inspected and accepted during the installation of the battery racks. The IDS batteries were also installed in the racks with cables already terminated.

The inspectors noted step 3010 of work packages SV3-IDS-DBW-860173 and SV3-DS-DBW-860174 required rack installation per vendor manual SV3-DB01-V8M-001. The vendor manual required spring nuts to be seated in accordance with Figure 7.3 d, steps 1 through 4. After a review of the work packages, specifically Section 3.3, the inspectors noted the QC inspection staff had concluded, by initial on the electrical equipment installation inspection records, the equipment and hardware (e.g. spring bolts and nuts) were mounted correctly.

On July 28, and August 5, 2020, responding to the NRCs follow-up questions on the condition of misaligned spring nuts, the licensee initiated CR 50057411 and CR 50058215 respectively, that identified multiple instances where the grooves in the vendor supplied spring nuts were not seated in the Unistrut channel sections of several IDS battery racks (i.e., SV3-IDSC-DB-1A, SV3-IDSC-DB-1B and SV3-IDSS-DB-1A) in rooms 12102 and 12103. The spring nuts were already QC inspected and accepted during the installation of the battery racks. In addition, ESR 50057274 was also initiated to determine if this as-built condition was adequate, as originally intended by ESR 50053212.

In addition, the licensee conducted a QA surveillance from August 5 through November 16, 2020, where additional nonconformances were identified for the batteries, specifically with the as-built condition of the battery racks after QC inspections were previously completed. Specifically, Quality Surveillance 26193-000-GQA-QSSS-20160 of the Unit 3 battery racks as-built configuration was performed to verify compliance with vendor instructions and project specifications. This quality surveillance identified several cross bracings were not installed per the manufacturers instructions in rooms 12102 and 12202, and CR 50062315 was initiated to address this issue.

As a result of the extent of condition performed, the licensee initiated CR 50062981 that identified the battery racks vendor was not consulted to determine whether material hardware substitution (i.e., bolts, washers and nuts) met the quality requirements under its commercial dedication program. Specifically, nonconformance and disposition (N&D) SV3-IDSB-GNR-000002 allowed use of a substitute material for rail nuts and related hardware on IDS battery racks for 3-IDSB-DB-2B. The N&D accepted the form, fit, and function of the alternate material as meeting APP-DB01-Z0-001, Design Specification for Class 1E 250 VDC Batteries and Racks for System IDS, Revision 7.

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However, the vendor was not consulted, and the NRC inspectors noted that material weight differences were not documented as part of the original evaluation for this material substitution.

The licensees extent of condition inspection identified additional safety related spring nuts not seated, as required in vendor manuals Figure 7.3d, steps 1 through 4. This nonconforming condition was found in all the IDS battery racks from both Unit 3 and Unit 4, thus potentially affecting the safety function of all the 250 Vdc 24-hour, 72-hour, and spare batteries. Further, the spring nuts in Unit 3 rooms 12101, 12102, 12103, 12104, 12105, 12202 and 12204 had already been QC inspected and accepted during the installation of the battery racks. These issues were captured in the CAP as CRs 50057411, 50058215, and 50054000.

Due to the cumulative effects of multiple nonconforming issues, it was indeterminate if the applicable Category 1 equipment could withstand seismic design basis loads without a loss of safety function and if the as-built equipment, including anchorage, was seismically bounded by the tested or analyzed conditions. The licensee entered all these issues into its CAP as CR 50066999. Investigation and resolution of several of these issues were addressed under the scope of ESR 50057274. The licensee completed evaluations SVP-SV0-006012, Battery Rack Nonconformance Structural Safety Evaluation and SVP-SV0-006099, Battery Rack Nonconformance Structural Safety Evaluation - Updated Based on Completed Extent of Condition Work, that demonstrated there was reasonable assurance that the design function of the system would not have been impaired by the deficiency based on engineering analysis of the nonconforming conditions identified. The licensee also restored the Unit 3 and 4s as-built configuration of the IDS battery racks to match the seismically qualified condition as specified by the design.

Analysis The inspectors determined the licensees failure to construct and perform quality inspections on battery racks for the Unit 3 and Unit 4 IDS 24-hour, 72-hour, and spare batteries in accordance with ITAAC 2.6.03.02.i and the approved design requirements for Vogtle Units 3 and 4 was a performance deficiency. The inspectors determined that the failure to meet the requirements in SV3-DB01-V8M-001 and APP-DB01-Z0-001 was contrary to the requirements of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, and resulted in a performance deficiency that required substantive corrective action. Per the guidance in IMC 0613, Power Reactor Construction Inspection Reports, Appendix B, Issue Screening, dated November 4, 2020, the inspectors determined traditional enforcement or enforcement discretion would not apply to this performance deficiency.

Per further guidance in IMC 0613, Appendix E, Examples of Minor Construction Issues, dated November 4, 2020, the inspectors determined this performance deficiency was of more than minor safety significance, and thus a finding, because it was material to the acceptance criteria of an ITAAC and invalidated the Inspection, Test, or Analysis described in the ITAAC. Specifically, the design commitment for ITAAC 2.6.03.02.i (Sequence 597) is the seismic Category I equipment identified in Table 2.6.3-1 can withstand seismic design basis loads without loss of safety function.

Table 2.6.3-1 lists IDS 250 Vdc 24-hour, 72-hour, and spare batteries as applicable seismic Category I equipment.

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The acceptance criteria for this ITAAC states in part that a report exists and concludes that the as-built equipment including the anchorage is seismically bounded by the tested or analyzed conditions. The inspectors determined that the performance deficiency was material to ITAAC 2.6.03.02.i because the cumulative effects for the multiple non-conformances with the as-built seismic Category I IDS equipment, after QC inspections were completed and deemed acceptable, it was indeterminate if the applicable Category 1 equipment could withstand seismic design basis loads without a loss of safety function and if the as-built equipment, including anchorage, was seismically bounded by the tested or analyzed conditions.

The inspectors determined this finding was related to the Construction/Installation cornerstone of the Construction Reactor Safety strategic performance area. The inspectors determined this finding was not associated with a security program; it was not associated with an IMC 2504 operational/construction program; and it was not associated with a repetitive, NRC-identified omission of a program critical attribute. In accordance with IMC 2519, Construction Significance Determination Process, Appendix A, AP 1000 Construction Significance Determination Process, dated October 26, 2020, the inspectors determined this finding was a performance deficiency of very low safety significance (Green) because the licensee was able to demonstrate with reasonable assurance the design function of the structure or system would not be impaired by the deficiency, and the nonconforming conditions were corrected such that the installation was seismically bounded by the tested or analyzed conditions. Under the AP 1000 Construction Significance Determination Matrix in Attachment A of IMC 2519, the IDS is classified as a High Safety System under the System/Structure Risk Column and the finding concerned the same design and safety functions of multiple trains or the entire IDS battery system as listed in AP 1000 System Design Function Definitions and the COL. Based upon the NRC review of the licensees evaluations SVP-SV0-006012 and SVP-SV0-006099 that demonstrated there was reasonable assurance the design function of the system would not have been impaired by the deficiency, the inspectors determined the performance deficiency would not impair the design function of the IDS, therefore the finding screened for Row 1 under Table Construction Significance Determination Process Matrix Quality of Construction Y -

Axis Flow Diagram.

The inspectors determined the finding was indicative of present licensee performance and was associated with the cross-cutting aspect of Avoiding Complacency in the area of Human Performance, in accordance with IMC 0613, Appendix F, Construction Cross-Cutting Areas and Aspects, dated November 4, 2020. The proximate cause of the performance deficiency was attributed to a failure to use human error reduction techniques, namely a failure to perform a thorough review of the work instructions and to plan the activity every time without relying on past successes and assumed conditions. [H.12]

Enforcement 10 CFR 50 Appendix B, Criterion V, Instructions, Procedures, and Drawings, requires, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.

25

Contrary to the above, on and before August 5, 2020, the licensee failed to install battery racks for the Unit 3 and Unit 4 250 Vdc 24-hour, 72-hour, and spare IDS batteries in accordance with ITAAC 2.6.03.02.i and the approved design requirements specified in SV3-DB01-V8M-001 and APP-DB01-Z0-001. The licensee entered this finding into its CAP for evaluation and identification of appropriate corrective actions (CR 50066999). Corrective actions were completed for this issue, which included rework on the battery racks to correct the nonconforming conditions in both units.

Because this violation was not repetitive or willful; was of very low safety significance; and was entered into the licensees CAP, it is being treated as an NCV consistent with Section 2.3.2.a of the NRC Enforcement Policy (NCV 05200025/2020004-02 and 05200026/2020004-02, Failure to Construct and Perform Quality Inspections on the Battery Racks for the Class 1E DC and Uninterruptible Power Supply System).

1A16 (Unit 3) ITAAC Number 3.3.00.02a.i.a (760) / Family 01F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.02a.i.a (760). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.01 - Inspection of ITAAC-Related Foundations & Buildings

65001.01-02.07 - Identification and Resolution of Problem

65001.02-02.07 - Problem Identification and Resolution

65001.A- As-Built Attributes for SSCs associated with ITAAC

65001.A.02.04 - Review As-built Deviations/Nonconformance The inspectors reviewed the as-built summary report for the containment internal structures to verify the report reconciled deviations during construction, including Table 3.3-1 wall and floor thicknesses, and concluded the as-built containment internal structures, including the critical sections, conform to the approved design and would withstand the design basis loads specified in the Design Description without loss of structural integrity or the safety-related functions, and without impacting compliance with the radiation protection licensing basis. Specifically, the inspectors verified if the as-built summary report addressed deviations that were reconciled after the effective date of the as-designed summary report.

The inspectors reviewed Table 3-2.1 and Table 3-2.2 of the as-built summary report to verify margin existed in the structural components and connections after reconciliation of the site specific nonconformance and disposition reports (N&Ds) and E&DCRs. The inspectors also reviewed the design summary of critical sections provided in the as-built summary report to verify they were consistent with VEGP Units 3 and 4 UFSAR Tables 3.3.8-4, 3.3.8-5, and 3.3.8-6.

Additionally, the inspectors reviewed Table 4-2 of the as-built summary report to determine if the as-built construction met the concrete wall thicknesses and radiation shielding requirements of VEGP Units 3 and 4 UFSAR Table 3.3-1.

26

b. Findings No findings were identified.

1A17 (Unit 3) ITAAC Number 3.3.00.02a.i.d (763) / Family 01F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.02a.i.d (763). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.02-02.01 - Inspection of Concrete Placement

65001.02-02.06 - Record Review

65001.02-02.07 - Problem Identification and Resolution

65001.F- Inspection of the ITAAC-Related Design and Fabrication Requirements

65001.F-02.01-Design Document Review The inspectors reviewed pre-placement inspection records to verify the quality and technical requirements were met. Specifically, the inspectors reviewed concrete pre-placement, reinforcing bar, and mechanical splicing inspection records to verify the bars met material requirements, inspection was performed to determine if the bars were installed in accordance with the construction documents, and records were completed in accordance with Bechtel Project Procedures, 26139-000-4MP-T81C-N3210-CPM1F2 and 26139-000-4MP-T81C-N3223. The inspectors also reviewed mechanical splicer qualification records to verify the installers were qualified to perform the work in accordance with SV3-CR01-Z0-010.

The inspectors reviewed five E&DCRs to verify design changes made to the roof structure were performed in accordance with 10 CFR 50 Appendix B, Criterion III, Design Control. Specifically, the inspectors determined if the design changes were subject to control measures commensurate with those applied to the original design and were approved by the organization that performed the original design or the designated responsible organization. The inspectors also reviewed the E&DCRs to verify a technical justification was provided for the design change, deviations from applicable quality standards such as American Concrete Institute (ACI) 349-01 were controlled, and the revised design was correctly translated into the updated design output documents.

The inspectors also reviewed two N&Ds to verify nonconforming conditions were documented in the CAP. Additionally, the inspectors reviewed the N&Ds to determine if nonconforming items dispositioned use-as-is or repair were reviewed and approved by the design authority and evaluated for impacts to the licensing basis.

b. Findings No findings were identified.

1A18 (Unit 3) ITAAC Number 3.3.00.02b (770) / Family 01A 27

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.02b (770). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.01-02.01 - Procedures

65001.01-02.06 - Records

65001.A.02.01 - Observation of in-Process Installation Activities

65001.A.02.02 - Installation Records Review

65001.A.02.04 - Review As-built Deviations/Nonconformance The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.02b (770) to verify the as-built configuration demonstrated the site-grade is consistent with the design plant grade and is within the dimensions defined in Table 3.3-5 of Appendix C of the COL.

The inspectors performed an inspection of the as-built site grade elevation of Unit 3 relative to the floor elevation of 100-feet to determine whether the as-built site grade is consistent with design plant grade, including a tolerance of +/-3 feet 6-inches, as specified in Table 3.3-5 of Appendix C of the COL.

The inspectors verified the contractors construction survey procedure included quantitative and qualitative acceptance criteria for determining that the site survey inspection was accomplished in accordance with site procedures. The inspectors reviewed the calibration records of site survey instruments to verify the instruments were maintained, calibrated, and traceable to a known standard. The inspectors reviewed the contractors survey personnel qualification records and verified the survey personnel were qualified to perform site survey work. The inspectors conducted a walkdown of the site excavation and verified the re-installation of storm drains DI-NI-24 through DI-NI-27. The inspectors observed the surveying of storm drain covers using calibrated survey equipment in accordance with the Power Block Grading Plan. The inspectors also reviewed the power block grading plan to verify revisions reflected the design change documented in E&DCR SV3-0000-GEF-000243. The inspectors reviewed a CR describing a damaged storm drain lid and the corrective action taken. Furthermore, the inspectors reviewed the associated PCD to determine whether the ITAAC requirements were satisfied.

b. Findings No findings were identified.

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1A19 (Unit 3) ITAAC Number 3.3.00.02h (776) / Family 11A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.02h (776). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.01-02.06 - Records

65001.A.02.02 - Installation Records Review The inspectors performed an inspection to verify a report exists and concludes the flood up volume of PXS valve/equipment room B (room 11207) is less than 71,960 ft3 to an elevation of 107.68-feet to satisfy the ITAAC requirement.

The inspectors performed a walkdown with the licensee of the as-built containment structures and equipment in room 11207 to verify the as-built structures and components in the room matched the design such that the inputs into the licensees calculation for flood elevation (volume) were valid.

The inspectors reviewed the licensees methodology, assumptions and selection of applicable design drawings, calculations, QA data packages, and the PCD to verify the inspections and calculations demonstrated the as-built installed containment flood up volume met the ITAAC acceptance criteria. The inspectors reviewed inspection results from the component as-built dimensional and elevational data, and volumetric and construction survey data incorporated in the volumetric calculations and documented in WEC calculation report SV3-PXS-M3C-033, to determine if the calculated volumes met the ITAAC acceptance criteria. The inspectors reviewed the calibration reports of the survey instruments used to conduct surveys to verify they had been calibrated and were within their tolerance range.

b. Findings No findings were identified.

1A20 (Unit 3) ITAAC Number 3.3.00.07e (812) / Family 09A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.07e (812). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.09-02.01 - Physical Separation of Cables

65001.09-02.03 - Documentation 29

The inspectors reviewed the routing and separation of the Class 1E communication cables for the protection and safety monitoring system (PMS) to verify the as-built configuration met the acceptance criteria specified in the UFSAR Section 8.3.2.4 and the ITAAC.

Specifically, the inspectors reviewed cable pull tickets to determine routing methods used in the installation of interdivisional cable for the PMS voting logic. The inspectors reviewed cable termination inspection reports to determine if possible damage occurred during installation. The inspectors reviewed the separation between fiber optic cables to verify if distance and fire zone separation requirements, from the different divisions, were met to maintain the integrity of the PMS voting logic for these Class 1E communication cables.

The inspectors reviewed the PCD associated with this ITAAC to verify the analysis documented the effects of fire damage or damage to any single raceway carrying PMS interconnection cables potentially defeating the PMS voting logic.

b. Findings No findings were identified.

1A21 (Unit 3) ITAAC Number 3.3.00.13 (819) / Family 01A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.13 (819). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.01-02.06 - Records

65001.01-02.07 - Identification and Resolution of Problem

65001.A.02.02 - Installation Records Review The inspectors reviewed the licensees PCD for this ITAAC, including the survey results, to determine if the results and methods used met the ITAAC acceptance criteria.

Specifically, the inspectors reviewed PCDs and the survey results to determine if separation was provided between the structural elements of the turbine and annex buildings and the nuclear island structure. The separation permits horizontal motion of the buildings in the safe shutdown earthquake without impact between structural elements of the buildings.

The inspectors verified whether a minimum horizontal clearance above floor elevation 100-0 between the structural elements of the annex building and the nuclear island, and between turbine building and the nuclear island was 3-inches; except that the minimum north-south horizontal clearance between elevations 141-0 and 154-0 and between structural elements of the annex building and the nuclear island west of column line I was 2-1/16 inches in accordance with the acceptance criteria of ITAAC 3.3.00.13 of Appendix C to the Vogtle Unit 3 COL.

30

b. Findings No findings were identified.

1A22 (Unit 4) ITAAC Number 3.3.00.02a.i.b (761) / Family 01F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.02a.i.b (761). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.02-02.01 - Inspection of Concrete Placement The inspectors observed concrete placement in the tension ring of the SB, specifically module TR10 located on the west side. The inspectors reviewed the generic placement plan developed for the TR06 module to verify preplacement planning had been completed to assure good quality construction and contingency plans had been made to address unexpected events.

The inspectors reviewed two concrete batch plant delivery tickets to verify the batched mixes conformed to the placement plan and were discharged in accordance with the construction specification.

Additionally, the inspectors observed in-process record testing to verify concrete temperature, flow, air content, and unit weight conformed to requirements and in-process testing was completed at the proper location and frequency as required by the construction specification.

The inspectors also observed placement activities to verify placement locations and sequences were consistent with the placement plan and concrete was observed escaping from the air evacuation ports prior to concluding the placement.

b. Findings No findings were identified.

1A23 (Unit 4) ITAAC Number 3.3.00.02a.i.b (761) / Family 01F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.02a.i.b (761). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.01-02.05 - Steel Structures

65001.01-02.06 - Records

65001.A.02.02 - Installation Records Review

65001.B-02.04-Production Controls 31

65001.B-02.06-Records

65001.F-02.02-Fabrication Records Review The inspectors reviewed the following sample of Chicago Bridge and Iron Services (CBIS) travelers for welded and bolted connections associated with the Unit 4 SB conical roof module:

G4-R01 thru G4-R16 to G4-C01 thru G4-C03 for welds of the conical roof block to compressing ring assemblies;

G4-R17E, F and G thru G4-R32E, F and G for the weld studded panel assemblies; and

Roof-CompRing-Bolting-M06/M23 sliding joint at the G4-M23 bolt-up location of the compression ring assemblies.

The inspectors reviewed welding documents of weld joints near the completion stages of the conical roof module to verify the applicable weld preparations for weld joint alignment and fit-up, tack weld and root opening, preheat during welding, initial and interpass weld cleanliness, and final visual and NDE were performed and signed-off in accordance with the requirements of the CBIS general welding procedure and American Welding Society (AWS) Code D1.1:2000, Structural Welding Code Steel.

The inspectors reviewed two weld travelers used for joint assemblies of the SB roof to determine if established QC inspection hold points were signed-off, and the traceability of weld filler metals and welders were maintained in accordance with the CBIS general welding procedure. The inspectors reviewed spreadsheets for these weld travelers to determine if QC inspection hold points were established and signed-off for visual inspection, magnetic particle testing, and ultrasonic testing in accordance with the CBIS general welding procedure.

The inspectors performed an independent visual inspection of completed welds after flat toping of the surfaces and final ultrasonic testing to determine whether the quality of the weld toes were visually free from defects such as cracks, lack of fusion, or excessive undercut in accordance with the visual inspection acceptance criteria of AWS Code D1.1:2000, Structural Welding Code Steel.

The inspectors reviewed a traveler for bolting of the M06-M23 sliding joint at the G4-M23 bolt-up location of the compression ring assemblies to determine if established QC inspection hold points were signed-off, and the traceability of bolts and washers were maintained along with the position numbers of bolts and tightening sequence using 1/3 turn-of-nut permanent bolting.

The inspectors reviewed a sample of five design changes associated with the conical roof module to verify design changes were conducted in accordance with the requirements of APP-GW-GAP-420. Additionally, the inspectors reviewed the dispositions of the design changes to verify the changes from the original design did not make substantial changes that would require a revision to the design calculations.

b. Findings No findings were identified.

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1A24 (Unit 4) ITAAC Number 3.3.00.02a.i.b (761) / Family 01F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.02a.i.b (761). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.01-02.05 - Steel Structures

65001.B-02.03-Welder Qualification

65001.B-02.04-Production Controls The inspectors observed in-process assembly of Unit 4 tension ring modules in the nuclear island. Specifically, the inspectors observed in-process welding of the following joints:

external complete joint penetration (CJP) horizontal weld connecting tension ring module TR09 to the air inlet modules along the western edge of the SB at approximate azimuth 270 degrees;

interior CJP vertical weld with weld designation CJP4 connecting closure plate in access opening between tension ring modules TR06 and TR07;

external CJP vertical weld with weld designation CJP2 connecting tension ring modules TR08 and TR09; and

internal CJP horizontal weld with weld designation CJP1 connecting bottom flanges of tension ring modules TR09 and TR10.

For the welds listed above, the inspectors reviewed training records for the welders to verify they were appropriately qualified to perform the work. The inspectors also reviewed the weld travelers to verify work was being conducted in accordance with a document that coordinates and sequences all operations, references procedures, drawings, and instructions, establishes hold points, and provides for production welding and inspection signoffs. The inspectors reviewed the travelers to verify if the hold points for fit-up had been appropriately signed off prior to proceeding to the next work step.

Additionally, the inspectors verified if the variables for voltage and amperage being used for completing the horizontal seam weld connecting tension ring module TR09 to the air inlet modules were consistent with welding procedure specification (WPS) 181816-000-WS-WP-E8018. The inspectors reviewed the filler metal certificate of conformance to verify the material being used for completing the weld connecting the bottom flanges of tension ring modules TR09 and TR10 was consistent with WPS 181816-000-WS-WP-E8018.

b. Findings No findings were identified.

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1A25 (Unit 4) ITAAC Number 3.3.00.02a.i.c (762) / Family 01F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.02a.i.c (762). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.02-02.01 - Inspection of Concrete Placement

65001.02-02.06 - Record Review The inspectors observed concrete placement in walls 11 and Q approximately between wall P and the SB from elevation 135-3 to 153-0. The inspectors reviewed the pre-placement concrete inspection record and the concrete placement/order pour card to verify the required approvals were received prior to the final release for placement and records were completed in accordance with Bechtel Project Procedure 26139-000-4MP-T81C-N3210-CPM1F2.

The inspectors reviewed two concrete batch plant delivery tickets to verify the batched mixes conformed to the placement plan and were discharged in accordance with the construction specification. Additionally, the inspectors observed in-process record testing to verify concrete temperature, flow, air content, and unit weight conformed to requirements and in-process testing was completed at the proper location and frequency as required by the construction specification.

The inspectors also observed placement activities to verify drop distances did not exceed specification requirements, placement rates were consistent with the placement plan, and appropriate attention was given to areas of obstruction within the modules to minimize the potential for voids or honeycombing.

b. Findings No findings were identified.

1A26 (Unit 4) ITAAC Number 3.3.00.02a.i.c (762) / Family 01F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.02a.i.c (762). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.02-02.01 - Inspection of Concrete Placement

65001.F- Inspection of the ITAAC-Related Design and Fabrication Requirements

65001.F-02.01-Design Document Review 34

The inspectors observed in progress construction of the roof over Area 2 of the auxiliary building approximately between the SB cylindrical wall and the walls along column lines 7.3, 11, I and L. Specifically, the inspectors observed the installation of the main top and bottom reinforcing bars in the concrete roof slab to verify the sizes, spacing, material designation, grade, lap splices, and layout of the bars were consistent with the applicable design drawings, E&DCRs, construction specification SV4-CC01-Z0-31, and ACI 349-01.

The inspectors reviewed two E&DCRs to verify design changes made to the roof slab were performed in accordance with 10 CFR 50 Appendix B, Criterion III, Design Control. Specifically, the design changes were subject to control measures commensurate with those applied to the original design and were approved by the organization that performed the original design or the designated responsible organization. The inspectors also reviewed the E&DCRs to verify a technical justification was provided for the design change, deviations from applicable quality standards such as ACI 349-01 were controlled, and the revised design was correctly translated into the updated design output documents.

b. Findings No findings were identified.

1A27 (Unit 4) ITAAC Number 3.3.00.02a.i.d (763) / Family 01F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.02a.i.d (763). The inspectors used the following NRC IPs/sections to perform this inspection:

65001.02-02.01 - Inspection of Concrete Placement

65001.02-02.06 - Record Review The inspectors observed concrete placement in wall N between wall 1 and the SB from approximately elevation 155-0 to 180-0. The inspectors reviewed the pre-placement concrete inspection record and the concrete placement/order pour card to verify the required approvals were received prior to the final release for placement and records were completed in accordance with Bechtel project procedure 26139-000-4MP-T81C-N3210-CPM1F2.

The inspectors reviewed two concrete batch plant delivery tickets to verify the batched mixes conformed to the placement plan and were discharged in accordance with the construction specification. Additionally, the inspectors observed in-process record testing to verify concrete temperature, flow, air content, and unit weight conformed to requirements and in-process testing was completed at the proper location and frequency as required by the construction specification.

35

The inspectors also observed placement activities to verify drop distances did not exceed specification requirements, placement rates were consistent with the placement plan, and appropriate attention was given to areas of obstruction within the modules to minimize the potential for voids or honeycombing.

b. Findings No findings were identified.

IMC 2504, Construction Inspection Program - Inspection of Construction and Operational Programs 1P01 Construction QA Criterion 16

35007-A16.04 - Inspection Requirements and Guidance

35007-A16.04.01 - Inspection of QA Implementing Documents

35007-A16.04.02 - Inspection of QA Program Implementation

a. Inspection Scope The inspectors reviewed issues entered into the licensees CAP daily to assess issues that might warrant additional follow-up inspection, to assess repetitive or long term issues, to assess adverse performance trends, and to ensure the CAP appropriately included regulatory required non-safety related SSCs. The inspectors periodically attended the licensees CAP review meetings, held discussions with licensee and contractor personnel, and performed reviews of CAP activities during the conduct of other baseline inspection procedures. The inspectors reviewed conditions entered into the licensees CAP to determine whether the issues were classified in accordance with the licensees QA program and CAP implementing procedures. The inspectors reviewed corrective actions associated with conditions entered into the CAP to determine whether appropriate actions to correct the issues were identified and implemented effectively, including immediate or short-term corrective actions, in accordance with the applicable QA program requirements and 10 CFR 50, Appendix B, Criterion XVI. Additionally, the inspectors reviewed the corrective actions taken to determine whether they were commensurate with the significance of the associated conditions in accordance with the licensees CAP implementing procedures. The inspectors completed reviews of CAP entry logs to verify issues from all aspects of the project, including equipment, human performance, and program issues, were being identified by the licensee and associated contractors at an appropriate threshold and entered into the CAP as required by licensees CAP implementing procedures.

b. Findings No findings were identified.

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4. OTHER INSPECTION RESULTS 4OA5 Other Activities

.1 Review of World Association of Nuclear Operators (WANO) Pre-Startup Review (PSUR)

Report for Vogtle Unit 3.

The inspectors reviewed the WANO PSUR Report of Vogtle Unit 3 conducted in August 2020. During this review, the inspectors did not identify any new significant safety issues.

4OA6 Meetings, Including Exit

.1 Exit Meeting.

On January 14, 2021, the inspectors presented the inspection results to Mr. Glen Chick, Vogtle Units 3 and 4 Executive Vice President, and other licensee and contractor staff members. Proprietary information was reviewed during the inspection period but was not included in the inspection report.

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SUPPLEMENTAL INFORMATION KEY POINTS OF CONTACT Licensees and Contractor Personnel R. Beilke, ITAAC Project Manager C. Castell, SNC Licensing Engineer N. Kellenberger, SNC Licensing Supervisor S. Leighty, SNC Licensing Supervisor T. Petrak, SNC ITAAC Manager L. Pritchett, SNC Licensing Engineer K. Roberts, SNC, Licensing Manager G. Scott, SNC Licensing Engineer M. Yox, SNC Regulatory Affairs Director LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED Item Number Type Status Description 05200025/2020003-02 URI Closed ASME Code Section III Level C Service Limits May Not Be Met for Containment Penetrations 44 and 45 (Section 1A08)05200025/2020004-01 NCV Open/Closed ASME Code Section III Level C Service Limits May Not Be Met for Containment Penetrations 44 and 45 (Section 1A08)05200025/2020004-02 NCV Open/Closed Failure to Construct and Perform 05200026/2020004-02 Quality Inspections on the Battery Racks for the Class 1E DC and Uninterruptible Power Supply System (Section 1A15) 38

LIST OF DOCUMENTS REVIEWED Section 1

[2503 Documents]

Section 1A01 VEGP 3&4 UFSAR, Section 5.1.2, Reactor Coolant System and Connected Systems - Design Description, Revision 7 SV3-RCS-ITR-800012, Unit 3 Functional Arrangement Inspection: ITAAC 2.1.02.01 NRC Index Number 12, Revision 2 SV3-RCS-M6-001, Piping and Instrumentation Diagram Reactor Coolant System, Revision 6 SV3-RCS-M6-002, Piping and Instrumentation Diagram Reactor Coolant System, Revision 8 SV3-RCS-M6-003, Piping and Instrumentation Diagram Reactor Coolant System, Revision 4 SV3-PXS-M6-002, Piping and Instrumentation Diagram Passive Core Coolant System, Revision 8 S6V3-CVS-M6-001, Piping and Instrumentation Diagram Chemical and Volume Control System, Revision 6 SV3-RNS-M6-001, Piping and Instrumentation Diagram Normal Residual Heat Removal System, Revision 4 SV3-RCS-M9K-FA001, SV3-Reactor Coolant System (RCS) ITAAC Functional Arrangement Guideline Sketch, Revision 1 SV3-RCS-M6K-FA001, SV3-RCS-M6-001 RCS ITAAC Functional Arrangement Sketch, Revision 1 SV3-RCS-M6K-FA002, SV3-RCS-M6-002 RCS ITAAC Functional Arrangement Sketch, Revision 1 SV3-RCS-M6K-FA003, SV3-RCS-M6-003 RCS ITAAC Functional Arrangement Sketch, Revision 0 SV3-PXS-M6K-FA102, SV3-PXS-M6-002 RCS ITAAC Functional Arrangement Sketch, Revision 1 SV3-CVS-M6K-FA201, SV3-CVS-M6-001 RCS ITAAC Functional Arrangement Sketch, Revision 0 SV3-RNS-M6K-FA201, SV3-RNS-M6-001 RCS ITAAC Functional Arrangement Sketch, Revision 0 Section 1A02 WEC SV3-CVS-GNR-000075, AP1000 Nonconformance and Disposition Report Dents and arc strikes on SV3-CVS-PLW-171 ESR 50064767, (23 pages), Revision 0 S&W SV3-CVS-P0W-1122998, Work Package ASME III - Repair Arc Strikes/Dents/Defects in accordance with N&D SV3-CVS-GNR-000075 for ISOs SV3-CVS-PLW-171 and for SV3-CVS ISOs to Support Cold Hydro, with Special Operations Data Sheets (45 pages), Revision 0 WEC SV3-CVS-PLW-171, Chemical and Volume Control System Containment Building Rooms 11401/11403 CVS Letdown Line, Revision 3 MISTRAS V-20-PT-301-1904, Nondestructive Examination Report Liquid Penetrant Examination, 10/11/2020 MISTRAS V-20-UT-303-0764, Ultrasonic Thickness Survey Report, 10/11/2020 WEC SV3-PXS-GNR-000262, AP1000 Nonconformance and Disposition Report SV3-PXS-PLW-041 Arc Strike - ESR 50048154, (118 pages), Revision 0 39

S&W SV3-PXS-P0W-1106429, Work Package ASME III - Repair Arc Strikes/Defects iaw N&D SV3-PXS-GNR-000262 for ISOs SV3-PXS-PLW-041 and additional SV3-PXS ISOs to Support Cold Hydro, with Special Operations Data Sheets (153 pages), Revision 0 WEC SV3-PXS-PLW-041, Passive Core Cooling System Containment Building Room 11300 PRHR Return Line to SG 01, Revision 2 MISTRAS V-20-PT-301-1996, Nondestructive Examination Report Liquid Penetrant Examination, 10/14/2020 MISTRAS V-20-UT-303-0810, Ultrasonic Thickness Survey Report, 10/15/2020 WEC SV3-RCS-GNR-000174, AP1000 Nonconformance and Disposition Report Inadequate Weld Crown Gap 360 Degrees Around on SV3-RCS-PLW-022 Welds (ESR 50039352), (19 pages), Revision 0 S&W SV3-RCS-P0W-1120695, Work Package ASME III - Perform Weld Crown Modifications for SV3-RCS-PLW-022 and SV3-RCS-PLW-024 in accordance with SV3-RCS-GNR-000174, with Special Operations Data Sheets (38 pages), Revision 0 MISTRAS V-20-PT-301-1690, Nondestructive Examination Report Liquid Penetrant Examination, 09/11/2020 MISTRAS V-20-PT-301-1691, Nondestructive Examination Report Liquid Penetrant Examination, 09/11/2020 WEC SV3-RCS-GNR-000211, AP1000 Nonconformance and Disposition Report SV3-RCS-PLW-03A-FW12 has deleterious conditions: ESR 50054382, (10 pages), Revision 0 S&W SV3-RCS-PLW-1117515, Work Package ASME III - Remove Indications to Support Preservice Inspections iaw ESR 50054382 & N&D SV3-RCS-GNR-000211 for Weld FW12 on ISO SV3-RCS-PLW-03A, with Special Operations Data Sheets (28 pages), Revision 0 WEC SV3-RCS-PLW-03A, Reactor Coolant System Containment Building Room 11301 ADS Stage 4 West Compartment, Revision 2 MISTRAS V-20-UT-303-0731, Ultrasonic Thickness Survey Report, 10/04/2020 MISTRAS V-20-PT-301-1848, Nondestructive Examination Report Liquid Penetrant Examination, 10/05/2020 WEC SV3-RCS-GNR-000251, AP1000 Nonconformance and Disposition Report Indications on SV3-RCS-PLW-820 ESR 50064238, (12 pages), Revision 0 S&W SV3-RCS-P0W-1122798, Work Package ASME III - Remove Indications on ISO SV3-RCS-PLW-820 iaw ESR 50064238 and N&D SV3-RCS-GNR-000251, with Special Operations Data Sheets (29 pages), Revision 0 WEC SV3-RCS-PLW-820, Reactor Coolant System Containment Building Room 11202/11205 I&C Line L173A from CL to FT173, Revision 0 MISTRAS V-20-UT-303-0729, Ultrasonic Thickness Survey Report, 10/04/2020 MISTRAS V-20-PT-301-1844, Nondestructive Examination Report Liquid Penetrant Examination, 10/05/2020 WEC SV3-RCS-GNR-000252, AP1000 Nonconformance and Disposition Report Dents on RCS Lines SV3-RCS-PLW-233 & 236 ESR 50064557, (101 pages), Revision 0 S&W SV3-RCS-P0W-1122892, Work Package ASME III - Repair Arc Strikes/Defects iaw N&D SV3-RCS-GNR-000252 for ISOs SV3-RCS-PLW-233 and for SV3-RCS ISOs to Support Cold Hydro, with Special Operations Data Sheets (124 pages), Revision 0 WEC SV3-RCS-PLW-233, Reactor Coolant System Containment Building Room 11601 Reactor Head Vent Line, Revision 1 WEC SV3-RCS-PLW-236, Reactor Coolant System Containment Building Room 11601 Reactor Head Vent Line, Revision 1 S&W Weld Data Sheet (WDS) SV3-RCS-PLW-571-BMR-1 (also for base metal repair work package SV3-RCS-PLW-1123430), 10/13/2020 S&W SV3-RCS-PLW-1123430, Work Package ASME III - Repair Piping on SV3-RCS-PLW-571 iaw SV3-RCS-GNR-000261. Reference ESR 50065525, Revision 0 40

MISTRAS V-20-PT-301-1933, Nondestructive Examination Report Liquid Penetrant Examination, (for WDS SV3-RCS-PLW-571-BMR-1 with note change from work package SV3-RCS-P0W-1122892), Revision 1, 10/15/2020 MISTRAS V-20-PT-301-1997, Nondestructive Examination Report Liquid Penetrant Examination, (for WDS SV3-RCS-PLW-571-BMR-1), 10/14/2020 MISTRAS V-20-UT-303-0809, Ultrasonic Thickness Survey Report, (for WDS SV3-RCS-PLW-571-BMR-1), 10/14/2020 MISTRAS V-20-RT-302-0905, Computed Radiography Examination Report, (for WDS SV3-RCS-PLW-571-BMR-1), 10/14/2020 WEC SV3-RCS-GNR-000265, AP1000 Nonconformance and Disposition Report Arc Strike on Hot Leg RCS-PL-L001B ESR 50065467, (11 pages), Revision 0 S&W SV3-RCS-PLW-1123295, Work Package ASME III - Remove Arc Strikes on RCS-PLW-L001B Hot Leg Piping iaw SV3-RCS-GNR-000265 and ESR 50065467, with Special Operations Data Sheets (27 pages), Revision 0 MISTRAS V-20-PT-301-2018, Nondestructive Examination Report Liquid Penetrant Examination, 10/16/2020 WEC SV3-PV01-GNR-000034, AP1000 Nonconformance and Disposition Report Arc strike found on the bottom of Valve RCS-PL-V012B (ESR 50064997), (12 pages), Revision 0 S&W SV3-RCS-PLW-1123141, Work Package ASME III - Remove Arc Strikes on Valve SV3-RCS-PL-V012B iaw N&D SV3-PV01-GNR-000034 and ESR 50064997, with Special Operations Data Sheets (27 pages), Revision 0 MISTRAS V-20-PT-301-1936, Nondestructive Examination Report Liquid Penetrant Examination, 10/11/2020 Section 1A03 SV3-RCS-M6-001-R5, Piping and Instrumentation Diagram Reactor Coolant System (including note 21), Revision 5 S&W Work Package SV3-RCS-P0W-1057531, ASME Section III - Install Squib Valve SV3-RCS-PL-V004D & Supports Per ISO SV3-RCS-PLW-03D (102 pages), Revision 0 S&W Valve Installation Data Sheet SV3-RCS-PLW-03D, Install Squib Valve SV3-RCS-PL-V004D, 10/16/2020 S&W Bolted Joint Data Sheet SV3-RCS-PLW-03D-1-BC, Install Squib Valve SV3-RCS-PL-V004D, 10/16/2020 S&W Special Operations Data Sheet SV3-RCS-PLW-03D, Install Squib Valve SV3-RCS-PL-V004D, 10/16/2020 Section 1A04 VEGP 3&4 UFSAR, Section 5.1.2, Reactor Coolant System and Connected Systems - Design Description, Revision?7 American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, 1998 Edition including 2000 Addenda APP-RCS-M6-001, Piping and Instrumentation Diagram Reactor Coolant System, Revision 19 APP-RCS-M6-002, Piping and Instrumentation Diagram Reactor Coolant System, Revision 21 APP-RCS-M6-003, Piping and Instrumentation Diagram Reactor Coolant System, Revision 16 APP-PXS-M6-001, Piping and Instrumentation Diagram Passive Core Cooling System, Revision 12 APP-PXS-M6-002, Piping and Instrumentation Diagram Passive Core Cooling System, Revision 17 41

APP-PXS-M6-003, Piping and Instrumentation Diagram Passive Core Cooling System, Revision 12 APP-RNS-M6-001, Piping and Instrumentation Diagram Normal Residual Heat Rem. System, Revision 13 APP-CVS-M6-001, Piping and Instrumentation Diagram Chemical and Volume Control System, Revision 15 APP-CVS-M6-005, Piping and Instrumentation Diagram Chemical and Volume Control System, Revision 14 3-RCS-ITPP-503, Reactor Coolant System Cold Hydrostatic Test - Preoperational Test Procedure, Revision 5 APP-RCS-T1-501, Reactor Coolant System Preoperational Test Specification, Revision 4 NCSP 03-77, Construction Pressure Testing, Revision 5 SV3-RCS-THW-1013872, ASME III - RCS Cold Hydrotest SV3-TH-H8001A [ASME III Hydrotest of RCS, PXS, CVS &RNS Lines], Revision 0 Section 1A05 2.1.02.12a.i-U3-EQRR-PCD001, Reactor Coolant System (RCS) EQ Reconciliation Report (EQRR), ADS MOV, Revision 0 2.1.02.12a.i-U3-EQRR-PCD002, Reactor Coolant System (RCS) EQ Reconciliation Report (EQRR), ADS ISOLATION MOV, Revision 0 SV3-PV01-VBR-001, WEC Document No. APP-PV01-VBR-001, Equipment Qualification Summary Report for TopWorx C7 GO Switches for Use in AP1000 Plant, Revision 1 SV3-PV01-VBR-002, WEC Document No. APP-PV01-VBR-002, Equipment Qualification Data Package for TopWorx C7 GO Switches for Use in AP1000 Plant, Revision 1 SV3-PV01-VBR-011, WEC Document No. APP-PV01-VBR-011, Equipment Qualification Summary Report for Flowserve Flex Wedge Gate Valves with Limitorque Motor Operators for Use in AP1000 Plant, Revision 2 SV3-PV01-VBR-012, WEC Document No. APP-PV01-VBR-012, Equipment Qualification Data Package for Flowserve Flex Wedge Gate Valves with Limitorque Motor Operators for Use in AP1000 Plant, Revision 2 SV3-PV01-VBR-013, WEC Document No. APP-PV01-VBR-013, Equipment Qualification Summary Report for Flowserve Globe Stop Valves with Limitorque Motor Operators for Use in AP1000 Plant, Revision 2 SV3-PV01-VBR-014, WEC Document No. APP-PV01-VBR-014, Equipment Qualification Data Package for Flowserve Globe Stop Valves with Limitorque Motor Operators for Use in AP1000 Plant, Revision 2 SV3-PV01-Z0D-131, WEC Document No. APP-PV01-Z0D-131, AP1000 Valve Datasheet PV01 Datasheet 131, Revision 6 SV3-PV01-Z0D-132, WEC Document No. APP-PV01-Z0D-132, AP1000 Valve Datasheet PV01 Datasheet 131, Revision 6 SV3-PV01-VMM-002, WEC Document No. SV0-PV01-VMM-002, Instruction Manual for AP1000 PV01 Size 3 and Larger Motor Operated Globe Valves,Section III, Class 1,2 and 3, Revision 1 AP1000 Nonconformance & Disposition Report (N&DR) SV3-PV01-GNR-000026, ADS Valves

- Yoke and Bonnet Configuration (ESR 50052220), Revision 0 N&DR SV3-PV01-GNR-00027, PV01 Bonnet to Valve Body Fit-up Damage 3-RCS-V003A (ESR 50052606), Revision 0 42

Section 1A06 VEGP 3&4 UFSAR, Section 4.5, Reactor Materials, Revision 9 American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, 1998 Edition including 2000 Addenda 3-RCS-ITPP-503, Reactor Coolant System Cold Hydrostatic Test - Preoperational Test Procedure, Revision 5 APP-RCS-T1-501, Reactor Coolant System Preoperational Test Specification, Revision 4 NCSP 03-77, Construction Pressure Testing, Revision 5 SV3-RCS-THW-1013872, ASME III - RCS Cold Hydrotest SV3-RCS-TH-H8001A [ASME III Hydrotest of RCS, PXS, CVS & RNS Lines], Revision 0 Section 1A07 APP-SSAR-F5-001, AP1000 Safety Analysis Checklist, Revision 1 VEGP 3&4 UFSAR, Chapter 4, Reactor, Revision 8 Core Operating Limits Report (COLR) for the Vogtle Electric Generating Plant, Unit 3 Cycle 1, April 2020 2.1.03.13-USPRF, ITAAC 88 Core Design Principal Closure Document, Revision 0 NF-GP-20-085, from Westinghouse to Mr. Rob Szollosy, SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT UNIT 3, Notification of Fabrication of Fuel and ACCAs, 11/24/2020 NF-GP-20-030, VEGP Unit 3 Cycle 1 Core Loading Plan, Revision 0 Section 1A08 SNC Condition Report, Missing results in calculation for penetration P44 and P45 guard pipes, 09/23/20 WEC Engineering & Design Coordination Report (E&DCR) APP-ML10-GEF-046, Updates for Penetrations P44 and P45, Revision 0 WEC Calculation APP-ML10-S3C-001, AP1000 Containment Piping Penetrations with Flued Heads Analysis and Verification, Revision 5 Section 1A09 Condition Report (CR) 50051608, Epoxy Coating on Weld Prevent Solution Film Testing, 5/29/20 CR 5055621, Additional Testing Requirement, 7/11/20 CBIS Power Procedure Qualification Record (PQR) PQ607A, Manual Gas Tungsten Arc Welding (GTAW) and Submerged Arc Welding (SMAW) of P-No. 1 A/SA-4738 Gr. B to P-No.

1 A/SA-516 Gr. 60/70 with ER70S-6/E7018, with PWHT and with Impacts, Revision 2 WEC E&DCR APP-MV50-GEF-403, Welding Joints Preheat Temperatures Updates to APP-MV50-V8-001, Revision 0 PCI Attachment No. 7- Retaining Ring As-Built Dimensions PCI Energy Services Weld Process Traveler 917701-021 FW-05 Threadolet PCI Energy Services Weld Process Traveler 917701-021 FW-03 Pen. Sleeve PCI Energy Services Weld Process Traveler 917701-021 FW-04 Ext. Sleeve PCI Energy Services Weld Process Traveler 917701-021 FW-02 Right Half Joint PCI Energy Services Weld Process Traveler 917701-021 FW-01 Left Half Joint PCI Energy Services Welders Maintenance Log, 9/2/20 PCI Energy Services Calibration Certificate for Light Meter Gage PCI-QLM-43, 11/10/19 43

PCI Energy Services Calibration Certificate for Fluke Digital Thermometer Gage PCI-QTC-738, 3/16/20 SUPERHEAT Wrapping Specification Sheet, 20-inch EPA Collar Weld- Pre-Heat, for Line No.

917701-021, SV3-EY01-V6-001, SV3-1100-P0-909, Weld No. FW-03 PCI Energy Services Purchase Order 450808026 issued to SUPERHEAT, 9/12/20 SUPERHEAT qualification records for heat treat technicians, 7/24/20 CBIS Procedure CMS-830-15-PR-45164, Solution Film Testing Vacuum Box Technique ASME Section III, Division 1, Subsection NE, Revision 1 S&W Form 132175-112-051-AJH8524-00012, Record of Welder Performance Qualification Test - ASME Section IX Groove Weld, for Welder ID AJH8524 S&W Form 132175-112-051-JMB4293-00020, Record of Welder Performance Qualification Test - ASME Section IX Groove Weld, for Welder ID JMB4293 S&W Form 132175-112-051-LVH7308-00002, Record of Welder Performance Qualification Test - ASME Section IX Groove Weld, for Welder ID LVH7308 Lincoln Electric Company Certificate of Conformance for 3/32-Inch X 36-Inch Lincoln ER70S-6 Weld Rods, Lot No. 1093W Lincoln Electric Company Certificate of Conformance for 1/8-Inch Lincoln ER70S-6 Weld Rods, Lot No. 1186G Lincoln Electric Company Certificate of Conformance for 1/8-Inch X 14-Inch Excalibur 7018 MR Electrodes, Lot No. 1231D Certificate of Material Test Report (CMTR) 3-P44-S, Penetration Sleeve (P44), Heat/Lot No.

J0L4527/AF47901 CMTR 3-P45-S, Penetration Sleeve (P45), Heat/Lot No. J0L4527/AF48001 Section 1A10 Reports B-GEN-ITPCE-024, Version 3.0-01, TPC for Schweitzer Engineering Laboratories (SEL) Relay Commissioning, dated: 10/18/2019 ES31 Comparison for Device 710 006 (SEL-710-R407-V0-Z006004-D20111123, dated:

12/16/2020 ES32 Comparison for Device 751A 011 (SEL-751A-R417-Vo-Z011003-D20130329, dated:

12/16/2020 ES61 Comparison for Device 710 006 (SEL-710-R407-V0-Z006004-D20111123, dated:

12/16/2020 Calculations APP-ECS-E0C-015, Relay Coordination & Settings RCP Switchgear - SEL-710, Revision 1 APP-ECS-E0C-006, Relay Coordination and Setting - Medium Voltage Buses, Revision 2 APP-ECS-E0C-007, Low Voltage Switchgear Relay and Setting Calculation, Revision 4 APP-ECS-E0C-016, Verification of Primary and Backup Electrical Protection of Low Voltage Non-Safety Related Power and Control Containment Electrical Penetrations, Revision 3 Drawings APP-IDSB-E3- DK101, One Line Diagram Class 1E 250 V DC MCC IDSB-DK-1 Auxiliary Bldg Sheet 1 of 3, Revision 5 Westinghouse Drawing 1006D75, DK01 DC MCC APP-IDS-DK01, Sheet 12, Revision 2 APP-PSS-E5-PLV81C02, Combined Wiring diagram APP-PSS-PLV Containment Class 1E Solenoid Operated Valve, Sheets 1 through 3, Revision 0 APP-IDSB-E3-DD101, Panel Schedule IDSB-DD-1 250 VDC Distribution Panel Auxiliary Bldg, Revision 5 44

Section 1A11 2.2.01.11a.i-U3-EQRR-PCD001, Containment System (CNS) EQ Reconciliation Report (EQRR), Revision 0 ND-18-1100, Southern Nuclear Operating Company Resubmittal Notice of Uncompleted ITAAC 225 days Prior to Initial Fuel Load Item 2.2.01.11a.i (Index Number 114), Revision 0 SV3-PV11-VBR-005, WEC Document No. APP-PV11-VBR-005, Equipment Qualification Summary for Motor-Operated TRICENTRIC Butterfly Valve for Use in the AP1000 Plant, Revision 2 SV3-PV11-VBR-006, WEC Document No. APP-PV11-VBR-006, Equipment Qualification Data Package for Motor-Operated TRICENTRIC Butterfly Valve for Use in the AP1000 Plant, Revision 3 SV3-GW-VBR-001, WEC Document No. APP-GW-VBR-001, Equipment Qualification Summary Report for TopWorx C7 GO Switches for Use in AP1000 Plant, Revision 1 SV3-GW-VBR-002, WEC Document No. APP-PV01-VBR-002, Equipment Qualification Data Package for TopWorx C7 GO Switches for Use in AP1000 Plant, Revision 1 SV3-PV11-Z0-001, WEC Document No. APP-PV11-Z0-001, Design Specification for Butterfly Valves, ASME Boiler and Pressure Vessel Code Section III, Class 2 and 3, Revision 13 SV3-PV11-Z0D-122, WEC Document No. APP-PV11-Z0D-122, PV11 Datasheet 122, Revision 7 SV3-PV11-Z0D-124, WEC Document No. APP-PV11-Z0D-124, PV11 Datasheet 124, Revision 5 APP-GW-G1-002, AP1000 Equipment Qualification Methodology, Revision 4 APP-GW-G1-002, AP1000 Equipment Qualification Methodology, Revision 5 APP-PV11-GEF-080- Engineering & Design Coordination Report (E&DCR), PV11 Equipment Qualification Documentation Updates for ITAAC Inspection Comments, Revision 0 APP-GW-GEF-1923, Electromagnetic Compatibility Changes to PV01 and PV11 and Grease Changes to PV01, Revision 0 APP-PV11-GEF-85000, Update to APP-PV11-VBR-005, Revision 0 APP-GW-GEF-850303, Increase Conduit Length greater than as-tested length (ESR 50059232), Revision 0 Bechtel Calibration Report No. V-N-0309-4 for Torque Wrench Serial No. DTK69458, Serial No.

V-N-0309, 11/15/19 APP-PV11-VMM-001, Instruction Manual for AP1000 PV11 Tricentric Butterfly Valves, Revision 5 Material Receiving Report No. J132175 for NEVERSEEZNG165NUC-E-EBYN Lubricant, batch No. 201275, 6/7/17 Section 1A12 FW-Nos. SV3-PCS-PLW-010-1 and -2 WEC Piping Isometric Drawing-No. SV3-PCS-PLW-010-R0, Passive Containment Cooling System Auxiliary Building Rooms 12541/12701 Supply Line B to Distribution Bucket, Revision 0

S&W Weld Data Sheets SV3-PCS-PLW-010-1 (inlet side) and -2 for valve PCS-PL-V002B with line-no. PCS-PL-L003B, 10/03/2019 MISTRAS V-20-PT-301-1206, Nondestructive Examination Report Liquid Penetrant Examination, Weld-No. SV3-PCS-PLW-010-1, 07/01/2020 MISTRAS V-20-PT-301-1051, Nondestructive Examination Report Liquid Penetrant Examination, Weld-No. SV3-PCS-PLW-010-2, 06/10/2020 45

FW-Nos. SV3-PCS-PLW-011-3 and -4 WEC Piping Isometric Drawing-No. SV3-PCS-PLW-011-R1, Passive Containment Cooling System Auxiliary Building Rooms 12541/12701 Supply Line A to Distribution Bucket, Revision 1

S&W Weld Data Sheets SV3-PCS-PLW-011-3 (inlet side) and -4 for valve PCS-PL-V002A with line-no. PCS-PL-L003A, 10/03/2019 MISTRAS V-20-PT-301-1203, Nondestructive Examination Report Liquid Penetrant Examination, Weld-No. SV3-PCS-PLW-011-3, 07/01/2020 MISTRAS V-20-PT-301-1050, Nondestructive Examination Report Liquid Penetrant Examination, Weld-No. SV3-PCS-PLW-011-4, 06/10/2020 FW-Nos. SV3-PCS-PLW-013-4 and -5 WEC Piping Isometric Drawing-No. SV3-PCS-PLW-013-R0, Passive Containment Cooling System Auxiliary Building Room 12701 Supply Line to Distribution Bucket, Revision 0 S&W Weld Data Sheets SV3-PCS-PLW-013-4 and -5 (inlet side) for valve PCS-PL-V001C with line-no. PCS-PL-L005, 10/03/2019 FW-Nos. SV3-PCS-PLW-014-5 and -013-6 WEC Piping Isometric Drawing-No. SV3-PCS-PLW-013-R0, Passive Containment Cooling System Auxiliary Building Room 12701 Supply Line to Distribution Bucket, Revision 0 WEC Piping Isometric Drawing-No. SV3-PCS-PLW-014-R0, Passive Containment Cooling System Auxiliary Building Room 12701 Supply Line to Distribution Bucket (Common Header),

Revision 0 S&W Weld Data Sheets SV3-PCS-PLW-014-5 (inlet side) and 013-6 (bull-end of tee fitting) for valve PCS-PL-V002C to bull-end of 6 by 6 tee fitting with line-no. PCS-PL-L002, 9/24/2019 and 10/3/2019 MISTRAS V-20-PT-301-1043, Nondestructive Examination Report Liquid Penetrant Examination, Weld-No. SV3-PCS-PLW-014-5, 06/11/2020 MISTRAS V-20-PT-301-1204, Nondestructive Examination Report Liquid Penetrant Examination, Weld-No. SV3-PCS-PLW-013-6, 01/01/2020 Lincoln Electric Certified Material Test Report (CMTR) 4974203 for 1/16 by 18 ER308/308L with heat-no. 1030L, 12/01/2011 Lincoln Electric Certified Material Test Report (CMTR) 9907887 for 1/8 by 18 ER308/308L with heat-no. 1408D, 04/24/2019 S&W Record of Welder Performance Qualification Test - ASME Section IX, Test-No. 1CS-02 for welder DAD, 01/14/2020 S&W Record of Welder Performance Qualification Test - ASME Section IX, Test-No. 1SS-02 for welder JMB, 04/12/2018 S&W Record of Welder Performance Qualification Test - ASME Section IX, Test-No. 1CS-02 for welder MLF, 05/30/2019 Section 1A13 S&W Work Package SV3-PXS-P0W-1057547, ASME Section III - Install Squib Valve SV3-PXS-PL-V125B & Supports Per ISO SV3-PXS-PLW-02U (48 pages), Revision 0 S&W Valve Installation Data Sheet SV3-PXS-PLW-02U, Install Squib Valve SV3-PXS-PL-V125B, 10/14/2020 S&W Bolted Joint Data Sheet SV3-PXS-PLW-02U-1-BC, Install Squib Valve SV3-PXS-PL-V125B, (inlet side), 10/14/2020 S&W Bolted Joint Data Sheet SV3-PXS-PLW-02U-1-BC, Install Squib Valve SV3-PXS-PL-V125B, (outlet side), 10/14/2020 46

S&W Special Operations Data Sheet SV3-RCS-PLW-02U, Install Squib Valve SV3-PXS-PL-V125B, 10/14/2020 Section 1A14 SV3-PXS-PHW-ME3359, Fabrication/Installation of Pipe Supports for Isometric SV3-PXS-PLW-01H, Revision 0 Weld Data Sheet WCP-1 for Weld no. SV3-PXS-PH-11Y2059-1, Revision 0 WEC Nonconformance & Disposition Report (N&DR) No. SV3-PXS-GNR-000196, SV3-PXS-11Y2052 Pin to Pin (ESR 50034584), Revision 0 WEC N&DR no. SV3-PXS-GNR-001225, Pipe Support SV3-PXS-11Y2057 Out of Tolerance Attaching to OLP 04-017, Revision 0 SV3-PXS-PH-11Y2059, Pipe Support Drawing PXS System PXS-PH-11Y2059, Revision 1 SV3-PXS-PLW-01H, Passive Core Cooling System Containment Bldg. Room 11206 Containment Recirc. To DVI-A, Revision 2 SV3-PXS-PHK-ME6342, Weld Map for Support SV3-PXS-PH-11Y2059, Revision 0 Section 1A15 Work Order Packages SV3-IDS-DBW-860173 SV3-IDS-DBW-860174 Specifications SV3-G1-V8-001 AP1000 Electrical Installation Specification, Revision 7 APP-DB01-Z0-001 Design Specification for Class 1E 250 VDC Batteries and Racks, Revision 9

Procedures 26139-000-4MP-T81C-N3301 Electrical Equipment Installation, Revision 3 26139-000-2QI-Q07C-N3301 Quality Control Instruction, Revision 1 SV3-DB01-V8M-001, AP1000 Class 1E 250 VDC Battery Assembly Drawings: Instruction for Assembling 1E Racks, Revision 0 Drawings SV3-DB01-V2-001 AP1000 Class 1E 250 VDC Battery System Assembly Drawings: Two Step Rack Assembly Drawing High Seismic - 132 for Type G Batteries, Revision 0 SV3-ECS-E9-101, Conduit Notes and Support Details, Revision 1 Design Documents SV3-DB01-VBR-001 Equipment Qualification Summary Report for Class 1E 250 VDC Batteries for Use in the AP1000 Plant, Revision 2 APP-DB01-VBR-002 Equipment Qualification Data Package for Class 1E 250 VDC Batteries for Use in the AP1000 Plant, Revision 0 Engineering & Design Coordination Report (E&DCR) APP-ECS-GEF-850659, Allow Re-Use of Structural Bolts Associated to Electrical Commodities (ESR 50027545), Revision 0 Inspection Reports Battery Rack Inspection 20200605 Final Battery Rack Torque Check 20200622 Final 47

Engineering Service Requests (ESRs)

ESR 50053212 ESR 50057274 Condition Reports (CRs)

CR 50049527 CR 50054000 CR 50049527 CR 50054000 CR 50057411 CR 50058215 CR 50062315 CR 50062981 CR 50064326 Engineering Evaluation SVP-SV0-006012, Battery Rack Nonconformance Structural Safety Evaluation SVP-SV0-006099, Battery Rack Nonconformance Structural Safety Evaluation - Updated Based on Completed Extent of Condition Work Nonconformance & Disposition (N&D) Reports SV3-IDSB-GNR-000002 Quality Surveillances Quality Surveillance 26193-000-GQA-QSSS-20160, Unit 3 Safety Related Battery Rack Configuration, Revision 0 Section 1A16 Miscellaneous SV3-1010-GCR-001, Vogtle Unit #3 As-Built Summary Report: Nuclear Island Basemat, Revision 1 SV3-1100-GCR-001, Vogtle Unit #3 As-Built Summary Report: Containment Internal Structures and Modules, Revision 1 Section 1A17 Drawings SV3-1260-CD-567-R2, AUXILIARY BUILDING AREA 6 ROOF LEVEL METAL DECK PLAN BETWEEN COLS J-2 & N SV3-1260-CR-560-R1, AUXILIARY BUILDING AREAS 5 & 6 CONCRETE REINFORCEMENT FLOOR EL 180-0 TO 190-9 PLAN VIEW SV3-1260-CR-586-R0, AUXILIARY BUILDING AREAS 5 & 6 CONCRETE REINFORCEMENT FLOOR EL 180-0 TO 190-9 SECTIONS (SHEET 2 SV3-1266-CC-606-R1, AUXILIARY BUILDING CONCRETE OUTLINE AREA 6 ROOF ELEVATION Shop Drawings SV3-CR01-C8-801237-R0, A6 - ROOF SLAB @180 AREA 5&6, REVISION 0 SV3-CR01-C8-801238-R0, A6 - ROOF SLAB @180 AREA 5&6, REVISION 0 SV3-CR01-C8-801239-R0, A6 - ROOF SLAB @180 AREA 5&6, REVISION 0 48

E&DCRs APP-1208-GEF-320, Shield Building - SC panel connection to Aux Building Roof Area 6, Revision 0 APP-1208-GEF-328, Shield Building SC Panels - Clarification on Area 6 Wall N Connection Drawings, Revision 0 APP-1208-GEF-850124, Shield Building Panel 09E and Roof Connection Access, Revision 0 APP-1260-GEF-850026, Area 5&5 Roof REINF Corrections (ESR 50017580), Revision 0 SV0-CR01-GEF-001259, NI3 Wall 4 connection to Area 6 roof slab @ the (Wedge) area El.

180-0 (ESR 50039460), Revision 0 N&Ds SV3-CR01-GNR-001084, Wall N EL. 155-0 ~ 180-9 from CL 1 to CL 4, Rebar Fabrication &

Installation (ESR 50022850), Revision 0 SV3-12562-GNR-000001, 180-0 Elev. Roof Slab, Areas 5&6 (Repair Fab & Installation),

Revision 0 Specifications Westinghouse Specification, SV3-CR01-Z0-010, Specification for Supply and Installation of Mechanical Splices for Reinforcing Steel, Revision, Revision 8 Westinghouse Specification, SV3-CC01-Z0-011, Furnishing of Safety Related Reinforcing Steel, Westinghouse Class C Nuclear Safety Related, Revision 4 Bechtel Project Procedure, 26139-000-4MP-T81C-N3210-CPM1F2, Concrete Operations, Revision 1 Bechtel Project Procedure, 26139-000-4MP-T81C-N3223, Reinforcing Bar Mechanical Splicing, Revision 4 Miscellaneous 26139-SV4-QS-20-0559-000, Mechanical Splicer Qualification Record, CW0478 26139-SV4-QS-20-0558-000, Mechanical Splicer Qualification Record, CW0478 26139-SV0-QS-20-0596-000, Mechanical Splicer Qualification Record, DJ1686 26139-SV0-QS-20-0597-000, Mechanical Splicer Qualification Record, DJ1686 26139-SV0-QS-20-0608-000, Mechanical Splicer Qualification Record, FA1488 26139-SV0-QS-20-0609-000, Mechanical Splicer Qualification Record, FA1488 26139-SV0-QS-20-0606-000, Mechanical Splicer Qualification Record, JC2096 26139-SV0-QS-20-0607-000, Mechanical Splicer Qualification Record, JC2096 26139-SV3-QS-20-0544-000, Mechanical Splicer Qualification Record, ON9551 26139-SV3-QS-20-0545-000, Mechanical Splicer Qualification Record, ON9551 26139-SV3-QS-20-0499-000, Mechanical Splicer Qualification Record, SS4539 26139-SV3-QS-20-0500-000, Mechanical Splicer Qualification Record, SS4539 WP: SV3-1260-CRW-1017574, IR: 26139-SV3-IR-C0-01063, Attachment B, Concrete Pre-Placement Inspection Record WP: SV3-1260-CCW-1017578, IR: 26139-SV3-IR-C0-01227, Attachment G, Concrete Placement/ Order Pour Card WP: SV3-1260-CRW-1017574, IR: 26139-SV3-IR-FF-00321, Attachment L, Reinforcing Steel Bar Fabrication Inspection Record WP: SV3-1260-CRW-1017574, IR: 26139-SV3-IR-FF-C0-00321, Attachment K, Inspection Record for Reinforcing Steel Bar Fabrication Request WP: SV3-1260-CRW-1017574, IR: 26139-SV3-IR-C0-01064, Attachment E, Tapered, Threaded Bar Inspection Record WP: SV3-1260-CRW-1017574, IR: 26139-SV3-IR-C0-01064, Attachment E1, Continuation Sheet, Tapered, Threaded Bar Inspection Record 49

WP: SV3-1260-CRW-1017574, IR: 26139-SV3-IR-C0-01065, Attachment F, Tapered, Threaded Headed Bar Assemblies, Terminators, and Welded Couplers Inspection Record WP: SV3-1260-CRW-1017574, IR: 26139-SV3-IR-C0-01065, Attachment F2, Continuation Sheet, Tapered, Threaded Headed Bar Assemblies, Terminators, and Welded Couplers Inspection Record Section 1A18 SNC document no. ND-19-1262, Southern Nuclear Operating Company Notice of Uncompleted ITAAC 225 Days Prior to Initial Fuel Load Item 3.3.00.02b [Index No. 770], Revision 0, 10/28/20 SNC Principal Closure Document SV3-0000-ITR-800770, ITTAC Technical Report Unit 3 of the As-Built Grade: ITAAC 3.3.00.02b, NRC Index Number 770, Revision 0 CR 50065332, Pre-Cast Lid for DI-NI-27 Damaged, 10/8/20 SV-0000-SG-800009, Vogtle Electric Generating Plant Power Block Grading Plan, Revision 2 SV0-0000-GEF-000243, Power Block Grading Plan Revisions, Revision 0 26139-000-4MP-781C-N3201, Construction Survey, Revision 5 Bechtel Personnel Qualification Record for Vogtle 3 & 4 Survey Signature Log for Trimble SPS930 Total Station Manual Review, 11/1/19 Instrument Collimation Report for Job # T27 Collimation 10-12-20 GA, using Trimble Model#

SPS 930, Serial# 72616396, 10/12/20 Instrument Collimation Report for Job # T28 Collimation 10-2-20 GA, using Trimble Model# SPS 930, Serial# 72616393, 10/2/20 Bechtel Site Baseline Instrument Check Sheet S9 SN72631420 - EDM Verification of Trimble Model No. SPS 930 Serial# 72631420, 9/23/20 Bechtel Site Baseline Instrument Check Sheet SN72616393 083120 - EDM Verification of Trimble Model No. SPS 930 Serial# 72616393, 8/31/20 Bechtel Site Baseline Instrument Check Sheet SN72616396 SPS930 - EDM Verification of Trimble Model No. SPS 930 Serial# 72616396, 7/15/20 Certificate of Calibration for Trimble Model # SPS930, Serial# 72631420, certified on 9/21/20 Certificate of Calibration for Trimble Model # SPS930, Serial# 72616393, certified on 8/27/20 Certificate of Calibration for Trimble Model # SPS930, Serial# 72616396, certified on 12/17/19 Section 1A19 SV3-110-ITR-800776, Unit 3 Containment Flooding Volume Inspection, ITAAC 3.3.00.02h, NRC Index no. 776, Revision 0 SV3-PXS-M3C-033, Vogtle Unit 3 As-Built Containment Flood-Up Volume Calculation, Revision 0 SV3-MV01-V1-001, AP1000 Reactor Vessel Outline Elevation, Revision 0 SV3-MB01-V1-001, AP1000 Steam Generator Outline, Revision 0 SV3-MP01-V2-001, AP1000 Reactor Coolant Pump Volume, Revision 1 SV3-MV01-VQQ-001, Reactor Vessel Assembly QAPD, Revision 4 SV3-PL01-VQQ-002, AP1000 Reactor Coolant Loop Hot and Cold Leg QADP, Revision 0 SV3-PL01-V2-003, Primary Coolant Outline S/G and PRZ Compartments, Revision 0 SV3-MT3J-VQQ-001, Reactor Coolant Drain Tank QADP, Revision 1 SV3-MT3J-V0-001, General Arrangement of MT3J Reactor Coolant Drum Tank Envelope Dimensions, Revision 0 SV3-MB01-VQQ-003P1P3, Vogtle #3B Steam Generator QADP, Revision 5 SV3-1120-CC-341, Containment/Shield Building Concrete Floor @ El. 80-0 Areas 3 & 4, Revision 3 50

SV3-1120-CC-343, Containment/Shield Building Concrete Floor @ El. 96-6 Areas 3 & 4, Revision 1 Bechtel EDM Verification Checklist for Trimble serial# 38310203, model S9, 11/17/20 Bechtel EDM verification checklist for Trimble serial# 38320028, model S9, 11/17/20 Certificate of Calibration for Scanner ID# BS-SCHSX-04104210, 5/23/20 Section 1A20 Principal Closure Document 3.3.00.07e-U3-CAR-PCD, Cable Analysis Report for Vogtle Unit 3 ITAAC 3.3.00.07e (COL#

812), dated: 12/12/2020 Drawings APP-1231-ER-001, Auxiliary Building Area 1 Class 1E Cable Tray Arrangement Plan at Elevation 100-0, Revision 12.

APP-1231-ER-105, Auxiliary Building Area 1 Class 1E Conduit Arrangement at Elevation 100-0 Room 12304 (Partial) Revision 7 APP-1231-ER-106, Auxiliary Building Area 1 Class 1E Conduit Arrangement at Elevation 100-0 Room 12304 & 12300 (Partial) Revision 7 APP-1231-ER-110, Auxiliary Building Area 1 Class 1E Conduit Arrangement at Elevation 100-0 Sections and Details Revision 3 APP-1232-ER-105, Auxiliary Building Area 2 Class 1E Conduit Arrangement at Elevation 100-0 Room 12301 Revision 6 APP-1222-ER-101, Auxiliary Building Area 2 Class 1E Conduit Arrangement at Elevation 82-6 Revision 18 APP-1221-ER-101, Auxiliary Building Area 1 Class 1E Conduit Arrangement at Elevation 82-6 Revision 15 Pull Tickets SV3-PMS-EW-JDBCCA0101DZA, Cable Pull Ticket, Revision 0 SV3-PMS-EW-JDBCCA0101EZA, Cable Pull Ticket, Revision 0 SV3-PMS-EW-JDBCCA0201DZA, Cable Pull Ticket, Revision 0 SV3-PMS-EW-JDBCCA0201EZA, Cable Pull Ticket, Revision 0 SV3-PMS-EW-JDBCCC0101CZC, Cable Pull Ticket, Revision 0 SV3-PMS-EW-JDBCCC0201BZC, Cable Pull Ticket, Revision 0 SV3-PMS-EW-JDBCCC0201CZC, Cable Pull Ticket, Revision 0 SV3-PMS-EW-JDBCCB0101BZB, Cable Pull Ticket, Revision 0 SV3-PMS-EW-JDBCCB0101CZB, Cable Pull Ticket, Revision 0 SV3-PMS-EW-JDBCCB0101DZB, Cable Pull Ticket, Revision 0 SV3-PMS-EW-JDBCCB0101EZB, Cable Pull Ticket, Revision 0 SV3-PMS-EW-JDBCCD0101BZD, Cable Pull Ticket, Revision 0 SV3-PMS-EW-JDBCCD0101CZD, Cable Pull Ticket, Revision 0 SV3-PMS-EW-JDBCCD0101DZD, Cable Pull Ticket, Revision 0 SV3-PMS-EW-JDBCCD0101EZD, Cable Pull Ticket, Revision 0 Inspection Records SV3-PMS-EWW-1061477 / 26139-000-4MP-T81C-N3303 Version 6, Cable Installation Inspection Record, dated: 10/13/2020 SV3-PMS-EWW-1055329, Fiber Optics Terminations Inspection Record, dated: 11/15/2020 SV3-PMS-EWW-1054911, Fiber Optics Terminations Inspection Record, dated: 11/13/2020 SV3-PMS-EWW-1061477, Fiber Optics Terminations Inspection Record, dated: 9/24/2020 51

SV3-PMS-EWW-1061534, Fiber Optics Terminations Inspection Record, dated: 10/23/2020 Section 1A21 SV0-0030-ITR-800000, Vogtle Units 3 & 4 Validation of RT & SS Survey Tools, Revision 1 SV3-1200-ITR-801819, Unit 3 Seismic Gap Verification Wall 140 Along Column Line 11 from Just West of I to L, Elevation 135-3 to 155-6, Revision 0 SV3-1200-ITR-819000, Unit 3 Seismic Gap Verification Wall 70 & 117, Along Column Line 11 from Just West of I to L, Elevation 100-0 to 135-3, Revision 1 SV3-1260-ITR-800819, Unit 3 Seismic Gap Verification Auxiliary Building Roof ITAAC#

3.3.00.13 (NRC# 819), Revision 0 SV3-2000-ITR-800819, Unit 3 Seismic Gap Verification Auxiliary & Turbine Building Roof ITAAC# 3.3.00.13 (NRC# 819), Revision 0 SV3-4030-ITR-800819, Unit 3 Seismic Gap Verification Auxiliary & Annex Building, Elevation 100-00 ITAAC# 3.3.00.13 (NRC# 819), Revision 0 SV3-4040-ITR-800819, Unit 3 Seismic Gap Verification Auxiliary & Annex Building, Elevation 117-6 ITAAC# 3.3.00.13 (NRC# 819), Revision 0 SV3-4050-ITR-800819, Unit 3 Seismic Gap Verification Auxiliary & Annex Building, Elevation 135-3 ITAAC# 3.3.00.13 (NRC# 819), Revision 0 Survey Data File 1190553 3-31-20 AT Survey Data File SWR 1191897 REPORT Survey Data File 1208894 6-17-20 AT Survey Data File SWR 1208894 6-17-20 AT U3 UIN ND-19-0499, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.3.00.13 [Index Number 819], dated May 10, 2019 U3 ND-20-1335ITAAC, Closure Notification on Completion of ITAAC 3.3.00.13 [Index Number 819], dated November 20, 2020 Section 1A22 Specifications SV4-CC01-Z0-031, Safety Related Placing Concrete and Reinforcing Steel, Revision 8 SV4-CC01-Z0-027, Safety Related Concrete Testing Services, Westinghouse Seismic Category I, Safety Class C NUCLEAR SAFETY, Revision 7 Miscellaneous Unit 4 Nuclear Island Shield Building Air Inlet/ Tension Ring Panel TR06 Concrete Placement, Revision 0 Concrete/Grout Delivery Ticket No. 58752, Pour #6425, Load #1, Date 11/04/2020 Concrete/Grout Delivery Ticket No. 58761, Pour #6425, Load #6, Date 11/04/2020 Section 1A23 Drawings:

231123-000-SP-01-000201 Drawing 2, Sheet 1, Orientation Framing Plan 1, AP1000, 145 Dia Shield Building Roof WECTEC Global Project Services Inc. Southern Company (Plant Vogtle)

Unit 3 & 4 - Waynesboro, GA, Revision 1 231123-000-SP-01-000401 Drawing 2, Sheet 1, Compression Ring Assembly, AP1000, 145 Dia Shield Building Roof WECTEC Global Project Services Inc. Southern Company (Plant Vogtle) Unit 3 & 4 - Waynesboro, GA, Revision 0 52

CBIS Weld Records:

Weld Traveler U4-Roof-RoofBlocks-Welds, Weld Roof Block to Compression Ring Assemblies, G4-R01 thru G4-R16 (top flange, web, and bottom flange) with Spreadsheets for Welds-R01 (Joint IDs R01/C01-G02-TF,-W,-BF and -G03-TF,-W,-BF) for Sequences 2A (sheet 2), 4A (sheet 6), 6A (sheet 9), 8 thru 11 (sheet 12 thru 15); and Weld-R02 Sequences 1 (sheet 1), 2A (sheet 2), 4A (sheet 6), 6A (sheet 9), 9 (sheet 13), 10 (sheet 14), Revision 2 Weld Traveler U4-Roof-RoofBlocks-Welds, Weld Roof Block to Compression Ring Assemblies, G4-R01 thru G4-R16 (top flange, web, and bottom flange) with Spreadsheets for Welds-R02 (Joint IDs R02/C02-G04-TF,-W,-BF and -G05-TF,-W,-BF) for Sequences 1 (sheet 1), 2A (sheet 2), 4A (sheet 6), 6A (sheet 9), 9 (sheet 13), 10 (sheet 14), Revision 2 Weld Traveler U4-Roof-RoofBlock-CrossBeam-Welds R17D [Joint IDs R17D/R01-G02-TF (top flange) and -BF (bottom flange)] and R17D-L/R01-G02-W (web) and R17D-L/R17D-W with Spreadsheets for Sequences 2A (sheet 3), 4A (sheet 6), 6A (sheet 9), and 8 thru 11 (sheets 12 thru 15), Revision 1 Traveler for bolting of the U4-Roof-CompRing-Bolting M06-M23 sliding joint with Spreadsheets used at the G4-M23 bolt-up location, 03/04/2020 E&DCRs:

SV0-1278-GEF-000003, Shield Building Roof Proposed Built-up Beam Modification, Revision 0

SV0-1278-GEF-000027, Reduction of overlap in connection of plates between Tension Ring and Conical Roof (ESR 50036413), Revision 0 SV4-1278-GEF-000002, Conical Roof Potential Interferences with the Tension Ring (ESR 50057397), Revision 0 SV4-1278-GEF-850071, Conical Roof to Tension Ring Welded Connection Changes, Revision 0

APP-ML05-GEF-850064, Penetration Outer Sleeve Material Substitution, Revision 0 Section 1A24 Miscellaneous Weld Travelers for Assembly of Tension Ring Modules TR09 to AI, TR06 to TR07, TR08 to TR09, and TR09 to TR10.

Welding Procedure Specification 181816-000-WS-SP-E8018, Revision 3 Certificate of Conformance and Certified Material Test Report, 3/16 Excalibur 8018-C1 MR 50EO, Q3 Lot 1419H Welder Performance Qualification Record for Welder ID AG1409 Welder Performance Qualification Record for Welder ID JAF1424 Welder Performance Qualification Record for Welder ID NGH3904 Welder Performance Qualification Record for Welder ID TLA9009 Section 1A25 Specifications SV4-CC01-Z0-031, Safety Related Placing Concrete and Reinforcing Steel, Revision 8 SV4-CC01-Z0-027, Safety Related Concrete Testing Services, Westinghouse Seismic Category I, Safety Class C NUCLEAR SAFETY, Revision 7 Bechtel Project Procedure, 26139-000-4MP-T81C-N3210-CPM1F2, Concrete Operations, Revision 1 53

Miscellaneous WP: SV4-1251-C0W-1015504, IR: 26139-SV4-IR-C0-01228, Attachment B, Concrete Pre-Placement Inspection Record WP: SV4-1251-C0W-1015504, IR: 26139-SV4-IR-C0-01229, Attachment G, Concrete Placement/ Order Pour Card WP: SV4-1251-C0W-1010965, IR: IR: 26139-SV4-IR-C0-01138, Attachment B, Concrete Pre-Placement Inspection Record WP: SV4-1251-C0W-1010965, IR: 26139-SV4-IR-C0-01139, Attachment G, Concrete Placement/ Order Pour Card Concrete/Grout Delivery Ticket No. 83307, Pour #6048, Load #1, Date 10/03/2020 Concrete/Grout Delivery Ticket No. 83321, Pour #6048, Load #11, Date 10/03/2020 Section 1A26 Specifications SV4-CC01-Z0-031, Safety Related Placing Concrete and Reinforcing Steel, Revision 8 Drawings SV4-1260-CR-995-R0, AUXILIARY BUILDING AREAS 1&2 CONCRETE REINFORCEMENT ROOF SECTIONS & DETAILS SHEET 10 SV4-1262-CR-206, AUXILIARY BUILDING AREA 2 CONCRETE REINFORCEMENT FLOOR EL. 153-0 TO 155-6 PLAN VIEW, REVISION 1.

SV4-1262-CR-216-R0, AUXILIARY BUILDING AREA 2 CONCRETE REINFORCEMENT FLOOR EL. 153-0 TO 155-6 DETAILS (SHEET 1)

SV4-1262-CR-226-R1, AUXILIARY BUILDING AREA 2 CONCRETE REINFORCEMENT FLOOR EL. 153-0 TO 155-6 DETAILS (SHEET 2)

SV4-1262-CR-236-R0, AUXILIARY BUILDING AREA 2 CONCRETE REINFORCEMENT FLOOR EL. 153-0 TO 155-6 SECTIONS Engineering and Design Coordination Reports APP-1262-GEF-005, Roof Area 2. Concrete Structure Drawings Revision. Revision 0 SV0-CR01-GEF-001204, North Face Shield Wall 7.3 Connection Slab Reinforcement (ESR 50015802), Revision 0 Section 1A27 Specifications SV4-CC01-Z0-031, Safety Related Placing Concrete and Reinforcing Steel, Rev.8 SV4-CC01-Z0-027, Safety Related Concrete Testing Services, Westinghouse Seismic Category I, Safety Class C NUCLEAR SAFETY, Revision 7 Bechtel Project Procedure, 26139-000-4MP-T81C-N3210-CPM1F2, Concrete Operations, Revision 1 Miscellaneous WP: SV4-1266-C0W-1038221, IR: 26139-SV4-IR-C0-01181, Attachment B, Concrete Pre-Placement Inspection Record WP: SV4-1266-C0W-1038221, IR: 26139-SV4-IR-C0-01182, Attachment G, Concrete Placement/ Order Pour Card Concrete/Grout Delivery Ticket No. 83292, Pour #6318, Load #1, Date 10/02/2020 Concrete/Grout Delivery Ticket No. 83304, Pour #6318, Load #11, Date 10/02/2020 54

[2504 Documents]

Section 1P01 APP-GW-GAP-420, Engineering and Design Coordination Reports, Revision 20 APP-GW-GAP-428, Nonconformance and Disposition Report, Revision 17 ND-AD-002, Nuclear Development Program Corrective Action Program, Revision 7.0 ND-AD-002-025, Issue Identification, Screening, and Dispatching, Revision 4.0 ND-AD-002-026, Corrective Action Program Processing, Revision 4.0 ND-AD-002-027, Nonconforming Items, Revision 8.0 55

LIST OF ACRONYMS ACI American Concrete Institute ADS Automatic Depressurization System ANI Authorized Nuclear Inspector ASME American Society of Mechanical Engineers CAP Corrective Action Program CBIS Chicago Bridge and Iron Services CFR Code of Federal Regulations CLB Current Licensing Basis CMTR Certified Material Test Report CNS containment system COL Combined License COLR Core Operating Limits Report CR Condition Report E&DCR Engineering & Design Coordination Report EPA Electrical Penetration Assemblies EQDP Equipment Qualification Data Package EQRR Equipment Qualification Reconciliation Report EQSR Equipment Qualification Summary Report ESR Engineering Service Request FW Field Weld IDS Class 1E DC and Uninterruptible Power Supply System IMC Inspection Manual Chapter IP Inspection Procedure ITAAC Inspections, Tests, Analyses, and Inspection Criteria MOV Motor Operated Valve N&D Nonconformance and Disposition Report NCV Non-Cited Violation NDE Nondestructive Examination NRC Nuclear Regulatory Commission PCD Principal Closure Document PCI PCI Energy Services PCS Passive Containment Cooling System PMS Protection and Safety Monitoring System PRHR HX Passive Residual Heat Removal Heat Exchanger PT Liquid Penetrant Examination PXS Passive Core Cooling System QA Quality Assurance QC Quality Control RCCA Rod Cluster Control Assembly RCS Reactor Coolant System RT Radiographic Examination RXS Reactor System SB Shield Building SEL Schweitzer Engineering Laboratories SSC Structures, Systems, and Component S&W Stone and Webster UFSAR Updated Final Safety Analysis Report 56

URI Unresolved Item VEGP Vogtle Electric Generating Plant WDS Weld Data Sheet WEC Westinghouse Electric Company 57

ITAAC INSPECTED No. ITAAC No. Design Commitment Inspections, Tests, Acceptance Criteria Analysis 12 2.1.02.01 1. The functional Inspection of the as- The as-built RCS arrangement of the built system will be conforms with the RCS is as described performed. functional in the Design arrangement Description of this described in the Section 2.1.2. Design Description of this Section 2.1.2.

58

13 2.1.02.02a 2.a) The components Inspection will be The ASME Code identified in Table conducted of the as- Section III design 2.1.2-1 as ASME built components and reports exist for the Code Section III are piping as documented as-built components designed and in the ASME design and piping identified constructed in reports. Inspection of in Tables 2.1.21 and accordance with the as-built pressure 2.1.22 as ASME ASME Code Section boundary welds will Code Section III. A III requirements. 2.b) be performed in report exists and The piping identified accordance with the concludes that the in Table 2.1.2-2 as ASME Code Section ASME Code Section ASME Code Section III. A hydrostatic test III requirements are III is designed and will be performed on met for non-constructed in the components and destructive accordance with piping required by the examination of ASME Code Section ASME Code Section pressure boundary III requirements. 3.a) III to be hydrostatically welds. A report exists Pressure boundary tested. Inspection will and concludes that welds in components be performed for the the results of the identified in Table existence of a report hydrostatic test of the 2.1.21 as ASME verifying that the as- components and Code Section III meet built piping meets the piping identified in ASME Code Section requirements for Table 2.1.21 and III requirements. 3.b) functional capability. Table 2.1.22 as Pressure boundary Inspection will be ASME Code Section welds in piping performed for the III conform with the identified in Table existence of an LBB requirements of the 2.1.2-2 as ASME evaluation report or ASME Code Section Code Section III meet an evaluation report III. A report exists ASME Code Section on the protection from and concludes that III requirements. 4.a) dynamic effects of a each of the as-built The components pipe break. Section lines identified in identified in Table 3.3, Nuclear Island Table 2.1.2-2 for 2.1.2-1 as ASME Buildings, contains which functional Code Section III retain the design capability is required their pressure descriptions and meets the boundary integrity at inspections, tests, requirements for their design pressure. analyses, and functional capability.

4.b) The piping acceptance criteria for An LBB evaluation identified in Table protection from the report exists and 2.1.2-2 as ASME dynamic effects of concludes that the Code Section III pipe rupture. LBB acceptance retains its pressure criteria are met by the boundary integrity at as-built RCS piping its design pressure. and piping materials, 5.b) Each of the lines or a pipe break identified in Table evaluation report 2.1.2-2 for which exists and concludes functional capability is that protection from required is designed the dynamic effects of to withstand combined 59

No. ITAAC No. Design Commitment Inspections, Tests, Acceptance Criteria Analysis normal and seismic a line break is design basis loads provided.

without a loss of its functional capability.

6. Each of the as-built lines identified in Table 2.1.2-2 as designed for LBB meets the LBB criteria, or an evaluation is performed of the protection from the dynamic effects of a rupture of the line.

53 2.1.02.12a.i 12.a) The automatic i) Tests or type tests i) A test report exists depressurization of motor-operated and concludes that valves identified in valves will be each motor-operated Table 2.1.2-1 perform performed that valve changes an active safety- demonstrate the position as indicated related function to capability of the valve in Table 2.1.2-1 under change position as to operate under its design conditions. ii) indicated in the table. design conditions. ii) A report exists and Inspection will be concludes that the as-performed for the built motor-operated existence of a report valves are bounded verifying that the as- by the tests or type built motor-operated tests.

valves are bounded by the tests or type tests.

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No. ITAAC No. Design Commitment Inspections, Tests, Acceptance Criteria Analysis 72 2.1.03.03 3. The components Inspection will be The ASME Code identified in Table conducted of the as- Section III design 2.1.3-1 as ASME built components as reports exist for the Code Section III are documented in the as-built components designed and ASME design reports. identified in Table constructed in Inspection of as-built 2.1.3-1 as ASME accordance with pressure boundary Code Section III. A ASME Code Section welds will be report exists and III requirements. 4. performed in concludes that the Pressure boundary accordance with the ASME Code Section welds in components ASME Code Section III requirements are identified in Table III. A hydrostatic test met for non-2.1.3-1 as ASME will be performed on destructive Code Section III meet the components of the examination of ASME Code Section RXS required by the pressure boundary III requirements. 5. ASME Code Section welds. A report exists The pressure III to be hydrostatically and concludes that boundary components tested. the results of the (RV, CRDMs, and hydrostatic test of the incore instrument pressure boundary QuickLoc assemblies) components (RV, identified in Table CRDMs, and incore 2.1.3-1 as ASME instrument QuickLoc Code Section III retain assemblies) conform their pressure with the requirements boundary integrity at of the ASME Code their design pressure. Section III.

88 2.1.03.13 13. The fuel An analysis is A report exists and assemblies and rod performed of the concludes that the cluster control reactor core design. fuel assemblies and assemblies intended rod cluster control for initial core load assemblies intended and listed in Table for the initial core load 2.1.3-1 have been and listed in Table designed and 2.1.3-1 have been constructed in designed and accordance with the constructed in established design accordance with the requirements. principal design requirements.

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No. ITAAC No. Design Commitment Inspections, Tests, Acceptance Criteria Analysis 91 2.2.01.02a 2.a) The components Inspection will be The ASME Code identified in Table conducted of the as- Section III design 2.2.1-1 as ASME built components and reports exist for the Code Section III are piping as documented as-built components designed and in the ASME design and piping identified constructed in reports. Inspection of in Table 2.2.1-1 and accordance with the as-built pressure 2.2.1-2 as ASME ASME Code Section boundary welds will Code Section III. A III requirements. 2.b) be performed in report exists and The piping identified accordance with the concludes that the in Table 2.2.1-2 as ASME Code Section ASME Code Section ASME Code Section III. i) A hydrostatic or III requirements are III is designed and pressure test will be met for constructed in performed on the nondestructive accordance with components required examination of ASME Code Section by the ASME Code pressure boundary III requirements. 3.a) Section III to be welds. i) A report Pressure boundary tested. A hydrostatic exists and concludes welds in components or pressure test will that the results of the identified in Table be performed on the pressure test of the 2.2.1-1 as ASME piping required by the components identified Code Section III meet ASME Code Section in Table 2.2.1-1 as ASME Code Section III to be pressure ASME Code Section III requirements. 3.b) tested. III conform with the Pressure boundary requirements of the welds in piping ASME Code Section identified in Table III. A report exists 2.2.1-2 as ASME and concludes that Code Section III meet the results of the ASME Code Section pressure test of the III requirements. 4.a) piping identified in The components Table 2.2.1-2 as identified in Table ASME Code Section 2.2.1-1 as ASME III conform with the Code Section III retain requirements of the their pressure ASME Code Section boundary integrity at III.

their design pressure.

4.b) The piping identified in Table 2.2.1-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.

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No. ITAAC No. Design Commitment Inspections, Tests, Acceptance Criteria Analysis 109 2.2.01.08 8. Containment An analysis for the as- Analysis exists for the electrical penetration built containment as-built containment assemblies are electrical penetration electrical penetration protected against assemblies will be assemblies and currents that are performed to concludes that the greater than the demonstrate (1) that penetrations are continuous ratings. the maximum current protected against of the circuits does currents which are not exceed the greater than their continuous rating of continuous ratings.

the containment electrical penetration assembly, or (2) that the circuits have redundant protection devices in series and that the redundant current protection devices are coordinated with the containment electrical penetration assemblys rated short circuit thermal capacity data and prevent current from exceeding the continuous current rating of the containment electrical penetration assembly.

114 2.2.01.11a.i 11.a) The motor- i) Tests or type tests i) A test report exists operated and check of motor-operated and concludes that valves identified in valves will be each motor-operated Table 2.2.1-1 perform performed to valve changes an active safety- demonstrate the position as indicated related function to capability of each in Table 2.2.1-1 under change position as valve to operate under design conditions. ii) indicated in the table. design conditions. ii) A report exists and Inspection will be concludes that the as-performed for the built motor-operated existence of a report valves are bounded verifying that the by the tests or type asbuilt motor- tests.

operated valves are bounded by the tests or type tests.

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120 2.2.02.02a 2.a) The components Inspection will be The ASME Code identified in Table conducted of the as- Section III design 2.2.2-1 as ASME built components and reports exist for the Code Section III are piping as documented as-built components designed and in the ASME design and piping identified constructed in reports. Inspection of in Table 2.2.2-1 and accordance with the as-built pressure 2.2.2-2 as ASME ASME Code Section boundary welds will Code Section III. A III requirements. 2.b) be performed in report exists and The pipelines accordance with the concludes that the identified in Table ASME Code Section ASME Code Section 2.2.2-2 as ASME III. A hydrostatic test III requirements are Code Section III are will be performed on met for non-designed and the components and destructive constructed in piping required by the examination of accordance with ASME Code Section pressure boundary ASME Code Section III to be hydrostatically welds. A report exists III requirements. 3.a) tested. Inspection will and concludes that Pressure boundary be performed for the the results of the welds in components existence of a report hydrostatic test of the identified in Table concluding that the components and 2.2.2-1 as ASME as-built pipelines meet piping identified in Code Section III meet the requirements for Table 2.2.2-1 and ASME Code Section functional capability. 2.2.2-2 as ASME III requirements. 3.b) Code Section III Pressure boundary conform with the welds in the pipelines requirements of the identified in Table ASME Code Section 2.2.2-2 as ASME III. A report exists Code Section III meet and concludes that ASME Code Section each of the as-built III requirements. 4.a) pipelines identified in The components Table 2.2.2-2 for identified in Table which functional 2.2.2-1 as ASME capability is required Code Section III retain meets the their pressure requirements for boundary integrity at functional capability.

their design pressure.

4.b) The pipelines identified in Table 2.2.2-2 as ASME Code Section III retain their pressure boundary integrity at their design pressure.

5.b) Each of the pipelines identified in Table 2.2.2-2 for which functional capability is required 64

No. ITAAC No. Design Commitment Inspections, Tests, Acceptance Criteria Analysis is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability.

65

159 2.2.03.02a 2.a) The components Inspection will be The ASME Code identified in Table conducted of the as- Section III design 2.2.3-1 as ASME built components and reports exist for the Code Section III are piping as documented asbuilt components designed and in the ASME design and piping identified constructed in reports. Inspection of in Table 2.2.31 and accordance with the as-built pressure 2.2.3-2 as ASME ASME Code Section boundary welds will Code Section III. A III requirements. 2.b) be performed in report exists and The piping identified accordance with the concludes that the in Table 2.2.3-2 as ASME Code Section ASME Code Section ASME Code Section III. A hydrostatic test III requirements are III is designed and will be performed on met for non-constructed in the components and destructive accordance with piping required by the examination of ASME Code Section ASME Code Section pressure boundary III requirements. 3.a) III to be hydrostatically welds. A report exists Pressure boundary tested. Inspection and concludes that welds in components will be performed for the results of the identified in Table the existence of a hydrostatic test of the 2.2.3-1 as ASME report verifying that components and Code Section III meet the as-built piping piping identified in ASME Code Section meets the Table 2.2.31 and III requirements. 3.b) requirements for 2.2.3-2 as ASME Pressure boundary functional capability. Code Section III welds in piping Inspection will be conform with the identified in Table performed for the requirements of the 2.2.3-2 as ASME existence of an LBB ASME Code Section Code Section III meet evaluation report or III. A report exists ASME Code Section an evaluation report and concludes that III requirements. 4.a) on the protection from each of the as-built The components dynamic effects of a lines identified in identified in Table pipe break. Section Table 2.2.3-2 for 2.2.3-1 as ASME 3.3, Nuclear Island which functional Code Section III retain Buildings, contains capability is required their pressure the design meets the boundary integrity at descriptions and requirements for their design pressure. inspections, tests, functional capability.

4.b) The piping analyses, and An LBB evaluation identified in Table acceptance criteria for report exists and 2.2.3-2 as ASME protection from the concludes that the Code Section III dynamic effects of LBB acceptance retains its pressure pipe rupture. criteria are met by the boundary integrity at as-built RCS piping its design pressure. and piping materials, 5.b) Each of the lines or a pipe break identified in Table evaluation report 2.2.3-2 for which exists and concludes functional capability is that protection from required is designed the dynamic effects of to withstand combined 66

No. ITAAC No. Design Commitment Inspections, Tests, Acceptance Criteria Analysis normal and seismic a line break is design basis loads provided.

without a loss of its functional capability.

6. Each of the as-built lines identified in Table 2.2.3-2 as designed for LBB meets the LBB criteria, or an evaluation is performed of the protection from the dynamic effects of a rupture of the line.

597 2.6.03.02.i 2. The seismic i) Inspection will be i) The seismic Category I equipment performed to verify Category I equipment identified in Table that the seismic identified in Table 2.6.31 can withstand Category I equipment 2.6.31 is located on seismic design basis identified in Table the Nuclear Island. ii) loads without loss of 2.6.31 is located on A report exists and safety function. the Nuclear Island. ii) concludes that the Type tests, analyses, seismic Category I or a combination of equipment can type tests and withstand seismic analyses of seismic design basis loads Category I equipment without loss of safety will be performed. iii) function. iii) A report Inspection will be exists and concludes performed for the that the as-built existence of a report equipment including verifying that the as- anchorage is built equipment seismically bounded including anchorage is by the tested or seismically bounded analyzed conditions.

by the tested or analyzed conditions.

67

No. ITAAC No. Design Commitment Inspections, Tests, Acceptance Criteria Analysis 760 3.3.00.02a.i.a 2.a) The nuclear i) An inspection of the i.a) A report exists island structures, nuclear island which reconciles including the critical structures will be deviations during sections listed in performed. Deviations construction, including Table 3.3-7, are from the design due to Table 3.3-1 wall and seismic Category I as-built conditions will floor thicknesses, and and are designed and be analyzed for the concludes that the as-constructed to design basis loads, built containment withstand design and for radiation internal structures, basis loads as shielding. including the critical specified in the sections, conform to Design Description, the approved design without loss of and will withstand the structural integrity and design basis loads the safety-related specified in the functions. 3.) Walls Design Description and floors of the without loss of nuclear island structural integrity or structures as defined the safety-related on Table 3.3-1 except functions, and without for designed openings impacting compliance or penetrations, with the radiation provide shielding protection licensing during normal basis.

operations.

68

No. ITAAC No. Design Commitment Inspections, Tests, Acceptance Criteria Analysis 761 3.3.00.02a.i.b 2.a) The nuclear i) An inspection of the i.b) A report exists island structures, nuclear island which reconciles including the critical structures will be deviations during sections listed in performed. Deviations construction, including Table 3.3-7, are from the design due to Table 3.3-1 wall and seismic Category I as-built conditions will floor thicknesses, and and are designed and be analyzed for the concludes that the as-constructed to design basis loads, built shield building withstand design and for radiation structures, including basis loads as shielding. the critical sections, specified in the conform to the Design Description, approved design and without loss of will withstand the structural integrity and design basis loads the safety-related specified in the functions. 3.) Walls Design Description and floors of the without loss of nuclear island structural integrity or structures as defined the safety-related on Table 3.3-1 except functions, and without for designed openings impacting compliance or penetrations, with the radiation provide shielding protection licensing during normal basis.

operations.

69

No. ITAAC No. Design Commitment Inspections, Tests, Acceptance Criteria Analysis 762 3.3.00.02a.i.c 2.a) The nuclear i) An inspection of the i.c) A report exists island structures, nuclear island which reconciles including the critical structures will be deviations during sections listed in performed. Deviations construction, including Table 3.3-7, are from the design due to Table 3.3-1 wall and seismic Category I as-built conditions will floor thicknesses, and and are designed and be analyzed for the concludes that the as-constructed to design basis loads, built structures in the withstand design and for radiation non-radiologically basis loads as shielding. controlled area of the specified in the auxiliary building, Design Description, including the critical without loss of sections, conform to structural integrity and the approved design the safety-related and will withstand the functions. 3.) Walls design basis loads and floors of the specified in the nuclear island Design Description structures as defined without loss of on Table 3.3-1 except structural integrity or for designed openings the safety-related or penetrations, functions, and without provide shielding impacting compliance during normal with the radiation operations. protection licensing basis.

70

No. ITAAC No. Design Commitment Inspections, Tests, Acceptance Criteria Analysis 763 3.3.00.02a.i.d 2.a) The nuclear i) An inspection of the i.d) A report exists island structures, nuclear island which reconciles including the critical structures will be deviations during sections listed in performed. Deviations construction, including Table 3.3-7, are from the design due to Table 3.3-1 wall and seismic Category I as-built conditions will floor thicknesses, and and are designed and be analyzed for the concludes that the as-constructed to design basis loads, built structures in the withstand design and for radiation radiologically basis loads as shielding. controlled area of the specified in the auxiliary building, Design Description, including the critical without loss of sections, conform to structural integrity and the approved design the safety-related and will withstand the functions. 3.) Walls design basis loads and floors of the specified in the nuclear island Design Description structures as defined without loss of on Table 3.3-1 except structural integrity or for designed openings the safety-related or penetrations, functions, and without provide shielding impacting compliance during normal with the radiation operations. protection licensing basis.

770 3.3.00.02b 2.b) Site grade level Inspection of the as- Site grade is is located relative to built site grade will be consistent with design floor elevation 100'-0" conducted. plant grade within the per Table 3.3-5. dimension defined on Table 3.3-5.

71

No. ITAAC No. Design Commitment Inspections, Tests, Acceptance Criteria Analysis 776 3.3.00.02h 2.h) The free volume An inspection will be A report exists and in the containment performed of the as- concludes that the allows for floodup to built containment floodup volume of this support long-term structures and portion of the core cooling for equipment. The containment is less postulated portions of the than 71,960 ft3 to an lossofcoolant containment included elevation of 107.68'.

accidents. in this inspection are the volumes that flood with a lossofcoolant accident in passive core cooling system valve/equipment room B (11207). The in-containment refueling water storage tank volume is excluded from this inspection.

812 3.3.00.07e 7.e) Class 1E Inspections of the as- Class 1E communication cables built Class 1E communication cables which interconnect communication cables which interconnect two divisions are will be conducted. two divisions are routed and separated routed and separated such that the such that the Protection and Safety Protection and Safety Monitoring System Monitoring System voting logic is not voting logic is not defeated by the loss defeated by the loss of any single raceway of any single raceway or fire area. or fire area.

819 3.3.00.13 13. Separation is An inspection of the The minimum provided between the separation of the horizontal clearance structural elements of nuclear island from above floor elevation the turbine and annex the annex and turbine 100-0 between the buildings and the building structures will structural elements of nuclear island be performed. The the annex building structure. This inspection will verify and the nuclear island separation permits the specified is 3 inches. The horizontal motion of horizontal clearance minimum horizontal the buildings in the between structural clearance above floor safe shutdown elements of the elevation 100-0 earthquake without adjacent buildings, between the structural impact between consisting of the elements of the structural elements of reinforced concrete turbine building and the buildings. walls and slabs, the nuclear island is 3 structural steel inches.

columns and floor beams.

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73

ML21041A051

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ML21041A051

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SUBJECT:

Dear Mr. Yox:

Enclosure:

SUBJECT:

SUMMARY

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