ML19309D596

NRC Integrated Inspection Reports 05200025/2019003 and 05200026/2019003

ML19309D596
Person / Time
Site:	Vogtle
Issue date:	11/04/2019
From:	Nicole Coovert NRC/RGN-II
To:	Yox M Southern Nuclear Operating Co
Geanette D
References
IR 2019003
Download: ML19309D596 (127)

Text

November 4, 2019 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 05200025/2019003, 05200026/2019003

Dear Mr. Yox:

On September 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Vogtle Electric Generating Plant, Units 3 and 4. The enclosed inspection report documents the inspection results, which the inspectors discussed on October 16, 2019 with Mr. Mike Meier and other members of your staff.

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.

The NRC inspectors did not identify any finding or violation of more than minor significance.

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.

M. Yox 2 Should you have any questions concerning this letter, please contact us.

Sincerely,

/RA/

Nicole C. Coovert, Chief Construction Inspection Branch 1 Division of Construction Oversight Docket Nos.: 5200025, 5200026 License Nos: NPF-91, NPF-92

Enclosure:

NRC Inspection Report (IR) 05200025/2019003, 05200026/2019003 w/attachment: Supplemental Information

M. Yox 3 cc:

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 Southern Nuclear Operating Company, Inc. Team Leader Document Control Coordinator Bin N-226-EC Environmental Radiation Program 3535 Colonnade Parkway Air Protection Branch Birmingham, AL 35243 Environmental Protection Division 4244 International Parkway, Suite 120 Office of the Attorney General Atlanta, GA 30354-3906 40 Capitol Square, SW Atlanta, GA 30334 Brian H. Whitley 3535 Colonnade Parkway, Bin N-226-EC Anne F. Appleby 42 Inverness Center Parkway, BIN B237 Olgethorpe Power Corporation Birmingham, AL 35243 2100 East Exchange Place Tucker, GA 30084 Mr. Michael Yox Site Regulatory Affairs Director County Commissioner Vogtle Units 3 & 4 Office of the County Commissioner 7825 River Road, Bin 63031 Burke County Commission Waynesboro, GA 30830 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 Email acchambe@southernco.com (Amy Chamberlian) agaughtm@southernco.com (Amy Aughtman) awc@nei.org (Anne W. Cottingham) becky@georgiawand.org (Becky Rafter) bhwhitley@southernco.com (Brian Whitley)

Bill.Jacobs@gdsassociates.com (Bill Jacobs) bjadams@southernco.com (Brad Adams) bwwaites@southernco.com (Brandon Waites) castelca@westinghouse.com (Curtis Castell) comerj@westinghouse.com (James Comer) crpierce@southernco.com (C.R. Pierce) dahjones@southernco.com (David Jones) david.hinds@ge.com (David Hinds) david.lewis@pillsburylaw.com (David Lewis) dgbost@southernco.com (Danny Bost) dlfulton@southernco.com (Dale Fulton) drculver@southernco.com (Randy Culver) durhamdc@westinghouse.com (David Durham) ed.burns@earthlink.net (Ed Burns) edavis@pegasusgroup.us (Ed David) erg-xl@cox.net (Eddie R. Grant) fdhundle@southernco.com (Forrest Hundley) fhwillis@southernco.com (Fred Willis)

G2NDRMDC@southernco.com (SNC Document Control)

George.Taylor@opc.com (George Taylor) graysw@westinghouse.com (Scott W. Gray) jadwilli@southernco.com (J.D. Williams) james1.beard@ge.com (James Beard) jantol1dj@westinghouse.com (David Jantosik) jenmorri@southernco.com (Jennifer Buettner)

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

John.Bozga@nrc.gov (John Bozga)

Joseph_Hegner@dom.com (Joseph Hegner) jpredd@southernco.com (Jason R. Redd) karen.patterson@ttnus.com (Karen Patterson) 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)

M. Yox 5 Melissa.Smith@Hq.Doe.Gov (Melissa Smith) mike.price@opc.com (M.W. Price)

MKWASHIN@southernco.com (MKWashington) mlgraves@southernco.com (Michelle Graves)

MSF@nei.org (Marvin Fertel) myox@southernco.com (Mike Yox) nirsnet@nirs.org (Michael Mariotte)

Nuclaw@mindspring.com (Robert Temple)

Paul@beyondnuclear.org (Paul Gunter) pbessette@morganlewis.com (Paul Bessette) r.joshi15@comcast.net (Ravi Joshi)

Ronald.Jones@scana.com (Ronald Jones) rwink@ameren.com (Roger Wink) sabinski@suddenlink.net (Steve A. Bennett) sara@cleanenergy.org (Sara Barczak) 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) sroetger@psc.state.ga.us (Steve Roetger) stephen.burdick@morganlewis.com (Stephen Burdick) tom.miller@hq.doe.gov (Tom Miller)

TomClements329@cs.com (Tom Clements)

Vanessa.quinn@dhs.gov (Vanessa Quinn) vcsummer2n3@gmail.com (Brian McIntyre) wasparkm@southernco.com (Wesley A. Sparkman) wayne.marquino@gmail.com (Wayne Marquino) weave1dw@westinghouse.com (Doug Weaver)

William.Birge@hq.doe.gov (William Birge) x2gabeck@southernco.com (Gary Becker) x2kmseib@southernco.com (Kristin Seibert)

ML19309D596 OFFICE DCO DCO DCO DCO DCO DRS DCO DCO SIGNATURE AArtayet PCarmen KCarrington LCastelli GCrespo SDowney JEargle TFredette DATE 10/17/2019 Via CIPIMS Via CIPIMS 10/17/2019 10/17/2019 10/17/2019 VIA CIPIMS 10/22/2019 OFFICE DCO DCO DCO DCO DCO DCO DCO DCO SIGNATURE BGriman DHarmon PHeher NKarlovich BKemker JKent ALerch JLizardi DATE Via CIPIMS 10/21/2019 10/22/2019 10/23/2019 Via CIPIMS 10/17/2019 Via CIPIMS 10/22/2019 OFFICE DRS DCO DFFI DCO DCO DCO DCO DCO SIGNATURE MMagyar RMathis KMcCurry APonko SSmith STemple JVasquez NCoovert DATE 10/20/2019 10/28/2019 10/21/2019 10/29/2019 10/17/2019 10/25/2019 10/23/2019 11/4/2019 U.S. NUCLEAR REGULATORY COMMISSION Region II Docket Numbers: 5200025 5200026 License Numbers: NPF-91 NPF-92 Report Numbers: 05200025/2019003 05200026/2019003 Licensee: Southern Nuclear Operating Company, Inc.

Facility: Vogtle Electric Generating Plant, Units 3 and 4 Location:

Inspection Dates: July 1, 2019 through September 30, 2019 Inspectors: A. Artayet, Senior Construction Inspector, DCO P. Carman, Project Manager, DCO K. Carrington, Resident Inspector, DCO L. Castelli, Senior Construction Inspector, DCO G. Crespo, Senior Construction Inspector, DCO S. Downey, Senior Reactor Inspector, DRS J. Eargle, Senior Project Manager, DCO T. Fredette, Reactor Operations Engineer, NRR/VPO B. Griman, Construction Inspector, DCO D. Harmon, Construction Inspector, DCO P. Heher, Resident Inspector, DCO N. Karlovich, Resident Inspector, DCO B. Kemker, Senior Resident Inspector, DCO J. Kent, Construction Inspector, DCO A. Lerch, Construction Inspector, DCO J. Lizardi-Barreto, Construction Inspector, DCO M. Magyar, Reactor Inspector, DRS R. Mathis, Test Inspector, DCO K. McCurry, Construction Inspector, DFFI A. Ponko, Senior Construction Inspector, DCO S. Smith, Senior Construction Inspector, DCO S. Temple, Resident Inspector, DCO J. Vasquez, Construction Inspector, DCO Approved by: Nicole C. Coovert, Chief Construction Inspection Branch 1 Division of Construction Oversight Enclosure

SUMMARY

OF FINDINGS Inspection Report (IR) 05200025/2019003, 05200026/2019003; 07/01/2019 through 09/30/2019; Vogtle Unit 3 Combined License, Vogtle Unit 4 Combined License, routine integrated inspection report.

This report covers a three months period of inspection by regional and resident inspectors, and announced Inspections, Tests, Analysis, and Acceptance Criteria (ITAAC) inspections by Regional inspectors. The U.S. Nuclear Regulatory Commission (NRC) program for overseeing the construction of commercial nuclear power reactors is described in Inspection Manual Chapter (IMC) 2506, Construction Reactor Oversight Process General Guidance and Basis Document.

A. NRC-Identified and Self Revealed Findings None B. Licensee-Identified Violations None

REPORT DETAILS Summary of Plant Construction Status Unit 3: The licensee completed installation of the air baffle assemblies and is in the process of welding the tension ring modules for the shield building. In the containment building, the licensee commenced installation of reactor coolant system (RCS) and passive core cooling system (PXS) instrumentation, continued electrical conduit and cable installation (safety and non-safety related (NSR)), and commenced flushing RCS and connecting systems piping. The licensee continued construction of the auxiliary building structure from elevation 117-6 to the roof, completed staging or setting major electrical equipment, and commenced installation of safety related raceways and cables.

Unit 4: The licensee continued welding of the shield building reinforced concrete/steel composite transition panel at the interface of the auxiliary building roof. In the containment building, the licensee continued construction on the operating deck frame work, completed installation of electrical penetration assemblies and commenced routing of electrical conduits.

The licensee continued construction of the auxiliary building structure from elevation 117-6 to 135-3 and commenced routing of electrical conduits.

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 2.1.02.02a (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 Inspection Procedures (IPs)/sections to perform this inspection:

• 65001.03-02.03 - Installation and Welding

• 65001.B-02.03-Welder Qualification

• 65001.B-02.04-Production Controls The inspectors performed an inspection of two field welds SV3-RCS-PLW-03A-1 and SV3-RCS-PLW-03A-2-C that join an 18-inch diameter pipe extension between the automatic depressurization system (ADS) stage 4 inlet piping L136A and reactor coolant system (RCS) hot leg L001A to verify if the branch connection was installed in accordance with the American Society of Mechanical Engineers (ASME) Code Section III, Subsection NB, for Class 1 components. Specifically, the inspectors observed in-

process manual gas tungsten arc welding (GTAW) for both welds to verify if the cleanliness, use of amperage, and each welder's ability to deposit sound weld metal were in accordance with welding procedure WPS1-8.8T01 using previously inspected ER316L welding rods. In addition, the inspectors reviewed the Stone & Webster (S&W) weld data sheet (WDS) entries for both welds to determine if quality control (QC) inspection hold points were signed-off and dated for material identification markings, cleanliness, and joint fit-up in accordance with the ASME Code,Section III, Subsections NCA-4134.10 and NB-4230. The inspectors reviewed nine welding material requisitions (WMRs) against the S&W WDS entries for both welds to determine if traceability of the welding rods and welders were controlled in accordance with Subsections NB-4122 and NB-4300. The inspectors reviewed five welder qualification records to determine if they were tested and certified in accordance with the requirements of the ASME Code,Section IX.

b. Findings No findings were identified.

1A02 (Unit 3) ITAAC Number 2.1.02.05a.i (19) / Family 14A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.1.02.05a.i (19). The inspectors used the following NRC IPs/sections to perform this inspection:

• 65001.A.02.04 - Review As-built Deviations/Nonconformance

• 65001.E-02.04-Documentation The inspectors reviewed the equipment qualification reconciliation report (EQRR) to determine whether the licensee assessed work packages, design changes, and nonconformances to confirm the as-built ADS sparger B, tag number SV3-PXS-MW-01B, including anchorage, was seismically bounded by the analyzed conditions in accordance with the applicable data sheet report (SV3-MW01-Z0R-001), design specification (SV3-MW01-Z0-001), and generic design report (APP-MW01-Z0C-001).

Specifically, the inspectors reviewed the licensee's methodology and selection of applicable work orders, data sheets, and design drawings to conclude those inspections and analyses demonstrated the installed sparger design characteristics were bounded by the design characteristics that were analyzed in its seismic analysis.

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

The inspectors had previously observed in-process welding of Unit 3 sparger B and its support structure, took independent measurements, and reviewed design, fabrication, and installation records, including nonconformance and disposition (N&D) reports and 4

the seismic analysis, as documented in inspection reports 2018001 (ML18134A348),

2018002 (ML18226A348), 2018003 (ML18317A395), and 2019002 (ML19220B678).

b. Findings No findings were identified.

1A03 (Unit 3) ITAAC Number 2.1.02.08d.v (36) / Family 07A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.1.02.08d.v (36). The inspectors used the following NRC IPs/sections to perform this inspection:

• 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 The inspectors performed an inspection for the four Unit 3 fourth-stage ADS valves (RCS-PL-V004A, V004B, V004C, and V004D) to verify the minimum elevation of the bottom inside surface of the outlet was greater than plant elevation 110'0" as specified in Table 2.1.2-4 of Appendix C of the Vogtle Unit 3 Combined License (COL).

Similarly, the inspectors performed an inspection to verify the discharge of these valves was directed into the steam generator compartments as specified in Table 2.1.2-4 of Appendix C of the Vogtle Unit 3 COL. The inspectors observed the licensee survey the elevation of the centerline of each pipe flange at the inlet to the four ADS valves; reviewed the vendor's as-built reports for each ADS valve; and reviewed the vendor's assembly drawing for the ADS valves and compared the drawing dimensions with the as-built (or as-measured) dimensions from the as-built reports. The inspectors reviewed the survey results; reviewed the licensee's calculations of the minimum elevation of the bottom inside surface of the outlet of each valve; and performed independent calculations to verify the licensee's results. The inspectors also observed the discharges lines for the valves to verify they would discharge directly into the steam generator compartments to satisfy the ITAAC.

b. Findings No findings were identified.

1A04 (Unit 3) ITAAC Number 2.1.03.03 (72) / Family 05F (Unit 4) ITAAC Number 2.1.03.03 (72) / Family 05F 5

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.B-02.02-Welding Procedure Qualification The inspectors reviewed a sample of welding procedures used by Westinghouse Newington and their sub-vendor American Tank & Fabrication (AT&F) Nuclear to fabricate the core barrel lower reactor vessel internals, and the associated procedure qualification records (PQRs), to determine if the core barrel had been fabricated using procedures that had been written and qualified per the requirements of the ASME Code,Section III, Subsection NG, 1998 edition 2000 addenda.

b. Findings No findings were identified.

1A05 (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:

• 65001.03-02.03 - Installation and Welding

• 65001.11-02.03 - Installation and Welding

• 65001.B-02.03-Welder Qualification

• 65001.B-02.04-Production Controls The inspectors performed an inspection of field weld SV3-CCS-PLW-812-6 for joining 10-inch diameter carbon steel pipes for the component cooling water supply to containment piping L201A located in the annulus between the containment P03 penetration and shield building to verify installation was performed in accordance with the ASME Code,Section III, Subsection NC, for Class 2 components. Specifically, the inspectors observed in-process manual GTAW to verify if the cleanliness, use of amperage, and welders' ability to deposit sound weld metal were in accordance with welding procedure WPS1-1.1C21 using previously inspected ER70S-6 welding rods.

In addition, the inspectors reviewed the S&W WDS to determine if QC inspection hold points were signed-off and dated for material identification markings, cleanliness, and joint fit-up in accordance with the ASME Code,Section III, Subsections NCA-4134.10 and NC-4230.

The inspectors also reviewed a sample of WMRs for weld SV3-CCS-PLW-812-6 against the S&W WDS entries to determine if traceability of the welding rods and 6

welders were controlled in accordance with NC-4122 and NC-4300. The inspectors also reviewed a sample of welder qualification records to determine if the welders were tested and certified in accordance with the requirements of the ASME Code,Section IX.

The inspectors performed an inspection of in-process welding for the Unit 3 spent fuel pool cooling discharge piping. Specifically, the inspectors observed weld SV3-SFS-PLW-520-2, connecting pipe spools SV3-SFS-PLW-520-1 and SV3-SFS-PLW-521-1 on line SFS-PL-L017 (ASME Class 2). The inspectors observed manual GTAW to verify if the piping was welded in accordance with S&W weld procedure specification (WPS) 1-8.8T01 and the ASME Code,Section III, Subsection NC. The inspectors reviewed the WDS, WMR 465897, and material markings on the weld rods and base material in the field to verify if traceability of the ER308L weld rods, base material, and welder identification (ID) were controlled in accordance with the ASME Code,Section III, Subsections NCA and NC. The inspectors also observed the amperage setting on the welding machine to verify if the value was within the range listed in the WPS.

The inspectors reviewed a certified material test report (CMTR) for the weld filler metals being used for weld SV3-SFS-PLW-520-2 to determine if they met the requirements for chemical analysis and mechanical properties in accordance with the ASME Code, Section II-C, SFA-5.9 specification for bare stainless-steel rods. The inspectors also reviewed welder qualification records to determine if the welder was qualified and tested in accordance with the requirements of the ASME Code,Section IX.

b. Findings No findings were identified.

1A06 (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:

• 65001.07-02.01 - General Installation

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

• 65001.A.02.03 - Independent Assessment/Measurement Inspection The inspectors performed an as-built inspection of a containment vessel penetration valve to determine if it conformed to installation requirements in the design specification and construction drawings. Specifically, the inspectors examined valve SV3-CCS-PL-V208 to determine if the valve size, class, type, location, flow direction, elevation, body-to-actuator joint, and bolt size and quantity was in accordance with the design specification, valve data sheet, and construction drawings. The inspectors reviewed a material issue report for the gaskets used to determine if the size and type 7

was in accordance with the design specification and construction drawing. The inspectors independently measured a sample of dimensions to determine if they conformed to the construction drawing.

b. Findings No findings were identified.

1A07 (Unit 3) ITAAC Number 2.2.01.05.i (98) / Family 11A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.01.05.i (98). The inspectors used the following NRC IPs/sections to perform this inspection:

• 65001.A.02.04 - Review As-built Deviations/Nonconformance

• 65001.E-02.04-Documentation The inspectors reviewed the EQRR to determine whether the licensee assessed work orders, design changes, and nonconformances to confirm the as-built fuel transfer tube (FTT), tag number SV3-FHS-FT-01, including anchorage, was seismically bounded by the analyzed conditions in accordance with the design specification (SV3-FT01-Z0-001) and equipment design report (SV3-FT01-S3R-001). Specifically, the inspectors reviewed the licensee's methodology and selection of applicable work orders and design drawings to conclude those inspections and analyses demonstrated the installed FTT design characteristics, including the quick opening transfer tube closure (QOTTC), were bounded by the design characteristics analyzed in its seismic analysis. The inspectors also interviewed licensing personnel to determine how inspection and analysis were performed for applicable FTT non-conformances and E&DCR issued during fabrication, handling, installation, and testing to ensure all deviations were bounded by the seismically analyzed conditions.

The inspectors had previously observed in-process welding and conducted independent reviews of design, fabrication, and installation records, including N&D reports and the seismic analysis, for the Unit 3 FTT, as documented in inspection reports 2018003 (ML18317A395), 2019001 (ML19135A691), and 2019002 (ML19220B678).

b. Findings No findings were identified.

1A08 (Unit 3) ITAAC Number 2.2.03.08c.iii (182) / Family 03A 8

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.03.08c.iii (182). The inspectors used the following NRC IPs/sections to perform this inspection:

• 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 The inspectors performed an inspection to verify both Unit 3 core makeup tank (CMT) inlet lines from the RCS cold legs had no downward sloping sections between the connections to the RCS and the high point of the lines as specified in Table 2.2.3-4 of Appendix C of the Vogtle Unit 3 COL. Similarly, the inspectors performed an inspection to verify the Unit 3 passive residual heat removal (PRHR) heat exchanger (HX) line from the RCS hot leg had no downward sloping sections between the connection to the RCS and the high point of the line as specified in Table 2.2.3-4 of Appendix C of the Vogtle Unit 3 COL. This inspection involved three piping sections consisting of seven pipe segments (i.e., three PRHR HX to RCS hot leg segments and two segments each for CMT A and CMT B from the RCS cold legs). The inspectors performed a walkdown of the three piping sections with the licensee, observed the licensee measure the slope of the lines, and performed independent measurements to verify the as-built piping was consistent with the as-built drawings. In addition, the inspectors reviewed quality records including the principal closure document (PCD),

survey results, and as-built elevation drawings to verify the lines had no downward sloping sections between the connection to the RCS and the high point of the lines to satisfy the ITAAC acceptance criteria.

b. Findings No findings were identified.

1A09 (Unit 3) ITAAC Number 2.2.03.08c.iv.02 (184) / Family 03A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.03.08c.iv.02 (184). The inspectors used the following NRC IPs/sections to perform this inspection:

• 65001.01-02.04 - Key Dimensions and Volumes

• 65001.01-02.06 - Records

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

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

• 65001.A.02.02 - Installation Records Review

• 65001.A.02.03 - Independent Assessment/Measurement Inspection 9

The inspectors observed the licensee's survey verification, performed independent evaluations, and reviewed records for the PXS containment recirculation lines and the in-containment refueling water storage tank (IRWST). The inspectors reviewed the survey procedures to verify they included instructions for performing ITAAC related surveys and appropriate quantitative acceptance criteria in accordance with 10 CFR 50, Appendix B, Criterion V. The inspectors observed the licensee perform surveying for pipe lines: SV3-PXS-PL-L100, SV3-PXS-PL-L101, SV3-PXS-PL-L106, SV3-PXS-PL-L113A/B, SV3-PXS-PL-L116A/B, SV3-PXS-PL-L117A/B, SV3-PXS-PL-L118A/B, SV3-PXS-PL-L123A/B, SV3-PXS-PL-L124A/B, SV3-PXS-PL-L125A/B, SV3-PXS-PL-L127A/B, SV3-PXS-PL-L131A/B, and SV3-PXS-PL-L132A/B. The inspectors observed surveying of the above pipe lines to determine whether calibrated and verified equipment was used and the surveying was done in accordance with procedures. Additionally, the inspectors observed surveying of the outside of these pipe lines to verify the selection of survey points and pipe diameters would lead to determining the maximum elevations for each line in accordance with the acceptance criteria. The inspectors reviewed the training records for the individuals who performed the surveys to verify the individuals were trained and qualified as required by the survey procedures. The inspectors reviewed the survey results to verify the data was correctly recorded and translated into quality records.

The inspectors reviewed the survey data for the bottom inside surface of the IRWST to verify the surveys were documented in accordance with the survey procedures and the data was correctly translated into quality records. The inspectors independently walked down the IRWST, the above pipe lines, and pipe lines SV3-PXS-PL-L021A/B to verify the maximum elevations of the pipe lines were lower than the bottom inside surface of the IRWST as specified in Table 2.2.3-4 of Appendix C of the Vogtle Unit 3 COL.

The inspectors reviewed the PCD and its included references to verify the data was correctly translated from the survey records. The inspectors reviewed the pipe wall thicknesses listed on the PCD to verify they were the correct wall thicknesses for the pipe size and classification in accordance with the drawings, SV3-PL02-Z0-001, and the ASME Code,Section III, Subsection NCA. The inspectors reviewed the calculated maximum elevation of the top inside surface of each pipe listed in the PCD to verify the maximum elevations of the pipe lines were lower than the bottom inside surface of the IRWST as specified in Table 2.2.3-4 of Appendix C of the Vogtle Unit 3 COL.

b. Findings No findings were identified.

1A10 (Unit 3) ITAAC Number 2.2.05.07e (880) / Family 19A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.05.07e (880). The inspectors used the following NRC IPs/sections to perform this inspection:

10

• 65001.12-02.01 - General Installation

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

• 65001.A.02.03 - Independent Assessment/Measurement Inspection The inspectors observed the main control room emergency habitability system (VES) filter shielding to verify the as-built shielding met the functional requirements and conformed to the system design description of the Updated Final Safety Analysis Report (UFSAR), Section 6.4.2 and the Vogtle Unit 3 COL, Section 2.2.5 and Table 2.2.5-1. The inspectors performed a walk down of the installed shielding to verify shielding existed below the filtration unit and was within its vertical projection as specified in the ITAAC acceptance criteria. The inspectors observed the licensee's inspection of the VES air filter assembly shielding panel, including the dimensions, material, and location within the assembly, prior to installation of the assembly to verify the shielding panel was of the correct dimensions and material as specified in the design drawings. The inspectors observed the rigging and lifting activities to verify they were performed in accordance with the work package and work package hold points were maintained. The inspectors observed the final installed air filter unit assembly to verify the shielding panel was not damaged or altered during installation.

b. Findings No findings were identified.

1A11 (Unit 3) ITAAC Number 2.6.03.02.i (597) / Family 08A

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:

• 65001.08-02.02 - In-Process Installation

• 65001.F-02.04-General QA Review The inspectors performed an in-process inspection of installation of the following Unit 3 Class 1E uninterruptible power supply system (IDS) components:

• Division B low voltage fuse panels (SV3-IDSB-EA-4, SV3-IDSB-EA-5, and SV3-IDSB-EA-6), Division B battery monitor fuse panels (SV3-IDSB-EA-7, SV3-IDSB-EA-8) and Division B motor control center (SV3-IDSB-DK-1);

• Division C voltage regulating transformer (SV3-IDSC-DT-1);

• Division D DC voltage distribution panel (SV3-IDSD-DD-1); and

• Division D AC voltage distribution panels (SV3-IDSD-EA-1, SV3-IDSD-EA-2)

The inspectors observed torquing of anchor/mounting bolts for the components to verify the torque wrenches and torque values used were in accordance with the work 11

packages, vendor documents, and design documents. The inspectors also reviewed the calibration labels on the torque wrenches to verify the torque wrenches had not passed their calibration due date in accordance with the Bechtel project nuclear quality control manual (PQNM). The inspectors also observed torquing of mounting bolts for bus bars in the Division B IDS motor control center battery monitor fuse panels to verify the work was performed in accordance with the work package. For the Division B battery monitor fuse panels, the inspectors also observed the installation activity to verify the strut sizes were as listed on design drawings.

b. Findings No findings were identified.

1A12 (Unit 3) ITAAC Number 2.7.01.02a (678) / Family 12F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.7.01.02a (678). The inspectors used the following NRC IPs/sections to perform this inspection:

• 65001.12-02.01 - General Installation

• 65001.12-02.02 - Welding

• 65001.B-02.03-Welder Qualification

• 65001.B-02.04-Production Controls

• 65001.B-02.05-Inspection The inspectors performed a welding inspection on the 28-inch diameter carbon steel ventilation system to the main control room. Specifically, the inspectors observed in-process manual GTAW on field welds SV3-VBS-PLW-030-9, for pipe to straight tee fitting, and SV3-VBS-PLW-030-14, for pipe to weld-neck flange of line VBS-L311, to verify if welding was performed in accordance with ASME Code Section III, Subsection ND, for Class 3 components. The inspectors observed the fit-up and amperage usage for the root pass on the pipe to flange weld to determine if the fit-up tolerances and welding machine readings were within the range described on welding procedure WPS1-1.1C21. The inspectors also observed the internal root pass for the pipe to tee fitting to verify if the fit-up and full joint penetration welding was performed in accordance with the requirements of ASME Code Section III, Article ND-4000, for Class 3 components. In addition, the inspectors reviewed the WDSs to determine if inspection hold points for QC were signed-off for material identification markings, cleanliness, and joint fit-up in accordance with the ASME Code,Section III, Subsections NCA-4134.10 and ND-4230.

The inspectors observed the classification and heat number markings on the 1/8-inch diameter weld rods to determine if the previously inspected ER70S-6 weld rods were used in accordance with the WDSs and WPS. The inspectors reviewed six welder qualification records for three welders to determine if they were qualified and tested in 12

accordance with the requirements of the ASME Code,Section IX. The inspectors reviewed the WMR against the WDS entries for the pipe to flange weld to determine if traceability of the welder and welding rods were controlled in accordance with the ASME III, ND-4122 and ND-4300. The inspectors reviewed MISTRAS nondestructive evaluation (NDE) magnetic particle testing (MT) report, V-19-MT-301-3625 for weld-no. SV3-VBS-PLW-030-14, to verify whether final magnetic particle examination was performed with acceptable results using an alternating current (AC) yoke with 10 lbs pre/post lift tests and red dry particle in accordance with ASME Sections III, Article ND-5000, and Section V, Article 7, for magnetic particle examination.

b. Findings No findings were identified.

1A13 (Unit 3) 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:

• 65001.01-02.06 - Records

• 65001.01-02.07 - Identification and Resolution of Problem

• 65001.A.02.02 - Installation Records Review

• 65001.A.02.03 - Independent Assessment/Measurement Inspection

• 65001.B-02.04-Production Controls

• 65001.B-02.05-Inspection

• 65001.B-02.06-Records

• 65001.F-02.02-Fabrication Records Review

• 65001.F-02.03-Observation of Fabrication Activities The inspectors observed in-process welding activities and reviewed records associated with welding of the Unit 3 shield building air inlet modules. The inspectors selected the following welds for inspection:

• 16/AI-E horizontal outside (between panels AI1-AI5 and 16A and 16B, between approximately azimuth 3 degrees and azimuth 39 degrees, at elevation 248'-

6");

• 16/AI-F horizontal inside (between panels AI6-AI8 and 16B, between approximately azimuth 39 degrees and azimuth 62 degrees, at elevation 248'-

6"); and

• AIF/G vertical outside (between panels AI11and AI12, approximately at azimuth 90 degrees, between elevations 248'-6" and 266'-4").

13

The inspectors performed an independent visual inspection of fit-up and tack welding, intermediate passes, and portions of completed welds to determine whether:

• the quality of the tack welds, weld toes, and cover passes were free from defects such as cracks, lack of fusion, or excessive overlap/undercut/porosity;

• the welds met the type, size, and location requirements of the drawings, SV3-1208-Z0-001, and the WPSs; and

• the welds met the visual inspection acceptance criteria for 181816-000-WS-PR-45056 and American Welding Society (AWS) D1.1-2000.

The inspectors observed in-process flux-cored arc welding (FCAW) and shielded metal arc welding (SMAW) to verify weld passes were performed in accordance with the requirements of AWS D1.1:2000. The inspectors verified the weld joint cleanliness was maintained between weld passes with staggered starts/stops and the welding operator's ability to deposit sound weld metal was performed in accordance with WPS 181816-000-WS-SP- E71T1 and WPS 181816-000-WS-SP-E8018. In addition, the inspectors observed the following attributes during in-process welding to verify welding was performed in accordance with the drawings and 181816-000-WS-SP-45001:

• the weld material being used at the work locations, including AWS electrode classification;

• the weld variables, including voltage, amperage, and travel speed;

• the heat input and interpass temperature;

• the joint configuration and weld position; and

• the environmental conditions, including protection from wind and moisture.

The inspectors reviewed the welding material authorization and release reports for the weld electrodes used to verify the material had been inspected and approved for use in accordance with CMS-720-03-PR-09154. The inspectors reviewed the weld travelers and associated spreadsheets for the weld joint locations to determine if established QC visual inspection hold points were signed-off and dated for cleanliness and fit-up alignment, and traceability of welders were maintained in accordance with GWPS 181816-000-WS-SP-45001.

The inspectors reviewed the weld travelers for the weld joints listed above to determine if established QC inspection hold points and required visual inspections were signed-off in accordance with 181816-000-WS-SP-45001. The inspectors also reviewed the weld travelers to determine if the traceability of weld filler metals and welders were maintained in accordance with 181816-000-WS-SP-45001. The inspectors observed the QC final visual inspection of 16/AI-E and 16/AI-F to verify it was performed in accordance with 181816-000-WS-PR-45056. The inspectors reviewed the ultrasonic test (UT) report for the horizontal welds to verify the UT was performed and documented in accordance with 181816-000-WS-PR-45054 and American National Standards Institute (ANSI) / American Institute of Steel Construction (AISC) N690 and the weld quality met the acceptance criteria of AWS D1.1, Section 6 and Part F.

The inspectors reviewed a sample of N&Ds associated with the concrete placements to verify the nonconformances had supporting technical evaluations and were dispositioned in accordance with APP-GW-GAP-428, "Nonconformance and Disposition Report." The inspectors observed weld build-up activities and reviewed the 14

weld traveler associated with N&D SV3-1278-GNR-000012 to verify the work was completed in accordance with the disposition of the N&D. Additionally, the inspectors reviewed the required MT report for the weld build-up activities to verify the MT was performed and documented in accordance with 181816-000-WS-PR-45058 and ANSI/AISC N690, and the weld quality met the acceptance criteria of AWS D1.1, Section 6. The inspectors observed installation of additional D2L bars into the modules as a result of horizontal seam weld 16/AI joint mis-match to verify the additional bars were installed and welded in accordance with the drawings and procedures. The inspectors reviewed an E&DCR to verify the design change had a supporting technical evaluation and was dispositioned in accordance with APP-GW-GAP-420, "Engineering and Design Coordination Reports."

b. Findings No findings were identified.

1A14 (Unit 3) 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:

• 65001.01-02.06 - Records

• 65001.01-02.07 - Identification and Resolution of Problem

• 65001.02-02.01 - Inspection of Concrete Placement

• 65001.02-02.02 - Laboratory Testing

• 65001.02-02.03 - Special Considerations

• 65001.02-02.06 - Record Review

• 65001.02-02.07 - Problem Identification and Resolution

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

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

• 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 observed concrete placement activities, observed testing activities, reviewed quality records, and performed independent inspection of Vogtle Unit 3 shield building air inlet panels between elevations 247'-6 1/2" and 264'-4".

The inspectors independently assessed the placement area prior to concrete placement to determine whether it was secure, leak tight, and free from debris or excess water as required by American Concrete Institute (ACI) 349-01 and SV3-CC01-Z0-031. The inspectors reviewed the concrete placement plan included in the 15

work package to determine whether pre-placement planning had been completed, including considerations for weather, mass concrete, and unexpected events.

The inspectors observed concrete placement activities to determine whether approved work instructions and specifications were available in the work area and were followed throughout the concrete placement as required by the licensee's quality assurance program (QAP) and Title 10, Code for Federal Regulations Part 50 (10 CFR 50),

Appendix B, Criterion 5. The inspectors observed concrete placement activities and reviewed batch plant records to determine whether the following were in accordance with ACI 349-01, SV3-CC01-Z0-026, and SV3-CC01-Z0-031:

• the maximum water/cement ratio was not exceeded;

• concrete was placed in lifts;

• placement drop distances did not exceed requirements and did not result in concrete segregation;

• the time interval between mixing and placing was less than 90 minutes and the concrete trucks had less than 300 revolutions for each batch of concrete; and

• the concrete in the concrete trucks and at the point of placement was uniformly mixed.

The inspectors evaluated a sample of the batch tickets as they were being filled out and signed to verify the following was conducted in accordance with ACI 349-01 and SV3-CC01-Z0-031:

• batch records were generated, controlled, and indicated placement location, mix, volume, date, time, and special instructions;

• each truck was measured, and each trip received proper ticketing and documentation;

• the mix listed, and the weights of each constituent were reviewed prior to placing the concrete;

• each batch ticket was reviewed for transport time and truck rotations; and

• water was adjusted to account for moisture content of aggregates.

The inspectors observed field engineering and QC inspections throughout the concrete placement to verify inspection was performed during placement as required by ACI 349-01, SV3-CC01-Z0-031, and 26139-000-4MP-T81C-N3210. The inspectors reviewed the QC and quality assurance (QA) inspection reports for the concrete placement to verify the inspections were documented and the activities were accepted in accordance with SV3-CC01-Z0-031 and 26139-000-4MP-T81C-N3210.

During the placement, the inspectors observed in-process concrete testing to determine whether:

• concrete temperature, slump, air content, and unit weight were determined at the proper location and frequency as required by ACI 349-01, SV3-CC01-Z0-027, 132175-102-006-04-000052, and the applicable ASTM standards;

• sample collection, testing techniques, and testing equipment conformed to ACI 349-01, SV3-CC01-Z0-027, and the applicable American Society for Testing and Materials (ASTM) standards; 16

• test results were evaluated against applicable quantitative and qualitative acceptance criteria in accordance with 10 CFR 50, Appendix B, Criterion 5; and

• concrete strength test sample cylinders were made at the required location and frequency and were cured in accordance with ACI 349-01, SV3-CC01-Z0-027, and the applicable ASTM standards.

The inspectors reviewed a sample of batch tickets to verify the records contained the required information in accordance with ACI 349-01, SV3-CC01-Z0-027, and the applicable ASTM standards. The inspectors observed concrete curing activities to determine whether curing was in accordance with ACI 349-01 and SV3-CC01-Z0-031 with regard to the method, materials, duration, and temperature.

The inspectors reviewed corrective action reports 50027521 and 70000284 associated with the concrete placement to verify the evaluations and corrective actions were conducted in accordance with the licensee's corrective action program (CAP); the issues were identified and documented in a timely manner; and the issues were classified and resolved commensurate with their safety significance. The inspectors reviewed the associated N&Ds to verify the nonconformances had supporting technical evaluations and were dispositioned in accordance with APP-GW-GAP-428, "Nonconformance and Disposition Report." The inspectors reviewed the associated E&DCR to verify the design change had a supporting technical evaluation and was dispositioned in accordance with APP-GW-GAP-420, "Engineering and Design Coordination Reports."

b. Findings No findings were identified.

1A15 (Unit 3) 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 - Inspection of ITAAC-Related Foundations & Buildings

• 65001.01-02.05 - Steel Structures

• 65001.B-02.02-Welding Procedure Qualification

• 65001.B-02.03-Welder Qualification

• 65001.B-02.04-Production Controls

• 65001.B-02.06-Records The inspectors observed in-process welding of horizontal and vertical field welds FW05 and FW06, respectively, connecting tension ring modules TR05 and TR06. The inspectors also observed in-process welding of interior horizontal weld TR06-AI-18A 17

connecting tension ring module TR06 to air inlet module AI18. Specifically, the inspectors observed interpass SMAW on internal vertical and horizontal seams for the shield building upper tension ring panels TR05 and TR06 to verify whether the welders were depositing sound weld metal in clean weld butt joints using staggered starts and stops in accordance with the AWS D1.1:2000 Code. The inspectors also verified if the certified welders were using E8018-C1 electrodes in accordance with the applicable WPS.

The inspectors reviewed the weld travelers associated with the welds listed above to verify that work was conducted in accordance with a document/procedure which sequences all operations, references procedures and instructions, establishes hold points, and provides for production welding and inspection sign-offs. The Inspectors also verified that QC inspection hold points for fit-up and tack of seams were signed-off on in the weld traveler in accordance with the Chicago Bridge and Iron (CB&I)

QAP.

The inspectors reviewed general welding procedure specification 181816-000-WS-SP-45001 and WPS 181816-000-SP-E8018 along with supporting PQRs to verify that the WPS used for welding the joints listed above was qualified in accordance with the ASME Boiler and Pressure Vessel (BPV) Code,Section IX. Additionally, the inspectors reviewed the Certificate of Conformance (CoC) and CMTR for the weld filler material being used to determine if it met the requirements of the WPS.

The inspectors reviewed welder performance qualification records for two welders having site identification designations HWL4089 and RTR3688 to determine if the welders were qualified in accordance with ASME BPV Code,Section IX and had maintained their qualifications.

b. Findings No findings were identified.

1A16 (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.A.02.04 - Review As-built Deviations/Nonconformance

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

• 65001.F-02.01-Design Document Review The inspectors observed the section of wall along column 1 between column lines I and N from elevation 163-0 to approximately elevation 180-0. For this section of wall, the inspectors reviewed the size, spacing, material designation, grade, and layout 18

of the main horizontal and vertical reinforcing bars to verify if installation of this reinforcing steel was consistent with the applicable design drawings E&DCRs, construction specification SV3-CC01-Z0-31, and ACI 349-01. The inspectors also reviewed the lap splices between the vertical and horizontal bars, respectively, to verify if they met the lengths specified in the concrete general notes provided on drawing SV3-0000-C9-001 and were installed in accordance with design specification SV3-CC01-Z0-31 and ACI 349-01.

The inspectors reviewed a sample of nine E&DCRs to verify if design changes were performed in accordance with 10 CFR Part 50 Appendix B, Criterion III, Design Control. Specifically, the inspectors verified that 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 if a technical justification was provided for the design change, deviations from applicable quality standards such ACI 349-01 were controlled, and the revised design was correctly translated into the updated design output documents.

The inspectors reviewed a condition report and associated licensing document change request to verify that deviations from the approved design were being identified, documented, and reconciled using the appropriate change process.

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:

• 65001.01-02.06 - Records

• 65001.01-02.07 - Identification and Resolution of Problem

• 65001.02-02.01 - Inspection of Concrete Placement

• 65001.02-02.02 - Laboratory Testing

• 65001.02-02.06 - Record Review

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

• 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 observed concrete placement activities, observed testing activities, reviewed quality records, and performed independent inspection of the wall along 19

column line N between column lines 1 and 4 from elevation 155'-0" to the roof at 180'-

9" of the Vogtle Unit 3 auxiliary building.

The inspectors observed concrete placement activities to determine whether approved work instructions and specifications were available in the work area and were followed throughout the concrete placement as required by the licensee's QAP and 10 CFR 50, Appendix B, Criterion 5. The inspectors observed concrete placement activities and reviewed batch plant records to determine whether the following were in accordance with ACI 349-01, SV3-CC01-Z0-026, and SV3-CC01-Z0-031:

• concrete was placed in lifts;

• placement drop distances did not exceed requirements and did not result in concrete segregation;

• the time interval between mixing and placing was less than 90 minutes and the concrete trucks had less than 300 revolutions for each batch of concrete; and

• the concrete in the concrete trucks and at the point of placement was uniformly mixed.

The inspectors evaluated a sample of the placement's batch tickets as they were being filled out and signed to verify the following was conducted in accordance with ACI 349-01 and SV3-CC01-Z0-031:

• batch records were generated, controlled, and indicated placement location, mix, volume, date, time, and special instructions;

• each truck was measured, and each trip received proper ticketing and documentation;

• the mix listed, and the weights of each constituent were reviewed prior to placing the concrete;

• each batch ticket was reviewed for transport time and truck rotations; and

• water was adjusted to account for moisture content of aggregates.

The inspectors observed field engineering and QC inspections throughout the concrete placement to verify inspection was performed during placement as required by ACI 349-01 and SV3-CC01-Z0-031. The inspectors reviewed the QC inspection reports for the concrete placement to verify the inspections were documented and the activities were accepted in accordance with SV3-CC01-Z0-031. The inspectors reviewed a sample qualification records for the QC inspectors for the concrete placement to verify the individuals conducting the inspection were qualified and authorized to conduct the inspection in accordance with SV3-CC01-Z0-031.

During the placement, the inspectors observed in-process concrete testing to determine whether:

• concrete temperature, slump, air content, and unit weight were determined at the proper location and frequency as required by ACI 349-01, SV3-CC01-Z0-027, 26139-000-4MP-T81C-N3210, 132175-102-006-04-000052, and the applicable ASTM standards;

• sample collection, testing techniques, and testing equipment conformed to ACI 349-01, SV3-CC01-Z0-027, and the applicable ASTM standards; 20

• test results were evaluated against applicable quantitative and qualitative acceptance criteria in accordance with 10 CFR 50, Appendix B, Criterion 5; and

• concrete strength test sample cylinders were made at the required location and frequency and were cured in accordance with ACI 349-01, SV3-CC01-Z0-027, and the applicable ASTM standards.

The inspectors reviewed a sample of batch tickets and test reports, including the concrete cylinder strength testing, to verify the records contained the required information in accordance with ACI 349-01, SV3-CC01-Z0-027, and the applicable ASTM standards. Additionally, the inspectors reviewed the concrete cylinder break test results to verify the concrete tested met the strength requirements for the specified concrete mix in accordance with SV3-CC01-Z0-026.

The inspectors observed concrete curing activities to determine whether curing was in accordance with ACI 349-01 and SV3-CC01-Z0-031 with regard to the method, materials, duration, and temperature. The inspectors performed independent inspection and measurements of the as-built concrete, including finishes and dimensions, to determine whether the as-built configuration was in accordance with ACI 349-01, SV3-CC01-Z0-031, and the work package.

The inspectors reviewed corrective action reports 50021530, 50023851, and 50027085 associated with the concrete placement to verify the evaluations and corrective actions were conducted in accordance with the licensee's CAP; the issues were identified and documented in a timely manner; and the issues were classified and resolved commensurate with their safety significance. The inspectors reviewed the associated N&D to verify the nonconformance had a technical evaluation and was dispositioned in accordance with APP-GW-GAP-428, "Nonconformance and Disposition Report." The inspectors reviewed the associated E&DCRs to verify the design changes had a technical evaluation and were dispositioned in accordance with APP-GW-GAP-420, "Engineering and Design Coordination Reports."

b. Findings No findings were identified.

1A18 (Unit 3) ITAAC Number 3.3.00.07bb (793) / Family 09A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.07bb (793). 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

• 65001.09-02.04 - Problem Identification and Resolution

• 65001.A.02.01 - Observation of in-Process Installation Activities 21

• 65001.A.02.02 - Installation Records Review The inspectors observed the installation of Class 1E electrical and communication cables into raceways in the non-radiological portion of the auxiliary building on elevations 82'-6", 100'-0", and 117'-6" for IDS electrical equipment in rooms 12201,12301, 12205, 12207,12304, 12305, and 12412. Specifically, the inspectors observed the installation of Class 1E cables SV3-IDSA-EW-DK1BXA , SV3-IDSA-EW-DK1DXA, SV3-IDSA-EW-DK1EXA, SV3-IDSA-EW-DD1AXA, SV3-IDSB-EW-DK1CXB, SV3-IDSD-EW-DK1CXD,and SV3-IDSD-EW-DK1EXD into their respective raceways to verify the following attributes performed were in accordance with the design installation specification, work packages, or cable pull ticket:

• cables were routed in the correct location (i.e. respective room and raceway sections);

• cables were marked with the proper color-code designations for their respective divisions;

• cable bend radii were not exceeded during the cable pulls;

• cable mark numbers indicated on the pull tickets matched the labels on the cables;

• cable voltage and temperature ratings, and descriptions specified on the pull ticket were as indicated on the cables;

• cable insulation remained undamaged during the pulls;

• cables were ty-wrapped to the cable tray rungs at the correct frequency; and

• cables did not overlap within the cable trays.

b. Findings No findings were identified.

1A19 (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:

• 65001.01-02.04 - Key Dimensions and Volumes

• 65001.01-02.06 - Records This inspection was to verify that the minimum horizontal clearance between structural elements of the annex building and nuclear island structures was greater than or equal to three inches. These buildings consist of reinforced concrete walls and slabs, structural steel columns and floor beams. A minimum horizontal clearance of three inches between these structural elements, above floor elevation 100-0, permits horizontal motion of the buildings during the safe shutdown earthquake thus, preventing impact between structural elements from those buildings.

22

The inspectors accompanied licensee staff conducting measurements, using a standard tape, to verify that the separation between the annex building and the nuclear island was at least three inches, as required by Appendix C of the Vogtle Unit 3 COL. Specifically, the inspectors observed licensee staff measuring gaps between structural members at seven pre-selected points in accordance with as-built layout drawing SV3-4030-C0K-819000, "Verification of Seismic Gap Annex Building to Auxiliary Building Elevation 100-0," Revision 0. The inspectors reviewed approved drawing SV3-4030-C0K-819000 to verify that these measurements were documented and stored in accordance with NCSP 02-24, Revision 3. Qualification records were reviewed to determine if personnel performing surveys or measurements were qualified and knowledgeable for this activity.

b. Findings No findings were identified.

1A20 (Unit 3) ITAAC Number E.3.9.05.01.07 (855) / Family 18D (Unit 4) ITAAC Number E.3.9.05.01.07 (855) / Family 18D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number E.3.9.05.01.07 (855). The inspectors used the following NRC IPs/sections to perform this inspection:

• 65001.18-02.08-Emergency Facilities and Equipment The inspectors performed an inspection to verify a reliable and backup electrical power supply is available for the technical support center (TSC) as specified in Table E.3.9-5 of Appendix C of the Vogtle Unit 3 & 4 COL. Specifically, the inspectors observed selected portions of the TSC backup electrical power supply battery and inverter functional testing, which demonstrated the capability of the battery to supply required load and the inverter to transfer load between the normal power transformer and the battery. The inspectors observed the test to verify plant operators followed an approved procedure with appropriate quantitative acceptance criteria; test instrumentation was available and used; and test results were recorded and evaluated in accordance with 10 CFR 50, Appendix B, Criteria V and XI. The inspectors also reviewed the completed test package to verify the acceptance criteria for the test were satisfied in accordance with 10 CFR 50, Appendix B, Criterion XI.

b. Findings No findings were identified.

1A21 (Unit 4) ITAAC Number 2.1.02.02a (13) / Family 06F

a. Inspection Scope 23

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:

• 65001.06-02.01 - General Installation

• 65001.A.02.03 - Independent Assessment/Measurement Inspection

• 65001.B-02.06-Records

• 65001.F-02.02-Fabrication Records Review The inspectors reviewed records associated with the weld that joins the steam generator lower lateral support for steam generator A to module CA-01 to determine if it met the requirements of ASME BPV Code Section III subsection NF, Supports.

Specifically, the inspectors reviewed the weld process traveler to determine if work process steps had been planned and accomplished in a controlled manner. The inspectors reviewed associated E&DCRs and tensile test reports to determine if the weld joint met the design requirements of Subsection NF and acceptance criteria to prevent lamellar tearing.

The inspectors also performed an as-built inspection of the steam generator A lower lateral support. The inspectors examined the support to determine if the wall bracket clevis plate, extension bar, link bar, spacers, vertical pins, and keeper plates were installed in the correct orientation and location in accordance with the construction drawings. The inspectors took independent measurements to verify the as-built support dimensions met the specifications of the design drawings.

b. Findings No findings were identified.

1A22 (Unit 4) 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 - Inspection of ITAAC-Related Installation of Piping

• 65001.03-02.03 - Installation and Welding

• 65001.03-02.07 - Review of Records

• 65001.B- Inspection of the ITAAC-Related Welding Program

• 65001.B-02.02-Welding Procedure Qualification

• 65001.B-02.03-Welder Qualification

• 65001.B-02.04-Production Controls 24

• 65001.B-02.06-Records The inspectors performed an inspection of in-process welding for the Unit 4 pressurizer surge line piping. Specifically, the inspectors observed weld SV4-RCS-PLW-043-1, connecting pipe spools SV4-RCS-PLW-042-1 and SV4-RCS-PLW-043-1 on line RCS-PL-L003 (ASME Class 1). The inspectors observed machine GTAW on the root pass to determine if the piping was welded in accordance with PCI Energy Services welding procedure 8 MC-GTAW and the ASME Code,Section III, Subsection NB. The inspectors reviewed the weld process traveler and weld material withdrawal slip to determine if traceability of the ER316L weld wire and weld operator IDs were controlled, and quality assurance hold points were observed, in accordance with the ASME Code,Section III, Subsections NCA and NB. The inspectors observed the amperage and voltage settings of the welding machine, weld speed, and preheat temperature to determine if the values were within the range listed in the WPS.

The inspectors reviewed the receipt inspection report, CMTR, and CoC for the weld filler metal used for weld SV4-RCS-PLW-043-1 to determine if it met the requirements for chemical analysis in accordance with the ASME Code, Section II-C, SFA-5.9. The inspectors reviewed WPS 8 MC-GTAW and associated PQRs to determine if the WPS was qualified in accordance with ASME Code,Section IX. The inspectors reviewed welder performance qualification records and welder maintenance logs to determine if the welder operators were qualified and maintained proficiency for the machine GTAW weld process used for the weld in accordance with ASME Code,Section IX.

The inspectors reviewed the weld traveler to verify NDE was performed on the weld met the requirements of ASME Code,Section III. The inspectors also reviewed the computed radiography report and observed the associated images to determine whether the weld met the acceptance criteria defined in the ASME Code and whether relevant indications were identified, documented, and repaired appropriately.

b. Findings No findings were identified.

1A23 (Unit 4) 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:

• 65001.03-02.03 - Installation and Welding

• 65001.03-02.07 - Review of Records

• 65001.06-02.01 - General Installation

• 65001.B-02.04-Production Controls

• 65001.F-02.02-Fabrication Records Review 25

The inspectors performed an inspection of in-process welding and valve installation on the Unit 4 ADS stage 4 system. Specifically, the inspectors observed welding on stainless steel field welds SV4-RCS-PLW-03A-12, joining motor operated valve (MOV)

RCS-PL-V014A to pipe spool SV4-RCS-PLW-03A-1 on line RCS-PL-L136A, and SV4-RCS-PLW-03B-8, joining MOV RCS-PL-V014C to pipe spool SV4-RCS-PLW-03B-1 on line RCS-PL-L137A. The inspectors observed machine GTAW on several weld passes (including the root pass) to determine whether both piping to valve joints were welded in accordance with the requirements of ASME Code,Section III, Subsection NB, for Class 1 components. The inspectors also observed the amperage and voltage settings of the welding machine, travel speed, preheat, and interpass temperatures to determine if the values were within the range listed on the previously reviewed welding procedure WPS1-8.8T01. The inspectors observed that the pipe spools and valves were supported and aligned, the gate valve was fully closed into the seat, and the valve orientation was in the direction of fluid flow to verify valve installation was conducted in accordance with the MOV maintenance manual SV0-PV01-VMM-001.

In addition, the inspectors reviewed the WDSs and WMRs to determine if QC inspection hold points were signed-off and dated, and the traceability of the previously inspected ER316L weld filler metals and welding operators were performed in accordance with the ASME Code,Section III, Subsections NCA and NB. The inspectors also reviewed welding operator performance qualification records to determine whether the welding operators were qualified and maintained proficiency for the GTAW process used in accordance with ASME Code,Section IX.

The inspectors reviewed CMTRs to verify that the applicable chemical analysis, mechanical properties, heat treatment, corrosion and hardness testing, pressure testing, and nondestructive examination were performed on the pipe spool pieces and valve bodies in accordance with requirements of ASME Code Sections II-Part A and III-NB. The inspectors reviewed two CB&I Laurens ASME NPP-1 Code data reports to verify the fabrication activities for the piping subassemblies shown on Westinghouse Electric Company (WEC) design drawings, SV4-RCS-PLW-03A and -03B, were signed-off by the ASME NPT certificate holder and an Authorized Nuclear Inspector (ANI) in accordance with the requirements of ASME Code Section III, Article NCA-8000.

b. Findings No findings were identified.

1A24 (Unit 4) 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:

• 65001.11-02.05 - Nondestructive Examination 26

• 65001.11-02.07 - Offsite Fabrication of Assemblies

• 65001.B-02.02-Welding Procedure Qualification

• 65001.B-02.03-Welder Qualification

• 65001.B-02.04-Production Controls

• 65001.B-02.05-Inspection

• 65001.B-02.06-Records

• 65001.F-02.02-Fabrication Records Review The inspectors reviewed welding fabrication records for the Unit 4 FTT assembly that connects the refueling cavity in the containment building with the fuel transfer canal in the spent fuel building. The inspectors reviewed weld maps to determine whether base and weld materials, examinations, and testing for pressure boundary welds were in accordance with the requirements of the UFSAR chapter 3 for FTT Tag-No. FHS-FT-01 and 2001 Edition including 2002 Addenda of the ASME Code,Section III, Subsection NE.

Specifically, the inspectors reviewed stainless steel base material test records to verify if the transfer tube, flange, test angle, and hatch for mechanical properties, chemical analysis, heat treatment, hardness, and corrosion resistance were in accordance with the applicable ASME Code provisions of Section III-NE and WEC design specification APP-FT01-Z0-001 for the FTT. The inspectors reviewed stainless steel weld filler metal CMTRs to verify if the mechanical properties, chemical analysis, and ferrite numbers were as required by ASME Sections III-NE and II-Part C.

In addition, the inspectors reviewed NDE reports (including personnel certifications and visual acuity) to determine if welds were inspected by the appropriate level of NDE inspectors and found to be acceptable in accordance with ASME Section III-NE. The inspectors reviewed test reports for pneumatic, hydrostatic, vacuum box bubble leak, and functional clearance testing to verify if record entries met the requirements of the WEC fabrication specification APP-FT01-Z0-200 for the FTT. The inspectors also reviewed the WEC ASME Form N-2 code data report to determine if it was completed and signed by the ANI for a hydrostatic test pressure of 72.4 psi in accordance with ASME Sections III, NCA-8000 and NE-6000.

b. Findings No findings were identified.

1A25 (Unit 4) 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 27

• 65001.11-02.05 - Nondestructive Examination

• 65001.11-02.07 - Offsite Fabrication of Assemblies

• 65001.F-02.02-Fabrication Records Review The inspectors conducted an inspection of electrical penetration assemblies (EPAs) to determine if they were fabricated in accordance with the requirements of ASME BPV Code Section III, 2001 Edition 2002 Addenda, Subsection NE, WEC design specification and the UFSAR chapters 3 and 6. The inspectors reviewed fabrication and procurement records for the following EPAs:

• Electrical Penetration P09 (ECS-EY-P09W, S/N 9093);

• Electrical Penetration P26 (ECS-EY-P26W, S/N 9096); and

• Electrical Penetration P31 (IDSB-EY-P31Y, S/N 9111).

The inspectors reviewed ASME N-2 code data reports and CoC from the vendor to determine if the materials specified and pressure tests performed met the requirements of the ASME code and the design specification. In addition, the inspectors reviewed the data reports to verify if they were signed by an authorized representative of the N-stamp holder and an ANI.

The inspectors reviewed fabrication records to determine if the base and weld materials were fabricated in accordance with the requirements of the ASME Code,Section III, Section II, and the WEC design specifications. For the weld filler metals, the inspectors reviewed CMTRs to determine if the filler metal met the following requirements:

• chemical composition;

• tensile strength;

• yield strength;

• elongation; and

• impact testing.

For the base metal, the inspectors reviewed the fabrication plan to determine if the plan outlined the requirements of the ASME Code,Section III for material fabrication and testing. The inspectors reviewed CMTRs to determine if the base metal met the following requirements:

• chemical composition;

• tensile strength;

• yield strength;

• hardness testing;

• impact testing; and

• heat treatment.

The inspectors reviewed fabrication control plans for the welds above to verify that fabrication activities were performed in accordance with the ASME Code and the EPA design specification requirements. The inspectors reviewed the fabrication control plans to verify that weld preparation and welding were performed in accordance with the welding procedure and that NDE was performed in accordance with the vendor 28

procedures. Additionally, the inspectors reviewed the tabulation of materials to determine if the records provided traceability to all aspects of the fabrication activities, including traceability to materials, weld records, NDE reports, and nonconformance reports, as applicable.

The inspectors reviewed NDE records of the welds to determine if the NDE followed the methods and met the acceptance criteria described in the ASME Code,Section III and Section V. Specifically, the inspectors reviewed the vendor procedure QCI 9-23 to determine if it met the requirements of the ASME Code,Section V. In addition, the inspectors reviewed liquid penetrant testing (PT) reports to determine if required examinations were performed in accordance with the ASME Code,Section III, Subsection NE-5000 and Section V, Article 6, the design specification, and the vendor procedure QCI 9-23. In addition, the inspectors reviewed pneumatic testing records to determine if the pneumatic testing was performed in accordance with, and met the acceptance criteria of the ASME Code,Section III, NE-6300 and the vendor procedure IPS-2412.

The inspectors reviewed welding records and NDE records to determine if welding was performed in accordance with the ASME Code,Section III, and Section IX. The inspectors reviewed the PQRs used to qualify the welding procedures to determine if the PQRs defined the required variables specified in the ASME Code,Section IX. In addition, the inspectors reviewed material testing performed on the welding samples to determine if the type and number of qualification tests required received acceptable results in accordance with the ASME Code requirements. Additionally, the inspectors reviewed the WPSs used to verify if they were written in accordance with the ASME Code,Section IX requirements and were bounded by the PQR.

The inspectors reviewed nameplates for the EPAs to verify if the name plates were labeled with part numbers, serial numbers, tag numbers and the ASME N stamp and the name plates were visible. The inspectors reviewed corrective actions, including a condition report (CR) and material disposition report that were respectively related to a missing CMTR and a change in pneumatic test procedure to determine if the corrective actions were in accordance with the licensee's CAP.

b. Findings No findings were identified.

1A26 (Unit 4) 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.F-02.02-Fabrication Records Review

• 65001.F-02.04-General QA Review 29

The inspectors reviewed fabrication records and design documents for a sample of containment isolation valves to determine if the valves were fabricated in accordance with ASME BPV Code,Section III, Class 2, 1998 Edition 2000 Addenda and WEC design specifications. The inspectors sampled the following containment isolation valves:

• SV3-CCS-PL-V208, CCS containment isolation MOV - outlet line ORC, serial number 4-55022-L; and

• SV3-SFS-PL-V037, SFS discharge line, serial number 11899.

The inspectors reviewed fabrication records to determine if fabrication requirements of the valves and valve parts, such as material type and tests, were captured in the final as-built condition of the valves in accordance with the ASME Code, WEC design specifications, and design drawings.

The inspectors reviewed ASME NPV-1 Code data reports to determine if the materials specified and hydrostatic tests performed met the requirements of the ASME Code and the WEC design specifications. In addition, the inspectors reviewed the data reports to determine if they were signed by an authorized representative of the N-stamp holder and an ANI.

The inspectors reviewed material records associated with the following safety related and pressure retaining valve parts:

• SV3-CCS-PL-V208 (body, disc, cover plate, hex cap screw, and drive shaft);

and

• SV3-SFS-PL-V037 (body and disc).

For the valve parts above, the inspectors reviewed the CoC and CMTRs to determine if the valve part materials were fabricated in accordance with the requirements of ASME Section III, Section II, and the WEC design specifications. The inspectors reviewed these records to determine if the materials met the following requirements, as applicable:

• chemical composition;

• mechanical testing (tensile strength, yield strength, hardness); and

• heat treatment.

The inspectors reviewed NDE records (radiographic, ultrasonic, and liquid penetrant) for the valves and valve parts sampled to determine if required examinations were performed in accordance with ASME Code and the WEC design specifications, and if the results conformed to the requirements of ASME Code and the WEC design specifications.

The inspectors reviewed test reports to determine if required tests (hydrostatic shell test, valve closure and seat leakage test, packing leakage test, pneumatic seat test, and minimum wall thickness) were performed in accordance with ASME Code and the WEC design specifications, and if the results conformed to the requirements of ASME Code and the WEC design specifications.

30

b. Findings No findings were identified.

1A27 (Unit 4) 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-02.04-Production Controls The inspectors observed machine GTAW and reviewed documents for the P23 main steam penetration assembly for line A to the containment vessel sleeve. Specifically, the inspectors verified that welding of the partial joint penetration (PJP) groove weld and QC inspections were performed in accordance with the requirements of ASME Code Section III, Subsection NE, for Class MC containment. In addition, the inspectors reviewed S&W WDS for SV4-SGS-PY-C01A-1 to verify if the entries for QC inspection hold points were signed-off and dated for material identification markings, cleanliness, and joint fit-up, and the traceability for weld filler metals; and to verify that WDS were maintained in accordance with the requirements of ASME III, Subsections NCA-4134.10 and NE-4230. The inspectors also reviewed a WMR against the WDS entries to determine if traceability of the welding wire and welders were controlled in accordance with the requirements of ASME Section III, Subsections NE-4122 and NE-4320.

b. Findings No findings were identified.

1A28 (Unit 4) 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:

• 65001.03-02.03 - Installation and Welding

• 65001.03-02.06 - Nondestructive Examination

• 65001.03-02.08 - Problem Identification and Resolution

• 65001.B-02.03-Welder Qualification 31

• 65001.B-02.04-Production Controls The inspectors observed welding for three stainless steel field welds located at the 8-inch diameter discharge nozzle of the CMT B to verify that the piping for line L015B was installed in accordance with the requirements of ASME Code Section III, Subsection NB, for Class 1 components. Specifically, the inspectors observed in-process manual GTAW for welds SV4-PXS-PLW-021-7, -10, and -11 to verify if the cleanliness, fit-up and tack, internal root pass, use of amperage, and abilities of three welders to deposit sound weld metal were in accordance with welding procedure WPS1-8.8T01 using previously inspected ER316L welding rods. In addition, the inspectors reviewed the S&W WDS entries for each of these three welds to determine if QC and applicable ANI inspection hold points were signed-off and dated for material identification markings, bevel-end preparations, joint fit-up, and internal argon purge in accordance with ASME III, Subsections NCA-4134.10 and NB-4230. The inspectors also reviewed WMRs against the entries of WDSs for these three welds to determine if the traceability of the welding rods and welders were controlled in accordance with NB-4122 and NB-4300. In addition, the inspectors reviewed two welder qualification records for JCW3983 and KDW0949 to verify they were tested and certified in accordance with ASME Section IX.

The inspectors reviewed the WDS to verify the final NDE was performed and traceable to each of the three welds in accordance with the requirements of NCA-3853.5.

Specifically, the inspectors reviewed the final MISTRAS liquid penetrant and computed radiography examination reports and observed the associated radiographic images to determine whether the NDE methods and acceptance criteria of the welds were in accordance with Article NB-5000.

The inspectors reviewed N&D SV4-PXS-GNR-000063 to verify that the engineering justification and disposition for cutting and repositioning pipe spool PXS-PLW-021-3 was processed, reviewed, and approved in accordance with procedure APP-GW-GAP-428, "Nonconformance and Disposition Report (N&D)." The inspectors also observed the as-built configuration in the field to verify it matched the changes described in the N&D and the revised dimensions in the applicable drawing.

b. Findings No findings were identified.

1A29 (Unit 4) 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:

• 65001.04-02.01 - General Installation

• 65001.04-02.02 - Pipe Support and Restraint Welding 32

• 65001.B-02.04-Production Controls

• 65001.B-02.05-Inspection The inspectors reviewed the licensee's completed rigging plan for the Unit 4 PRHR HX to determine if the activities were performed in accordance with ASME Code requirements and the technical manual. The inspectors reviewed the design specification to determine if it contained instructions for handling and installation in accordance with ASME Section III, Subsection NCA-3250 and the UFSAR Section 5.2.1.1. The inspectors reviewed the technical manual, APP-ME02-Z0M-101, to determine if it included installation requirements and restrictions in accordance with the design specification. The inspectors reviewed the wind speed, ambient temperature, and total load in the completed rigging plan to determine if any stresses on the lifting lugs were exceeded. The inspectors also reviewed the completed rigging plan to determine if all steps were met and signed off by appropriate, qualified personnel.

The inspectors performed a direct welding inspection of the fillet welded connection that joins the lower CA02 structural module wall penetration to the PRHR HX, SV4-PXS-ME-01, using a circumferential mounting ring. Specifically, the inspectors observed manual GTAW and reviewed documents for both continuous fillet welds SV4-PXS-ME-01-3 using ER 309L weld rods for the dissimilar metal weld and SV4-PXS-ME-01-4 using ER308L to verify that the connections were installed in accordance with ASME Section III, Subsection NF, for supports. The inspectors reviewed both S&W WDS to verify entries for QC inspection hold points were signed-off for inaccessible surface cleanliness and fit-up (including remark to increase fillet weld size by 1/8" to make up for gap between mating surfaces). The inspectors also verified that the traceability of materials and welders were maintained in accordance with ASME III, Article NF-4000.

b. Findings No findings were identified.

1A30 (Unit 4) ITAAC Number 2.2.03.08c.iv.02 (184) / Family 03A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.03.08c.iv.02 (184). The inspectors used the following NRC IPs/sections to perform this inspection:

• 65001.01-02.04 - Key Dimensions and Volumes

• 65001.02-02.06 - Record Review

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

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

• 65001.A.02.02 - Installation Records Review

• 65001.A.02.03 - Independent Assessment/Measurement Inspection 33

The inspectors observed licensee's survey verification, performed independent evaluations, and reviewed records for the PXS containment recirculation lines and the IRWST. The inspectors reviewed the survey procedures to verify they included instructions for performing ITAAC related surveys and appropriate quantitative acceptance criteria in accordance with 10 CFR 50, Appendix B, Criterion V. The inspectors independently walked down the IRWST and pipe lines SV4-PXS-PL-L113A/B, SV4-PXS-PL-L131A/B, and SV4-PXS-PL-L132A/B during in-process installation to verify the maximum elevations of the pipe lines were lower than the bottom inside surface of the IRWST as specified in Table 2.2.3-4 of Appendix C of the Vogtle Unit 4 COL.

The inspectors observed the survey verification of the bottom inside surface of the IRWST to determine whether verified equipment was used, and the surveying was done in accordance with procedures. Additionally, the inspectors observed surveying of the bottom inside surface of the IRWST to verify the selection of survey points included the minimum elevations for the tank in accordance with the ITAAC acceptance criteria. The inspectors reviewed the survey results to verify the data was correctly recorded and translated into quality records.

b. Findings No findings were identified.

1A31 (Unit 4) ITAAC Number 2.6.03.02.i (597) / Family 08A

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.A.02.03 - Independent Assessment/Measurement Inspection The inspectors conducted an inspection of the Unit 4 battery racks mounting configuration to verify they were constructed in accordance with design. Specifically, for battery racks in rooms 12101, 12102, 12104, and 12105 at elevation 66-0, the inspectors verified the battery racks were welded to the embed plates in the same manner as was used for the seismic qualification testing as documented in APP-DB01-VBR-100 seismic qualification report and in accordance with drawing APP-1211-CE-001.

b. Findings No findings were identified.

1A32 (Unit 4) ITAAC Number 3.3.00.02a.i.a (760) / Family 01F 34

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

• 65001.01-02.05 - Steel Structures

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

• 65001.A.02.02 - Installation Records Review

• 65001.B-02.04-Production Controls

• 65001.B-02.05-Inspection

• 65001.B-02.06-Records The inspectors performed inspections of structural steel connections inside the Unit 4 containment building at elevation 107'-2" for the steel columns that support the operating floor at elevation 135'-3". The inspectors observed installation of bolted and welded connections, and reviewed drawings, welding records, and personnel qualification records.

The inspectors reviewed weld records and observed in-process welding of complete joint penetration welds FW-2 and FW-6, and fillet welds FW-8, and FW-10 associated with structure SPL 18, Sequence I. The inspectors reviewed weld maps, design specifications, and WDS to determine if weld position, amperes, volts, and filler metal requirements specified on WPS No. P1-A-Lh were in conformance with procedure No.

NCSP 03-40, and Clause 3 of AWS D1.1 2000. The inspectors also sampled four welder qualification records to verify whether they were qualified to perform the welds described on design drawings in accordance with Clause 4, Part C, of AWS D1.1 2000.

The inspectors observed storage conditions of fastener components (nuts, bolts, and washers) associated with the connections above. The inspectors evaluated the storage conditions to determine whether fastener components were stored in closed containers, free of dirt and rust, and only the necessary components were removed from protected storage prior to installation in accordance with section 2.2 of the Research Council on Structural Connections (RCSC).

The inspectors observed the installation of the following bolted connections for the SPL 18, Sequence I structure: 1057, 1057A, 1058, 1059, 1059A, 1060, 1061, and 1062to verify if the installation process was completed using the turn-of-the-nut method. Specifically, the inspectors observed torqueing of A490 bolts to verify whether the rotation amount used was specific to the bolt size as described in table 8.2 of the RCSC.

35

The inspectors reviewed qualification records for personnel installing the connections using the turn-of-the-nut method and observed QC personnel verifying the bolts were match-marked before the final torque was applied in accordance with section 6.7.7 of procedure NCSP 03-40.

The inspectors sampled two CRs associated with the structure to verify the evaluations and corrective actions were conducted in accordance with the licensee's CAP; the issues were Identified and documented in a timely manner; and the resolutions were prioritized commensurate with their safety significance. The inspectors followed up on the corrective actions associated with the CRs by reviewing the disposition of a nonconformance report associated with the SPL 18/51 structure to verify if a technical evaluation was provided and was dispositioned in accordance with APP-GW-GAP-428.

b. Findings No findings were identified.

1A33 (Unit 4) 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:

• 65001.01-02.06 - Records

• 65001.01-02.07 - Identification and Resolution of Problem

• 65001.02-02.01 - Inspection of Concrete Placement

• 65001.02-02.02 - Laboratory Testing

• 65001.02-02.03 - Special Considerations

• 65001.02-02.06 - Record Review

• 65001.02-02.07 - Problem Identification and Resolution

• 65001.02-02.08 - Construction Interface Concerns

• 65001.02-02.09 - Concrete Quality Process Problems

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

• 65001.A.02.02 - Installation Records Review

• 65001.A.02.03 - Independent Assessment/Measurement Inspection The inspectors observed concrete placement activities, observed testing activities, reviewed quality records, and performed independent inspection of the Unit 4 containment building internal structure operating deck at elevation 135'-3".

The inspectors observed concrete placement activities to determine whether approved work instructions and specifications were available in the work area and were followed throughout the concrete placement as required by the licensee's QAP and 10 CFR 50, 36

Appendix B, Criterion 5. The inspectors independently assessed the placement area prior to concrete placement to determine whether it was secure, leak tight, and free from debris or excess water as required by ACI 349-01 and SV4-CC01-Z0-031. The inspectors observed concrete placement activities and reviewed batch plant records to determine whether the following were in accordance with ACI 349-01, SV4-CC01-Z0-026, and SV4-CC01-Z0-031:

• the maximum water/cement ratio was not exceeded;

• concrete was placed in lifts;

• placement drop distances did not exceed requirements and did not result in concrete segregation;

• the time intervals between mixing and placing were less than 90 minutes and the concrete trucks had less than 300 revolutions for each batch of concrete; and

• the concrete in the concrete trucks and at the point of placement was uniformly mixed.

The inspectors evaluated a sample of the concrete batch tickets as they were being filled out and signed to verify the following were conducted in accordance with ACI 349-01 and SV4-CC01-Z0-031:

• batch records were generated, controlled, and indicated placement location, mix, volume, date, time, and special instructions;

• each truck was measured, and each trip received proper ticketing and documentation;

• the mix listed, and the weights of each constituent were reviewed prior to placing the concrete;

• each batch ticket was reviewed for transport time and truck rotations; and

• water was adjusted to account for moisture content of aggregates.

The inspectors observed adjacent, simultaneous concrete placement activities to verify coordination of structural concrete activities was completed in accordance with SV4-CC01-Z0-026. The inspectors observed field engineering and QC inspections throughout the concrete placement to verify inspection was performed during placement as required by ACI 349-01, SV4-CC01-Z0-031, and 26139-000-4MP-T81C-N3210. The inspectors reviewed the QC inspection reports for the concrete placement to verify the inspections were documented and the activities were accepted in accordance with SV4-CC01-Z0-031 and 26139-000-4MP-T81C-N3210.

During the placement, the inspectors observed in-process concrete testing to determine whether:

• concrete temperature, slump, j-ring, air content, and unit weight were determined at the proper location and frequency as required by ACI 349-01, SV4-CC01-Z0-027, 132175-102-006-04-000052, and the applicable ASTM standards;

• sample collection, testing techniques, and testing equipment conformed to ACI 349-01, SV4-CC01-Z0-027, and the applicable ASTM standards;

• test results were evaluated against applicable quantitative and qualitative acceptance criteria in accordance with 10 CFR 50, Appendix B, Criterion 5; and 37

• concrete strength test sample cylinders were made at the required location and frequency and were cured in accordance with ACI 349-01, SV4-CC01-Z0-027, and the applicable ASTM standards.

The inspectors reviewed a sample of batch tickets and test reports, including the concrete cylinder strength testing, to verify the records contained the required information in accordance with ACI 349-01, SV4-CC01-Z0-027, and the applicable ASTM standards. The inspectors reviewed the concrete cylinder break test results to verify the concrete tested met the strength requirements for the specified concrete mix in accordance with specification SV4-CC01-Z0-026. Additionally, the inspectors observed concrete curing activities and reviewed curing records to determine whether curing was in accordance with ACI 349-01 and SV4-CC01-Z0-031 with regard to the method, materials, duration, and temperature.

The inspectors reviewed CR 50015426 associated with the concrete placements to verify the evaluations and corrective actions were conducted in accordance with the licensee's CAP; the issues were identified and documented in a timely manner; and the issues were classified and resolved commensurate with their safety significance.

b. Findings No findings were identified.

1A34 (Unit 4) 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:

• 65001.02-02.01 - Inspection of Concrete Placement

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

• 65001.F-02.01-Design Document Review The inspectors observed the section of operating floor at elevation 135-3 located over the IRWST between the west wall of the refueling cavity, the south wall of the west steam generator compartment and the containment vessel. This section of floor was constructed using structural floor module CA55. For this section of floor, the inspectors reviewed the size, spacing, material designation, grade, and layout of the main reinforcing bars to verify if installation of this reinforcing steel was consistent with the applicable design drawings, E&DCRs, construction specification SV4-CC01-Z0-31, and ACI 349-01. The inspectors also reviewed the lap splices between the reinforcing bars to verify if they met the lengths specified in the concrete general notes provided on drawing SV4-0000-C9-001 and were installed in accordance with design specification SV4-CC01-Z0-31 and ACI 349-01.

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The inspectors reviewed structural calculations and design drawings to verify that the design basis was correctly translated in design output documents as required by 10 CFR 50 Appendix B, Criterion III, Design Control. Specifically, the inspectors verified if the required reinforcing steel determined by structural analysis were correctly translated into the design drawings used for construction of the floor.

The inspectors reviewed a sample of nine E&DCRs to verify if design changes were performed in accordance with 10 CFR Part 50 Appendix B, Criterion III, Design Control. Specifically, the inspectors verified that 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 if a technical justification was provided for the design change, deviations from applicable quality standards such ACI 349-01 were controlled, and the revised design was correctly translated into the updated design output documents.

b. Findings No findings were identified.

1A35 (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.A- As-Built Attributes for SSCs associated with ITAAC

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

• 65001.A.02.04 - Review As-built Deviations/Nonconformance

• 65001.B-02.01-Program and Procedures Review The inspectors observed construction activities associated with the shield building reinforced concrete/steel composite (RC/SC) horizontal transition modules located on the east side of the shield building (azimuth 67), at elevation 146-10. The inspectors observed on-going welding activities, and reviewed drawings, welding documentation, welders qualification records, and nonconformance reports.

The inspectors observed welding activities associated with the inside vertical seam between module 01B and the north jamb of the upper equipment hatch. The inspectors reviewed welders qualification records to verify their qualifications were up to date and the welders were qualified to produce sound welds in accordance with Clause 4 of AWS D1.1-2000. The inspectors also reviewed WPS P1-A-Lh(A10) (CVN-70 F) to determine whether welding position, joint configuration, amperes, volts, and filler metal requirements were in conformance with weld drawings, specification APP-1208-Z0-001, and Section IX of ASME 1998.

39

The inspectors reviewed UT reports to verify at least a 10% spot volumetric inspection was performed in accordance with Clause 6, Inspection, of AWS D1.1-2000. The inspectors also reviewed nonconformance and disposition reports to verify whether repair activities were performed in accordance with Clause 5 of AWS D1 .1-2000.

b. Findings No findings were identified.

1A36 (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 - Inspection of ITAAC-Related Foundations & Buildings

• 65001.01-02.05 - Steel Structures

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

• 65001.B-02.01-Program and Procedures Review

• 65001.B-02.02-Welding Procedure Qualification

• 65001.B-02.06-Records

• 65001.F- Inspection of the ITAAC-Related Design and Fabrication Requirements The inspectors performed document reviews and field inspections associated with the air-inlet (AI) modules located at elevation 248'-6" on the shield building. The inspectors reviewed documentation associated with the fabrication of the modules, reviewed design specifications, and performed field measurements.

The inspectors reviewed a sample of fabrication and receipt inspection documentation for AI modules AI-04 and AI-15. The inspectors reviewed CMTRs for steel plates, Nelson studs, and deformed bar anchor reinforcement tie-bars, to determine whether the materials used for assembly were in conformance with the requirements specified in table 3.8.6-4 of the UFSAR and section 10.0 of specification APP-1208-Z0-001.

The inspectors sampled a total of five WPS to verify welding processes were performed in accordance with clause 4 of AWS D1.1 2000. The inspectors also sampled design changes and nonconformance reports to determine if they were dispositioned within the requirements of ACI 349-01 and AISC N690.

The inspectors performed a walkdown of modules AI-04 and AI-15. Specifically, the inspectors performed independent measurements to determine if the as-built configuration of the modules was in conformance with approved design changes, design drawings, and the requirements of section 3.H.2.2 of the UFSAR. The inspectors also measured spacing of tie-bars, nelson studs, and the inside diameter of the air pipes to verify they were within the design tolerances specified in the general notes of drawing APP-1278-SC-150.

40

b. Findings No findings were identified.

1A37 (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.A.02.03 - Independent Assessment/Measurement Inspection

• 65001.B- Inspection of the ITAAC-Related Welding Program

• 65001.B-02.01-Program and Procedures Review

• 65001.B-02.02-Welding Procedure Qualification

• 65001.B-02.03-Welder Qualification

• 65001.B-02.04-Production Controls

• 65001.B-02.05-Inspection

• 65001.B-02.06-Records The inspectors observed in-process welding activities and reviewed records associated with the assembly of the steel composite (SC) panels for the Unit 4 cylindrical shield building. Specifically, the inspectors observed in-process FCAW activities for vertical seam weld 07A/B Vert I/O from elevation 149'-6" to 159'-6".

Additionally, the inspectors observed in-process submerged arc welding (SAW) activities with the following sections on the internal side of the horizontal circumferential weld seam between courses 7 and 8 at elevation 159'-6":

• 07D/08DE Horiz I;

• 07E/08EF Horiz I;

• 07F/08FG Horiz I; and

• 07G/08GF Horiz I.

The inspectors performed an independent visual inspection of fit-up and tack welding, intermediate passes, and portions of completed weld 07A/B Vert I/O to determine whether:

• the quality of the tack welds, weld toes, and cover passes were free from defects such as cracks, lack of fusion, or excessive overlap/undercut/porosity;

• the welds met the type, size, and location requirements of SV4-1208-Z0-001 and the WPSs; and

• the welds met the visual inspection acceptance criteria for 181816-000-WS-PR-45056 and AWS D1.1-2000.

41

The inspectors observed in-process FCAW for the vertical weld to verify intermediate weld passes were performed in accordance with the requirements of AWS D1.1:2000.

The inspectors verified the weld joint cleanliness was maintained between weld passes with staggered starts/stops and the welding operator's ability to deposit sound weld metal was performed in accordance with WPS 181816-000-WS-SP- E71T1. In addition, the inspectors observed the following attributes during in-process welding to verify welding was performed in accordance with 181816-000-WS-SP-45001:

• welding voltage, amperage, and travel speed;

• the heat input and interpass temperature;

• the joint configuration and weld position; and

• protection from wind and moisture.

The inspectors observed in-process SAW for the horizontal seam welds to verify intermediate weld passes were performed in accordance with the requirements of AWS D1.1:2000. The inspectors verified the weld joint cleanliness was maintained between weld passes with staggered starts/stops and the welding operator's ability to deposit sound weld metal was performed in accordance with WPS 181816-000-SP-ENi5S/842H. In addition, the inspectors observed the following attributes during in-process welding to verify welding was performed in accordance with 181816-000-WS-SP-45001:

• use of ENi5 classification electrode with wire spool at the work location;

• welding voltage, amperage, and travel speed resulting in cross-sectional sequenced weld bead patterns;

• SAW electrode nozzle positioning for the different locations of weld passes within the joint design to ensure complete joint penetration; and

• protection from wind and moisture.

The inspectors reviewed WPS 181816-000-SP-ENi5S/842H along with the supporting PQR to verify the WPS used for the weld joint was qualified in accordance with the requirements of the ASME Code,Section IX, including for fracture toughness. The inspectors reviewed the SAW performance qualification record for welding operator ID-No. 63171683 to verify the individual was qualified and certified in accordance with the essential variables of ASME Section IX, Article III, for welding performance qualifications. The inspectors also reviewed the weld travelers and associated spreadsheets for the weld joint locations to determine if established QC visual inspection hold points were signed-off and dated for cleanliness and fit-up alignment, and traceability of welding operators were maintained in accordance with GWPS 181816-000-WS-SP-45001.

The inspectors reviewed the UT reports for weld 07A/B Vert I/O to verify the UT was performed and documented in accordance with 181816-000-WS-PR-45054 and ANSI/AISC N690 and the weld quality met the acceptance criteria of AWS D1.1, Section 6 and Part F.

b. Findings No findings were identified.

42

1A38 (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

• 65001.B-02.05-Inspection The inspectors observed construction activities associated with the shield building RC/SC horizontal transition modules located on the east side of the shield building at elevation 146'-10". The inspectors observed interpass semi-automatic FCAW activities associated with the outside and inside vertical seams joining modules 01E/01F to verify welding was performed in accordance with AWS Code D1.1:2000.

The inspectors observed in-process FCAW for both welds to verify if the cleanliness, distortion control, use of amperage, and welder's ability to deposit sound weld metal were in accordance with previously reviewed WPS 181816-000-WS-SP-E71T1 using E71T-1M weld filler metal. In addition, the inspectors reviewed the CB&I weld traveler TRV-01039 entries for both welds to determine if QC inspection hold points were signed-off and dated for cleanliness and joint fit-up in accordance with the CB&I general welding procedure specification. The inspectors reviewed three welder qualification records to verify if their FCAW qualifications were current, and each were qualified and certified to produce sound welds in accordance with Clause 4 of AWS D1.1-2000.

b. Findings No findings were identified.

1A39 (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 43

The inspectors observed the section of wall along column 11 between column lines L and Q from elevation 117-6 to approximately elevation 135-3. For this section of wall, the inspectors reviewed the size, spacing, material designation, grade, and layout of the main horizontal, vertical, and transverse reinforcing bars to verify if installation of this reinforcing steel was consistent with the applicable design drawings, E&DCRs, construction specification SV4-CC01-Z0-31, and the applicable provisions of ACI 349-01, Chapters 1, 2, 3, 6, 7, 10, 11, 12, 14, 18, and 21. The inspectors also reviewed the lap splices between the vertical and horizontal bars, respectively, to verify if they met the lengths specified in the concrete general notes provided on drawing SV4-0000-C9-001 and were installed in accordance with design specification SV4-CC01-Z0-31 and AC349-01.

The inspectors reviewed a sample of eight E&DCRs to verify if design changes were performed in accordance with 10 CFR Part 50 Appendix B, Criterion III, Design Control. Specifically, that 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 if a technical justification was provided for the design change, deviations from applicable quality standards such ACI 349-01 were controlled, and the revised design was correctly translated into the updated design output documents.

b. Findings No findings were identified.

1A40 (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:

• 65001.01-02.07 - Identification and Resolution of Problem

• 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

• 65001.F-02.02-Fabrication Records Review The inspectors observed the section of the main control room floor between column lines 9.2, 11, I and K at elevation 117-6. For this section of floor, the inspectors reviewed the size, spacing, material designation, grade, and layout of the top and bottom reinforcing bars to verify if installation of this reinforcing steel was consistent with the applicable design drawings, E&DCRs, construction specification SV4-CC01-Z0-31, and the applicable provisions of ACI 349-01, Chapters 1, 2, 3, 6, 7, 10, 11, 12, 14, 18, and 21. The inspectors also reviewed the lap splices between the top and 44

bottom reinforcing bars, respectively, to verify if they met the lengths specified in the concrete general notes provided on drawing SV4-0000-C9-001 and were installed in accordance with design specification SV4-CC01-Z0-31 and AC349-01.

The inspectors reviewed a sample of two E&DCRs to verify if design changes were performed in accordance with 10 CFR Part 50 Appendix B, Criterion III, Design Control. Specifically, the inspectors verified that 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 if a technical justification was provided for the design change, deviations from applicable quality standards such ACI 349-01 were controlled, and the revised design was correctly translated into the updated design output documents.

The inspectors reviewed two N&Ds reports to verify if the nonconforming conditions had been documented in the corrective action program. The inspectors reviewed the disposition of the nonconforming conditions to verify if they were consistent with the requirements of ACI 349-01 and complied with the final design.

b. Findings No findings were identified.

1A41 (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.A.02.01 - Observation of in-Process Installation Activities The inspectors observed construction activities associated with the combined concrete placement of the main control room floor located on Area 2 of the auxiliary building at elevation 117'-6", and connecting wall segments at the northeast corner of the auxiliary building (i.e. wall 11 between column lines I and L and wall I between column lines 7.3 to column line 11 at elevations 117-6 up to 133-3). The inspectors reviewed quality records and observed concrete placement and testing activities. The inspectors observed concrete placement activities to determine whether placement drop distances met the requirements specified in Section 4.2.4 of specification SV4-CC01-Z0-031. The inspectors also observed the use of concrete vibrators to verify they were handled and operated to ensure consolidation of the mix was in accordance with Section 4.2.9 of SV4-CC01-Z0-031, and Section 7.5 of Concrete Placement Plan, U4 RG Combo Concrete Placement WP124, WP126, and SP-34, Revision 0.

45

During the concrete placement, the inspectors evaluated a sample of batch tickets as they were being filled out and signed by the concrete truck drivers, field engineers, and QC inspectors to determine whether each batch ticket was reviewed for the following, in accordance with specification SV4-CC01-Z0-026, Basic Requirements 5 of NQA-1 1994, and ACI code 349-01:

• verification of proper concrete mix;

• transport time and truck rotations;

• placement location;

• amount of temper water being added at the truck delivery point;

• temperature of the concrete mix; and

• ambient conditions.

The inspectors evaluated a sample of batch tickets and associated truck inspection reports after the concrete placement to verify if quality records were retrievable, verified by QC, and were identical to the ones generated during the concrete placement in accordance with Basic Requirement 18 of NQA-1 1994. The inspectors reviewed concrete pour card number 5037 and batch tickets 54424, 54439, 54441, 54443 and 54460 to determine whether concrete mix design requirements were translated from specification SV4-CC01-Z0-026 as required by NQA-1 1994, Basic Requirements 3 and 5.

The inspectors observed concrete testing activities to determine whether the processes for testing self-consolidated concrete (SCC) met the requirements of specification SV4-CC01-Z0-027. The inspectors also observed testing of fresh SCC to verify mix characteristics such as slump range, air content, mix temperature, and target wet density met the requirements of specification SV4-CC01-Z0-027. During in-process concrete testing, the inspectors observed the making and initial curing of concrete strength test sample cylinders to determine whether they were made at the required location and frequency and were cured in accordance with SV4-CC01-Z0-027. In addition, the inspectors observed the sampling of concrete strength test cylinders to verify if sample collection and testing techniques were performed in accordance with specification ASTM-C172.

b. Findings No findings were identified.

1A42 (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.A.02.04 - Review As-built Deviations/Nonconformance 46

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

• 65001.F-02.01-Design Document Review The inspectors observed the section of wall along column 7.3 between column lines I to the shield building from elevation 117'-6' to approximately elevation 135'-3'. For this section of wall, the inspectors reviewed the size, spacing, material designation, grade, and layout of the main horizontal and vertical reinforcing bars to verify if installation of this reinforcing steel was consistent with the applicable design drawings, E&DCRs, construction specification SV4-CC01-Z0-31, and the applicable provisions of ACI 349-01, Chapters 1, 2, 3, 6, 7, 10, 11, 12, 14, 18, and 21. The inspectors also reviewed the lap splices between the vertical and horizontal bars, respectively, to verify if they met the lengths specified in the concrete general notes provided on drawing SV4-0000-C9-001 and were installed in accordance with design specification SV4-CC01-Z0-31 and AC 349-01.

The inspectors reviewed an E&DCR to verify if design changes were performed in accordance with 10 CFR Part 50 Appendix B, Criterion III, Design Control.

Specifically, that 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&DCR to verify if a technical justification was provided for the design change; deviations from applicable quality standards such ACI 349-01 were controlled; and the revised design was correctly translated into the updated design output documents.

The inspectors reviewed a Licensing Amendment Request (LAR) associated with nonconforming horizontal reinforcing bars in walls 7.3 and 11 from elevations 117'-6" to 135'-3" to verify if deviations from the approved design where being identified, documented, and reconciled using the appropriate change process.

b. Findings No findings were identified.

1A43 (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.A.02.03 - Independent Assessment/Measurement Inspection The inspectors observed concrete placement in wall 11 between column lines M and Q from elevation 117'-6" to 135'-3". The inspectors attended the licensees 47

preplacement planning meeting and reviewed the placement plan to verify if preplacement planning had been completed to assure quality construction and contingency plans had been made to address unexpected events.

The inspectors reviewed two concrete batch plant tickets to verify if the batched mix conformed to the placement plan and was discharged in accordance with the construction specification. Additionally, the inspectors reviewed the results of in-process record testing and observed an in-process check test to verify if 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 reviewed placement activities to verify that drop distances did not exceed specification requirements, vibrators were used in accordance with concrete placement guidance, and licensee attention was given to areas of high reinforcing density to minimize the potential for voids or honeycombing.

b. Findings No findings were identified.

1A44 (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:

• 65001.01-02.06 - Records

• 65001.01-02.07 - Identification and Resolution of Problem

• 65001.02-02.01 - Inspection of Concrete Placement

• 65001.02-02.02 - Laboratory Testing

• 65001.02-02.03 - Special Considerations

• 65001.02-02.06 - Record Review

• 65001.02-02.07 - Problem Identification and Resolution

• 65001.02-02.09 - Concrete Quality Process Problems

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

• 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 observed concrete placement activities, observed testing activities, reviewed quality records, and performed independent inspection of the following Unit 4 radiologically controlled auxiliary building wall sections:

48

• column line 1 from column lines I to N from elevations 125'-0" to 135'-3"

• column line 2 from column lines I to J-1 from elevations 117'-6" to 135'-3"

• column line I from column lines 1 to 4 from elevations 117'-6" to 135'-3" The inspectors reviewed the concrete placement plans included in the work packages to determine whether pre-placement planning had been completed, including considerations for weather, mass concrete, and unexpected events. The inspectors observed concrete placement activities to determine whether approved work instructions and specifications were available in the work area and were followed throughout the concrete placement as required by the licensee's QAP and 10 CFR 50, Appendix B, Criterion 5. The inspectors observed concrete placement activities and reviewed batch tickets to determine whether the following were in accordance with ACI 349-01, SV4-CC01-Z0-026, and SV4-CC01-Z0-031:

• the maximum water/cement ratio was not exceeded;

• concrete was placed in lifts;

• placement drop distances did not exceed requirements and did not result in concrete segregation;

• the time intervals between mixing and placing were less than 90 minutes and the concrete trucks had less than 300 revolutions for each batch of concrete; and

• the concrete in the concrete trucks and at the point of placement was uniformly mixed.

The inspectors reviewed batch plant calibration records to verify the scales used during the concrete placements were calibrated and verified prior to use in accordance with SV4-CC01-Z0-026. The inspectors evaluated a sample of the batch tickets as they were being filled out and signed to verify the following were conducted in accordance with ACI 349-01 and SV4-CC01-Z0-031:

• batch records were generated, controlled, and indicated placement location, mix, volume, date, time, and special instructions;

• each truck was measured, and each trip received proper ticketing and documentation;

• the mix listed, and the weights of each constituent were reviewed prior to placing the concrete;

• each batch ticket was reviewed for transport time and truck rotations; and

• water was adjusted to account for moisture content of aggregates.

The inspectors observed field engineering and QC inspections throughout the concrete placement to verify inspections were performed during placement as required by ACI 349-01, SV4-CC01-Z0-031, and 26139-000-4MP-T81C-N3210. The inspectors reviewed the QC inspection reports for the concrete placements to verify the inspections were documented and the activities were accepted in accordance with SV4-CC01-Z0-031 and 26139-000-4MP-T81C-N3210. During the placements, the inspectors observed in-process concrete testing to determine whether:

• concrete temperature, slump, j-ring, air content, and unit weight were determined at the proper location and frequency as required by ACI 349-01, 49

SV4-CC01-Z0-027, 132175-102-006-04-000052, and the applicable ASTM standards;

• sample collection, testing techniques, and testing equipment conformed to ACI 349-01, SV4-CC01-Z0-027, and the applicable ASTM standards;

• test results were evaluated against applicable quantitative and qualitative acceptance criteria in accordance with 10 CFR 50, Appendix B, Criterion 5; and

• concrete strength test sample cylinders were made at the required location and frequency and were cured in accordance with ACI 349-01, SV4-CC01-Z0-027, and the applicable ASTM standards.

The inspectors reviewed a sample of batch tickets and test reports, including the concrete cylinder strength testing, to verify the records were contained the required information in accordance with ACI 349-01, SV4-CC01-Z0-027, and the applicable ASTM standards. Additionally, the inspectors reviewed the concrete cylinder break test results to verify the concrete tested met the strength requirements for the specified concrete mix in accordance with SV4-CC01-Z0-026.

The inspectors reviewed a sample of corrective action documents associated with the concrete placements to verify the evaluations and corrective actions were conducted in accordance with the licensee's CAP, the issues were identified and documented in a timely manner, and the issues were classified and resolved commensurate with their safety significance. The inspectors reviewed a sample of N&Ds associated with the concrete placements to verify the nonconformances had supporting technical evaluations and were dispositioned in accordance with APP-GW-GAP-428, "Nonconformance and Disposition Report." The inspectors reviewed an E&DCR to verify the design change had a supporting technical evaluation and was dispositioned in accordance with APP-GW-GAP-420, "Engineering and Design Coordination Reports."

b. Findings No findings were identified.

1A45 (Unit 4) ITAAC Number 3.3.00.02a.ii.c (766) / Family 01A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.02a.ii.c (766). The inspectors used the following NRC IPs/sections to perform this inspection:

• 65001.A.02.02 - Installation Records Review The inspectors reviewed concrete thickness verification reports associated with the following areas identified below to verify if the as-built concrete thicknesses were in accordance with UFSAR Table 3.3.-1:

50

• column line Q wall from shield building wall to column line 11 between elevations 100'-0" and 117'-6"; and

• floor at elevation 100'-0" from column lines k to l and shield building wall to column line 10.

b. Findings No findings were identified.

1A46 (Unit 4) ITAAC Number 3.3.00.02a.ii.d (767) / Family 01A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.02a.ii.d (767). The inspectors used the following NRC IPs/sections to perform this inspection:

• 65001.A.02.02 - Installation Records Review The inspectors reviewed concrete thickness verification reports associated with the following areas identified below to verify if the as-built concrete thicknesses were in accordance with UFSAR Table 3.3.-1:

• column line I wall from 1 to 4 between elevations 100'-0" and 117'-6";

• column line I wall from 4 to 5 between elevations 107'-2" and 117'-6";

• column line N wall from 1 to 12'-9" north of 1 between elevations 100'-0" and 125'-0";

• column line N wall from 12'-9" north of 1 to 2 between elevations 100'-0" to 118'-2 1/2"; and

• floor at elevation 105'-0" from column line I to shield building wall and from intersecting vertical wall before column line 5 to column line 5.

b. Findings No findings were identified.

1A47 (Unit 4) ITAAC Number 3.3.00.07ab (790) / Family 09A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.07ab (790). The inspectors used the following NRC IPs/sections to perform this inspection:

• 65001.09-02.02 - Attributes of Electrical Cable installation

• 65001.09-02.04 - Problem Identification and Resolution 51

• 65001.A.02.01 - Observation of in-Process Installation Activities The inspectors performed an inspection to verify Class 1E electrical raceways that route cables associated with only one division in the non-radiologically controlled area of the Unit 3 auxiliary building were identified by the appropriate color code as specified in Table 2.6.3-3 of Appendix C of the Vogtle Unit 3 COL. Specifically, the inspectors performed inspection of in-process labeling of cables and raceways in rooms 12104 (Division B 24-hour battery room) and 12105 (Division D 24-hour battery room) to verify:

• labels were pressure-sensitive and, adhesive markers installed less than 15 feet apart in accordance with UFSAR Section 8.3.2.3 and Westinghouse Design Specification APP-G1-V8-001, "AP1000 Electrical Installation Specification;"

• labels were in accordance with the division color schemes specified in UFSAR Section 8.3.2.3 and APP-G1-V8-001; and

• label identification numbering of Class 1E electrical raceways were in accordance with approved design drawings.

Additionally, the inspectors reviewed procurement documents for the labels to determine whether the licensee incorporated requirements from the electrical installation specification into the procurement documents. The inspectors also reviewed material requisition documents for the labels to determine whether the material installed met the requirements of the electrical installation specification.

b. Findings No findings were identified.

1A48 (Unit 4) ITAAC Number C.2.6.12.05 (675) / Family 08F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number C.2.6.12.05 (675). The inspectors used the following NRC IPs/sections to perform this inspection:

• 65001.16-02.04 - Design Analysis

• 65001.16-02.05 - Design Verification The inspectors performed a review of design documents, test reports and engineering analyses associated with this ITAAC. The inspectors reviewed the PCD to verify if the onsite equipment was rated to withstand and interrupt offsite fault currents. The inspectors reviewed the ratings of the onsite interface equipment and compared these to the offsite fault current analyses. The interface components reviewed during this inspection included:

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• the isolated phase bus duct and its associated equipment;

• main generator circuit breaker;

• main step-up transformer;

• unit auxiliary transformers; and

• reserve auxiliary transformers.

The inspectors reviewed the PCD of the short circuit analysis to verify if the licensee's analyses using Electrocons computer aided protection engineering (CAPE) program, version 14, followed industry accepted standards for calculating and documenting the anticipated grid available fault currents.

The inspectors reviewed qualification test reports to verify if interface components were tested in accordance with the design specifications. In addition, the inspectors reviewed drawings to verify if the interface component ratings were in accordance with the design specifications. The inspectors compared the offsite fault currents to the onsite interface component withstand and interrupting ratings to verify whether they were compatible at the interface points. The inspectors also reviewed the PCD to determine whether documents identified the author, verifier, and approver with associated signatures and dates, in accordance with the ITAAC closure procedure.

b. Findings No findings were identified.

1A49 (Unit 4) ITAAC Number C.2.6.12.06 (676) / Family 08F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number C.2.6.12.06 (676). The inspectors used the following NRC IPs/sections to perform this inspection:

The inspectors reviewed the PCD for this ITAAC to verify if the licensee's analysis, using Siemens software PSSE Version 33, satisfied the acceptance criteria. The inspectors reviewed drawings to determine if the analysis appropriately covered components associated with the power feed to the reactor coolant pumps (RCPs).

The inspectors reviewed results from two scenarios to verify the RCPs would continue to receive power for a minimum of three seconds at greater than 85% voltage, in accordance with UFSAR chapter 8.2.2. The two scenarios reviewed the power being provided by the grid upon loss of the main generator (1) through the unit auxiliary transformer, and (2) through the reserve auxiliary transformer.

The inspectors reviewed PCD drawings and graphs to determine if results appropriately considered for normal operations, anticipated operational configurations, and postulated accident conditions. Also, the inspectors reviewed drawings and specifications to determine if the PCD contained the author, verifier, and approver with signatures and dates.

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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 Quarterly Resident Inspector Corrective Action Program (CAP) Routine Review The inspectors reviewed issues entered into the licensee's 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 verify the CAP appropriately included regulatory required non-safety related structures, systems, and components (SSCs). The inspectors periodically attended the licensee's 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 licensee's CAP to determine whether the issues were appropriately classified in accordance with the licensee's QAP and CAP implementing procedures. The inspectors reviewed corrective actions associated with conditions entered into the CAP to determine whether actions to correct the issues were identified and implemented effectively, including immediate or short-term corrective actions, in accordance with the applicable QAP 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 licensee's CAP implementing procedures. The inspectors completed reviews of CAP entry logs to verify issues from different aspects of the project, including equipment, human performance, and program issues, were being identified by the licensee and its contractors at an appropriate threshold and entered into the CAP as required by licensee's CAP implementing procedures.

b. Findings No findings were identified.

1P02 Construction QA Criterion 16

• 35007-A16.04.02 - Inspection of QA Program Implementation 54

a. Inspection Scope Resident Inspector Follow-Up of Selected Issues The inspectors selected an issue that was entered into the licensee's CAP for additional follow-up inspection. The inspectors reviewed SNC CRs 50013812, 50016164, and 50019624 regarding potential 10 CFR Part 21 reportable deficiencies for welds on the Vogtle Unit 3 & 4 shield buildings. The inspectors reviewed the licensee's evaluations and corrective actions to verify the following attributes were performed in accordance with the licensee's CAP implementing procedures:

• identification of the cause of the problem in a timely manner commensurate with its safety significance and ease of discovery;

• consideration of the extent of condition, generic implications, common cause, and previous occurrences; and

• classification and prioritization of the resolution of the problem commensurate with its safety significance.

The inspectors reviewed the associated evaluations, N&D reports, Part 21 evaluations, and communications with the vendor to verify the hardware nonconformances had acceptable technical evaluations and were dispositioned in accordance with approved procedures and specifications. The inspectors reviewed the weld qualification records and revised weld procedures to verify the as-built welds were requalified in accordance with procedures and AWS D1.1-2000.

b. Findings No findings were identified.

1P03 Construction QA Criterion 16

• 35007-A16.04.01 - Inspection of QA Implementing Documents

a. Inspection Scope The inspectors selected one issue that was entered into the licensee's CAP for additional follow-up inspection. Two CRs were written for Unit 3 IDS battery division A cell terminal posts that were damaged from an electrical arc created while installing jumper cables when a cable shorted between positive and negative terminals. The inspectors reviewed the CRs to verify the licensee identified the conditions adverse to quality and the causes of the problem in accordance with ND-AD-002-025, "Issue Identification, Screening, and Dispatching." The inspectors reviewed the licensee's CR evaluations and corrective actions to verify corrective actions were appropriate to address the causes of the problem commensurate with their safety significance in accordance with ND-AD-002-025. Additionally, the inspectors reviewed the licensee's evaluations and corrective actions to verify consideration of the extent of condition, generic implications, common cause, and previous occurrences was in accordance with ND-AD-002-025. The inspectors also reviewed the trending codes applied to each item to verify they were identified, tracked, and trended in accordance with ND-55

AD-002-025. The inspectors reviewed the CRs to verify they were closed in accordance with ND-AD-002-026, "Corrective Action Program Processing", and ND-AD-002-027, "Nonconforming Items." The inspectors reviewed the associated N&D report to verify the hardware nonconformances were evaluated in accordance with APP-GW-GAP-428, "Nonconformance and Disposition Report" and performed a field walkdown of the batteries to verify the actions in the N&D had been completed.

b. Findings No findings were identified.

b. Findings No findings were identified.

1P04 Pre-operational Testing Program

• 70367 - Part 52, Inspection of Preoperational Test Program

• 70367-02.01 - Test Program

• 70367-02.02 - Test Organization

• 70367-02.03 - Test Program Administration

• 70367-02.04 - Document Control

• 70367-02.05 - Design Changes and Modifications

• 70367-02.06 - Plant Maintenance/Preventive Maintenance During Preoperational Testing

• 70367-02.07 - Equipment Protection and Cleanliness

• 70367-02.08 - Test and Measurement Equipment

a. Inspection Scope The inspectors interviewed responsible personnel, reviewed applicable documents, and observed licensee activities to confirm that the licensees administrative controls over preoperational testing were developed in accordance with UFSAR commitments and regulatory requirements.

Test Program The inspectors reviewed the B-GEN-ITPA series of procedures to determine if the licensee's preoperational testing program was specified by a formally reviewed and approved initial test program (ITP) administrative manual, containing administrative controls for the conduct of preoperational testing, consistent with the description in the UFSAR section 14.2. Additionally, the inspectors reviewed these procedures o determine if UFSAR section 14.2.1.2 was translated into the Vogtle ITP Administrative Control Manual.

The inspectors reviewed a sample of the licensee's preoperational test schedule to determine if the tests were identified and sequenced so that the safety of the plant was not dependent on untested systems, components, or features as described in UFSAR 56

section 14.2.8. Additionally, the inspectors reviewed procedures 3-RCS-ITPP-503 and 3-PXS-ITPP-502 against the licensee's procedure writing guide and the preoperational test procedure description in UFSAR section 14.2.3 to verify that the following information was identified:

• objectives for performing the test;

• prerequisites that must be completed before the test could be performed;

• initial conditions under which the test was started;

• special precautions required for the safety of personnel or equipment;

• instructions delineating how the test was to be performed;

• identification of the required data to be obtained and the methods for documentation;

• data reduction analysis methods as appropriate; and

• test acceptance criteria.

The inspectors reviewed B-GEN-ITPA-011 and NMP-AP-002 to determine if the preoperational test program specified the format and content of preoperational test procedures in accordance with UFSAR section 14.2.3. Additionally, the inspectors sampled preoperational test procedure 3-RCS-ITPP-503 to determine if content and format specifications were in accordance with B-GEN-ITPA-011 and NMP-AP-002.

Test Organization The inspectors reviewed B-GEN-ITPA-001 to determine if the ITP administrative program met the following requirements for organizational responsibilities in accordance UFSAR Section 14.2.2:

• responsibility for staffing the ITP organization; and

• lines of authority and responsibilities for test personnel.

The inspectors interviewed personnel and reviewed 26139-000-4MP-T81C-N1601 and B-GEN-ITPA-007 to verify that measures for the administrative process, responsibilities and organizational interfaces for the management of SSCs from the construction organization to the ITP organization were established in accordance with UFSAR 14.2.3.1.3 and UFSAR 14.2.2.1.2. The inspectors reviewed the following attributes of the program and process:

• specification of organizational responsibilities for managing turnover;

• identification of boundaries;

• identification and review of design engineering open items; and

• documenting results of construction testing.

The inspectors reviewed B-GEN-ITPA-003 to verify that administrative requirements were identified to ensure the independence of personnel conducting test activities and personnel responsible for performance of the design features in accordance UFSAR Section 14.2.2.2.

The inspector reviewed B-GEN-ITPA-003 to determine if requirements were established for training and qualification of the ITP organization in accordance with the current ITP organizational chart and UFSAR Section 14.2.2.2. The inspectors 57

reviewed B-GEN-ITPA-003 to verify that administrative requirements for the personnel who will manage and perform the preoperational tests were identified. Specifically, the inspectors reviewed B-GEN-ITPA-003 to determine if qualification requirements were identified for the following positions: Balance of Plant (BOP) Manager, Nuclear Instrumentation (NI) Manager, Startup Test Manger, Digital Test Manager, Test Support Supervisor, and Electrical Test Manager.

The inspectors reviewed B-GEN-ITPA-003, B-GEN-ITPA-004, and B-GEN-ITPA-011 to determine if the responsibilities, qualifications, and training of ITP test engineers were specified in writing in accordance with UFSAR 14.2.2.2 and UFSAR 14.2.2.1.4.

The inspectors reviewed these procedures to determine if the responsibilities of the ITP test engineers were identified for the development, performance, review and approval of the ITP test procedures.

The inspectors reviewed the ITP administrative manual procedure B-GEN-ITPA-002 to determine if the responsibilities for safety related preoperational test procedure approval and test results review were identified for the joint test working group (JTWG) in accordance with the UFSAR 14.2.2.3 and 14.2.3.2.1.

Test Program Administration The inspectors interviewed personnel and reviewed the administrative process, responsibilities and organizational interfaces for the management of SSCs from the construction organization to the ITP organization. Specifically, the inspectors reviewed 26139-000-4MP-T81C-N1601 and B-GEN-ITPA-007 to verify if the following attributes were incorporated in accordance with UFSAR 14.2.3.1.3 and UFSAR 14.2.2.1.2:

• specification of organizational responsibilities for managing turnover;

• identification of boundaries;

• identification and review of design engineering open items; and

• documenting results of construction testing.

The inspectors reviewed B-GEN-ITPA-004 to verify if administrative measures were established for controls of system status before and during testing. Specifically, the inspectors reviewed B-GEN-ITPA-004-F11 to verify the following attributes were addressed in accordance with UFSAR 14.2.3.1:

• pre-test walkdown;

• review of open items;

• review of system boundary, lockout/tagout;

• review of software configuration; and

• review of temporary modifications.

In addition, the inspectors reviewed B-GEN-ITPA-004 to verify administrative measures were established for jurisdictional control subsequent to ITP testing to support modifications or repairs by the construction organization in accordance with UFSAR 14.2.3.1.

The inspectors reviewed B-GEN-ITPA-001 to verify that formal administrative measures were established governing the conduct of testing in accordance with UFSAR 14.2.3.

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The inspectors reviewed B-GEN-ITPA-004 to determine if a method was established for verifying a test procedure was current before its use and ensure marked-up drawings showing current modification status were provided in accordance with B-GEN-ITPA-001. Specifically, the inspectors reviewed the requirement for the test engineer to obtain the latest revision of the test procedure and establish it as the official copy.

The inspectors reviewed B-ADM-MNT-006, B-ADM-WCO-001, and NMP-DP-001 to verify that the effect of testing on other nuclear facilities at the same site were considered in accordance with UFSAR 14.2.3. Specifically, the inspectors reviewed these procedures to verify that the planners were directed to do a risk assessment during work package preparation and activities impacting operating units were coordinated with work managers.

The inspectors reviewed B-GEN-ITPA-004 to verify that measures were established to conduct pre-job briefs in accordance with UFSAR 14.2.3.1. The inspectors reviewed NMP-GM-005-002 to verify that pre-job briefs included safety hazards and mitigating actions, operating experience, and contingency actions in accordance with B-GEN-ITPA-004.

The inspectors reviewed B-GEN-ITPA-004 to verify that a method was established to ensure personnel involved in the conduct of the test were knowledgeable of the test procedure in accordance with B-GEN-ITPA-001. The inspectors reviewed NMP-GM-005-002 to verify that pre-job briefs included responsible personnel to review the test procedure and tasks to be performed prior to the commencement of testing in accordance with B-GEN-ITPA-004.

The inspector reviewed NMP-AP-003 to verify requirements for procedure use were established in accordance with B-GEN-ITPA-004. Specifically, the inspectors reviewed the requirements for sign-offs, performance of steps, and place-keeping when performing a test procedure.

The inspectors reviewed B-GEN-ITPA-004 to verify that measures were established to change a test procedure during the conduct of testing in accordance with UFSAR 14.2.3. The inspectors reviewed NMP-AP-001-003 and B-GEN-ITPA-011 to verify that changes to test procedures during testing were appropriately initiated, documented, approved, and incorporated in accordance with B-GEN-ITPA-004.

The inspectors reviewed B-GEN-ITPA-004 and B-GEN-ITPA-011 to verify that criteria for termination or interruption of a test and continuation of an interrupted test were required to be specified in accordance with UFSAR 14.2.3.

The inspectors reviewed B-GEN-ITPA-001 and B-ADM-WCO-001 to verify that methods were established to control scheduling of test activities in accordance with UFSAR 14.2.8. Specifically, the inspectors reviewed the requirements for test schedule controls including development, duration, sequencing, overlap, and coordination with exiting operating unit work.

The inspectors reviewed B-GEN-ITPA-004 and B-GEN-ITPA-002 to verify that a formal program for evaluation of test results had been established in accordance with 59

UFSAR 14.2.3. Additionally, the inspectors reviewed B-GEN-ITPA-011 and B-GEN-ITPA-013 associated with the evaluation of test results. Specifically, the inspectors reviewed these procedures to determine that the program included the following:

• test data was verified and compared to test results in a qualitative, quantitative, meaningful and understandable form;

• test results were checked against design and compared with previously determined performance standards, limits or acceptance criteria;

• deficiencies were clearly identified, documented, and appropriate corrective action were proposed, reviewed, and completed;

• after corrective actions or modifications were completed, tests or portions of a test were rerun as necessary to ensure that tests on the as-built system were adequate and meet standards, limits or acceptance criteria; and

• test result evaluations were reviewed and formally approved by appropriate licensee personnel and/or contractor personnel, including the person(s) responsible for approving the original test procedures.

Document Control The inspectors reviewed B-GEN-ITPA-011 and B-GEN-ITPA-002 to verify that administrative measures were established which control the test procedure processes for review, approval, and issuance in accordance with UFSAR 14.2.3.1. Additionally, the inspectors reviewed NMP-AP-001-003 to verify that the review process required reviewers to be qualified individuals in accordance with B-GEN-ITPA-011. The inspectors also reviewed NMP-AP-001-003 to determine if the procedures were reviewed against defined quality attributes, required a managers approval, and issuance of the procedure was completed by individuals with appropriate access authority in accordance with B-GEN-ITPA-011.

The inspectors reviewed B-GEN-ITPA-004 to verify that administrative measures were established which control revision of approved procedures in accordance with UFSAR 14.2.3.1. Specifically, the inspectors reviewed B-GEN-ITPA-011 and NMP-AP-001-003 to verify that the revision of approved procedures included the following controls in accordance with B-GEN-ITPA-004:

• review by same persons and/or groups as the original procedure;

• approval by same persons and/or groups as the original procedure;

• issuance of revisions and control of obsolete procedures; and

• screen changes to test procedures to determine if a change to UFSAR is needed.

The inspectors reviewed B-GEN-ITPA-011 and B-GEN-ITPA-015 to verify that operating procedures to be used during preoperational testing have administrative controls to ensure that they receive the same reviews and approvals required for preoperational test procedures in accordance with UFSAR 14.2.6.

The inspectors reviewed B-GEN-ITPA-011 and B-GEN-ITPA-015 to verify that responsibilities were assigned in writing to verify that procedure controls will be implemented in accordance with UFSAR 14.2.3.1. Specifically, the inspectors reviewed these procedures to determine if the responsibilities to review, approve, and issue procedures were included for ITP personnel.

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The inspectors reviewed 26139-000-4MP-T81CN1601 to verify that administrative controls were adequately established to provide current approved drawings and vendor technical manuals to the plant site in a timely manner in accordance with UFSAR 14.2.2.3.

The inspectors reviewed ND-DC-001 and NMP-AD-025 to verify that a master index was available for drawings and manuals which indicate their current revision numbers in accordance with UFSAR 14.2.3.1.3. Additionally, the inspectors observed licensee personnel use the document management system to retrieve drawings and manuals with indication of current revision numbers.

Design Changes and Modifications The inspectors reviewed B-GEN-ITPA-001 and B-GEN-ITPA-004 to verify that appropriate measures were in place to govern and control modifications or design changes to SSCs within the ITP scope in accordance with UFSAR 14.2.3.1 and 10 CFR 52.98. The inspectors reviewed the interfaces that existed between the test organization and design authority (WEC) to track and disposition equipment test issues through test deficiency reports and engineering service requests as inputs to a formal design changes process.

The inspectors also reviewed a sample of engineering service requests (ESRs) related to reserve auxiliary transformer switchyard breaker testing to determine that coordination existed between the test organization and WEC to resolve test performance issues through the WEC formal engineering evaluation process in accordance with B-GEN-ITPA-001 and B-GEN-ITPA-004.

The inspectors interviewed ITP personnel and reviewed B-GEN-ITPA-001, B-GEN-ITPA-010, and B-GEN-ITPA-015 to verify that formal processes were developed and implemented to control SSC status with respect to temporary system configurations and modifications in accordance with UFSAR 14.2.3.1. The inspectors interviewed ITP test managers and test engineers to determine that they were cognizant of processes related to temporary configuration changes and modifications. The inspectors interviewed selected electrical test engineers to verify their awareness of the temporary modification procedure, configuration control requirements, and the need to perform pre-test walkdowns in accordance with B-GEN-ITPA-004 and B-GEN-ITPA-004-F08.

The inspectors examined a sample of temporary modification documents and test narrative logs to determine if appropriate detail regarding temporary modification installation and restoration was included in the narrative and that engineering evaluations were included in accordance with UFSAR 14.2.3.1. Specifically, the inspectors reviewed active temporary modification and temporary operating plan documentation to verify that documentation was being maintained in the ITP work control center. The inspectors reviewed selected active temporary modifications associated with electrical testing to verify that they included instructions for engineering evaluation, control of electrical jumpers, and control of lifted leads.

Plant Maintenance and Preventative Maintenance The inspectors reviewed B-GEN-ITPA-001, B-GEN-ITPA-004, NMP-MA-012, and B-ADM-MNT-006 to verify that controls for the conduct of maintenance for SSCs were in 61

place and coordinated during initial test activities in accordance with UFSAR 14.2.3.1.5. The inspectors reviewed interfaces between the test groups and maintenance support to determine if test deficiencies were resolved through troubleshooting and corrective maintenance. The inspectors reviewed a sample of test deficiency reports related to main AC power system (ECS) system testing to verify that maintenance support was active in retesting of components.

The inspectors reviewed NMP-ES-006 to verify that a preventive maintenance (PM) strategy was in place for SSCs throughout the scope of the initial test program in accordance with UFSAR 14.2.3.1.5. Specifically, the inspectors reviewed the controls in effect to ensure periodic maintenance/surveillance activities would be performed for all SSCs, including those in a test environment. The inspectors reviewed specific PM support requirements to verify that SSCs in test environments were delegated to Maintenance Support and implemented through plant equipment preservation.

The inspectors reviewed B-ADM-WCO-001 to verify that the designated Work Controls Manager and Test Coordinator also functioned to coordinate, schedule, and review PM activities in accordance with B-GEN-ITPA-001. The inspectors reviewed Bechtel procedure 26139-000-4MP-T81C-N1601 and ND-AD-VNP-029 to verify that the maintenance support group and test engineers were given direction for coordination of PM activities as part of turnover from construction-to-testing-to-operations in accordance with B-ADM-WCO-001.

The inspectors reviewed NMP-AD-025 to verify that a process was developed and implemented for control, archiving, storage and retrieval of QA and non-QA maintenance and work package documents (records) for SSCs as they are turned over from construction to testing in accordance with UFSAR 14.2.3.1.3. The inspectors observed the process for work package closure and transmittal of work order documentation to the document management system to determine that maintenance work order documents were being adequately controlled in accordance with B-ADM-MNT-005.

Equipment Protection and Cleanliness The inspectors reviewed NMP-MA-054, B-GEN-PLMC-076, B-ADM-PLMM-002, "B-GEN-ITPA-004, B-GEN-ITPA-007, and 26139-000-4MP-T81C-N2102 to verify that a formal program for housekeeping activities during preoperational testing has been established in accordance with NQA-1-1994 Subpart 2.1 Section 8, Subpart 2.2 Section 2, and Subpart 2.3. The inspectors also reviewed the housekeeping program to verify that responsibilities were assigned in writing for program implementation in accordance with NQA-1-1994 Subpart 2 Sections 3 and 4. Specifically, the inspectors reviewed the housekeeping program to determine if provisions had been included for the following control methods:

• protection of equipment and control of personnel access to prevent damage from adjacent construction activities;

• implementation of cleanliness zones, keyed to the progress of construction and testing;

• control of facilities and equipment including cleanliness, environment, and fire protection/prevention; and

• periodic inspection to ensure the adequacy of housekeeping.

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The inspectors reviewed B-GEN-PLMC-076, B-GEN-ITPA-004, B-GEN-ITPA-014, NMP-MA-009-001, and APP-GW-GEM-200 to verify that a program for maintaining the appropriate degree of cleanliness of nuclear plant components and piping during preoperational testing was established in accordance NQA-1-1994, Subpart 2.1 Section 8.

The inspectors reviewed B-GEN-ITPA-011, B-GEN-ITPA-014, APP-GW-GEM-200, "AP1000 Chemistry Manual," and B-GEN-PLMC-076 to verify that water chemistry controls were established for fluid system undergoing preoperational testing in accordance with UFSAR Section 5.2.3.2.1 and NQA-1-1994 Subpart 2.1 Section 8.

Specifically, the inspectors reviewed the water chemistry controls to determine if the following controls were established:

• water quality requirements;

• layup of systems and components;

• sampling requirements; and

• procedures to be followed for "out-of-specification" conditions.

Test and Measurement Equipment The inspectors reviewed B-GEN-ITPA-004, B-GEN-ITPA-011, NMP-MA-053, and 26139-000-4MP-T81C-N7102 to verify that controls were established for special test equipment and all instrumentation used to provide data in accordance with NQA 1994, Basic Requirement 12 and NQA-1-1994, 12S-1. Specifically, the inspectors reviewed administrative controls for special test equipment and instrumentation to determine if acceptance criteria had been met or significant limitations were not exceeded that included:

• a listing of controlled test equipment, the calibration requirements, and the calibration history;

• controls for storage and issuance to preclude use of test equipment which had not been calibrated within the specified interval;

• requirements for recording test equipment identity and calibration date in test procedures to permit retest if equipment was subsequently found out of calibration;

• controls for ensuring that installed instrumentation had been calibrated before being used to provide data to show an acceptance criterion had been met; and

• requirements for actions to be taken when M&TE or reference standards was found out of calibration, lost, or stolen, including a documented evaluation of the validity of previous tests.

b. Findings No findings were identified.

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3. OPERATIONAL READINESS Cornerstones: Operational Programs IMC 2504, Construction Inspection Program - Inspection of Construction and Operational Programs 3P01 License and Non-Licensed Plant Staff Training Program

• 41501-02.03 - Accreditation

a. Inspection Scope The inspectors reviewed the renewed accreditation letters from INPO's National Academy for Nuclear Training to the licensee and confirmed accreditation had been renewed for the following Vogtle Electric Generating Plant Units 3 & 4 training programs: non-licensed operator, reactor operator, senior reactor operator, shift manager, continuing training for licensed personnel, shift technical advisor, instrument and control technician, electrical maintenance personnel, mechanical maintenance personnel, radiological protection technician, chemistry technician, and engineering support personnel.

b. Findings No findings were identified.

3P02 Preservice Inspection

• 73054-02.01 - Program Approval

• 73054-02.02 - Program Organization

• 73054-02.03 - Program Scope

• 73054-02.05 - Code Repair/Replacement Program Review

a. Inspection Scope The inspectors conducted an onsite review of the implementation of the licensees preservice inspection (PSI) program for Unit 3. The PSI program is designed to provide the baseline examination data for which future inservice inspection (ISI) results can be compared to monitor degradation of pressure retaining components in vital system boundaries. The scope of this program included components within the reactor coolant system boundary, risk-significant piping boundaries, and containment system boundaries.

The inspectors reviewed the PSI program plan to verify that any proposed alternatives to the ASME Code Section XI requirements were approved by the NRC prior to use in accordance with 10 CFR 50.55a(z). In addition, the inspectors reviewed the licensees 64

process for demonstrating alternative examination methods to the Authorized Nuclear Inservice Inspector (ANII) to verify if their process was in accordance with ASME Code Section XI, IWA-2240.

The inspectors reviewed the following repair/replacement activities to verify if they were performed in accordance with ASME Code Section III requirements and evaluated for any 10 CFR 50.59 impact:

• N&D: SV3-RCS-GNR-000046; and

• N&D: SV3-MV01-GNR-000013.

The inspectors obtained drawings of all ASME Code Class 1 piping systems and components. The inspectors reviewed the drawings to verify if the ASME Code Class boundaries were identified in accordance with 10 CFR 50.55a. The inspectors reviewed 15% of the ASME Code Class 1 components listed in the licensees PSI database to verify if appropriate examination category, item number, and examination method were listed in accordance with ASME Section XI, IWB-2500 requirements.

The inspectors also reviewed the licensees PSI database to verify that all items (welds, bolted connections, integral attachments, interior surfaces, etc.) associated with the selected components subject to inspection per ASME Section XI, IWB-2500 were identified. In addition, the inspectors performed this database review to very if the appropriate number of items subject to inspection were selected for preservice examination in accordance with ASME Section XI, IWB-2200. The sample included the following components:

• reactor vessel (MV-01);

• steam generator 01 (MB-01);

• passive residual heat removal heat exchanger (ME-01);

• pressurizer (MV-02);

• core makeup tank (MT-02a);

• RCS piping system;

• welds associated with valves (RCS-PL-V004A, RCS-PL-V012B);

• welds associated with piping lines (RCS-L137A, RCS-L213)

• PXS Piping System;

• welds associated with valves (PXS-PL-V122A, PXS-PL-V016A, PXS-PL-V122B, PXS-PL-V014A);

• welds associated with piping lines (PXS-L021A, PXS-L102, PXS-L015A, PXS-L125A);

• chemical and volume control system (CVS) Piping System;

• welds associated with piping lines (CVS-L038);

• normal residual heat removal system (RNS) Piping System; and

• welds associated with valves (RNS-PL-V002B).

The inspectors obtained drawings for a sample of ASME Code Class 2 piping systems and components. The inspectors reviewed the drawings to verify that the ASME Code Class boundaries were identified in accordance with 10 CFR 50.55a. The inspectors reviewed a sample of components associated with three ASME Code Class 2 systems listed in the licensees PSI database to verify that appropriate examination category, item number, and examination method were listed and in accordance with ASME 65

Section XI, IWC-2500 requirements. The inspectors also reviewed the licensee PSI database to verify if all bolted connections, welds, and welded attachments associated with the selected components subject to inspection per ASME Section XI, IWC-2500 were identified. The sample included the following components and piping systems:

• RCS;

• RNS; and

• steam generator system (SGS).

The inspectors obtained drawings for all ASME Code Class 3 components, piping, and welded attachments. The inspectors reviewed the drawings to verify if the ASME Code Class boundaries were identified in accordance with 10 CFR 50.55a. The inspectors reviewed the ASME Code Class 3 components listed in the licensees PSI database to verify if appropriate examination category, item number, and examination method were listed in accordance with ASME Section XI, IWD-2500 requirements.

The inspectors reviewed the licensees PSI database to verify if the welded attachments associated with the components subject to inspection per ASME Section XI, IWC-2500 were identified and the appropriate number were selected for preservice examination as required by ASME Section XI, IWD-2200. In addition, the inspectors walked down components present on site to verify if the accuracy of welded attachment details shown in the drawings was the same as that implemented on the component. The review included the following components/piping:

• accumulators (MT-01A/B);

• 10 pipe from the IRWST to direct vessel injection (DVI)-B (PXS-L112B);

• 16 ADS pipe to sparger B (PXS-L130B); and

• 6 pipe from fuel transfer canal (FTC) to spent fuel cooling system (SFS) pumps (SFS-PL-L047).

The inspectors obtained a total of 30 piping isometric drawings from ASME Code Class 1, 2, and 3 systems that indicated pipe support designation and location. Using the drawings, the inspectors identified all supports subject to inspection per ASME Section XI, IWF-2500 to verify if they were listed in the licensees PSI database and assigned the appropriate examination category, item number, and examination method. The inspectors also reviewed the licensees PSI database to verify if the appropriate number of supports were selected for preservice examination as required by ASME Section XI, IWF-2200. The sample included the following systems:

• RCS;

• RNS;

• PXS; and

• SGS.

The inspectors reviewed the following augmented inspections to verify if they were included in the PSI program plan as required by the UFSAR and other licensee commitments:

• inspection of high energy fluid system piping between containment isolation valves (break exclusion zone);

• inspection of piping systems qualified for Leak-before-Break; 66

• visual and volumetric preservice examination requirements of Code Case N-729-4; and

• inspection of weld buildups, including reactor vessel head quickloc nozzles, CVS nozzles, and core make-up tank (CMT) inlet and outlet nozzles.

b. Findings No findings were identified.

4. OTHER INSPECTION RESULTS 4OA5 Other Activities Review of National Academy for Nuclear Training Maintenance and Technical Training Assessment Report The inspectors reviewed the National Academy for Nuclear Training Maintenance and Technical Training Assessment Report of Vogtle 3&4 maintenance and technical training programs dated July 17, 2019. During this review, the inspectors did not identify any new significant training issues.

4OA6 Meetings, Including Exit On October 16, 2019, the inspectors presented the inspection results to Mr. M. Meier, SNC Vice President of Regulatory Affairs, and other licensee and contractor staff members. Proprietary information was reviewed during the inspection period but was not included in the inspection report.

67

SUPPLEMENTAL INFORMATION KEY POINTS OF CONTACT Licensees and Contractor Personnel R. Beilke, ITAAC Project Manager B. Bennett, Security Supervisor C. Castell, SNC Licensing Engineer S. Gambill, SNC Electrical Test Engineer B. Hirmanpour, SNC I&C Manager J. Hurst, WEC ASME S. Leighty, SNC Licensing Supervisor D. Martrano, WEC Test Coordinator E. Odem, SNC Supervisor, Maintenance Preservation L. Pritchett, SNC Licensing Engineer K. Roberts, SNC, Licensing Manager G. Scott, SNC Licensing Engineer N. Wetherell, SNC Electrical Test Manager M. Wilson, SNC Electrical Test Engineer M. Yox, SNC Regulatory Affairs Director LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED Item Number Type Status Description None LIST OF DOCUMENTS REVIEWED Section 1 Section 1A01 WEC APP-RCS-M6-001, "Piping and Instrumentation Diagram Reactor Coolant System" (F-6),

Revision 17 WEC APP-RCS-PLW-03A, Reactor Coolant System Containment Building Room 11301 ADS Stage 4 Piping West Compartment, Revision 5 S&W Weld Data Sheet (WDS) SV3-RCS-PLW-03A-1 (Work Package SV3-RCS-P0W-800021),

2/4/2019 (3 pages)

S&W Welding Material Requisition (WMR) 443090, 464899, 464904, 465018, 465580, and 469366 Attachment

S&W Weld Data Sheet (WDS) SV3-RCS-PLW-03A-2-C (Work Package SV3-RCS-P0W-800021), 6/13/2019 S&W Welding Material Requisition (WMR) 465495, 465497, and 465632 S&W Record of Welder Performance Qualification Test - ASME Section IX Groove Weld for DPW6171, EBF8327, JRS0561, KWS2254, and RTM4678 Section 1A02 2.1.02.05a.i-U3-EQRR-PCD002, "EQ Reconciliation Report (EQRR)," ADS Sparger B (PXS-MW-01B), Revision 0 Section 1A03 APP-PV70-V2-003, "14" Squib Valve Assembly Drawing Sheet 1 of 3," Revision 3 SV3-PV7C-V6-002, "14" Inch Squib Valve Class 2500 Weld Neck Flange," Revision 1 SV3-PV70-VQQ-002, "Quality Release & Certificate of Conformance for PV70 Squib Valves,"

Revision 3 SV3-RCS-P0K-800036, "ADS Stage 4 Valves Elevation of Bottom Inside Surface of Outlet and Direction of Discharge," Revision 0 Survey Report 1122334, 8/29/19 Condition Report 50028484, "14-Inch Squib Valve Documentation Discrepancy" Section 1A04 Westinghouse Newington WPSs: I-20-8.8-30 Revision 3; I-30-8.8-20 Revision 2; VI-20-8.8-24 Revision 1; VI-20-8.8-28 Revision 0; VI-25-8.8-8 Revision 1; VI-35-8.8-21 Revision 0; VI-35-8.8-22 Revision 4 PQRs: GMA-8.8-1G-12 Revision 3; GMA-8.8-1G-9 Revision 0; SMA-8.8-1G-4 Revision 1; SA-8.8-1G-10 Revision 0; SA-8.8-1G-6 Revision 2; SMA-8.8-1G-4 Revision 1; SMA-8.8-1G-3 Revision 2; GTA-8.8-1G-10 Revision 2; GTA-8.8-1G-6 Revision 1; GTA-SMA-8.8-2G-3 Revision 4

AT&F Nuclear WPS WPSN-030 Revision 2 PQR PQRN-012 Revision 1 Section 1A05 Weld SV3-CCS-PLW-812-6 WEC APP-CCS-M6-002, "Piping and Instrumentation Diagram Component Cooling Water System" (H-2), Revision 11 S&W Weld Data Sheet (WDS) SV3-CCS-PLW-812-6 (Work Package SV3-CCS-P0W-1004882),

2/7/2019 S&W Welding Material Requisitions (WMR) 465584 and 465587 S&W Record of Welder Performance Qualification Test - ASME Section IX Groove Weld for BS0668 and RLB4485 Weld SV3-SFS-PLW-520-2 WPS1-8.8T01, Manual and Machine GTAW of P-No. 8 to P-No. 8, ASME III All Subsections &

Non-ASME III," Revision 10 SV3-SFS-PLW-521, Spent Fuel Pool Cooling System Auxiliary Building Room 12454 Supply from SFS Pumps, Revision 3 SV3-SFS-PLW-520, Spent Fuel Pool Cooling System Auxiliary Building Room 12454 Supply from SFS Pumps, Revision 1 2

Stone & Webster, Inc. Welding Material Requisition (WMR) 465897, 7/19/2019 Stone & Webster, Inc. Weld Data Sheet, Weld No. SV3-SFS-PLW-520-2, 8/16/2018 S&W Record of Welder Performance Qualification Test - ASME Section IX Groove Weld for DKC1089 Lincoln Electric Company CMTR 7341106 ES-RAXM, Q3 Lot 1243R, 1/8" X 18" ER308/308L Rods of SFA-5.9, 9/18/2015 Section 1A06 SV3-CCS-PLW-820, Component Cooling Water System Auxiliary Building Room 12405 Return Conn. from CCS IRC Loads, Revision 2 SV3-PV11-Z0-001, Design Specification for Butterfly Valves, ASME Boiler and Pressure Vessel Code III Class 2 and 3, Revision 7 SV3-PV11-Z0D-122, PV11 Data Sheet 122, Revision 2 Material Issue Report 26139-19-MIR-35285, 7/8/2019 Section 1A07 2.2.01.05.i-U3-EQRR-PCD002, "EQ Reconciliation Report (EQRR)," Fuel Transfer Tube (FHS-FT-01), Revision 0 Section 1A08 SV3-PXSW-ITR-800182, "Unit 3: ITAAC 182 Walkdown 2.2.03.08c.iii NRC Index Number 182,"

Revision 0 SV3-PXS-M6K-800182, "RCS Cold Leg to the High Point of the CMT "A" Inlet Line," Revision 1 SV3-PXS-M6K-801182, "RCS Cold Leg to the High Point of the CMT "B" Inlet Line," Revision 1 SV3-PXS-M6K-802182, "RCS Hot Leg to the High Point of the PRHR HX Inlet Line," Revision 1 Section 1A09 Drawings:

SV3-PXS-M6-001, "Piping and Instrumentation Diagram Passive Core Cooling System,"

Revision 5 SV3-PXS-M6-002, "Piping and Instrumentation Diagram Passive Core Cooling System,"

Revision 8 SV3-PXS-MTK-891586, "IRWST Bottom Inside Tank Surface Comparison to DVI Nozzle Centerline Elevation," Revision 0 SV3-PXS-PLW-01A, "Passive Core Cooling System Containment Bldg. Room 11206 from Containment Recirc. to DVI-A," Revision 0 SV3-PXS-PLW-01B, "Passive Core Cooling System Containment Bldg. Room 11206 Containment Recirc. Valves," Revision 2 SV3-PXS-PLW-01C, "Passive Core Cooling System Containment Bldg. Room 11206 Containment Recirc. to DVI-A," Revision 1 SV3-PXS-PLW-01D, "Passive Core Cooling System Containment Bldg. Room 11206 Containment Recirc. to DVI-A," Revision 1 SV3-PXS-PLW-01H, "Passive Core Cooling System Containment Building Room 11206 Containment Recirc. to DVI-A," Revision 1 SV3-PXS-PLW-01Z, "Passive Core Cooling System Containment Building Room 11206 Containment Recirc. to DVI-A," Revision 2 SV3-PXS-PLW-02A, "Passive Core Cooling System Containment Building Room 11207 Containment Recirculation to DVI-B," Revision 0 SV3-PXS-PLW-02B, "Passive Core Cooling System Containment Bldg. Room 11202, 11207 from Containment Recirculation to DVI-B," Revision 1 3

SV3-PXS-PLW-02C, "Passive Core Cooling System Containment Bldg. Room 11202, 11207 Containment Recirculation to DVI-B," Revision 1 SV3-PXS-PLW-02E, "Passive Core Cooling System Containment Building Room 11207 IRWST to DVI-B & RNS Pump Suction," Revision 1 SV3-PXS-PLW-02Z, "Passive Core Cooling System Containment Building Room 11207 Containment Recirculation to DVI-B," Revision 0 SV3-PXS-PLW-090, "Passive Core Cooling System Containment Bldg. Room 11204 Containment Recirculation to DVI-B," Revision 1 SV3-PXS-PLW-470, "Passive Core Cooling System Containment Bldg. Room 11206 from Containment Recirc. Valves," Revision 1 Miscellaneous:

Certificate of Calibration for the Trimble S9 Total Station, T14, 38320012, 3/15/19 Principle Closure Document SV3-PXS-FSK-800183, "As-Built IRWST Injection Lines Top Inside Surface Elevation Comparison to IRWST Bottom Inside Surface," Revision 1 Principle Closure Document SV3-PXS-FSK-800184, "As-Built IRWST Injection/ Recirculation Lines Top Inside Surface Elevation Comparison to IRWST Bottom Inside Surface," Revision 0 Principle Closure Document SV3-PXS-FSK-800185, "CMT Disch Line EL vs CMT Inside Bottom EL, Vogtle Unit 3 PCD Review," Revision 0 Survey Data Obtained from SWR Number 1048162 Survey Data Obtained from SWR Number 1110243 Procedures:

26139-000-4MP-T81C-N3201, "Construction Survey," Revision 5 26139-000-4MP-T81C-N7102, "Control of Measuring and Test Equipment," Revision 2 NCSP 02-24, "ITAAC Support Activities (AP1000)," Revision 02.00 SV3-PL02-Z0-001, "Piping Class Sheets and Standard Details," Revision 7 Section 1A10 Drawing SV3-MS59-V2-001, "AP1000 Vendor Drawing Air Filter Unit Assembly Sheet 1 of 2,"

Revision 0 Drawing SV3-MS59-V2-002, "AP1000 Vendor Drawing Air Filter Unit Assembly Sheet 2 of 2,"

Revision 0 Work Package SV3-VES-MYW-1024242, "U3 Auxiliary Install VES HVAC Inline Equipment for ISOs: SV3-VES-MD-420 & SV3-VES-MD-429," Revision 0 Section 1A11 WO SV3-1222-DTW-800000, "U3 IDSC Regulating Transformer Aux Building 82'6" RM 12203, Area 2," Revision 0 APP-1220-GEF-369, "Auxiliary Building Anchor Bolt Drawings Require Corrections to Tag Numbers," Revision 0 APP-DT01-Z0-010, "Design Specification for Class 1E Regulating Transformers," Revision 8 SV3-1222-CE-003, "Auxiliary Building Area 2 Division C Electrical Cabinet Anchor Bolt Locations Room 12203, Plan EL 82'6"," Revision 1 ESR50028839, "Use EDCR APP-DC01-GEF-850000 to Address Other Equipment," 9/11/19 APP-DC01-GEF-850000, "Mounting Detail for DC01 Battery Chargers," Revision 0 WO SV3-IDSD-EAW-1021443, "U3-Aux Install and Label Electrical Equipment SV3-IDSD-EA-1 and SV3-IDSD-EA-2-ELEV. 100'0" Area 1 Room 12305," Revision 0 SV3-IDSD-DDW-1021447, "U3- Aux Install and Label Electrical Equipment SV3-IDSD-DDD-1, Elevation 100'-" Area 1, Room 12305," Revision 0 4

SV3-DD01-Z01-010, "Design Specification for Class 1E 250 VDC Distribution Panels for System IDS," Revision 5 APP-EA01-GEF-850002, "Mounting Details for Class 1E AC Distribution Panels," Revision 0 APP-EA01-V0M-001, "AP1000 EA01 Class 1E AC Distribution Panels-Technical Manual,"

Revision 1 APP-DD01-J0M-001, "AP1000 DD01 Class 1E Distribution Panels, Multipurpose Manual:

Technical Manual," Revision 1 SV3-IDSB-DKW-1023085, "U3- AUX -Install and Label Electrical Equipment (IDSB-DK-1),

Room 12304- Elev. 100'0" Area 1", Revision 0 APP-DK01-GEF-850007, "Alternate Detail to facilitate mounting IDSB-DK-1 cabinets with four corner bolts per enclosure," Revision 0 APP-DK01-GEF-850009, "DK01 Cabinet Mounting Shims," Revision 0 ESR50024886, "Alternate Mounting Detail," 7/22/19 WO SV3-IDSB-EAW-1032132, "U3 Aux Install & label 1E Fuse Panels (IDSB-EA-4, 5 & 6) Elev.

100'0"- Room 12304- Area 1," Revision 0 SV3-EA03-V0M-850000, "EA03 Class 1E Fuse Panels Technical Manual," Revision 0 WO SV3-IDSB-EAW-1003048, "U3 Aux Install and Label Battery Monitor Fuse Panels (SV3-IDSB-EA-7, 8) Elev. 82-'6"- Room 12207- Area 2," Revision 0 SV3-EA03-Z0-001, "Design Specification for Class 1E Fuse Panels for IDS System," Revision 9 ESR50029150, "U3 Class 1E IDS Fuse Panels Mounting Hardware, EL 82'," 9/14/19 SV3-1222-CE-004, "Auxiliary Building Area 2 Division C Electrical Cabinet anchor bolt locations Room 12207- Plan El 82'6"," Revision 1 SV3-1220-CE-997, "Auxiliary Building Areas 1&2 Anchor Bolt Details Plan at el 83'-6"," Revision 0

Section 1A12 WEC Isometric Drawing No. APP-VBS-PLW-030, "Nonradioactive Ventilation System Auxiliary Bldg Room 12401 Ventilation to MCR," Revision 4 WPS1-1.1C21, Manual GTAW and SMAW with supporting PQRs, Revision 4 S&W Weld Data Sheet (WDS) SV3-VBS-PLW-030-9 for work package SV3-VBS-P0W-1008052, 5/9/19 Record of Welder Performance Qualification Test 1CS-02 for Richmond County Constructors, Welder ID JEA4497, 09/16/2019 Record of Welder Performance Qualification Test 1CS-03 for Richmond County Constructors, Welder ID JEA4497, 09/16/2019 Record of Welder Performance Qualification Test 1CS-02 for Richmond County Constructors, Welder ID SLH6930, 05/20/2019 Record of Welder Performance Qualification Test 1CS-03 for Richmond County Constructors, Welder ID SLH6930, 05/20/2019 S&W Weld Data Sheet (WDS) SV3-VBS-PLW-030-14 for work package SV3-VBS-P0W-1008052, 5/9/19 S&W Welding Material Requisition (WMR) 478944, 9/5/19 Record of Welder Performance Qualification Test 1CS-02 for Richmond County Constructors, Welder ID STR1536, 05/02/2019 Record of Welder Performance Qualification Test 1CS-03 for Richmond County Constructors, Welder ID STR1536, 05/06/2019 MISTRAS V-19-MT-301-3625, Nondestructive Examination Report Magnetic Particle Examination, Weld # SV3-VBS-PLW-030-14, 09/17/2019 5

Section 1A13 Drawings:

231124-000-SP-01-000201 Drawing 2, Sheet 1, "Field Weld Joint Details AP1000, Air Inlet &

Tension Ring WECTEC Global Project Services Inc. Southern Company (Plant Vogtle) Unit 3 &

4 - Waynesboro, GA," Revision 3 231124-000-SP-01-000202 Drawing 2, Sheet 2, "Field Weld Joint Details AP1000, Air Inlet &

Tension Ring WECTEC Global Project Services Inc. Southern Company (Plant Vogtle) Unit 3 &

4 - Waynesboro, GA," Revision 0 SV3-1208-SC-101, "Shield Building Steel Wall Panels El. 100'-0" to El. 248'6 1/2" Location and Identification Rollout View," Revision 4 SV3-1208-SC-107, "Shield Building Steel Wall Panels El. 100'-0" to El. 274'-0 1/8" Construction

& Erection General Notes," Revision 0 SV3-1278-SC-150, "Shield Building Air Inlet & Tension Ring Structure Steel Panels General Notes," Revision 0 SV3-1278-SC-151, "Shield Building Air Inlet and Tension Ring Structure Steel Panels Location and Identification Rollout View," Revision 1 SV3-1278-SC-171, "Shield Building Air Inlet and Tension Ring Structure Steel Panels Inside Face Attachments Rollout View (Sheet 1)," Revision 0 SV3-1278-SC-172, "Shield Building Air Inlet and Tension Ring Structure Steel Panels Inside Face Attachments Rollout View (Sheet 2)," Revision 0 SV3-1278-SC-173, "Shield Building Air Inlet and Tension Ring Structure Steel Panels Inside Face Attachments Rollout View (Sheet 3)," Revision 0 SV3-1278-SC-174, "Shield Building Air Inlet and Tension Ring Structure Steel Panels Inside Face Attachments Rollout View (Sheet 4)," Revision 0 SV3-1278-SC-901, "Shield Building Air Inlet and Tension Ring Structure Steel Panels General Details (Sheet 1)," Revision 1 Miscellaneous:

APP-1278-GNR-850200, "HII Mechanical NCR 3778A-Delivered SV4-1278-SC-AI27: Wrong Stud Welding WPS used on Module," Revision 0 APP-1278-GNR-850201, "HII Mechanical NCR 3777A-DELIVERED SV3 MODULES - Wrong Stud Welding WPS Used," Revision 0 APP-HA04-GEF-850016, "SB-AI/TR Weld Joint Alternatives," Revision 0 SV3-1278-GNR-000007, "Unit 3 AI Vert 41/42 Peaking Inside (ESR#50017337)," Revision 0 SV3-1278-GNR-000012, "AI Panel excessive root gap to SB Course 16 (ESR#50022740),"

Revision 0 Welding Material Authorization and Release Report-Nuclear WMARR SB-46, Lincoln Electric Co. E8018-C1 Lot 1399Y, 5/16/19 Welding Material Authorization and Release Report-Nuclear WMARR SB-42, Lincoln Electric Co. E71T-1 Lot 1400C, 5/1/19 Welding Material Authorization and Release Report-Nuclear WMARR SB-49, Lincoln Electric Co. E8018-C1 Lot 1400D, 6/3/19 Nondestructive Examination Reports:

Magnetic Particle Examination Report 231124-003-IN-RP-M0181, "MT of Wide Gap 16/AI G, 6/30/19 Magnetic Particle Examination Report 231124-003-IN-RP-M0182, "MT of Wide Gap 16/AI G, 7/6/19 Magnetic Particle Examination Report 231124-003-IN-RP-M0183, "MT of Wide Gap 16/AI F, 7/9/19 6

Magnetic Particle Examination Report 231124-003-IN-RP-M0186, "MT of Wide Gap 16/AI E, 7/10/19 Magnetic Particle Examination Report 231124-003-IN-RP-M0187, "MT of Wide Gap Build Up on AI-E Assembly," 7/11/19 Ultrasonic Testing Report 231124-003-IN-RP-U0073, Weld Identification AI F-G, 6/30/19 Ultrasonic Testing Report 231124-003-IN-RP-U0097, Weld Identification AI F/G Vert OS, 6/30/19 Ultrasonic Testing Report 231124-003-IN-RP-U0679, Weld Identification 1516 AI 16-17, 7/15/19 Procedures and Specifications:

181816-000-WS-PR-45054, "Ultrasonic Examination Statically Loaded Nontubular Connection AWS D1.1 Shield Wall Work," Revision 3 181816-000-WS-PR-45056, "Visual Inspection Procedure AWS D1.1 Shield Wall Work,"

Revision 1 181816-000-WS-PR-45058, "Magnetic Particle Examination Yoke/Prod, Dry Visible Particles AWS D1.1 Shield Wall Work," Revision 2 181816-000-WS-SP-45001, "General Welding Procedure Specification for AWS D1.1, AWS D1.4, AWS D1.6, and ASME Section IX Qualified WPS's," Revision 1 APP-GW-GAP-420, "Engineering and Design Coordination Reports," Revision 18 APP-GW-GAP-428, "Nonconformance and Disposition Report," Revision 16 CMS-720-03-PR-09154, "Site Welding Material Distribution for ANSI/AISC N690 Projects,"

Revision 0 SV3-1208-Z0-001, "Specification for the Fabrication and Field Erection of the SC Panels and the Conical Roof Steel Structure for the AP1000 Shield Building," Revision 0 WPS 181816-000-WS-SP- E71T1, "Welding Procedure Specification E71T1," Revision 1 WPS 181816-000-WS-SP-E8018, "Welding Procedure Specification E8018," Revision 2 Weld Travelers:

231124-003-QA-TRV-AI069, "U3-AI-Assy. F/G Vert I/O," 6/14/19 231124-003-QA-TRV-AI072, "U3-AI-16/AI Horiz I/O," 6/28/19 231124-003-QA-TRV-AI073, " U3-AI-16/SI Horiz Wide Gap," 6/28/19 231124-003-QA-TRV-AI072, "U3-AI-1516B/AI-F Horiz I/O," 6/28/19 231124-003-QA-TRV-AI072, "U3-AI-1516AB/AI-E Horiz I/O," 6/28/19 231124-003-QA-TRV-AI076, "U3-AI-D2L-Mismatch-Install," 8/7/19 Section 1A14 Concrete Records:

Concrete/Grout Delivery Ticket #54365, Pour #5178, 8/12/19 Concrete/Grout Delivery Ticket #54367, Pour #5178, 8/12/19 Concrete/Grout Delivery Ticket #54373, Pour #5178, 8/12/19 Concrete/Grout Delivery Ticket #54379, Pour #5178, 8/12/19 Concrete/Grout Delivery Ticket #54409, Pour #5178, 8/12/19 Concrete/Grout Delivery Ticket #54419, Pour #5178, 8/12/19 Concrete/Grout Delivery Ticket #54420, Pour #5178, 8/12/19 Concrete/Grout Delivery Ticket #54421, Pour #5178, 8/12/19 Concrete/Grout Delivery Ticket #80091, Pour #5178, 8/12/19 Concrete/Grout Delivery Ticket #80106, Pour #5178, 8/12/19 Miscellaneous:

CR 50027521, Procedural Guidance for Correlation Testing, 8/22/19 7

CR 70000284, Unit 3 Air Inlet Concrete Placement Test, 8/14/19 E&DCR SV0-1278-GEF-000017, "Air Inlet Doorway Weep Holes (ESR#50020867)," Revision 0 N&D SV3-CC01-GNR-000422, "RC05B Failed Slump Tests," Revision 0 N&D SV3-CC01-GNR-000562, "Unit 3 Air Inlet Concrete Placement Failed Test (ESR 50026854)," Revision 0 QA Surveillance 26139-000-GQA-QSSS-19143, "Unit 3 Air Inlet Concrete Placement," Revision 0

QC Inspection Report 26139-SV3-IR-C0-00895, "Unit 3 Shield Building Wall Air Inlet Concrete Placement El. 247'-6 " to 264'-4"," 9/18/19 Work Package SV3-1208-CCW-1040450, "Unit 3 Air Inlet Concrete Placement, EL 247'-6 1/2" to 264'-4"," Revision 0 Procedures and Specifications:

132175-102-006-04-000052, "Approved Mix Designs," 12/3/18 26139-000-4MP-T81C-N3210, "Concrete Operations," Revision 6 APP-GW-GAP-420, "Engineering and Design Coordination Reports," Revision 18 APP-GW-GAP-428, "Nonconformance and Disposition Report." Revision 16 SV3-CC01-Z0-026, "Safety Related Mixing and Delivering Concrete," Revision 8 SV3-CC01-Z0-027, "Safety Related Concrete Testing Services," Revision 7 SV3-CC01-Z0-031, "Safety Related Placing Concrete and Reinforcing Steel," Revision 8 Section 1A15 Weld Travelers 231124-003-QA-TRV-AI084, CB&I Weld Traveler (9 pages) and associated Spreadsheets U3-AI-TR-Assy. 05/06 for Piece Mark U3-Tension Ring Panels Welding Procedure Specifications (WPS)

Welding Procedure Specification 181816-000-WS-SP-45001, General Welding Procedure Specification for AWS D1.1, AWS D1.4, AWS D1.6, and ASME Section IX Qualified WPSs, Revision 1 Welding Procedure Specification 181816-000-WS-SP-E8018, Revision 2 Welding Procedure Qualification Records (PQRs)

Procedure Qualification Record 13408 Procedure Qualification Record 13849 Procedure Qualification Record 13857 Welder Performance Qualification Records (WPQs)

ASME IX Welder Performance Qualification (WPQ) for Site Welder having Identification Designation HWL4089 ASME IX Welder Performance Qualification (WPQ) for Site Welder having Identification Designation RTR3688 Certificates of Conformance/Certified Material Test Reports (CMTRs)

Certificate of Conformance & Certified Material Test Report, 5/32" dia. Excalibur 8018-C1 MR 50E0, Q3 Lot 1400A Section 1A16 Drawings:

SV3-1200-CR-950-R9, Auxiliary Building Areas 5 & 6 Concrete Reinforcement Wall 1 Elevation 8

SV3-1250-CR-950-R4, Auxiliary Building Areas 5 & 6 Concrete Reinforcement Wall 1 Sections

& Details EL 135-3 Engineering and Design Coordination Reports APP-1200-GEF-850102, Aux Bldg. Wall/Roof Slab Joint Reinforcement Scrub, Revision 0 SV3-CC01-GEF-000124, Wall 1 horizontal CJ below Corbel reinforcing at EL 155-0 (ESR 50012839), Revision 0 SV3-CC01-GEF-000130, Wall 1 optional vertical CJ at 4-0 west of J2-line from EL 135-3 to roof (ESR 50013499), Revision 0 SV3-CR01-GEF-000370, Hold on Formwork Installation for East Portion of Wall 1 Between EL 163-0 and EL 180-0, Revision 0 SV3-CR01-GEF-000371, Hold on Formwork Installation for West Portion of Wall 1 Between EL 163-0 and EL 180-0, Revision 0 SV3-CR01-GEF-000376, Hold on Formwork Installation for West Portion of Wall 1 Between EL 135-3 and EL 163-0, Revision 1 SV3-CR01-GEF-000377, Hold on Formwork Installation for East Portion of Wall 1 Between EL 135-3 and EL 163-0, Revision 1 SV3-CR01-GEF-000478, Additional Horizontal Splices on Wall 1, EL. 135-3 to 163-0 (ESR 50007838), Revision 0 SV3-CR01-GEF-000489, U3 1-line Wall: Request added splice from 163-0 to roof connection (ESR 50017997), Revision 0 Specification SV3-CC01-Z0-031, Safety Related Placing Concrete and Reinforcing Steel, Westinghouse Seismic Category I, Safety Class C Nuclear Safety, Revision 8 Miscellaneous Condition Report 50026828 Licensing Document Change Request No. LDCR-2019-076 Section 1A17Concrete Records:

2019SCC1221, "Wood Report of Concrete Compression Test Results," 8/1/19 2019SCC1222, "Wood Report of Concrete Compression Test Results," 8/1/19 Concrete Placement/Order Pour Card, Pour Number 5056, "U3 Aux Bldg. Wall Placement 162.

N Line up tot Elevation 180'9"," 6/30/19 Concrete Placement/Order Pour Card, Pour Number 5056, "U3 Aux Bldg. Wall Placement 162.

N Line up tot Elevation 180'9"," 6/29/19 Concrete/Grout Delivery Ticket #53743, Pour #5056, 6/29/19 Concrete/Grout Delivery Ticket #53746, Pour #5056, 6/30/19 Concrete/Grout Delivery Ticket #53749, Pour #5056, 6/30/19 Concrete/Grout Delivery Ticket #53750, Pour #5056, 6/30/19 Concrete/Grout Delivery Ticket #53751, Pour #5056, 6/30/19 Concrete/Grout Delivery Ticket #53756, Pour #5056, 6/30/19 Miscellaneous:

CR 50021530, Unit 3 Concrete Placement, 6/5/19 CR 50023851, Improper Curing for SV3 Wall Placement 162, 7/9/19 CR 50027085, Concrete spilled during Aux Building wall placement, 8/19/19 E&DCR SV0-CC01-GEF-000427, "031 Specification Clarifications," Revision 0 9

E&DCR SV3-CE01-GEF-000098, "Post Installed Plate Modifications for Area 2, EL 82'-6" (ESR 50003383)," Revision 0 N&D SV3-CC01-GNR-000561, " Improper Curing for SV3 Wall Placement 162," Revision 0 QC IR 26139-SV3-C1-19-0072, "U3 Aux Bldg. Wall Placement 162. N Line up Elevation 180' 9"," 7/8/19 QC IR 26139-SV3-IR-C0-00913, "Wall from 155'-0" to 180'-9" Elev., CL N from 5'-0" north of CL 1 to Shield Building Wall, Concrete Placement"," 7/26/19 Work Package SV3-1222-S0W-800000, "Installation of Auxiliary Building Post-Installed Plates for Area 2 Including Shield Wall, El 82'-6"," Revision 0 Work Package SV3-1266-CCW-1010905, "Wall from 155'-0" to 180'-9" Elev., CL N from 5'-0" north of CL 1 to Shield Building Wall, Concrete Placement," Revision 0 Procedures and Specifications:

132175-102-006-04-000052, "Approved Mix Designs," 12/3/18 26139-000-4MP-T81C-N3210, "Concrete Operations," Revision 6 APP-GW-GAP-420, "Engineering and Design Coordination Reports," Revision 18 APP-GW-GAP-428, "Nonconformance and Disposition Report." Revision 16 SV3-CC01-Z0-026, "Safety Related Mixing and Delivering Concrete," Revision 8 SV3-CC01-Z0-027, "Safety Related Concrete Testing Services," Revision 7 SV3-CC01-Z0-031, "Safety Related Placing Concrete and Reinforcing Steel," Revision 8 Section 1A18 SV3-RNS-EWW-1030670, "U3 Auxiliary Pull RNS Cable from SV3-IDSA-DD-1 and associated EQP," Revision 0 SV3-RNS-EWW-1030639, "U3 Auxiliary Pull RNS Cable from SV3-IDSA-DS-1 and associated EQP," Revision 0 SV3-RNS-EWW-1030668, "U3 Auxiliary Pull RNS Cable from SV3-IDSA-DC-1 and associated EQP," Revision 0 SV3-PXS-EWW-1041168, "U3 Pull PXS-1 Cable from SV3-IDSD-DD-1 and associated EQP,"

Revision 0 SV3-G1-V8-001, "AP1000 Electrical installation Specification", Revision 7 Section 1A19 SV3-4030-AG-101, Annex Building Floor Plan EL 100'-0" & 107'-0", Revision 5 APP-GW-IT-001, Guidelines for Concrete Wall and Slab Thickness, Revision 0 APP-GW-GEF-2146, Revision to APP-GW-IT-001, Revision 0 NCSP 02-24, ITAAC Support Activities, Revision 3 SV3-4030-C0K-819000, Verification of Seismic Gap Annex Building to Auxiliary Building Elevation 100-0, Revision 0 Section 1A20 SV0-EDS9-E3-800001, "Vogtle Electric Generating Plant One Line Diagram CSC Bldg UPS System SH 1 of 1," Revision 3 Work Order 1007554, "TSC Battery Load Test and Inverter Functional Test," 9/6/19 Section 1A21 Weld Process Traveler 913581-016 Weld #12, 6/28/19 Tensile Test Reports: D284297N Revision 0; D276298N Revision 0 E&DCRs: APP-CA01-GEF-850673, Revision 0; APP-CA01-GEF-850673, Revision 0; SV0-CA01-GEF-000159, Revision 0; APP-CA01-GEF-850660, Revision 0; 10

Drawings:

SV4 -PH01-V8-009, "AP1000 Steam Generator Lateral Supports Field Welding Options to Meet ASME NF-4441", Revision 0 SV4-PH01-V2-001, "AP1000 Steam Generator Lateral Supports Assembly & Details", Revision 1

SV4-PH01-V1-004, "AP1000 Steam Generator Lower Lateral Support Assembly & Details,"

Revision 1 SV4-CA01-S5K-891277, "SV4 CA01 Plate Materials Testing Weld Map", Revision 0 PCI Drawing:

SGL-0612, "SGLL Temporary Attachment Weld Map Steam Generator "A" Lateral Supports",

Revision 0 Section 1A22 AP1-2410, RCS Piping Installation Surge Piping, Revision 0 SV4-RCS-PLW-042, Reactor Coolant System Containment Bldg. Room 11303 Surge Line-Spool Piece 2, Revision 1 SV4-RCS-PLW-043, Reactor Coolant System Containment Bldg. Rooms 11303/11304 Surge Line-Spool Piece 3, Revision 2 SV4-PL01-V6-003, AP1000 Primary Coolant Loop Surge Line Spool Pieces, Revision 0 PCI Quality Assurance Traveler, Weld Process Traveler 914842-010, Weld Number SV4-RCS-PLW-043-1, 12/4/2018 PCI Weld Material Withdrawal Slip for Weld Number SV4-RCS-PLW-043-1, Traveler Number 914842-010, 7/30/2019 RIR-914842-017, Receiving Inspection Report, 1/23/2019 WECTEC GPS Material Certification, J.O. Number 2554 / WSV02554, Lot 1093K, 270 Pounds, 0.035 Diameter, ER316L, Welding Wire, SFA-5.9, 11/27/2018 8 MC-GTAW, PCI Energy Services ASME Section IX Welding Procedure Specification, Revision 16 PQR 062, PCI Energy Services Procedure Qualification Record (PQR), Revision 3 PQR 600, PCI Energy Services ASME IX Welding Procedure Qualification Record, Revision 8 PQR 864, PCI Energy Services ASME IX Welding Procedure Qualification Record, Revision 2 PQR 899, PCI Energy Services ASME IX Welding Procedure Qualification Record, Revision 4 ASME - Welder Maintenance Log (WML) for M908, Machine GTAW ASME - Welder Maintenance Log (WML) for M2312, Machine GTAW ASME - Welder Maintenance Log (WML) for M2331, Machine GTAW ASME Section IX - Welder Performance Qualification (WPQ) for M908, Machine GTAW, 3/4/2016 ASME Section IX - Welder Performance Qualification (WPQ) for M2312, Machine GTAW, 3/12/2019 ASME Section IX - Welder Performance Qualification (WPQ) for M2331, Machine GTAW, 8/22/2017 ASME Section IX - Welder Performance Qualification (WPQ) for M2331, Machine GTAW, 10/18/2017 P-19-RT-302-0047, "Computed Radiography Examination Report," Weld No. SV4-RCS-PLW-043-1, 8/16/2019 Section 1A23 APP-PV01-Z0D-117, PV01 Datasheet 117, Revision 3 11

SV0-PV01-VMM-001, Maintenance Manual for AP1000 PV01 Size 3 or Larger Motor Operated Gate Valves,Section III, Class 1, 2 &3, Revision 0 WPS1-8.8T01, Welding Procedure Specification for GTAW, Revision 10 Weld No. SV4-RCS-PLW-03A-12 SV4-RCS-PLW-03A, Reactor Coolant System Containment Building Room 11301 ADS Stage 4 Piping West Compartment, Revision 2 Work Package No. SV4-RCS-P0W-800013, ASME III - U4 - Install Containment RCS Large Bore Pipe Per SV4-RCS-PLW-03A, Revision 0 Weld Data Sheet for Weld No. SV4-RCS-PLW-03A-12, 08/27/2019 Welder JCD 4541, SAC 6455 Welding Material Requisition 463872, 8/23/19 WEC Data Package SV4-PV01-VQQ-035, Quality Release 14" Gate Valve, (MOV RCS-PL-V014A, S/N BX279), Revision 3 CB&I Laurens Inc. Isometric Sketch No. 891300-42-00391, Piece Mark SV4-RCS-PLW-03A-1, Item F with Heat-No. 51016 for Line L133A, Revision 1B Aruna Alloy Steels PVT, CMTR CC01578, 14" dia. Sched. 160, MOV RCS-PL-V014A (S/N BX279) SA351-CF3M, Heat-No. E9710, 01/31/2015 Productos Tubulares Expana, Mill Test Certificate 0903/12 Revision 02, 14 dia. Sched. 160 pipe, SA312-TP316LN, Heat-No. 51016 (Specimen 1094-N), 03/04/2012 CB&I Laurens Inc., ASME Form NPP-1 Certificate Holders Data Report for Fabricated Nuclear Piping Subassemblies, Part Serial No. SV4-RCS-PLW-03A-1, 01/31/18 Weld No. SV4-RCS-PLW-03B-8 SV4-RCS-PLW-03B, Reactor Coolant System Containment Building Room 11301 ADS Stage 4 Piping West Compartment, Revision 2 Work Package No. SV4-RCS-P0W-1014069, ASME III - U4 - Install Containment RCS Piping &

Supports for ISO SV4-RCS-PLW-03B, Revision 0 Weld Data Sheet for Weld No. SV4-RCS-PLW-03B-8, 08/21/2019 Welder JCD 4541, SAC 6455 Welding Material Requisition 463863, 8/23/19 WEC Data Package SV4-PV01-VQQ-043, Quality Release 14" Gate Valve, (MOV RCS-PL-V014C, S/N BX417), Revision 0 CB&I Laurens Inc. Isometric Sketch No. 891300-42-00393, Piece Mark SV4-RCS-PLW-03B-1, Item D with Heat-No. F12A024 for Line L137A Revision 1A Aruna Alloy Steels PVT, CMTR CC01368, 14 dia. Sched. 160, MOV RCS-PL-V014C (S/N BX417) SA351-CF3M, Heat-No. E9540, 08/11/2014 Sumitomo Metal Industries Steel Tube Works, Test Certificate OYYD0484, 14 dia. Sched. 160 pipe, SA312-TP316LN, Heat-No. F12A024, 01/27/2012 CB&I Laurens Inc., ASME Form NPP-1 Certificate Holders Data Report for Fabricated Nuclear Piping Subassemblies, Part Serial No. SV4-RCS-PLW-03B-1, 02/24/16 Section 1A24 WEC APP-FT01-Z0-001, "AP1000 Fuel Transfer Tube, ASME Boiler and Pressure Vessel Code Section III, Subsection NE, Class MC," (design specification certified by RPE iaw NCA-3250),

Revision 3 WEC APP-FT01-Z0R-001, "AP1000 Fuel Transfer Tube Design Compliance Matrix," Revision 1 WEC APP-FT01-Z0-010, "AP1000 Fuel Transfer Tube Functional Specification," Revision 2 WEC APP-FT01-Z0-200, "AP1000 Fuel Transfer Tube Fabrication Specification," Revision 2 WEC SV4-FT01-VQQ-001, "Owner's Record Package", Revision 0 (3251 pages) 12

WEC-Newington Operations, "ASME Form N-2 Certificate Holder's Data Report for Identical Nuclear Parts and Appurtenances," (FTT that consists of the transfer tube, flange, test angle, and hatch), Part Serial No. 6217, 03/21/19 WEC-Newington, "Vogtle 4 Project Cross Index Material Test Reports and Material", Job 2412285 (no revision and date)

WECTEC Type "A" Inspection Report Q445-10-11630 for Receipt Inspection of Fuel Transfer Tube Assembly S/N 6217, 5/21/19 FUEL TRANSFER TUBE (WEC Identification-No. 16-0403, Material-No. FT01-V2-531-01-1S, Heat-No. 846899, GRS-No. 5001443759/0001):

Tioga Pipe Shop Order (S.O.)-No. 684341, "Customer Purchase Order Certificate of Compliance/CMTR", 05/04/2016 Bristol Metals, CMTR for 30" dia. X 0.375" min. wall thickness pipe, SA312 TP304/304L, Heat/Lot-no. 846899/136616, 04/08/2016 ATI Flat Rolled Products, "Certificate of Test" for chemistry and mechanical testing, ASTM A-262 Practices A and E, 01/21/2016 Brismet Radiographic Examination Report 30P-375-3/4, heat # 846899, actual mat'l thick.

0.402", certified by Level III, 04/07/2016 Brismet Liquid Penetrant Report, Piece-No. 074131-01 (OD and accessible ID), certified by Level II, 04/18/2016 Bristol Metals, Certification Summary Record for Level III (2 records of inspector with initials HM for RT, expiration 07/21/2016)

Bristol Metals, Eye Examination Report (inspector HM for visual acuity and color perception),

07/09/2015 WEC Radiographic Examination Report NDE-044398, transfer tube (SDCR 11134), SAP Material No. FT01-V2-531-01-1, Assembly 2412285, WEC Ident. 16-0403, Signed by two Level II inspectors with stamps 44 and 133 on 06/22/2016, and ANI on 06/23/2016 (2 pages)

WEC Liquid Penetrant Examination Report NDE-044285, transfer tube (SDCR 11134), Material No. FT01-V2-531-01-1, Assembly 2412285, WEC Ident. 16-0403, by Level II Inspector stamp 120, 06/13/2016 FLANGE (WEC ID-No. 16-0159, Mat'l-No. FT01-V2-531-01-2S, Heat-No. CD25201, Goods Receipt Slip (GRS)-No. 5001424341/0002):

Energy & Process Corporation, CMTR for PO 4500679159 CN1, 5" THK X 39" OD X 29.5" ID, Forged Ring MN: FT01-V2-531-01-2S, SA182 F304L, Heat: CD25201, Mfg.: Patriot Forge Item:

2, 1/13/16 Patriot Forge Co., Certificate of Compliance, P.O. P256-1453, Item #2, S.O. # Y2674-1, December 14, 2015 Patriot Forge Co. in Ontario, CMTR Shop Order No. Y2674-1 (Item 2), Heat # CD25201 with:

ELG Carrs Stainless Steel-England mill data chemical analysis Cert-No. 143298 (Item 2) of 03/06/15; Cambridge Material Testing Limited-Ontario, product Chemical Analysis Test Report Lab-No.

715868-15 (Item 2) of 11/10/2015; Tensile Test Report Lab-No. 717794-15 (Item 2) of 12/04/2015; and ASTM A262 Practice E Corrosion Test Report Lab-No. 717797-15 (Item 2) of 12/04/2015 TEST ANGLE (WEC Identification-No. 15-1446, Material-No. B01.250P041, Heat-No. W1J3, Jacquet Fische (JF) 55403 for Item 4, GRS-No. 5001410368/0004):

Energy & Process Corporation, CMTR for SA240 Type 304L, 1.25" THK X 34" X 34" plate, Heat W1J3, JF 55403, Item 4, M/N B01.250P041, 10/19/15 Jacquet Southeast, Certificate of Conformance, Heat W1J3, JF 55403 (3 pcs), 9/01/15 Laboratory Testing Inc., Certified Test Report EPC002-15-09-35019-1, tensile test of SA240 TP304L, 1.25" THK x 3" x 6" plate, Heat-No. W1J3, JF 55403, Page 1 of 2, 9/15/2015 13

Laboratory Testing Inc., Certified Test Report EPC002-15-09-35019-1, ASTM A262 Practice E Copper-Copper Sulfate-Sulfuric Acid Test of Sample ID: Heat W1J3, JF 55403, Grade 304L, Page 2 of 2, 9/15/2015 North American Stainless (NAS), Metallurgical Test Report 8941802, Heat-No. W1J3 and JF 55403 with mill chemical analysis and mechanical properties, 8/26/2015 Energy & Process Corporation, Material Test Report 46621C, chemical test, SA240 Type 304L, 1.25" Thk. plate, Heat W1J3, JF 55403, Item 4, 09/18/15 Energy & Process Corporation, Material Test Report 46621R, hardness test, SA240 Type 304L, 1.25" Thk. plate, Heat W1J3, JF 55403, Item 4, 09/18/15 HATCH (WEC Ident. No. 14-1981, Material-No. FT01-V2-532RS, Heat-No. M3X7, Jacquet Fische (JF) 52202, Piece 2 (Item 7), GRS-No. 5001389495/0002):

Energy & Process Corporation, Material Certification (*Revised) for 34" OD X 2" Thk. plate, Heat M3X7, JF 52202, Piece 2, Item 7, SA240 TP 304, 07/17/15 North American Stainless (NAS), Metallurgical Test Report 949553 for Heat-No. M3X7 and JF 52202 (Item 7) with mill chemical analysis and mechanical properties, 5/16/2014 Jacket Southeast, Certificate of Conformance, Heat M3X7, Jacquet Fische 52202 (Item 7) (4 pcs), 9/15/14 Energy & Process Corporation, CMTR 43512C, chemical test, SA240 Type 304, 2" Thk. X 34" dia. plate, Heat # M3X7, Jacquet Fiche 52202, Item 7, 09/26/14 Energy & Process Corporation, CMTR 43512T, tensile test, SA240 Type 304, 2" Thk. plate coupon, Heat # M3X7, Jacquet 52202, Item 7, 09/26/14 Energy & Process Corporation, CMTR 43512R, hardness test, SA240 Type 304, 2" Thk. plate, Heat # M3X7, Jacquet 52202, Item 7, 09/26/14 Element Materials Technology, Test Certificate-EAR-Controlled Data, ASTM A262 Practice E test for susceptibility to intergranular attack, 2" thick X 1" wide X 8" long test coupon, Heat M3X7, 52202, SA240 TP304, 10/1/2014 Weld Filler Metals:

WEC CMTR-Welding for Unit 4 FTT Job-No. 2412285 using ID-Nos. (diameter - S/N) 2152

(.045" - 15979), 2160 (.045" - YT9336), 2253 (1/16" - AF0029), 2254 (1/16" - DF0029), and 2258 (3/32" - 1212C), 3/21/19 ESAB, CMTR 2-49251-00-0-A, SFA-5.22, E308T1-4/308LT1-4, .045" dia., WEC Ident. No.

2152, Lot-No. 15979, 04/13/2010 Arcos, CMTR S.O. 114204, SFA-5.9, ER308/308L, .045" dia. WEC Ident. No. 2155, Heat-No.

740400, Lot-No. YT9336, 11/16/2010 Arcos, CMTR S.O. 140798, SFA-5.9, ER308/308L, 1/16" dia. X 36", WEC Ident. No. 2253, Heat-No. 537291, Lot-No. AF0029, 6/5/2014 Arcos, CMTR S.O. 140798, SFA-5.9, ER308/308L, 1/8" dia. X 36", WEC Ident. No. 2254, Heat-No. 537291, Lot-No. DF0029, 6/3/2014 Lincoln Electric Company, CMTR 6697050 ES-TADC, SFA-5.9, ER308/308L, 3/32" dia. X 36",

Heat-No. 539207, Lot-No. 1212C, 09/24/2014 Weldstar, Certificate of Compliance/Conformance for Arcos CMTRs S.O. 154326, 156689, 156682, and 156778 with SFA-5.9, ER308/308L, 3/32" and 1/8" dia. X 36" length with Heat-No.

541571 for Lot-Nos. CF0256 and DF0256; and Heat-No. 540811 for Lot-Nos. CF0270 and DF0270, 03/31/16 Weldstar, Certificate of Compliance/Conformance, Arcos, SFA-5.9, ER308/308L, 1/16" dia. X 36", Heat-No. 537291, Lot-No. AF0029, June 5, 2014 Weld Maps, NDE Reports, and Test Reports:

WEC Weld Map No. WM-2412285-01, Revision 03, Titled "FT01-Fuel Transfer Tube",

Reference Drawing APP-FT01-V2-531, 7 pages, 4-27-16 14

WEC Weld Map No. WM-2412284-10, Revision 01 Titled "FT01 Fuel Transfer Tube Assembly",

Reference Drawing APP-FT01-V2-530, 6 pages, 6-30-16 NDE Report for VT and PT for Assy. # C1, Joints 1 thru 11 with reference document Weld Map-2412285-01, accepted by Level II Inspectors 141 and 149, SV4-FT01-VQQ-001, pages 2958-2961, 3-21-19 NDE Report for VT and PT for Assy. # C1, Joints 1 thru 3 with reference document Weld Map-2412284-10, accepted by Level II Inspector 32, SV4-FT01-VQQ-001, page 2961, 3-21-19 WEC Pneumatic Test Report for WEC Ident. No. Assembly C1, at 67.8 psi for 10 minutes, signed by Level II Inspector 45, 10/16/18 WEC Hydrostatic Test Report NDE-051679 for WEC Ident. No. 2412285 Assy. C1, at 72 psi for 10 minutes, signed by Level II Inspector 78, 09/27/2018 WEC Fuel Transfer Tube Functional Testing Test Report WEC Ident. No. Assy. C1, signed by Level II Inspector 45, 10/16/18 Section 1A25 APP-EY01-Z0-001, Electrical Penetration Assembly Design Specification, Revision 8 Quality Release & Certificate of Conformance for Part 200002075 (S/N 9093), dated 2/1/19 Quality Release & Certificate of Conformance for Part 200002092 (S/N 9096), dated 2/1/19 Quality Release & Certificate of Conformance for Part 200002097 (S/N 9111), dated 11/30/18 Mirion Certificate of Conformance for Part 8113-10000-01 (S/N 9093), dated 1/29/19 Mirion Certificate of Conformance for Part 8113-10000-04 (S/N 9096), dated 1/29/19 Mirion Certificate of Conformance for Part 8113-10003-08 (S/N 9111), dated 11/1/18 QP 8113-02A, Quality Plan, Revision 5 QP 8113-02BA, Quality Plan, Revision 5 APP-100-P0-909, Electrical Penetration Assembly Details fr AP1000, Revision 7 Drawing 8113-10000, MVP Electrical Penetration Assembly (AP1000) for Vogtle, Units 3 & 4, dated 7/8/18 Drawing 8113-10003, LVP/C Electrical Penetration Assembly (AP1000) for Vogtle, Units 3 & 4, dated 7/2/18 ASME form N-2 for Medium Voltage Penetration Sub Assembly, Serial Number 9093, dated 1/8/19 ASME form N-2 for Medium Voltage Penetration Sub Assembly, Serial Number 9096, dated 1/8/19 ASME form N-2 for Low Voltage Control Penetration Sub Assembly, Serial Number 9111, dated 10/25/18 IPS 2323, Welding Procedure Specification for ASME Boiler and Pressure Vessel Code GTAW and FCAW of Carbon Steel to Stainless Steel Materials, Revision 0 IPS 2323 (PQR), Procedure Qualification Record for IPS 2323, dated 5/20/13 IPS 2406, Production Test Procedure for Electrical Penetration Assemblies for Westinghouse, Revision 0 IPS 2412, Production Test Procedure for Electrical Penetration Assemblies for Westinghouse, Revision 0 QCI 9-23, Quality Control Instruction Solvent Removable Visible Dye Penetrant Test, Revision U

Weld rods (All penetrations)

CMTR 2-55764-00-0-A from ESAB for weld rods, lot 10029760, dated 9/8/14 CMTR 7436648 from Lincoln Electric for weld rods, SFA 5.22, lot 1264Z, dated 6/14/16 CMTR 8305020 from Lincoln Electric for weld rods, SFA 5.22, lot 1310Z, dated 1/18/17 CMTR from Weldstar for weld rods, SFA 5.9, heat 10064, dated 6/8/88 15

Letter RE: Material Certification for Reconciliation of ASME Material for PO 4500430408, dated 7/20/18 Material Disposition Report N-002042, Canister Tube S/A for P31, dated 8/9/18 Material Disposition Report N-002039, Canister Tube S/A for P09 and P26, dated 8/9/18 CR 50025875, QA Data Package SV4-EY01-VQQ-003 missing a CMTR, dated 8/2/19 IR-2019-11856, EY01 Missing CMTR, dated 7/31/19 P31 CMTR SSC001-13-10-36607-2 from Laboratory Testing Inc., for P31 outside header, heat 285203, dated 10/15/13 CMTR TPS001-13-05-19226-2 from Laboratory Testing Inc., for P31 canister tube, heat T45241, dated 6/6/13 CMTR SSC001-13-10-36607-1 from Laboratory Testing Inc., for P31 inside header, heat 284588, dated 10/15/13 CMTR SSC001-13-10-36608-2 from Laboratory Testing Inc., for P31 weldment, heat 852672, dated 10/15/13 PT report for part 7ZR1-30002-01, dated 11/8/16 PT report for part 7ZR1-20022-03, dated 4/7/17 PT report for part 7ZR1-30003-01, dated 11/9/16 PT report for part 7ZR1-30012-01, dated 2/14/17 PT report for part 7ZR1-20022-03 (post weld), dated 5/31/17 Pneumatic pressure test for Subassembly P31 (SN 9111), dated 8/10/18 P09 CMTR SSC001-13-09-33904-5 from Laboratory Testing Inc., for P09 outside and inside header, heat SC17578, dated 11/5/13 CMTR TPS001-13-06-21374-1 from Laboratory Testing Inc., for P09 canister tube, heat T32197, dated 6/24/13 CMTR SSC001-13-10-36608-2 from Laboratory Testing Inc., for P09 weldment, heat 852672, dated 10/15/13 PT report for part 7ZR1-30000-01 Header Plate I/C and Header Plate O/C, dated 11/8/16 PT report for part 7ZR1-20020-02, dated 4/7/17 PT report for part 7ZR1-30012-01, dated 2/14/17 PT report for part 7ZR1-20020-02 (post weld), dated 5/2/17 Pneumatic pressure test for Subassembly P09 (SN 9093), dated 1/25/19 P26 CMTR SSC001-13-09-33904-5 from Laboratory Testing Inc., for P26 outside and inside header, heat SC17578, dated 11/5/13 CMTR TPS001-13-06-21374-1 from Laboratory Testing Inc., for P26 canister tube, heat T32197, dated 6/24/13 CMTR SSC001-13-10-36608-2 from Laboratory Testing Inc., for P26 weldment, heat 852672, dated 10/15/13 PT report for part 7ZR1-30000-01, dated 11/8/16 PT report for part 7ZR1-30001-01, dated 11/8/16 PT report for part 7ZR1-200XX-XX-OS, dated 4/7/17 PT report for part 7ZR1-30012-01, dated 2/14/17 PT report for part 7ZR1-20022-03 (post weld), dated 6/9/17 Pneumatic pressure test for Subassembly P26 (SN 9096), dated 1/25/19 16

Section 1A26 CCS-PL-V208 ASME Form NPV-1 for 10 Valve, Serial Number 4-55022-L, 11/13/2013 SV4-PV11-V2-122001, Motor Operated Butterfly Valve 10, CL 150, CS, Revision 1 SV4-PV11-VQQ-005, Quality Release and C of C for PV11 Valves, Revision 2 Certificate of Compliance for Valve Serial Number 4-55022-L from Weir, 3/14/2014 SV4-PV11-Z0-001, Design Specification for Butterfly Valves, ASME Boiler and Pressure Vessel Code Section III Class 2 and 3, Revision 4 SV4-PV11-Z0D-122, PV11 Data Sheet 122, Revision 2 SV4-PV11-Z0R-001, Butterfly Valves, ASME Boiler and Pressure Vessel Code Section III, Class 2 and 3 Valve Data Sheet Report, Revision 7 Certificate of Conformance / Compliance / CMTR for Valve Body from DuBose National Energy Services, Serial Number 287757, Heat Number R4280, 4/21/2011 Certificate of Conformance / Compliance / CMTR for Cover Plate from DuBose National Energy Services, Serial Number 288516, Heat Code BRG, 5/17/2011 Certificate of Compliance 6952 for Valve Disc from PRL Industries, Serial Number AC458, Heat Number 1138, 6/8/2011 Certificate of Conformance for Hex Cap Screw from Ronson Manufacturing, Customer PO Number 855696, Heat Number 10101291, 1/13/2011 CMTR for Hex Cap Screw from Ronson Manufacturing, Customer PO Number 855696, Heat Number 10101291, 1/13/2011 Certificate of Conformance for Drive Shaft from Ronson Manufacturing, Customer PO Number 2004078, Heat Number 9HM8, 10/8/2012 CMTR for Drive Shaft from Ronson Manufacturing, Customer PO Number 2004078, Heat Number 9HM8, 10/8/2012 Non-Destructive Examination Report, WVC S.O. # 55022, Heat Number R4280 S/N-7, Valve Body Liquid Penetrant Root Pass, 11/13/2013 Non-Destructive Examination Report, WVC S.O. # 55022, Heat Number R4280 S/N-7, Valve Body Liquid Penetrant Second Pass, 11/13/2013 Non-Destructive Examination Report, WVC C.O. # 55022, Heat Number R4280 S/N-7, Valve Body Liquid Penetrant Seat, 11/13/2013 Tricentric Wafer, Lug or Double Flange Valve Body Dimensional Report, S.O. # 55022, Heat Number R4280 S/N-7, 11/13/2013 Test Report, WVC Shop Order # 10000188-131, Valve Tag # 4-55022-L, 10/25/2013 SFS-PL-V037 ASME Form NPV-1 for 4 Nozzle Check Valve, Serial Number 11899, 10/18/2013 SV4-PV03-V2-181001, AP1000 Nozzle Check Valve, 4 Class 150, Assembly Drawing APP-PV03-Z0D-181, Revision 0 SV4-PV03-VQQ-013, Quality Release and Certification of Conformance, 3 &Larger Manually Operated Gate, Stop Check and Check Valves, ASME III, Revision 0 SV4-PV03-Z0-001, Design Specification for 3 and Larger Manually Operated Gate, Stop Check, and Check Valves, ASME Boiler and Pressure Vessel Code Section III Class 1, 2, and 3 for Various Systems, Revision 4 SV4-PV03-Z0D-181, PV03 Datasheet 181, Revision 0 SV4-PV03-Z0R-001, 3 or Larger Manually Operated Gate, Stop Check, and Check Valves, ASME Boiler and Pressure Vessel Code,Section III, Class 1, 2, and 3 Valve Datasheet Report, Revision 5 Certificate of Compliance from Enertech for 4 Class 150 Nozzle Check Valve, Serial Number 11899, 10/30/2013 17

CMTR for Valve Body from Jorgensen Forge Corporation, Heat Number 2H062 / 2, 12/13/2010 CMTR for Valve Disc from Energy & Process Corporation, Heat Number 251145, 11/23/2010 Test Report, Test Procedure for Nozzle Check Valve, Job Number 960033, Valve Serial Number 11899, 11/20/2012 Test Report, Dimensional Inspection Procedure for Enertech Nozzle Check Valve, Valve Serial Number 11899, 12/10/2011 Valve Body - Data Sheet, Nozzle Check Valve Wall Thickness Measurement Procedure, Valve Serial Number 11899, 12/10/2011 Valve Disc - Data Sheet, Nozzle Check Valve Wall Thickness Measurement Procedure, Serial Number 38150, 5/6/2011 N.D.E. Examination Report (Liquid Penetrant), Serial Number 36399, 6/8/2011 N.D.E. Examination Report (Liquid Penetrant), Serial Number 38150, 5/10/2011 Section 1A27 WEC SV4-SGS-PLW-031-R3, Steam Generator System Auxiliary Building Room 12406 Main Steam Line A, Revision 3 S&W Weld Data Sheet SV4-SGS-PY-C01A-1, 3/19/2019 S&W Welding Material Requisition, 9/12/19 Section 1A28 APP-PXS-M6-001, "Piping and Instrumentation Diagram Passive Core Cooling System" (E-2),

Revision 12 SV4-PXS-PLW-021, "Passive Core Cooling System Containment Building Room 11207 CMT B Injection HDR To ISOL Valves," Revision 2 (with mark-ups)

APP-PXS-PLW-021, "Passive Core Cooling System Containment Building Room 11207 CMT B Injection HDR To ISOL Valves", Revision 8 Record of Welder Performance Qualification Test - ASME Section IX Groove Weld for JCW3983 (1CS-02) and KDW0949 (1SS-02)

APP-GW-GAP-428, "Nonconformance and Disposition Report (N&D)," Revision 16 N&D SV4-PXS-GNR-000063, "SV4-PXS-PLW-021-3 Short (ESR 50019301)," 11 pages, Revision 0 Weld SV4-PXS-PLW-021-7 :

Weld Data Sheet (WDS) SV4-PXS-PLW-021-7 (Work Package SV4-PXS-P0W-800018),

8/21/2019 Welding Material Requisitions (WMR) 445012 and 445016 V-19-PT-301-2365, Liquid Penetrant Examination Report for Weld No. SV4-PXS-PLW-021-7, 8/19/2019 V-19-RT-302-0780, Computed Radiography Examination Report for Weld No. SV4-PXS-PLW-021-7, 8/22/2019 Weld SV4-PXS-PLW-021-10 :

Weld Data Sheet (WDS) SV4-PXS-PLW-021-10 (CMT-B discharge nozzle), 8/21/2019 Welding Material Requisitions (WMR) 463729, 4637 32, and 463740 V-19-PT-301-2186, Liquid Penetrant Examination Report for Weld No. SV4-PXS-PLW-021-10 (buildup), 8/2/2019 V-19-PT-301-2351, Liquid Penetrant Examination Report for Weld No. SV4-PXS-PLW-021-10, 8/15/2019 V-19-RT-302-0781, Computed Radiography Examination Report for Weld No. SV4-PXS-PLW-021-10, 8/22/2019 18

Weld SV4-PXS-PLW-021-11 :

Weld Data Sheet (WDS) SV4-PXS-PLW-021-11 (new field weld), 8/21/2019 Welding Material Requisitions (WMR that include all three welds) 463741, 463749, 463753, 463757, and 444996 V-19-PT-301-2352, Liquid Penetrant Examination Report for Weld No. SV4-PXS-PLW-021-11, 8/15/2019 V-19-RT-302-0782, Computed Radiography Examination Report for Weld No. SV4-PXS-PLW-021-11, 8/22/2019 Section 1A29 SV4-ME02-Z0-101, "Design Specification for AP1000 Passive Residual Heat Removal Heat Exchanger for System PXS," Revision 6 APP-ME02-Z0M-101, "AP1000 PRHR HX Standard Technical Manual," Revision 2 SV4-ME02-MHH-002, "Upending and Installing Unit 4 PRHR Heat Exchanger," Revision 0 WEC Drawing SV4-PXS-MEK-876863, "Weld Map for Passive RHR Heat Exchanger SV4-PXS-ME-01," Revision 0 S&W Weld Data Sheet SV4-PXS-ME-01-3, 5/13/19 S&W Welding Material Requisition (WMR) 473845, 9-11-19 S&W Weld Data Sheet SV4-PXS-ME-01-4, 5/13/19 S&W Welding Material Requisition (WMR) 473806, 9-12-19 Section 1A30 26139-000-4MP-T81C-N3201, "Construction Survey," Revision 5 NCSP 02-24, "ITAAC Support Activities (AP1000)," Revision 03.00 SV4-1130-CE-045, "Containment Concrete Embedment Drawing at Elevation 103'-0" Detail A3," Revision 1 SV4-1130-CE-061, "Containment Concrete Embedment Drawing at Elevation 103'-0" Detail B3," Revision 2 SV4-PXS-M6-001, "Piping and Instrumentation Diagram Passive Core Cooling System,"

Revision 5 SV4-PXS-M6-002, "Piping and Instrumentation Diagram Passive Core Cooling System,"

Revision 8 SV4-PXS-PLW-01B, "Passive Core Cooling System Containment Building Room 11206 Containment Recirc. Valves," Revision 2 SV4-PXS-PLW-01H, "Passive Core Cooling System Containment Building Room 11206 Containment Recirc. to DVI-A," Revision 1 SV4-PXS-PLW-01Z, "Passive Core Cooling System Containment Building Room 11206 Containment Recirc. to DVI-A," Revision 2 SV4-PXS-PLW-02A, "Passive Core Cooling System Containment Building Room 11207 Containment Recirculation to DVI-B," Revision 0 SV4-PXS-PLW-02E, "Passive Core Cooling System Containment Building Room 11207 IRWST to DVI-B & RNS Pump Suction," Revision 1 SV4-PXS-PLW-02Z, "Passive Core Cooling System Containment Building Room 11207 Containment Recirculation to DVI-B," Revision 0 SV4-PXS-PLW-090, "Passive Core Cooling System Containment Bldg Room 11204 Containment Recirculation to DVI-B," Revision 1 Section 1A31 APP-DB01-VBR-100, "AP1000 Class 1E 250 VDC Battery System Qualification Report:

Qualification Report for Batteries with Type GN-29 Cells", Revision 1, dated: 1/8/2016 19

SV3-MS40-VGR-850002, "MC808-APP-QAD-135 EEM Battery Rack Seismic Report", Revision A, dated: 2/9/2016 APP-1211-CE-001, "Auxiliary Building Area 1 Battery Racks Embedment Plate Locations Room 12104 Plan at EL. 66-6", Revision 7 Section 1A32 Work Package:

SV4-1140-SPW-800006, Date: 6/11/19 Specifications:

APP-SS01-Z0-001, Shop Fabrication of Structural Steel, Westinghouse Safety Class C, Seismic Category I, Revision 5 Procedures:

NCSP 03-40, Structural Steel Erection, Revision 4 Welding Procedure Specification, P1-A-Lh (Structural), Revision 0 APP-GW-GAP-428, Nonconformance and Disposition Report (N&D), Revision 15 Drawings:

SV4-FSK-C-00247, Unit 4 Containment Building SPL 18 Sequence 1 Connection Map elevation 118-6 sheet 1 of 2, Revision 0 SV4-FSK-C-00247, Unit 4 Containment Building SPL 18 Sequence 1 Connection Map elevation 118-6 sheet 2 of 2, Revision 0 SV4-1140-SPK-870405, Unit 4 SPL 18 Sequence 1 Installation Weld Map sheet 1 of 6, Revision 0

SV4-1140-SPK-870405, Unit 4 SPL 18 Sequence 1 Installation Weld Map sheet 2 of 6, Revision 0

SV4-1140-SPK-870405, Unit 4 Containment Building SPL 18 and SPL 51 installation Sequences, Revision 1 WM-C-4-11-323966, Unit 4 Containment BLDG SPL 18 Platform, Sequence 1 Installation EL.

118-6 Weld Map III, Revision 1 Inspection Report:

26139-SV4-IR-SS-00241, Qualification of Unit 4 Containment Building Bolt Installers, Date:

5/17/19 Condition Report:

50019858, NI4 Containment 107'-2" elevation Slab North East Placement 50026844, Match Marking on Structural Bolts Nonconformance and Disposition Report SV4-CE01-GNR-000181, Installation of Deformed Wire Anchors to Embedment at Elevation 107'-2", Revision 0 Section 1A33 Concrete Records:

2019SCC1244, "Wood Report of Concrete Compression Test Results," 9/27/19 2019SCC1245, "Wood Report of Concrete Compression Test Results," 9/27/19 Concrete Placement/Order Pour Card, Pour Number 5075, "Unit 4 Containment Operating Deck up to 135' South West," 7/29/19 20

Concrete Placement/Order Pour Card, Pour Number 5082, "Unit 4 NI Aux Bldg 117'-6" to 135'-

3" CL I (Wall 128) Concrete Placement," 7/29/19 Concrete Placement/Order Pour Card, Pour Number 5082, "Unit 4 NI Aux Bldg 117'-6" to 135'-

3" CL 2 (Wall 134) Concrete Placement," 7/29/19 Concrete/Grout Delivery Ticket #79941, Pour #5075, 7/29/19 Concrete/Grout Delivery Ticket #79955, Pour #5082, 7/29/19 Miscellaneous:

CR 50015426, "Concrete in SV4-1242-CP-S07 placement," 3/12/19 QC IR 26139-SV4-IR-C0-00848, "Wall Placement 128 located on CL I starting 5' north of CL 1 to 8' north of CL 4 between El 117'-6" and 135'-3"," 8/23/19 QC IR 26139-SV4-IR-C0-00930, " SV4-1150-C0W-1033996," 7/30/19 QC IR 26139-SV4-IR-C0-00989, "NI4 Cylindrical Shield Wall / Placement RC10B / El 135'-3","

8/20/19 Work Package SV4-1150-C0W-1033996, "Containment Concrete Placement 135'-3" West Placement. Areas 1, 2 & 4," Revision 0 Specifications:

132175-102-006-04-000052, "Approved Mix Designs," 12/3/18 26139-000-4MP-T81C-N3210, "Concrete Operations," Revision 6 26139-000-4MP-T81C-N7102, "Control of Measuring and Test Equipment," Revision 2 SV4-CC01-Z0-026, "Safety Related Mixing and Delivering Concrete," Revision 8 SV4-CC01-Z0-027, "Safety Related Concrete Testing Services," Revision 7 SV4-CC01-Z0-031, "Safety Related Placing Concrete and Reinforcing Steel," Revision 8 Section 1A34 Drawings:

SV4-0000-C9-001, AP1000 CONCRETE GENERAL NOTES, REVISION 9 SV4-1100-CRX-007-R0, CONTAINMENT CONCRETE REINFORCEMENT DRAWING INDEX OF DRAWINGS REINFORCEMENT FLOOR AT EL 135-3 SV4-1150-CR-010-R1, CONTAINMENT CONCRETE REINFORCEMENT PLAN VIEW AT EL 135-3 SV4-1150-CR-013-R2, CONTAINMENT CONCRETE REINFORCEMENT CA55 TOP SV4-1150-CR-021-R1, CONTAINMENT CONCRETE REINFORCEMENT DRAWING SECTIONS A&B FLOOR AT EL 135-3 SV4-1150-CR-022-R1, CONTAINMENT CONCRETE REINFORCEMENT DRAWING SECTIONS C, C1 & D FLOOR AT EL 135-3 SV4-1150-CR-045-R0, CONTAINMENT CONCRETE REINFORCEMENT DRAWING CA55 BOTTOM SV4-1150-CR-047-R0, CONTAINMENT CONCRETE REINFORCEMENT CA55, CA56, CA57 &

CA58 TYPE DETAILS Engineering and Design Coordination Reports:

APP-1150-GEF-85013, Coupler Rebar Clash with Diagonal Rebar in CA55, Revision 0 APP-1150-GEF-85033, Cont. Areas, EL 135-3, CA55/56/57 Reinf. Details, Revision 0 APP-1150-GEF-85040, CA55 Box Beam Missing Coupler Locations, Revision 0 APP-CA00-GEF-236, Resolution of CA55, CA56, CA57 & CA58 Design Recommendations, Revision 0 APP-CA01-GEF-077, Couplers on CA01 for Connection of CA55 and CA56, Revision 0 21

APP-CR01-GEF-850505, CV A1 W RFC EL 133-3 CA55 Girder Connection Concrete CJ 132-3, Revision 0 SV0-CR01-GEF-001138, CV A1&2 Rm 11500 CA55-56-57 Conc Reinf Type NB Coupler Addition, Revision 0 SV0-CR01-GEF-001139, CV A1 top CA01 CA55 Intersection El 135-3 Rebar Requires Coupler, Revision 0 SV0-CR01-GEF-001140, 50001630 CV A1 El 135 CA55 Box Beam Interference with Reinforcement, Revision 0 Calculations:

APP-CA55-S3C-008, AP1000 CA55 Structural Module Design Evaluation, Version 0 APP-CA55-S3C-009, AP1000 CA55 Structural Module Connection Evaluation, Version 0 Specifications:

SV4-CC01-Z0-031, Safety Related Placing Concrete and Reinforcing Steel, Westinghouse Seismic Category I, Safety Class C Nuclear Safety, Revision 8 Section 1A35 Specifications:

APP-1208-Z0-001, Specification for the Fabrication and Field Erection of the SC Panels and the Conical Roof Steel Structure for the AP1000 Shield Building, Revision 2 Drawings 231122-000-SP-01-000102, General Notes Welding AP 1000, Revision 0 231122-000-SP-01-000201, Weld Details Vert & Horiz AP 1000, Revision 2 231122-000-SP-01-000204, Field Weld Seams, Fit-up Panel Face offset AP1000, Revision 1 WM-C-4-12-145421, upper Equipment Hatch North Jamb to SC Panel Weld Map, Revision 1 Nonconformance Report:

231122-004-QA-NC-00038, Panel 01B arrived without the backup bar notch in the 2-inch support plate on the end connecting to the vault door, Revision 1 Nonconformance and Disposition Report SV4-1208-GNR-000051, Panel 01B 2 Support Pl Backing Opening, Revision 0 Traveler Documents 231122-004-QA-TRV-01054, Cut and Bevel Access hole for backup Bar, U4-01B BuB Access Hole, Date 7/19/2019 Procedures:

181816-000-WS-SP-45001, General Welding Procedure Specification for AWS D1.1, AWS D1.4, AWS D1.6, and ASME Section IX Qualified WPSs, Revision 1 1818-000-WS-PR-45054, Ultrasonic Examination Statically Loaded Nontubular Connections AWS D1.1 Shield Building Work, Revision 3 Welding Procedure Qualification Record 1984, Procedure Specification P1-A-Lh(A10) (CVN - 70 F), Date: 12/20/2018 Welding Procedure Specifications:

P1-A-Lh(A10) (CVN - 70 F), Welding Procedure Specification, Revision 0 Nondestructive Examination Reports:

V-19-UT-AWS-D1.1-0867, Ultrasonic Examination Report, Date: 08/02/2019 V-19-UT-AWS-D1.1-0869, Ultrasonic Examination Report, Date: 08/28/2019 22

Welder Performance Qualification Test Records (Bechtel)

BM080 BM175 BM174 Section 1A36 Design Specifications:

APP-1208-Z0-001, Specification for the Fabrication and Field Erection of the SC Panels and the Conical Roof Steel Structure for the AP 1000 Shield Building, Revision 2 Drawings:

SV4-1278-SC-150, Shield Building Air Inlet and Tension Ring Structure Steel Panels General Notes, Revision 0 Air Inlet Module AI-04 SV4-1278-SC-211, Shield Building Air Inlet and Tension Ring Structure Steel Panels Air Inlet Panel Group 21, Revision 1 SV4-1278-SC-212, Shield Building Air Inlet and Tension Ring Structure Steel Panels Air Inlet Panel Group 21 Details 1, Revision 1 SV4-1278-SC-213, Shield Building Air Inlet and Tension Ring Structure Steel Panels Air Inlet Panel Group 21 Details 2, Revision 1 SV4-1278-SC-214, Shield Building Air Inlet and Tension Ring Structure Steel Panels Air Inlet Panel Group 21 Details 3, Revision 1 SV4-1278-SC-215, Shield Building Air Inlet and Tension Ring Structure Steel Panels Air Inlet Panel Group 21 Details 4, Revision 1 SV4-1278-V0-850053, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 15 Assembly Sheet 1 of 8, Revision 8 SV4-1278-V0-850054, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 15 Assembly Sheet 2 of 8, Revision 9 SV4-1278-V0-850055, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 15 Assembly Sheet 3 of 8, Revision 9 SV4-1278-V0-850056, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 15 Assembly Sheet 4 of 8, Revision 9 SV4-1278-V0-850057, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 15 Assembly Sheet 5 of 8, Revision 9 SV4-1278-V0-850058, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 15 Assembly Sheet 6 of 8, Revision 9 SV4-1278-V0-850059, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 15 Assembly Sheet 7 of 8, Revision 9 SV4-1278-V0-850061, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 15 Weld Joint Index Map Sheet 1 of 7, Revision 3 SV4-1278-V0-850062, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 15 Weld Joint Index Map Sheet 2 of 7, Revision 3 SV4-1278-V0-850063, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 15 Weld Joint Index Map Sheet 3 of 7, Revision 3 SV4-1278-V0-850064, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 15 Weld Joint Index Map Sheet 4 of 7, Revision 3 SV4-1278-V0-850065, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 15 Weld Joint Index Map Sheet 5 of 7, Revision 3 SV4-1278-V0-850066, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 15 Weld Joint Index Map Sheet 6 of 7, Revision 3 23

SV4-1278-V0-850067, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 15 Weld Joint Index Map Sheet 7 of 7, Revision 3 SV4-1278-V0-850078, AP1000 Shield Bldg Lifting and Handling for Air Inlet Panel Group 15 Sheet 2 of 4, Revision 6 SV4-1278-V0-850077, AP1000 Shield Bldg Lifting and Handling for Air Inlet Panel Group 15 Sheet 4 of 4, Revision 6 SV4-1278-V0-850080, AP1000 Shield Bldg Lifting and Handling for Air Inlet Panel Group 15 Sheet 1 of 4, Revision 6 SV4-1278-V0-850201, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 15 Assembly, Revision 7 Air Inlet Module AI-15 SV4-1278-SC-261, Shield Building Air Inlet and Tension Ring Structure Steel Panels Air Inlet Panel Group 26, Revision 0 SV4-1278-SC-262, Shield Building Air Inlet and Tension Ring Structure Steel Panels Air Inlet Panel Group 26 Details 1, Revision 0 SV4-1278-SC-263, Shield Building Air Inlet and Tension Ring Structure Steel Panels Air Inlet Panel Group 26 Details 2, Revision 0 SV4-1278-SC-264, Shield Building Air Inlet and Tension Ring Structure Steel Panels Air Inlet Panel Group 26 Details 3, Revision 0 SV4-1278-SC-265, Shield Building Air Inlet and Tension Ring Structure Steel Panels Air Inlet Panel Group 26 Details 4, Revision 0 SV4-1278-V0-850120, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 26 Assembly, Revision 5 SV4-1278-V0-850121, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 26 Assembly, Revision 5 SV4-1278-V0-850122, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 26 Assembly, Revision 5 SV4-1278-V0-850123, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 26 Assembly, Revision 5 SV4-1278-V0-850124, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 26 Assembly, Revision 5 SV4-1278-V0-850125, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 26 Assembly, Revision 5 SV4-1278-V0-850126, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 26 Assembly, Revision 5 SV4-1278-V0-850127, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 26 Assembly, Revision 5 SV4-1278-V0-850165, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 26 Weld Joint Index Map Sheet 1 of 7, Revision 3 SV4-1278-V0-850166, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 26 Weld Joint Index Map Sheet 2 of 7, Revision 3 SV4-1278-V0-850167, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 26 Weld Joint Index Map Sheet 3 of 7, Revision 3 SV4-1278-V0-850168, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 26 Weld Joint Index Map Sheet 4 of 7, Revision 3 SV4-1278-V0-850169, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 26 Weld Joint Index Map Sheet 5 of 7, Revision 3 SV4-1278-V0-850170, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 26 Weld Joint Index Map Sheet 6 of 7, Revision 3 SV4-1278-V0-850171, AP1000 Shield Bldg Air Inlet Struct Steel Panels Group 26 Weld Joint Index Map Sheet 7 of 7, Revision 3 24

SV4-1278-V0-850270, AP1000 Shield Bldg Lifting and Handling for Air Inlet Panel Group 26 Sheet 1 of 4, Revision 4 Material Certification Reports:

132176D100.SB00540401200003, Deformed Wire Nelson D2S (D2L Mod.) and D2L Book D01 132176D100.SB00540401200004, Rebar Book R03 132176D100.SB00540401200005, Weld Metal Book W02 132176D100.SB00540401200007, ASTM A57207 Grade 50 Plate Book P16 132176D100.SB00540401200015, Nelson Stud (S3L) Book S01 132176D100.SB00540401200016, Seamless Pipe Book T01 132176D100.SB00540401200017, ASTM A57207 Grade 50 Plate Book P24 132176D100.SB00540401200019, Weld Metal Book W03 Receipt Inspection Packages:

132176D100.SB00540401200024, SV41278SCAI04 Documentation Package for AP1000 Air Inlet Structural Modules Group 15 132176D100.SB00540401200042, SV41278SCAI15 Documentation Package for AP1000 Air Inlet Structural Modules Group 26 Commercial Grade Dedication Packages:

132176D100.SB00540401200090, Attachment 1, Book P25 Revision A to HII Mechanical Instruction 7340FQ007 (Revision A) Material Certifications for Generic Document Package 132176D100.SB00540401200092, Attachment 1, Book P27 Revision A to HII Mechanical Instruction 7340FQ007 (Revision A) Material Certifications for Generic Document Package Engineering and Design Coordination Reports (E&DCR):

APP-1278-GEF-850074, Air Inlet Modified Strong-back Substitution, Revision 0 APP-1278-GNR-850168, HII Mechanical NCE 3761A for SV4-1278-SC-AI15 has WPS 1094 Violation, Revision 0 APP-1278-GEF-850054, Shield Building Air Inlet Steel Structure, Panel numbering, Revision 0 Nonconformance & Disposition Report:

APP-1278-GNR-850212, HII Mechanical NCR 3872A for SV4-1278-SC-AI15, WPS 1072 Used in Lieu of WPS 1084, Revision 0 SV4-1278-GNR-000001, HII Mechanical NCR 3909 A, Vogtle 4 (SV4), Air Inlet Groups, WPS 1072 Used in Lieu of WPS 1084, Revision 0 Welding Procedure Specifications:

135470-D100.SB005-0105 WPS 1006, FCAW/Semiautomatic (ASTM A572 Gr 50) 135470-D100.SB005-0105 WPS 1017, GTAW/Manual (ASTM A572 Gr 50 Plate to AWS D1.1-2000 Table 3.1 Group II or Group I steel) 135470-D100.SB005-0105 WPS 1021, Weld Procedure Specification FCAW/Semiautomatic 135470-D100.SB005-0105 WPS 1032, Weld Procedure Specification (WPS)

GTAW/Manual/Vertical 135470-D100.SB005-0105 WPS 1086, FCAW / Semi-automatic API 5L GR X65Q / ASTM A572-50 25

Section 1A37 181816-000-SP-ENi5, "Welding Procedure Specification for ENi5S/842H" with supporting PQR-No. 13416, Revision 2, 04/23/2018 181816-000-WS-PR-45054, "Ultrasonic Examination Statically Loaded Nontubular Connection AWS D1.1 Shield All Work," Revision 3 181816-000-WS-PR-45056, "Visual Inspection Procedure AWS D1.1 Shield Wall Work,"

Revision 1 181816-000-WS-SP- E71T1, "Welding Procedure Specification E71T1," Revision 1 181816-000-WS-SP-45001, "General Welding Procedure Specification for AWS D1.1, AWS D1.4, AWS D1.6, and ASME Section IX Qualified WPSs", Revision 1 CB&I Services ASME IX - Welder Performance Qualification (WPQ) SAW-2G-3/4-TLA for welding operator 63171683, 9/12/19 SV4-1208-Z0-001, "Specification for the Fabrication and Field Erection of the SC Panels and the Conical Roof Steel Structure for the AP1000 Shield Building," Revision 0 Ultrasonic Testing Report 231122-004-IN-RP-U0262, Weld Identification 07A/07B O/S, 7/1/19 Ultrasonic Testing Report 231122-004-IN-RP-U0263, Weld Identification 07A/07B I/S, 7/1/19 Weld Traveler 231122-004-QA-TRV-07013, "U4-07A/07B Vert. I/O," 5/8/19 Weld Traveler 231122-004-QA-TRV-07025, "Set-No. U4-0708 Horiz I/O" Spreadsheet Section 1A38 CB&I Traveler 231122-004-QA-TRV-01039, "U4-01E/01F Vert. I/O", Revision 1 CB&I 181816-000-WS-SP-45001, "General Welding Procedure Specification for AWS D1.1, AWS D1.4, AWS D1.6, and ASME Section IX Qualified WPSs", Revision 1 CB&I Services ASME IX - Welder Performance Qualification (WPQ) FCA-F6-2G3G4G-1/2-JPJ, 10/03/19 CB&I Services ASME IX - Welder Performance Qualification (WPQ) FCA-F6-2G3G4G-3/4-JPB, 10/03/19 CB&I Services ASME IX - Welder Performance Qualification (WPQ) FCA-F6-2G3G4G-1-JMH, 10/03/19 Section 1A39 Drawings:

SV4-0000-C9-001, AP1000 CONCRETE GENERAL NOTES, Revision 8 SV4-0000-C9-002, AP1000 CONCRETE GENERAL NOTES, Revision 8 SV4-1200-CR-910-R7, AUXILIARY BUILDING AREAS 1 & 2 CONCRETE REINFORCEMENT WALL 11 ELEVATION SV4-1240-CR-970-R4, AUXILIARY BUILDING WALL 11 PENETRATION AREA CONCRETE REINFORCEMENT SECTIONS AND DETAILS SV4-1240-CR-971-R3, AUXILIARY BUILDING WALL 11 PENETRATION AREA CONCRETE REINFORCEMENT SECTIONS AND DETAILS SV4-1240-CR-972-R2, AUXILIARY BUILDING WALL 11 PENETRATION AREA CONCRETE REINFORCEMENT SECTIONS AND DETAILS SV4-1240-CR-973-R3, AUXILIARY BUILDING WALL 11 PENETRATION AREA CONCRETE REINFORCEMENT SECTIONS AND DETAILS SV4-1240-CR-974-R3, AUXILIARY BUILDING WALL 11 PENETRATION AREA CONCRETE REINFORCEMENT SECTIONS AND DETAILS SV4-1240-CR-975-R4, AUXILIARY BUILDING WALL 11 PENETRATION AREA CONCRETE REINFORCEMENT SECTIONS AND DETAILS SV4-1240-CR-976-R4, AUXILIARY BUILDING WALL 11 PENETRATION AREA CONCRETE REINFORCEMENT SECTIONS AND DETAILS 26

SV4-1240-CR-977-R4, AUXILIARY BUILDING WALL 11 PENETRATION AREA CONCRETE REINFORCEMENT SECTIONS AND DETAILS SV4-1240-CR-978-R4, AUXILIARY BUILDING WALL 11 PENETRATION AREA CONCRETE REINFORCEMENT SECTIONS AND DETAILS SV4-1240-CR-980-R3, AUXILIARY BUILDING WALL 11 PENETRATION AREA CONCRETE REINFORCEMENT SECTIONS AND DETAILS SV4-1240-PO-917-R2, AUXILIARY BUILDING PIPING PENETRATIONS AREAS 1 & 2 EL.

117-6 SECTION K Engineering and Design Coordination Reports:

APP-1240-GEF-290, Auxiliary Building Wall 11 Constructability Changes, Revision 0 APP-1240-GEF-850015, Placement Tolerances on #14 Circumferential Bars, Revision 0 APP-1240-GEF-850060, Wall 11 Constructibility Changes, Revision 0 APP-CR01-GEF-850405, Wall 11 Radial and Circumferential Pattern, Revision 0 APP-CR01-GEF-850456, #4 U-bands between penetrations and openings require re-design, Revision 0 SV0-CR01-GEF-001111, Wall 11 117-6 to 135-3 Wall L to Q Constructability, Revision 0 SV0-CR01-GEF-001195, Wall 11 Drawing Discrepancies (ESR 50012954), Revision 0 SV0-CR01-GEF-001165, Alignment of Project Specifications with ACI 349 Reinforcement Traceability Requirements, Revision 0 Specifications:

SV4-CC01-Z0-031, Safety Related Placing Concrete and Reinforcing Steel, Westinghouse Seismic Category I, Safety Class C Nuclear Safety, Revision 8 SV4-CR01-Z0-011, Furnishing of Safety Related Reinforcing Steel, Revision 4 Section 1A40 Drawings:

SV4-0000-C9-001, AP1000 CONCRETE GENERAL NOTES, Revision 8 SV4-0000-C9-002, AP1000 CONCRETE GENERAL NOTES, Revision 8 SV4-1230-CR-910-R8, AUXILIARY BUILDING AREAS 1 & 2 CONCRETE REINFORCEMENT WALL 11 SECTIONS & DETAILS EL 100-0 EL 109-0 & EL 117-6 SV4-1242-CC-204-R9, AUXILIARY BUILDING CONCRETE OUTLINE AREA 2 FLOOR EL 117-6 SV4-1242-CR-204, AUXILIARY BUILDING AREA 2 CONCRETE REINFORCEMENT FLOOR EL 117-6 PLAN SV4-1242-CR-214-R3, AUXILIARY BUILDING AREA 2 CONCRETE REINFORCEMENT FLOOR EL 117-6 DETAIL (SHEET 1)

SV4-1242-CR-224, AUXILIARY BUILDING AREA 2 CONCRETE REINFORCEMENT FLOOR EL 117-6 DETAIL (SHEET 2), REVISION 2 SV4-1242-CR-234-R0, AUXILIARY BUILDING AREA 2 CONCRETE REINFORCEMENT FLOOR EL 125-8, 126-0 & 128-0 PLAN SV4-1242-CR-244-R3, AUXILIARY BUILDING AREA 2 CONCRETE REINFORCEMENT FLOOR EL 117-6 DETAIL (SHEET 3)

SV4-1242-CR-254-R3, AUXILIARY BUILDING AREA 2 CONCRETE REINFORCEMENT FLOOR EL 117-6 DETAIL (SHEET 4)

SV4-1242-CR-264-R3, AUXILIARY BUILDING AREA 2 CONCRETE REINFORCEMENT FLOOR EL 117-6 DETAIL (SHEET 5) 27

Engineering and Design Coordination Reports:

APP-1242-GEF-850014, Area 2 EL 117-6 Slab Reinf & Drawings Cleanup, Revision 0 SV0-CR01-GEF-001095, Wall K EL. 117-6 Floor Slab Connection, Revision 0 Nonconformance and Disposition Reports (N&Ds):

SV4-CR01-GNR-000557, Unit 4 Aux SP-34 Form Savers Out of Tolerance (ESR 50019999 &

50020852), Revision 0 SV4-CR01-GNR-000558, Aux Bldg El. 117-6. Development of additional #5 Slab bars ESR 50020861, Revision 0 Specification:

SV4-CC01-Z0-031, Safety Related Placing Concrete and Reinforcing Steel, Westinghouse Seismic Category I, Safety Class C Nuclear Safety, Revision 8 Section 1A41 Design Specifications:

SV4-CC01-Z0-026, Safety Related Mixing and Delivering Concrete, Revision 8 SV4-CC01-Z0-027, Safety Related Concrete Testing Services, Revision 7 SV4-CC01-Z0-031, Safety Related Placing Concrete and Reinforcement Steel, Revision 8 Engineering & Design Coordination Report:

SV0-CC01-GEF-000418, mixer trucks without water meters, Revision 0 Miscellaneous:

NRMCA Fleet Inspection Reporting Form Truck Mixers, 5.7 Inspection Record of Delivery Fleet, dated 01/25/2019 Section 1A42 Drawings:

SV4-0000-C9-001, AP1000 CONCRETE GENERAL NOTES, Revision 8 SV4-0000-C9-002, AP1000 CONCRETE GENERAL NOTES, Revision 8 SV4-1200-CR-931, AUXILIARY BUILDING AREAS 2 & 3 CONCRETE REINFORCEMENT WALL 7.3 ELEVATION, REVISION 10 SV4-1240-CR-931-R4, AUXILIARY BUILDING AREAS 2 & 3 CONCRETE REINFORCEMENT WALL 7.3 - SECTIONS & DETAILS EL 117-6 Engineering and Design Coordination Reports:

APP-1240-GEF-850074, Wall 7.3 Reinforcement and Penetrations, Revision 0 Specification:

SV4-CC01-Z0-031, Safety Related Placing Concrete and Reinforcing Steel, Westinghouse Seismic Category I, Safety Class C Nuclear Safety, Revision 8 Miscellaneous:

ND-19-1031, Southern Nuclear Operating Company, Vogtle Electric Generating Plant Unit 4, Request for License Amendment: Reinforcement Changes for Wall L and Wall 7.3 (LAR 016), August 22, 2019 28

Section 1A43 Specifications:

SV4-CC01-Z0-031, "Safety Related Placing Concrete and Reinforcing Steel," Revision8 SV4-CC01-Z0-027, "Safety Related Concrete Testing Services," Revision 7 Miscellaneous:

Concrete Placement Summary, "Unit 4 Nuclear Island, North Auxiliary Building Wall Placement

1. 121, 122, 123, Wall 11 Critical Section Stargate, Elevation 115'-6" and 117'-6" to 135'-3","

Revision 0 Concrete/Grout Delivery Ticket No. 54685, Pour #5039, Date 08/30/2019 Concrete/Grout Delivery Ticket No. 54696, Pour #5039, Date 08/30/2019 Section 1A44 Concrete Records:

2019SCC1244, "Wood Report of Concrete Compression Test Results," 9/27/19 2019SCC1271, "Wood Report of Concrete Compression Test Results," 9/16/19 Calibration Report No. V-LC-0009-20, Alkon Spectrum VI Load Cell Cement 46110065, 05/30/2019 Calibration Report No. V-LC-0010-20, Alkon Spectrum VI Load Cell Water 51110586, 05/30/2019 Calibration Report No. V-LC-0011-21, Alkon Spectrum VI Load Cell Ice 51110511, 05/30/2019 Calibration Report No. V-LC-0012-20, Alkon Spectrum VI Load Cell Aggregate 46110043, 05/30/2019 Concrete Placement/Order Pour Card, Pour Number 5082, "Unit 4 NI Aux Bldg 117'-6" to 135'-

3" CL I (Wall 128) Concrete Placement," 7/29/19 Concrete Placement/Order Pour Card, Pour Number 5082, "Unit 4 NI Aux Bldg 117'-6" to 135'-

3" CL 2 (Wall 134) Concrete Placement," 7/29/19 Concrete/Grout Delivery Ticket #79941, Pour #5075, 7/29/19 Concrete/Grout Delivery Ticket #80222, Pour #5117, 8/16/19 Concrete/Grout Delivery Ticket #80233, Pour #5117, 8/16/19 Concrete/Grout Delivery Ticket #80234, Pour #5117, 8/16/19 Concrete/Grout Delivery Ticket #80237, Pour #5117, 8/16/19 Out of Calibration Report M&TE ID Number V-LC-0011, Load Cell Ice, 9/7/19 QC IR 26139-SV4-IR-C0-00848, "Wall Placement 128 located on CL I starting 5' north of CL 1 to 8' north of CL 4 between El 117'-6" and 135'-3"," 8/23/19 QC IR 26139-SV4-IR-C0-00989, "NI4 Cylindrical Shield Wall / Placement RC10B / El 135'-3","

8/20/19 QC IR 26139-SV4-IR-C0-00996, "WP129B 1 Line. Elevations 125'-0" / 127'-0" to 135'-3","

8/20/19 Corrective Action Documents:

CR 50010054, Concrete Mixer Truck Sight Gauges, 12/18/18 CR 50021530, Indeterminate Concrete, 6/5/19 CR 50023942, Unit 4 Aux. I Lineconcrete spillage removal at Bulkhead, 7/10/19 CR 50025768, Batch plant ice scale, 8/1/19 E&DCR SV0-CC01-GEF-000461, "Slump Testing after Addition of Water to Concrete Trucks (ESR 50009473)," Revision 0 29

Nonconformance & Disposition Reports:

SV3-CC01-GNR-000564, "Batch plant ice scale out of calibration / U3 Yard Ramp Foundation placement (ESR 50027857)," Revision 0 SV4-CC01-GNR-000330, "WOOD CR-SV-358: Thermometer 4704 Lost without Closeout Calibration (ESR 50025871)," Revision 0 SV4-CE01-GNR-000184, "Aux. I-Line Embeds Damaged during Concrete Spillage Removal (ESR 50024611)," Revision 0 Procedures and Specifications:

132175-102-006-04-000052, "Approved Mix Designs," 12/3/18 26139-000-4MP-T81C-N3210, "Concrete Operations," Revision 6 APP-GW-GAP-420, "Engineering and Design Coordination Reports," Revision 18 APP-GW-GAP-428, "Nonconformance and Disposition Report." Revision 16 SV4-CC01-Z0-026, "Safety Related Mixing and Delivering Concrete," Revision 8 SV4-CC01-Z0-027, "Safety Related Concrete Testing Services," Revision 7 SV4-CC01-Z0-031, "Safety Related Placing Concrete and Reinforcing Steel," Revision 8 26139-000-4MP-T81C-N7102, "Control of Measuring and Test Equipment," Revision 2 Work Packages:

SV4-1240-C0W-1002601, "Wall from 127'-0" to 135'-3" Elev., CL 1 from CL I to CL N," Revision 0

SV4-1240-C0W-800007, "Wall from 117'-6" to 135'-3" Elev., CL I, Betw 8' North of CL 4 & 5' North of CL 1 (Placement 128)," Revision 0 SV4-1240-C0W-800008, "Wall from 117'-6" to 135'-3" Elev., CL 2 (Placement 134)," Revision 0 Section 1A45 SV4-1200-ITR-800082, "Unit 4 Non-Radiologically Controlled Auxiliary Building Concrete Thickness Verification: Column Line Q wall, from shield building wall to 11, Elevation 100'-0" to 117'-6", Wall 82," Revision 0 SV4-1200-ITR-812313, "Unit 4 Non-Radiologically Controlled Auxiliary Building Concrete Thickness Verification: Floor, from K to L and shield building wall to column line 10, Elevation 100'-0", Floor of Room 12313 (SP-18A)," Revision 0 Section 1A46 SV4-1200-ITR-800087, "Unit 4 Radiologically Controlled Auxiliary Building Concrete Thickness Verification: Column Line I Wall, from 1 to 3, Elevation 100'-0" to 117'-6"; Column Line I Wall, from 3 to 4, Elevation 100'-0" to 117'-6"; Column Line I Wall , From 4 to 16'-0" south of 5, Elevation 107'-2" to 117'-6", Wall 87," Revision 0 SV4-1200-ITR-800090, "Unit 4 Radiologically Controlled Auxiliary Building Concrete Thickness Verification: Column Line N Wall, from 1 to 12'-9" north of 1, Elevation 100'-0" to 125'-0";

Column Line N Wall, from 12'-9" north of 1 to 2, Elevation 100'-0" to 118'-2 1/2", Wall 90,"

Revision 0 SV4-1200-ITR-812352, "Unit 4 Radiologically Controlled Auxiliary Building Concrete Thickness Verification ITAAC Number 3.3.00.02a.ii.d and 3.3.00.03d: Floor, From I to shield building wall and from intersecting vertical wall before column line 5 to column line 5, Elevation 105'-0", Floor of Room 12352 (SP-21)," Revision 0 Section 1A47 216139-19-MIR-16715, "Material Issue Report- Unit 4 Labels for Setroute; WO#193578, Work Package #SV4-1000-VLW-800000," 02/05/2019 30

APP-ECS-E9-040, "Electrical Raceway and Cable Identification Markers," Revision 2 APP-G1-V8-001, "AP1000 Electrical Installation Specification," Revision 6 CAR 80000674, "NRC Identified- Cable Tray Identification Labels Not Consistently Colored."

CR 500019891, "Cable Tray Identification Labels Not Consistently Colored," 05/10/2019 FED-STD-595C, "Federal Standard Colors Used in Government Procurement," 01/16/2008 J132175-MRR-16-00204, "J132175- Vogtle EPC Unit 3 & Site Material Receiving Report,"

02/01/16 J132175-MRR-16-00205, "J132175- Vogtle EPC Unit 3 & Site Material Receiving Report,"

02/01/16 J132175-MRR-16-01844, "J132175- Vogtle EPC Unit 3 & Site Material Receiving Report,"

04/01/16 J132175-MRR-16-02261, "J132175- Vogtle EPC Unit 3 & Site Material Receiving Report,"

04/21/16 J132175-MRR-16-02481, "J132175- Vogtle EPC Unit 3 & Site Material Receiving Report,"

05/06/16 Purchase Order SNG101747956, 07/06/2018 Purchase Order SNV1000847, 11/06/2018 S-E225-021, "Conduit Installation- Exposed," Revision 01.01 Stores Requisition Report- 132175-SRR-18-01255, 02/13/2018 SV4-1211-ER-101, "Auxiliary Building Area 1 Conduit Arrangement Plan at Elevation 66'6","

Revision 14 SV4-ECS-E9-005, "Raceway Numbering and Raceway Mark Numbering," Revision 4 SV4-ECS-E9-030, Sheet 1, "Conduit Notes and Details," Revision 10 SV4-ECS-E9-030, Sheet 1, "Conduit Notes and Details," Revision 8 SV4-ECS-E9-030, Sheet 1, "Conduit Notes and Details," Revision 9 TE 60004243, "Review the Issue Documented in CR 500019891 for Compliance with ITAAC 790," 5/10/2019 Work Package SV4-1211-ERW-861226, "Install Design Routed Conduit and Conduit Supports in Battery Room "D", Room 12105 EL 66'6"," Revision 0 Section 1A48 Reports:

ND-19-1027 Enclosure, Vogtle Electric Generating Plant (VEGP) Unit 4 ITAAC Closure Notification on Completion of ITAAC C.2.6.12.05 [Index Number 675], dated: 8/30/2019.

C.2.6.12.05-U4-PCD-Rec0, Vogtle 3 & 4 Offsite Power Maximum Available Fault Currents, dated: 8/27/2019.

PCD Summary Report C.2.6.12.05-U4-SumRep-Rev0, Review of as-Designed Short Circuit Capabilities of Onsite AC Power System, dated: 8/29/2019.

SV4-EB01-VQQ-800000, Powell Delta / Unibus Project # 223953-20 In-Process Inspection and Test Plan Isolated Phase Bus Duct Batch 1 ITP, dated: 2/28/2019.

SV4-EB01-VQQ-800001, Powell Delta / Unibus Project # 223953-20 In-Process Inspection and Test Plan Isolated Phase Bus Duct Batch 2 ITP, dated: 3/7/2019.

SV4-EB01-VQQ-800002, Powell Delta / Unibus Project # 223953-20 In-Process Inspection and Test Plan Isolated Phase Bus Duct Batch 3 ITP, dated: 3/12/2019.

SV4-EB01-VQQ-800003, Powell Delta / Unibus Project # 223953-20 In-Process Inspection and Test Plan Isolated Phase Bus Duct Batch 4 ITP, dated: 3/18/2019.

SV4-EB01-VQQ-800004, Powell Delta / Unibus Project # 223953-20 In-Process Inspection and Test Plan Isolated Phase Bus Duct Batch 5 ITP, dated: 3/25/2019.

SV4-EB01-VQQ-800005, Powell Delta / Unibus Project # 223953-20 In-Process Inspection and Test Plan Isolated Phase Bus Duct Batch 8 ITP, dated: 4/5/2019.

31

SV4-EB01-VQQ-800006, Powell Delta / Unibus Project # 223953-20 In-Process Inspection and Test Plan Isolated Phase Bus Duct Batch 6 ITP, dated: 4/3/2019.

SV4-EB01-VQQ-800007, Powell Delta / Unibus Project # 223953-20 In-Process Inspection and Test Plan Isolated Phase Bus Duct Batch 7 ITP, dated: 4/3/2019.

SV4-EB01-VQQ-800008, Powell Delta / Unibus Project # 223953-20 In-Process Inspection and Test Plan Isolated Phase Bus Duct ITP 26, dated: 6/25/2019.

Miscellaneous:

VEGP 3 & 4 UFSAR, Chapter 8.2, Revision 6 SV4-ET01-VQQ-001, Westinghouse Quality Release and Certificate of Conformance QR 3902, Revision 0 SV4-ES03-VQQ-001, Westinghouse Quality Release and Certificate of Conformance QR 11325 (Main Generator Circuit Breaker Factory Acceptance Test Report), Revision 0 SV4-ES03-VQQ-002, Westinghouse Quality Release and Certificate of Conformance QR 1969 (2 - Circuit Breaker, Main Generator, 60hz Electrical, 5 - Factory Acceptance Test Report),

Revision 0 Calculations:

APP-ECS-E0C-001, AC Electrical System Equipment Sizing, Revision 3.

APP-ZAS-E0C-001, AC Electrical System Load Flow, Short Circuit and Motor Starting Calculation, Revision 1 APP-ZAS-E0C-003, Generator Circuit Breaker and Isolated Phase Bus Duct Continuous and Short Circuit Current Ratings, Revision 4 Specifications:

APP-EB01-Z0-001, Isolated Phase Bus Duct and Associated Equipment, Revision 2 APP-EB01-Z0D-001, Isolated Phase Bus Duct and Associated Equipment Data Sheet, Revision 3

APP-ET01-Z0-001, Design Specification for Main Step-Up Transformers for ZAS, Revision 7 APP-ES03-Z0-001, Main Generator Circuit Breaker, Revision 2 APP-ET02-Z0-001, Design Specification for Three-Winding Unit Auxiliary Transformer (76 MVA; 26 KV:6.9KV; 60Hz), Revision 0 APP-ET03-Z0-001, Design Specification for Two-Winding Unit Auxiliary Transformer (33 MVA; 26 KV:6.9KV; 60Hz), Revision 5 Procedures:

DAPP 05-09, Preparation and Control of Manual and Computerized Calculations, Revision 9 ND-RA-001-008, ITAAC Principal Closure Document Review and Development, Version 8.

Section 1A49 Drawings:

SV4-ECS-E3-001, Vogtle Electrical Generating Plant AC Power System One Line Diagram, Revision 3 Miscellaneous:

ND-RA-001-008-F01, ITAAC Principal Closure Document Review Form, Version 9.0., dated 8/23/2019.

UFSAR VEGP 3 & 4, Chapter 8.2 Offsite Power System.

ND-RA-001-008, ITAAC Principal Closure Document Review and Development, Version 11.2, dated: 7/27/2018.

32

Reports:

C.2.6.12.06-U4-PCD-Rev0, Vogtle Unit 4 Turbine Trip Study Report for ITAAC C.2.6.12.06 (Index 676).

Procedures:

ND-RA-001-008, ITAAC Principal Closure Document Review and Development, Revision 11.2.

Section 1P01 APP-GW-GAP-420, "Engineering and Design Coordination Reports," Revision 18 APP-GW-GAP-428, "Nonconformance and Disposition Report," Revision 16 ND-AD-002, "Nuclear Development Program Corrective Action Program," Revision 29.0 ND-AD-002-025, "Issue Identification, Screening, and Dispatching," Revision 2.0 ND-AD-002-026, "Corrective Action Program Processing," Revision 2.0 ND-AD-002-027, "Nonconforming Items," Revision 4.0 Section 1P02 HII (Huntington Ingalls Industries Mechanical Inc., formerly Newport News Industrial Corporation)

NNI (Newport News Industrial Corporation)

Corrective Action Program Documents:

E&DCR APP-HA04-GEF-850016, "SB-AI/TR Weld Joint Alternatives," Revision 0 HII Letter 1902-0087, Notice of Potential Reportable Deficiency under 10 CFR 21, 2/15/19 HII Letter 1902-0088, Notice of Potential Reportable Deficiency under 10 CFR 21, 2/15/19 HII Letter 1902-0089, Notice of Potential Reportable Deficiency under 10 CFR 21, 2/15/19 HII Letter 1902-0090, Notice of Potential Reportable Deficiency under 10 CFR 21, 2/15/19 HII Letter 1902-0093, Notice of Potential Reportable Deficiency under 10 CFR 21, 2/25/19 HII Letter 1903-0101, Notice of Potential Reportable Deficiency under 10 CFR 21, 3/21/19 HII Letter 1903-0102, Notice of Potential Reportable Deficiency under 10 CFR 21, 3/21/19 HII Letter 1903-0103, Notice of Potential Reportable Deficiency under 10 CFR 21, 3/21/19 HII Letter 1903-0104, Notice of Potential Reportable Deficiency under 10 CFR 21, 3/21/19 HII Letter 1905-0133, Notice of Potential Reportable Deficiency under 10 CFR 21, 5/6/19 HII Letter 1905-0134, Notice of Potential Reportable Deficiency under 10 CFR 21, 5/6/19 HII Letter 1905-0136, Notice of Potential Reportable Deficiency under 10 CFR 21, 5/8/19 HII Letter 1905-0137, Notice of Potential Reportable Deficiency under 10 CFR 21, 5/8/19 SNC CR 50013812, Potential 21 issues with panels received from Huntington Ingalls Industries, 2/19/19 SNC CR 50016164, Potential Part 21 Notification from HII Industries, 3/22/19 SNC CR 50019624, Potential Part 21 Notification from HII Industries, 5/7/19 WECTEC Evaluation Identification No. 19-0016, HII U3 Lower SB 26 Panels & Embed Plate WPS, 4/15/19 WECTEC Evaluation Identification No. 19-0017, HII U4 SB Air Inlet 43 Panels WPS, 4/15/19 WECTEC Evaluation Identification No. 19-0018, HII U4 SB Air Inlet 43 Panels WPS, 4/15/19 WECTEC Evaluation Identification No. 19-0019, HII U4 SB Air Inlet 25 Panels WPS, 4/16/19 Westinghouse CAP-IR 2018-18309, Shield Building Tension Ring SV3-1278-SC-TR02, 10/29/18 Westinghouse CAP-IR 2019-3061, Vogtle Unit 3 Shield Building SC Panel Weld Procedure Specification, 2/15/19 Westinghouse CAP-IR 2019-3062, Vogtle Unit 4 Shield Building SC Panel Weld Procedure Specification, 2/15/19 33

Westinghouse CAP-IR 2019-3065, Vogtle Unit 3 Shield Building Air Inlet Panels Weld Procedure Specification, 2/15/19 Westinghouse CAP-IR 2019-3748, Vogtle Unit 3 Shield Building Tension Ring Panels - Incorrect Weld Procedure Specification, 4/10/19 Westinghouse CAP-IR 2019-5185, Vogtle Unit 3 Shield Building SC Panels - WPS Interpass Temperature, 4/10/19 Westinghouse CAP-IR 2019-5186, Vogtle Unit 4 Shield Building SC Panels - WPS Interpass Temperature, 4/10/19 Westinghouse CAP-IR 2019-5188, Vogtle Unit 3 Shield Building Air Inlet/Tension Ring Panels -

WPS Interpass Temperature, 4/10/19 Westinghouse CAP-IR 2019-5189, Vogtle Unit 4 Shield Building Air Inlet Panels - WPS Interpass Temperature, 4/10/19 Nonconformance & Disposition Reports:

APP-1278-GNR-850200, "HII Mechanical NCR 3778A-Delivered SV4-1278-SC-AI27: Wrong Stud Welding WPS used on Module," Revision 0 APP-1278-GNR-850201, "HII Mechanical NCR 3777A-DELIVERED SV3 MODULES - Wrong Stud Welding WPS Used," Revision 0 APP-1278-GNR-850205, "HII-Mech pre-production shot studs to incorrect plate thickness on Delivered panels for SV4," Revision 0 APP-1278-GNR-850206, "HII-Mech pre-production shot studs to incorrect plate thickness on Delivered panels SV3," Revision 0 SV3-1208-GNR-000121, "Vogtle Unit 3 - Shield Building SC Panels - HII - Incorrect WPS,"

Revision 0 SV3-1208-GNR-000122, "HII Mech. NCR 3905A Vogtle 3 welds performed utilizing incorrect WPS 1006 in lieu of WPS 1050," Revision 0 SV3-1208-GNR-000130, "Shield Bldg SV3 SC Panels - HII - WPS Interpass Temperature,"

Revision 0 SV3-1208-GNR-000132, "Shield Bldg SC Panels - HII Rebar Coupler Tensile Test not qualified to 1.25 x Fy," Revision 0 SV3-1278-GNR-000002, "HII Mechanical NCR 3902 A, Vogtle 3 (SV3), Air Inlet Groups, WPS 1072 in lieu of WPS 1084," Revision 0 SV3-1278-GNR-000003, "HII Mechanical NCR 3906 A, Vogtle 3 (SV3), AI & TR Groups, WPS 1006 in lieu of WPS 1050," Revision 0 SV3-1278-GNR-000004, "HII Mechanical NCR 3940 A, Vogtle 3, (SV3-1278-SC-TR09) WPS 1006 used in Overhead Position," Revision 0 SV3-1278-GNR-000007, "Unit 3 AI Vert 41/42 Peaking Inside (ESR#50017337),"

SV3-1278-GNR-000010, "Vogtle Unit 3 - HII Air Inlet Panels - Incorrect WPS Used in Production," Revision 0 SV3-1278-GNR-000011, "Vogtle Unit 3 - HII AI/TR Shield Bldg Panels - WPS Interpass Temperature," Revision 0 SV3-1278-GNR-000013, "Vogtle Unit 3 - HII Tension Ring Panels - Incorrect WPS Used in Production," Revision 0 SV4-1208-GNR-000036, "Vogtle Unit 4 - Shield Building SC Panels - HII - Incorrect WPS,"

Revision 0 SV4-1208-GNR-000037, "HII Mechanical NCR 3907A for WPS 1006 in lieu of WPS 1050,"

Revision 0 SV4-1208-GNR-000041, "HII Mechanical NCR 3963A, welds were performed utilizing the incorrect WPS 1050 in lieu of WPS 1006," Revision 0 SV4-1208-GNR-000042, "Indications for D2L Bars Course 09/10 (ESR#50016115)," Revision 0 34

SV4-1208-GNR-000048, "Shield Bldg SC Panels - HII Rebar Coupler Tensile Test not qualified to 1.25 x Fy," Revision 0 SV4-1208-GNR-000049, "HII MECHANICAL NCR 4077 A, Delivered SC Modules to SV4 with interpass temperature 100F Violation.," Revision 0 SV4-1278-GNR-000001, "HII Mechanical NCR 3903 A, Vogtle 4 (SV4), Air Inlet Groups, WPS 1072 in lieu of WPS 1084," Revision 0 SV4-1278-GNR-000005, "Vogtle Unit 4 - HII Air Inlet Shield Bldg Panels - WPS Interpass Temperature," Revision 0 Procedures:

APP-GW-GAP-428, "Nonconformance and Disposition Report," Revision 16 ND-AD-002, "Nuclear Development Program Corrective Action Program," Revision 29.1 ND-AD-002-025, "Issue Identification, Screening, and Dispatching," Revision 2.0 ND-AD-002-026, "Corrective Action Program Processing," Revision 2.0 ND-AD-002-027, "Nonconforming Items," Revision 5.0 SV3-1208-Z0-001, "Specification for the Fabrication and Field Erection of the SC Panels and the Conical Roof Steel Structure for the AP1000 Shield Building," Revision 2 SV3-CR01-Z0-010, "Specification for Supply and Installation of Mechanical Splices for Reinforcing Steel," Revision 6 SV4-1208-Z0-001, "Specification for the Fabrication and Field Erection of the SC Panels and the Conical Roof Steel Structure for the AP1000 Shield Building," Revision 2 SV4-CR01-Z0-010, "Specification for Supply and Installation of Mechanical Splices for Reinforcing Steel," Revision 6 Welding Documents:

NNI PQR 1155, "Flux Core Arc Weld-Gas," Revision A NNI PQR 1156, "Flux Core Wire," Revision A NNI PQR 1193, "GTAW/Manual (ASTM A108 Gr 1030 to ASTM A572 Gr 50)," Revision B NNI PQR 1194, "GTAW/Manual (ASTM A108 Gr 1030 to ASTM A572 Gr 50)," Revision B NNI WPS 1006, "FCAW / Semiautomatic," Revision 11 NNI WPS 1050, "FCAW / Semiautomatic," Revision 1 NNI WPS 1059, "GTAW/Manual ASTM A572-50 to Lenton Couplers P9J (1030)," Revision 9 NNI WPS 1060, "GTAW/Manual ASTM A572 Gr. 50 to Lenton Couplers P9J (1030)," Revision 7 NNI WPS 1072, "FCAW Semiautomatic," Revision 3 NNI WPS 1072, "FCAW Semiautomatic," Revision 5 NNI WPS 1084, "FCAW Semiautomatic," Revision 0 NNI WPS 1106, "FCAW / Semiautomatic," Revision 2 NNI WPS 1106, "FCAW / Semiautomatic," Revision 3 Section 1P03 CR 50013430, "Arching Between Battery Terminal Plates," 2/13/19 CR 50014740, "Recreating CR for NCR disposition-Arching between battery terminal Plates,"

3/1/19 CAR 8000349, "Arching Between Battery Terminal Plates," 2/27/2019 SV3-DB01-GNR-000001, "Arching Between Battery Terminal Plates During Installation ESR 50017209," Revision 0 ND-AD-002, "Nuclear Development Program Corrective Action Program," Revision 29.0 ND-AD-002-025, "Issue Identification, Screening, and Dispatching," Revision 1.1 ND-AD-002-026, "Corrective Action Program Processing," Revision 1.1 ND-AD-002-027, "Nonconforming Items," Revision 4.0 35

Section 1P04 ASME Code:

ASME NQA-1-1994, "Quality Assurance Requirements for Nuclear Facility Applications" Bechtel Procedures:

26139-000-4MP-T81C-N2102, "Housekeeping," Revision 3 26139-000-4MP-T81C-N7102, "Control of Measuring and Test Equipment," Revision 2 26139-000-4MP-T81C-N1601, "System Completion And Turnover," Revision 4 Condition Reports (CRs):

CR 50025529, "B-GEN-ITPA-003 does not reflect current ITP Organization," Dated July 30, 2019 CR 50025648, "Apparent Typo UFSAR Rev 8 Pg 1A-28," Dated July 31, 2019 CR 50025760, "B-GEN-ITPA-001 procedure enhancement," Dated August 1, 2019 Licensing Documents:

Vogtle Electric Plant Unit 3 & 4 Updated Final Safety Analysis Report (UFSAR), Chapter 5, "Reactor Coolant System and Connected Systems," Revision 7 Vogtle Electric Plant Unit 3 & 4 Updated Final Safety Analysis Report (UFSAR), Chapter 14, "Initial Test Program," Revision 8 Vogtle Electric Plant Unit 3 & 4 Updated Final Safety Analysis Report (UFSAR), Chapter 17, "Quality Assurance," Revision 4 SNC Procedures:

B-ADM-MNT-005, "Work Package Closure," Version 2.0 B-ADM-MNT-006, "Work Package Preparation," Version 4.0 B-ADM-PLMM-002, "General Plant Housekeeping and In-Process Materials Control," Version 0.3 B-ADM-WCO-001, "Operational Readiness Work Management," Version 6.0 B-GEN-ITPA-001, "ITP Administration and Organization," Version 7.0 B-GEN-ITPA-002, "Joint Test Working Group (JTWG)," Version 7.0 B-GEN-ITPA-003, "Initial Test Program Personnel Qualification & Training," Version 4.2 B-GEN-ITPA-004, "Conduct of Test," Version 11.0 B-GEN-ITPA-004-F01, "Test Narrative Log," Version 2.1 B-GEN-ITPA-004-F08, "Pre-Test System Walkdown Guide," Version 1.1 B-GEN-ITPA-004-F11, :Pre-Test Checklist," Version 2.1 B-GEN-ITPA-004-F12, "Post Test Checklist," Version 2.4 B-GEN-ITPA-007, "Jurisdictional Control," Version 2.1 B-GEN-ITPA-009, "ITP Configuration Control of Digital Information," Version 5.1 B-GEN-ITPA-010, "ITP Temporary Modifications," Version 9.0 B-GEN-ITPA-011, "ITP Administrative and Test Procedure Development," Version 7.0 B-GEN-ITPA-013, "Initial Test Program Troubleshooting," Version 3.1 B-GEN-ITPA-014, "Flushing and Initial Cleanness Verification," Version 4.1 B-GEN-ITPA-015, "Initial Test Program Temporary Operating Plans," Version 4.0 B-GEN-ITPA-017, "ITP Control System Interface Access Control," Version 4.0 B-GEN-ITPA-019, "Protection and Safety Monitoring System Initial Test Program Test Plan,"

Version 1.0 B-GEN-PLMC-076, "Chemistry Control for Flushing, System Cleanliness, and Wet Layup,"

Version 0.2 ND-AD-VNP-029, "Project Completion and Transition to Operations," Version 5.1 36

ND-DC-001, "Records Management," Version 21.0 NMP-AP-001-003, "Review and Approval of Site Procedures," Version 13.0 NMP-AP-002, "SNC Fleet Procedures Writers Guide," Version 8.1 NMP-AP-003, "Procedure and Work Instruction Use and Adherence," Version 6 NMP-AD-025, "Quality Assurance and Non-Quality Assurance Records Administration," Version 8.0 NMP-DP-001, "Operational Risk Awareness," Version 16.0 NMP-ES-006, "Preventive Maintenance Implementation and Continuing Equipment Reliability Improvement," Version 10.0 NMP-GM-005-002, "Human Performance Tools Instruction," Version 8.1, Dated January 2019 NMP-MA-009-001, "Foreign Material Exclusion Program Requirements," Version 10.0 NMP-MA-012, "Conduct of Maintenance," Version 10.0 NMP-MA-053, "SNC Maintenance Department Measuring and Test Equipment Program (M&TE)," Version 2.2 NMP-MA-054, "General Plant Housekeeping," Version 1.1 Nuclear Development Quality Assurance Manual," Version 19.0 3-RCS-ITPP-503, "Reactor Coolant System Cold Hydrostatic Test Preoperational Test Procedure," Version 2.0 3-PXS-ITPP-502, "PXS Accumulator Mapping and Line Resistance Test," Version 1.0 Westinghouse Procedures:

APP-GW-GEM-200, "AP1000 Chemistry Manual," Revision 5 Other:

B-GEN-ITPA-004-F01, "Test Narrative Log: WO# SNC919531" B-GEN-ITPA-004-F01, "Test Narrative Log: WO# SNC919491; 3-EDS3-DC-1" ESR 50018362 ESR 50017190 TDR001-1037433/TE50005486 TDR002-1037433/TE50006749 TDR003-1037433/TE50006780 TDR004-1037433/TE50006782

3. OPERATIONAL READINESS Section 3P01 Letter from the National Academy for Nuclear Training to Stephen E. Kuczynski, Southern Nuclear Operating Company, "Vogtle Electric Generating Plant Three and Four Final Accreditation Report," 5/1/18 Letter from the National Academy for Nuclear Training to Stephen E. Kuczynski, Southern Nuclear Operating Company, "Vogtle Electric Generating Plant Three and Four Final Accreditation Report," 7/24/19 Section 3P02 SV3-GW-GEI-100, "AP1000 Preservice Inspection Program Plan for Vogtle Unit 3", Revision 2 N&D SV3-RCS-GNR-000046, "Pre-service Inspection PT Indication - SV3-RCS-PLW-04B-SW9 (ESR 50016250)", Revision 0 N&D SV3-MV01-GNR-000013, "PCI Nonconformance NCR-913241-010", Revision 0 37

APP-GW-G1-014, "AP1000 Plant Nuclear Safety Classification and Seismic Requirement Methodology", Revision 9 APP-PXS-M3-001, "Passive Core Cooling System, System Specification Document", Revision 10 APP-RCS-M3-001, "Reactor Coolant System, System Specification Document", Revision 12 38

LIST OF ACRONYMS 10 CFR 50 Title 10, Code for Federal Regulations Part 50 AC Alternating Current ADS Automatic Depressurization System AI Air-inlet AISC American Institute of Steel Construction ANI Authorized Nuclear Inspector ANII Authorized Nuclear Inservice Inspector ANSI American National Standards Institute ASME American Society of Mechanical Engineers ASTM American Society for Testing and Materials AT&F American Tank & Fabrication AWS American Welding Society BOP Balance of Plant BPV Boiler and Pressure Vessel CAP Corrective Action Program CAPE Computer Aided Protection Engineering CB&I Chicago Bridge and Iron CCS Component Cooling Water System CMT Core Makeup Tank CMTR Certified Material Test Report CoC Certificate of Conformance COL Combined License CR Condition Report CVS Chemical and Volume Control System E&DCR Engineering and Design Coordination Report ECS Main AC Power System EPA Electrical Penetration Assemblies EQRR Equipment Qualification Reconciliation Report ESR Engineering Service Requests FCAW Flux-Cored Arc Welding FTT Fuel Transfer Tube GTAW Gas Tungsten Arc Welding HX Heat Exchanger IDS Uninterruptible Power Supply System IMC Inspection Manual Chapter IP Inspection Procedure IR Inspection Report IRWST In-containment Refueling Water Storage Tank ISI Inservice Inspection ITAAC Inspections, Test, Analyses, and Acceptance Criteria ITP Initial Test Program JTWG Joint Test Working Group LAR Licensing Amendment Request MOV Motor Operated Valve MT Magnetic Particle Testing N&D Nonconformance and Disposition NDE Nondestructive Evaluation 39

NI Nuclear Instrumentation NRC U.S. Nuclear Regulatory Commission OCS Operation and Control Centers System PCD Principal Closure Document PXS Passive Core Cooling System PJP Partial Joint Penetration PM Preventative Maintenance PQNM Project Nuclear Quality Control Manual PQR Procedure Qualification Records PRHR Passive Residual Heat Removal System PSI Preservice Inspection PT Liquid Penetrant Testing PXS Passive Core Cooling System QA Quality Assurance QAP Quality Assurance Program QAPD Quality Assurance Program Description QC Quality Control QOTTC Quick Opening Transfer Tube Closure RC/SC Reinforced Concrete/Steel Composite RCS Reactor Coolant System RCSC Research Council on Structural Connections RNS Normal Residual Heat Removal System S&W Stone and Webster SAW Submerged Arc Welding SC Steel Composite SCC Self-Consolidated Concrete SFS Spent Fuel Pit Cooling System SGS Steam Generator System SMAW Shielded Metal Arc Welding SSC Structures, Systems, and Components TSC Technical Support Center UFSAR Updated Final Safety Analysis Report UT Ultrasonic Testing VES Main Control Room Emergency Habitability System WDS Weld Data Sheet WEC Westinghouse Electric Company WMR Welding Material Requisitions WPS Weld Procedure Specification 40

ITAAC INSPECTED No. ITAAC No. Design Commitment Inspections, Tests, Acceptance Criteria Analysis 13 2.1.02.02a 2.a) The components Inspection will be The ASME Code identified in Table conducted of the Section III design 2.1.2-1 as ASME as-built components reports exist for the Code Section III are and piping as as-built components designed and documented in the and piping identified constructed in ASME design in Tables 2.1.21 and accordance with reports. Inspection 2.1.22 as ASME ASME Code Section of the as-built Code Section III. A III requirements. 2.b) pressure boundary report exists and The piping identified welds will be concludes that the in Table 2.1.2-2 as performed in ASME Code Section ASME Code Section accordance with the III requirements are III is designed and ASME Code met for non-constructed in Section III. A destructive accordance with hydrostatic test will examination of ASME Code Section be performed on pressure boundary III requirements. 3.a) the components welds. A report exists Pressure boundary and piping required and concludes that welds in components by the ASME Code the results of the identified in Table Section III to be hydrostatic test of the 2.1.21 as ASME hydrostatically components and Code Section III meet tested. Inspection piping identified in ASME Code Section will be performed Table 2.1.21 and III requirements. 3.b) for the existence of Table 2.1.22 as Pressure boundary a report verifying ASME Code Section welds in piping that the as-built III conform with the identified in Table piping meets the requirements of the 2.1.2-2 as ASME requirements for ASME Code Section Code Section III meet functional III. A report exists ASME Code Section capability. and concludes that III requirements. 4.a) Inspection will be each of the as-built The components performed for the lines identified in identified in Table existence of an LBB Table 2.1.2-2 for 2.1.2-1 as ASME evaluation report or which functional Code Section III retain an evaluation report capability is required their pressure on the protection meets the boundary integrity at from dynamic requirements for their design pressure. effects of a pipe functional capability.

4.b) The piping break. Section 3.3, An LBB evaluation identified in Table Nuclear Island report exists and 2.1.2-2 as ASME Buildings, contains concludes that the Code Section III the design LBB acceptance retains its pressure descriptions and criteria are met by the 41

boundary integrity at inspections, tests, as-built RCS piping its design pressure. analyses, and and piping materials, 5.b) Each of the lines acceptance criteria or a pipe break identified in Table for protection from evaluation report 2.1.2-2 for which the dynamic effects exists and concludes functional capability is of pipe rupture. that protection from required is designed the dynamic effects of to withstand combined a line break is normal and seismic provided.

design basis loads 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.

19 2.1.02.05a.i 5.a) 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 2.1.21 can withstand Category I 2.1.21 is located on seismic design basis equipment and the Nuclear Island. ii) loads without loss of valves identified in A report exists and safety function. 7.a) Table 2.1.2-1 are concludes that the The Class 1E located on the seismic Category I equipment identified Nuclear Island. ii) equipment can in Table 2.1.2-1 as Type tests, withstand seismic being qualified for a analyses, or a design basis loads harsh environment combination of type without loss of safety can withstand the tests and analyses function. iii) A report environmental of seismic Category exists and concludes conditions that would I equipment will be that the as-built exist before, during, performed. iii) equipment including and following a design Inspection will be anchorage is basis accident without performed for the seismically bounded loss of safety function existence of a by the tested or for the time required report verifying that analyzed conditions.

to perform the safety the as-built i) A report exists and function. equipment including concludes that the anchorage is Class 1E equipment seismically identified in Table bounded by the 2.1.2-1 as being tested or analyzed qualified for a harsh conditions. i) Type environment can tests, analyses, or a withstand the 42

combination of type environmental tests and analyses conditions that would will be performed exist before, during, on Class 1E and following a equipment located design basis accident in a harsh without loss of safety environment. ii) function for the time Inspection will be required to perform performed of the the safety function. ii) as-built Class 1E A report exists and equipment and the concludes that the as-associated wiring, built Class 1E cables, and equipment and the terminations located associated wiring, in a harsh cables, and environment. terminations identified in Table 2.1.21 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

36 2.1.02.08d.v 8.d) The RCS v) Inspections of v) The minimum provides automatic the elevation of the elevation of the depressurization ADS stage 4 valve bottom inside surface during design basis discharge will be of the outlet of these events. conducted. vi) valves is greater than Inspections of the plant elevation 110 ADS stage 4 valve feet. vi) The discharge will be discharge of the ADS conducted. viii) stage 4 valves is Inspection of the directed into the elevation of each steam generator ADS sparger will be compartments. viii) conducted. The centerline of the connection of the sparger arms to the sparger hub is < 11.5 feet below the IRWST overflow level.

72 2.1.03.03 3. The components Inspection will be The ASME Code identified in Table conducted of the Section III design 2.1.3-1 as ASME as-built components reports exist for the Code Section III are as documented in as-built components designed and the ASME design identified in Table constructed in reports. Inspection 2.1.3-1 as ASME accordance with of as-built pressure Code Section III. A ASME Code Section boundary welds will report exists and III requirements. 4. be performed in concludes that the Pressure boundary accordance with the ASME Code Section 43

welds in components ASME Code III requirements are identified in Table Section III. A met for non-2.1.3-1 as ASME hydrostatic test will destructive Code Section III meet be performed on examination of ASME Code Section the components of pressure boundary III requirements. 5. the RXS required welds. A report exists The pressure by the ASME Code and concludes that boundary components Section III to be the results of the (RV, CRDMs, and hydrostatically hydrostatic test of the incore instrument tested. 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.

91 2.2.01.02a 2.a) The components Inspection will be The ASME Code identified in Table conducted of the Section III design 2.2.1-1 as ASME as-built components reports exist for the Code Section III are and piping as as-built components designed and documented in the and piping identified constructed in ASME design in Table 2.2.1-1 and accordance with reports. Inspection 2.2.1-2 as ASME ASME Code Section of the as-built Code Section III. A III requirements. 2.b) pressure boundary report exists and The piping identified welds will be concludes that the in Table 2.2.1-2 as performed in ASME Code Section ASME Code Section accordance with the III requirements are III is designed and ASME Code met for constructed in Section III. i) A nondestructive accordance with hydrostatic or examination of ASME Code Section pressure test will be pressure boundary III requirements. 3.a) performed on the welds. i) A report Pressure boundary components exists and concludes welds in components required by the that the results of the identified in Table ASME Code pressure test of the 2.2.1-1 as ASME Section III to be components identified Code Section III meet tested. A in Table 2.2.1-1 as ASME Code Section hydrostatic or ASME Code Section III requirements. 3.b) pressure test will be III conform with the Pressure boundary performed on the requirements of the welds in piping piping required by ASME Code Section identified in Table the ASME Code III. A report exists 2.2.1-2 as ASME Section III to be and concludes that Code Section III meet pressure tested. 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 44

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.

98 2.2.01.05.i 5. 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 2.2.11 can withstand Category I 2.2.11 is located on seismic design basis equipment and the Nuclear Island. ii) loads without loss of valves identified in A report exists and structural integrity and Table 2.2.1-1 are concludes that the safety function. 6.a) located on the seismic Category I The Class 1E Nuclear Island. ii) equipment can equipment identified Type tests, withstand seismic in Table 2.2.1-1 as analyses, or a design basis dynamic being qualified for a combination of type loads without loss of harsh environment tests and analyses structural integrity and can withstand the of seismic Category safety function. iii) environmental I equipment will be The as-built conditions that would performed. iii) equipment including exist before, during, Inspection will be anchorage is and following a design performed for the seismically bounded basis accident without existence of a by the tested or loss of safety function report verifying that analyzed conditions.

for the time required the as-built i) A report exists and to perform the safety equipment including concludes that the function. 6.d) The anchorage is Class 1E equipment non-Class 1E seismically identified in Table electrical penetrations bounded by the 2.2.1-1 as being identified in Table tested or analyzed qualified for a harsh 2.2.1-1 as being conditions. i) Type environment can qualified for a harsh tests, analyses, or a withstand the environment can combination of type environmental withstand the tests and analyses conditions that would environmental will be performed exist before, during, conditions that would on Class 1E and following a exist before, during, equipment located design basis accident and following a design in a harsh without loss of safety basis accident without environment. ii) function for the time loss of containment Inspection will be required to perform pressure boundary performed of the the safety function. ii) integrity. as-built Class 1E A report exists and equipment and the concludes that the as-associated wiring, built Class 1E 45

cables, and equipment and the terminations located associated wiring, in a harsh cables, and environment. i) terminations identified Type tests, in Table 2.2.1-1 as analyses, or a being qualified for a combination of type harsh environment tests and analyses are bounded by type will be performed tests, analyses, or a on nonClass 1E combination of type electrical tests and analyses. i) penetrations A report exists and located in a harsh concludes that the environment. ii) non-Class 1E Inspection will be electrical penetrations performed of the identified in Table as-built non-Class 2.2.11 as being 1E electrical qualified for a harsh penetrations environment can located in a harsh withstand the environment. environmental conditions that would exist before, during, and following a design basis accident without loss of containment pressure boundary integrity. ii)

A report exists and concludes that the as-built non-Class 1E electrical penetrations identified in Table 2.2.1-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

159 2.2.03.02a 2.a) The components Inspection will be The ASME Code identified in Table conducted of the Section III design 2.2.3-1 as ASME as-built components reports exist for the Code Section III are and piping as asbuilt components designed and documented in the and piping identified constructed in ASME design in Table 2.2.31 and accordance with reports. Inspection 2.2.3-2 as ASME ASME Code Section of the as-built Code Section III. A III requirements. 2.b) pressure boundary report exists and The piping identified welds will be concludes that the in Table 2.2.3-2 as performed in ASME Code Section 46

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

4.b) The piping break. Section 3.3, An LBB evaluation identified in Table Nuclear Island report exists and 2.2.3-2 as ASME Buildings, contains concludes that the Code Section III the design LBB acceptance retains its pressure descriptions and criteria are met by the boundary integrity at inspections, tests, as-built RCS piping its design pressure. analyses, and and piping materials, 5.b) Each of the lines acceptance criteria or a pipe break identified in Table for protection from evaluation report 2.2.3-2 for which the dynamic effects exists and concludes functional capability is of pipe rupture. that protection from required is designed the dynamic effects of to withstand combined a line break is normal and seismic provided.

design basis loads 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 47

performed of the protection from the dynamic effects of a rupture of the line.

182 2.2.03.08c.iii 8.c) The PXS iii) Inspections of iii) These lines have provides RCS the routing of the no downward sloping makeup, boration, and following pipe lines sections between the safety injection during will be conducted: - connection to the design basis events. CMT inlet line, cold RCS and the high leg to high point - point of the line.

PRHR HX inlet line, hot leg to high point 184 2.2.03.08c.iv.02 8.c) The PXS iv) Inspections of iv) The maximum provides RCS the elevation of the elevation of the top makeup, boration, and following pipe lines inside surface of safety injection during will be conducted: these lines is less design basis events. 2. Containment than the elevation of:

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

equipment including anchorage is seismically bounded by the tested or analyzed conditions.

664 C.2.6.09.05a 5. Access control Tests, inspections, The access control points are established or combination of points for the to: a) control tests and protected area: a) personnel and vehicle inspections of are configured to 48

access into the installed systems control personnel and protected area. b) and equipment at vehicle access. b) detect firearms, the access control include detection explosives, and points to the equipment that is incendiary devices at protected area will capable of detecting the protected area be performed. firearms, incendiary personnel access Tests, inspections, devices, and points. or combination of explosives at the tests and protected area inspections of personnel access installed systems points.

and equipment at the access control points to the protected area will be performed.

668 C.2.6.09.08a 8.a) Penetrations Inspections will be Penetrations and through the protected performed of openings through the area barrier are penetrations protected area barrier secured and through the are secured and monitored. 8.b) protected area monitored.

Unattended openings barrier. Inspections Unattended openings (such as underground will be performed of (such as underground pathways) that unattended pathways) that intersect the protected openings that intersect the area boundary or vital intersect the protected area area boundary will be protected area boundary or vital area protected by a boundary or vital boundary are physical barrier and area boundary. protected by a monitored by intrusion physical barrier and detection equipment monitored by intrusion or provided detection equipment surveillance at a or provided frequency sufficient to surveillance at a detect exploitation. frequency sufficient to detect exploitation.

675 C.2.6.12.05 5. The fault current Analyses of the A report exists and contribution of each asbuilt offsite concludes the short offsite circuit is circuit will be circuit contribution of compatible with the performed to each asbuilt offsite interrupting capability evaluate the fault circuit at the interface of the onsite short current contribution with the onsite ac circuit interrupting of each offsite power system is devices. circuit at the compatible with the interface with the interrupting capability onsite ac power of the onsite fault system. current interrupting devices.

676 C.2.6.12.06 6. The reactor coolant Analyses of the A report exists and pumps continue to asbuilt offsite concludes that receive power from power system will voltage at the 49

either the main be performed to highside of the generator or the grid confirm that power generator stepup for a minimum of 3 will be available to transformer (GSU),

seconds following a the reactor coolant and the RATs, does turbine trip. pumps for a not drop more than minimum of 3 0.15 per unit (pu) seconds following a from the pretrip turbine trip when steadystate voltage the buses powering for a minimum of 3 the reactor coolant seconds following a pumps are aligned turbine trip when the to either the unit buses powering the auxiliary reactor coolant transformers pumps are aligned to (UATs) or the either the UATs or the reserve auxiliary RATs.

transformers (RATs).

678 2.7.01.02a 2.a) The components Inspection will be The ASME Code identified in Table conducted of the Section III design 2.7.1-1 as ASME as-built components reports exist for the Code Section III are and piping as as-built components designed and documented in the identified in Table constructed in ASME design 2.7.1-1 as ASME accordance with reports. Inspection Code Section III. A ASME Code Section of the as-built report exists and III requirements. 2.b) pressure boundary concludes that the The piping identified welds will be ASME Code Section in Table 2.7.1-2 as performed in III requirements are ASME Code Section accordance with the met for III is designed and ASME Code nondestructive constructed in Section III. A examination of accordance with pressure test will be pressure boundary ASME Code Section performed on the welds. A report exists III requirements. 3.a) components and and concludes that Pressure boundary piping required by the results of the welds in components the ASME Code pressure test of the identified in Table Section III to be components and 2.7.1-1 as ASME pressure tested. piping identified in Code Section III meet Tables 2.7.1-1 and ASME Code Section 2.7.1-2 as ASME III requirements. 3.b) Code Section III Pressure boundary conform with the welds in piping requirements of the identified in Table ASME Code Section 2.7.1-2 as ASME III.

Code Section III meet ASME Code Section III requirements. 4.a)

The components identified in Table 50

2.7.1-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.

4.b) The piping identified in Table 2.7.1-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.

760 3.3.00.02a.i.a 2.a) The nuclear i) An inspection of i.a) A report exists island structures, the nuclear island which reconciles including the critical structures will be deviations during sections listed in performed. construction and Table 3.3-7, are Deviations from the concludes that the as-seismic Category I design due to as- built containment and are designed and built conditions will internal structures, constructed to be analyzed for the including the critical withstand design design basis loads. sections, conform to basis loads as the approved design specified in the and will withstand the Design Description, design basis loads without loss of specified in the structural integrity and Design Description the safety-related without loss of functions. structural integrity or the safety-related functions.

761 3.3.00.02a.i.b 2.a) The nuclear i) An inspection of i.b) A report exists island structures, the nuclear island which reconciles including the critical structures will be deviations during sections listed in performed. construction and Table 3.3-7, are Deviations from the concludes that the as-seismic Category I design due to as- built shield building and are designed and built conditions will structures, including constructed to be analyzed for the the critical sections, withstand design design basis loads. conform to the basis loads as approved design and specified in the will withstand the Design Description, design basis loads without loss of specified in the structural integrity and Design Description the safety-related without loss of functions. structural integrity or the safety-related functions.

762 3.3.00.02a.i.c 2.a) The nuclear i) An inspection of i.c) A report exists island structures, the nuclear island which reconciles including the critical structures will be deviations during 51

sections listed in performed. construction and Table 3.3-7, are Deviations from the concludes that the as-seismic Category I design due to as- built structures in the and are designed and built conditions will non-radiologically constructed to be analyzed for the controlled area of the withstand design design basis loads. auxiliary building, basis loads as 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. Design Description without loss of structural integrity or the safety-related functions.

763 3.3.00.02a.i.d 2.a) The nuclear i) An inspection of i.d) A report exists island structures, the nuclear island which reconciles including the critical structures will be deviations during sections listed in performed. construction and Table 3.3-7, are Deviations from the concludes that the as-seismic Category I design due to as- built structures in the and are designed and built conditions will radiologically constructed to be analyzed for the controlled area of the withstand design design basis loads. auxiliary building, basis loads as 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. Design Description without loss of structural integrity or the safety-related functions.

766 3.3.00.02a.ii.c 2.a) The nuclear ii) An inspection of ii.c) A report exists island structures, the asbuilt that concludes that including the critical concrete thickness as-built concrete sections listed in will be performed. thicknesses of the Table 3.3-7, are non-radiologically seismic Category I controlled area of the and are designed and auxiliary building constructed to sections conform to withstand design the building sections basis loads as defined in Table 3.3-specified in the 1.

Design Description, without loss of structural integrity and 52

the safety-related functions.

767 3.3.00.02a.ii.d 2.a) The nuclear ii) An inspection of ii.d) A report exists island structures, the asbuilt that concludes that including the critical concrete thickness the as-built concrete sections listed in will be performed. thicknesses of the Table 3.3-7, are radiologically seismic Category I controlled area of the and are designed and auxiliary building constructed to sections conform to withstand design the building sections basis loads as defined in Table 3.3-specified in the 1.

Design Description, without loss of structural integrity and the safety-related functions.

790 3.3.00.07ab 7.a) Class 1E Inspections of the b) Class 1E electrical electrical cables, as-built Class 1E cables, and communication cables cables and the as- communication associated with only built raceways that cables associated one division, and route the Class 1E with only one division, raceways that route cables will be and the raceways that the Class 1E electrical conducted. route these cables in cables and the the non-radiologically communication cables controlled area of the are identified auxiliary building are according to identified by the applicable color- appropriate color coded Class 1E code.

divisions.

793 3.3.00.07bb 7.b) Class 1E Inspections of the b) Class 1E electrical divisional electrical as-built Class 1E cables and cables and divisional cables communication communication cables and the as-built cables in the non-associated with only raceways that route radiologically one division are the Class 1E cables controlled area of the routed in their will be conducted. auxiliary building respective divisional associated with only raceways. one division are routed in raceways assigned to the same division. There are no other safety division electrical cables in a raceway assigned to a different division.

819 3.3.00.13 13. Separation is An inspection of the The minimum provided between the separation of the horizontal clearance 53

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

structural steel columns and floor beams.

820 3.3.00.14 14. The external Type test, analysis, A report exists and walls, doors, ceiling, or a combination of concludes that the and floors in the main type test and external walls, doors, control room, the analysis will be ceilings, and floors in central alarm station, performed for the the main control and the secondary external walls, room, the central alarm station are doors, ceilings, and alarm station, and the bulletresistant to at floors in the main secondary alarm least Underwriters control room, the station are Laboratory Ballistic central alarm bulletresistant to at Standard 752, level 4. station, and the least Underwriters

15. Deleted secondary alarm Laboratory Ballistic station. Standard 752, level 4.

855 E.3.9.05.01.07 5.1 The licensee has 5.1 An inspection of 5.1.7 A reliable and established a the asbuilt TSC backup electrical technical support and OSC will be power supply is center (TSC) and an performed, available for the TSC.

onsite operations including a test of support center (OSC). the capabilities.

[H.1]

880 2.2.05.07e 7e) Shielding below Inspection will be A report exists and the VES filter is performed for the concludes that the as-capable of providing existence of a built shielding attenuation that is report verifying that identified in Table sufficient to ensure the as-built 2.2.5-1 meets the main control room shielding meets the functional doses are below an requirements for requirements and acceptable level functional exists below the during VES operation. capability. filtration unit, and within its vertical projection.

54