ML19045A614

NRC Integrated Inspection Reports 05200025/2018004, 05200026/2018004

ML19045A614
Person / Time
Site:	Vogtle
Issue date:	02/14/2019
From:	Jamie Heisserer NRC/RGN-II
To:	Yox M Southern Nuclear Operating Co
Geanette D
References
IR 2018004
Download: ML19045A614 (69)

Text

February 14, 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 05200025/2018004, 05200026/2018004

Dear Mr. Yox:

On December 31, 2018, 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 January 15, 2019 with Mr.

G. Chick, Senior Vice President Vogtle Units 3 & 4, 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 G. Khouri for/

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

Enclosure:

NRC Inspection Report (IR) 05200025/2018004, 05200026/2018004 w/attachment: Supplemental Information

M. Yox 3 cc:

Office of the Attorney General Resident Inspector 40 Capitol Square, SW Vogtle Plant Units 3 & 4 Atlanta, GA 30334 8805 River Road Waynesboro, GA 30830 Resident Manager Oglethorpe Power Corporation Mr. Barty Simonton Alvin W. Vogtle Nuclear Plant Team Leader 7821 River Road Environmental Radiation Program Waynesboro, GA 30830 Air Protection Branch Environmental Protection Division Southern Nuclear Operating Company, Inc. 4244 International Parkway, Suite 120 Document Control Coordinator Bin N-226-EC Atlanta, GA 30354-3906 3535 Colonnade Parkway Birmingham, AL 35243 George B. Taylor, Jr.

2100 East Exchange Pl Anne F. Appleby Atlanta, GA 30084-5336 Olgethorpe Power Corporation 2100 East Exchange Place Brian H. Whitley Tucker, GA 30084 3535 Colonnade Parkway, Bin N-226-EC 42 Inverness Center Parkway, BIN B237 County Commissioner Birmingham, AL 35243 Office of the County Commissioner Burke County Commission Mr. Michael Yox Waynesboro, GA 30830 Site Regulatory Affairs Director Vogtle Units 3 & 4 Mr. Wayne Guilfoyle 7825 River Road, Bin 63031 Commissioner District 8 Waynesboro, GA 30830 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)

ALPUGH@southernco.com (Amanda Pugh) 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) graysw@westinghouse.com (Scott W. Gray) jadwilli@southernco.com (J.D. Williams) james1.beard@ge.com (James Beard) jannina.blanco@pillsburylaw.com (Jannina Blanco) 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) jranalli@meagpower.org (Jerry Ranalli) karen.patterson@ttnus.com (Karen Patterson) karlg@att.net (Karl Gross) kmstacy@southernco.com (Kara Stacy)

KSutton@morganlewis.com (Kathryn M. Sutton) kwaugh@impact-net.org (Kenneth O. Waugh) lchandler@morganlewis.com (Lawrence J. Chandler) markus.popa@hq.doe.gov (Markus Popa)

M. Yox 5 Matthew.Williams@hq.doe.gov (Matthew Williams) mdmeier@southernco.com (Mike Meier) media@nei.org (Scott Peterson)

Melissa.Smith@Hq.Doe.Gov (Melissa Smith)

Michael.Kuca@hq.doe.gov (Michael Kuca) 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) patriciaL.campbell@ge.com (Patricia L. Campbell)

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

RJB@NEI.org (Russell Bell)

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) skauffman@mpr.com (Storm Kauffman) sroetger@psc.state.ga.us (Steve Roetger) stephan.moen@ge.com (Stephan Moen) 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) x2gabeck@southernco.com (Gary Becker) x2kmseib@southernco.com (Kristin Seibert

M. Yox 6 Letter to Michael Yox from Jamie Heisserer dated February 14, 2019.

SUBJECT:

VOGTLE ELECTRIC GENERATING PLANT, UNITS 3 AND 4 - NRC INTEGRATED INSPECTION REPORTS 05200025/2018004, 05200026/2018004 Distribution F. Brown, NRO V. Hall, NRO W. Jones, NRO S. Walker, RII R. Mathis, RII J. Heisserer, RII S. Rose, RII A. Artayet, RII G. Crespo, RII C. Even, RII B. Griman, RII D. Harmon, RII N. Karlovich, RII B. Kemker, RII G. Khouri, RII A. Lerch, RII J. Lizardi-Barreto, RII K. McCurry, RII T. Nazario, RII R. Patterson, RII A. Ponko, RII S. Smith, RII C. Taylor, RII S. Temple, RII J. Vasquez, RII PUBLIC ADAMS Accession No.: ML19045A614 OFFICE DRS DCO DCO DCO DCO DCO DCO SIGNATURE R. Patterson A. Ponko D. Harmon G. Khouri S. Smith J. Lizardi S. Temple DATE 2/7/2019 2/7/2019 2/11/2019 2/7/2019 2/8/2019 2/11/2019 2/13/2019 OFFICE DCO DCO DCO DCO DCO DCO SIGNATURE J. Vasquez N. Karlovich B. Griman A. Artayet B. Kemker J. Heisserer

/GKhouri for/ /GKhouri for/

DATE 2/7/2019 2/11/2019 2/7/2019 2/7/2019 2/14/2019 2/14/2019

U.S. NUCLEAR REGULATORY COMMISSION Region II Docket Numbers: 5200025 5200026 License Numbers: NPF-91 NPF-92 Report Numbers: 05200025/2018004 05200026/2018004 Licensee: Southern Nuclear Operating Company, Inc.

Facility: Vogtle Electric Generating Plant Unit 3 Vogtle Electric Generating Plant Unit 4 Location: Waynesboro, GA Inspection Dates: October 1, 2018 through December 31, 2018 Inspectors: A. Artayet, Senior Construction Inspector, DCO B. Griman, Construction Inspector, DCO D. Harmon, Construction Inspector, DCO N. Karlovich, Resident Inspector, DCO B. Kemker, Senior Resident Inspector, DCO G. Khouri, Senior Construction Inspector, DCO J. Lizardi-Barreto, Construction Inspector, DCO R. Patterson, Physical Security Inspector, DRS A. Ponko, Senior Construction Inspector, DCO S. Smith, Senior Construction Inspector, DCO S. Temple, Resident Inspector, DCO J. Vasquez, Construction Inspector, DCO Approved by: Jamie Heisserer, Branch Chief Construction Inspection Branch 1 Division of Construction Oversight Enclosure

SUMMARY

OF FINDINGS Inspection Report (IR) 05200025/2018004, 05200026/2018004; 10/01/2018 through 12/31/2018; Vogtle Electric Generating Plant Units 3 & 4 integrated inspection report.

This report covers a three month period of inspection by regional and resident inspectors, and announced Inspections, Tests, Analysis, and Acceptance Criteria (ITAAC) inspections by Regional inspectors. The NRCs program for overseeing the safe 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 During this report period in Unit 3 containment, pipe and components that make up the passive core cooling system (PXS) and reactor coolant system (RCS) continued to be installed.

Additional structural modules were installed in containment that make up the rooms inside containment. In the shield building, steel composite transition modules were installed, welded, and concrete place up to 189-6. In the auxiliary building, floors at 117-6 and walls from 117-6 to 135 continued to be constructed and floors at 135-3 began installation.

In Unit 4 containment, piping work for the PXS and RCS continued to be installed. Steam generator A was set in containment. In the shield building, work continued on the reinforced concrete portion. In the auxiliary building, work continued on floors at 100 and work continued on walls up to 117-6.

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 IPs/sections to perform this inspection:

• 65001.03-02.03 - Installation and Welding

• 65001.B-02.04-Production Controls

• 65001.B-02.05-Inspection The inspectors conducted an inspection of a weld between line PXS-L130A and the sparger A outlet nozzle. The inspectors observed manual gas tungsten arc welding (GTAW) and reviewed the weld data sheet (WDS) and welding material requisition (WMR) for field weld SV3-PXS-PLW-070-8 to determine whether welding activities were performed in accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC),Section III, 1998 Edition 2000 Addenda, Subsection ND, for Class 3 components. Specifically, the inspectors observed welding of an intermediate weld bead in the horizontal position to verify the amperage used was in accordance with WPS 1-8.8T01. In addition, the inspectors reviewed the WDS to verify inspection hold points during fit up for quality control (QC) and the authorized nuclear inspector (ANI) were signed-off for material identification markings, cleanliness, fit-up, and internal purge/backing gas in accordance with Section X of the licensee's quality assurance manual. Finally, the inspectors reviewed the WMR against the WDS entries to verify traceability of the welder and welding rods were controlled in accordance with the ASME Code,Section III, Subsection ND.

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b. Findings No findings were identified.

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

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

• 65001.03-02.01 - Purchase and Receipt of Materials

• 65001.03-02.03 - Installation and Welding

• 65001.03-02.06 - Nondestructive Examination (NDE)

• 65001.03-02.07 - Review of Records

• 65001.03-02.08 - Problem Identification and Resolution

• 65001.B-02.04-Production Controls

• 65001.F-02.02-Fabrication Records Review The inspectors conducted an inspection of the Unit 3 module Q601. This module consists of the ASME piping, valves and supports for the Reactor Coolant System (RCS) Automatic Depressurization System (ADS) stages 1, 2, and 3.

The inspectors performed this inspection to verify if module Q601 was fabricated in accordance with the ASME Code,Section III, 1998 Edition 2000 Addenda, Westinghouse (WEC) design and fabrication specifications, and Chapter 3 of the Updated Final Safety Analysis Report (UFSAR). Specifically, the inspectors reviewed fabrication records which included piping pressure boundary welds as well as support welds for the following piping spools and supports:

• SV3-RCS-PLW-012-1 (RCS-L006A),

• SV3-RCS-PLW-01E-1 (RCS-L021B),

• SV3-RCS-PLW-01E-2A (RCS-L023B),

• SV3-RCS-PLW-01E-2B (RCS-L022B),

• piping support SV3-RCS-PH-11R2104

• piping support SV3-RCS-PH-11R2103, and

• the Q601 module support structure.

The inspectors reviewed fabrication records for the following motor operated valves (MOVs):

• SV3-RCS-PL-V002B, and

• SV3-RCS-PL-V012B.

The inspectors reviewed fabrication records for these components to determine if the module had been fabricated per the ASME Code,Section III, Subsection NB, NC, ND (for piping and valves) and NF (for the supports). The inspectors reviewed the applicable code data reports to verify that data reports were signed by the ANI. In addition, the inspectors reviewed design and fabrication drawings to determine if they

5 met the requirements of the design and fabrication specifications. The inspectors also reviewed the code data reports, weld travelers, design and fabrication drawings to verify traceability of the fabrication records to the components and their associated welding procedures, welders, NDE reports, and nonconformance reports. The inspectors reviewed the records to determine if they were fully traceable and retrievable per the ASME Code and Criterion XVII of Title 10 of the Code of Federal Regulations (CFR), Part 50, Appendix B. The inspectors reviewed the weld NDE reports to determine if the welds had been examined by certified examiners, and were in accordance with the ASME Code, Sections III and V. The inspectors reviewed the weld filler metal certified material test reports (CMTRs) to determine if the weld filler for the selected welds had been manufactured, tested, and certified per the requirements of the ASME Code, Sections II and III. The inspectors reviewed CMTRs for various components including pipe sections to verify if the materials were properly heat treated and met the specified chemical, mechanical, and nondestructive testing requirements of the ASME Code, Sections II and III. The inspectors reviewed the radiograph film of two welds to verify they were free of rejectable defects and were of sufficient film quality.

The inspectors performed a walkdown of module Q601 to determine if the selected piping spools, valves, and supports were fabricated per the design drawings. The inspectors compared the design drawings to the as built condition to determine if the selected sample of components was of the correct size, length, and installed in the designed location and orientation with the appropriate physical markings and nameplate data. The inspectors observed the weld joint geometry for the piping and supports to verify if clearances between the restraints and piping were as specified in the design drawings. The inspectors also inspected how the module was being stored to determine if it met the storage requirements as specified in the design specifications, site procedures, the MOV vendor manual, and Section 13 of the Southern Nuclear Company (SNC) Quality Assurance Program (QAP).

The inspectors reviewed a sample of nonconformances, condition reports, nonconformance and disposition reports (N&Ds), and engineering and design coordination reports (E&DCRs) to verify if fabrication issues were captured, initiated, processed, reviewed, dispositioned, and closed per the procedure for the control of nonconforming material and parts. Additionally, the inspectors reviewed these documents to verify if they were dispositioned by engineering as required by the QAP.

b. Findings No findings were identified.

1A03 (Unit 3) ITAAC Number 2.1.03.03 (72) / Family 05F

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

• 65001.B-02.05-Inspection

• 65001.F-02.02-Fabrication Records Review

6 The inspectors reviewed a sample of NDE records for special applications on the reactor vessel and its appurtenances, as described in Section 5.3.2.3 of the Vogtle Units 3 & 4 UFSAR, to verify that NDE was conducted as described in the UFSAR and performed in accordance with the requirements of the ASME Code.

The inspectors reviewed two volumetric ultrasonic examination reports consisting of 26 welds. The inspectors reviewed full penetration ferritic pressure boundary welds in the reactor vessel to verify if ultrasonic test (UT) examinations were performed upon completion of the welding and intermediate heat treatment but prior to the final postweld heat treatment in accordance with Section 5.3.2.3.1 of the UFSAR. The inspectors also reviewed the full penetration ferritic pressure boundary welds in the reactor vessel to verify if the welds were ultrasonically examined after hydrotesting in accordance with Section 5.3.2.3.1 of the UFSAR. Also, the inspectors reviewed these reports to verify the use of calibration blocks, size of transducers, couplant, straight and angle beams, frequencies, amplitude linearity, and scanning sensitivity to determine whether the examinations were performed in accordance with the ASME Code,Section V, Article 5.

The inspectors reviewed 11 liquid penetrant test (PT) examination reports for the eight core support block attachment welds to verify if the welds were inspected by dye penetrant after the first layer of weld metal and after each 0.5 inch of weld metal in accordance with Section 5.3.2.3.2 of the UFSAR. The inspectors also reviewed the penetration time, developer bleed-out time, visible light source, and surface temperature requirements to verify the PT examinations were performed in accordance with the ASME Code,Section V, Article 6.

The inspectors reviewed two magnetic particle (MT) examination reports for the exterior vessel surface after hydrostatic pressure testing and inside diameter surfaces of carbon and low alloy steel products. The inspectors reviewed the reports to verify if MT examinations were conducted as described in Section 5.3.2.3.3 of the UFSAR. Also, the inspectors reviewed the reports to determine if the proper yoke lifting power, visible light source, and surface temperature were in accordance with the ASME Code,Section V, Article 7.

b. Findings No findings were identified.

1A04 (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

• 65001.03-02.06 - Nondestructive Examination (NDE)

• 65001.B-02.04-Production Controls

• 65001.B-02.05-Inspection

7 The inspectors conducted an inspection of a weld on line CCS-PL-L207, which joins containment vessel penetration nozzle P04A to 10" diameter carbon steel pipe.

Specifically, the inspectors observed manual GTAW and reviewed the WDS for field weld SV3-CCS-PLW-050-1 to determine whether welding and inspection activities were performed in accordance with the requirements of the ASME Code, Section III-NC. The inspectors observed welding of an intermediate weld pass in the vertical position to verify if the amperage used to melt the welding rods and sidewalls was in accordance with WPS 1-1.1C21. The inspectors reviewed the WDS to verify if QC and ANI hold points were signed-off for acceptance of material identification markings, internal cleanliness, fit-up, internal purge gas, and radiography in accordance with the licensee's quality assurance program. The inspectors observed the layout of the piping and fittings for orientation, squareness, levelness, flange two-hole alignment, and physical markings for material specifications, diameters, and thicknesses to verify installation was consistent with the construction isometric drawing SV3-CCS-PLW-050-R1.

The inspectors reviewed computerized RT to determine whether the technique and image brightness at the body of the required wire image quality indicators (IQI) location in the area of interest were in accordance with the requirements of MISTRAS radiography procedure 521-RT-302. Finally, the inspectors reviewed the computerized RT to the radiographic report to determine if the acceptance criteria and results were accurately recorded in accordance with the requirements of the ASME Code,Section III, Subsection NC-5320.

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

• 65001.03-02.06 - Nondestructive Examination (NDE)

• 65001.B-02.05-Inspection The inspectors conducted an inspection of a weld on line CCS-PL-L201, which joins containment vessel penetration nozzle P03 to a 10" diameter carbon steel pipe.

Specifically the inspectors reviewed the WDS for field weld SV3-CCS-PLW-040-1 to determine whether welding and inspection activities were performed in accordance with the requirements of the ASME Code, Section III-NC. The inspectors reviewed the WDS to verify applicable QC and ANI hold points were signed-off for acceptance of material identification markings, internal cleanliness, fit-up, internal purge gas, and radiography in accordance with the licensee's quality assurance program. The inspectors observed the layout of the piping orientation, levelness, and physical markings for material

8 specification, diameter, and thickness to verify installation was consistent with the construction isometric drawing SV3-CCS-PLW-040-R3.

The inspectors reviewed computerized RT for each shot on the weld to determine whether the technique and image brightness at the body of the required wire IQI location in the area of interest were in accordance with the requirements of MISTRAS radiography procedure 521-RT-302. Finally, the inspectors reviewed the computerized RT against the radiographic report to determine if the acceptance criteria and results were accurately recorded in accordance with the requirements of the ASME Code,Section III, Subsection NC-5320.

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.B-02.04-Production Controls The inspectors observed in-process welding activities associated with three containment vessel penetrations to verify if the following welds were in accordance with the ASME Code,Section III, Subsection NE. Specifically, the inspectors observed manual GTAW and reviewed weld records in the field for the following pressure retaining mechanical penetrations through the containment vessel:

• SV3-SFS-PY-C01, in-containment refueling water storage tank (IRWST)

Reference Cavity Purification Inlet (P21);

• SV3-SGS-PY-C01A, Main Steam Line Outlet (Loop 1) (P23); and

• SV3-SGS-PY-C02A, Main Feedwater Inlet (Loop 1) (P25).

The inspectors observed in-process welding of the above welds to verify if amperage was within the limits specified in the qualified welding procedure specifications. The inspectors reviewed the work packages to determine if the proper welding procedure, detail drawings and instructions, and weld data sheet were readily available at the work location. The inspectors reviewed weld data sheets to verify if the applicable QC and ANI hold point sign-offs for material identification, cleanliness, location, preheat, and fit-up were controlled in accordance with the requirements of the ASME Code,Section III, NCA-4000. The inspectors also reviewed the associated WMR in the work area against the WDS entries to verify if traceability of the welders and electrodes were controlled in accordance with the requirements of ASME Code, Subsection NE.

b. Findings No findings were identified.

9 1A07 (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.F-02.04-General QA Review The inspectors reviewed the receipt inspection records for the Unit 3 fuel transfer tube to verify if the receipt inspection was performed in accordance with quality inspection plan F-Q445-014.

b. Findings No findings were identified.

1A08 (Unit 3) ITAAC Number 2.2.03.02a (159) / Family 06F

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

• 65001.B-02.05-Inspection

• 65001.F-02.02-Fabrication Records Review The inspectors reviewed corrective action documents that were created as a result of NRC identified NCV 2018002-02, Failure to Meet Radiographic Film Requirements on PRHR HX. The CAP documents included the limited cause analysis and the plan for the expanded scope to review radiographic films. The WEC extent of condition review of radiographic films was associated with the fabrication records for the following ASME Class 1 components:

• Passive Residual Heat Removal Heat Exchanger (PRHR HX);

• Pressurizer (PZR);

• Core Make-up Tank (CMT A & B); and

• Accumulator (ACC A & B).

The inspectors reviewed the extent of condition to verify if the welds of the above components were scoped into the review. The inspectors reviewed a limited sample of NDE-RT to gain reasonable assurance that the extent of condition was adequate to address the previously identified deficiency. Specifically, the inspectors selected weld-nos. CW-033 and CW-035 for the PZR, and weld-no. CW-029/1 for the PRHR HX. For each weld, the inspectors reviewed the film package and associated NDE-RT report to verify that the film quality, density, and IQI sensitivity were in accordance with the requirements of the ASME Code,Section V.

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b. Findings No findings were identified.

1A09 (Unit 3) ITAAC Number 2.2.03.08c.iv.01 (183) / Family 03A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.03.08c.iv.01 (183). 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.02.02 - Installation Records Review

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

• 65001.A.02.04 - Review As-built Deviations/Nonconformance The inspectors observed licensee survey verification, performed independent evaluations, and reviewed records for the PXS DVI 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 observed the licensee perform surveying and reviewed survey records for the following pipe lines:

• SV3-PXS-PL-L112A/B,

• SV3-PXS-PL-L114,

• 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, and

• SV3-PXS-PL-L127A/B.

The inspectors observed surveying to determine whether 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 included the maximum elevations for each line in accordance with the acceptance criteria. The inspectors reviewed the training records for the individual who performed the surveys to verify the individual was 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 and analysis for the portions of pipe SV3PXS-PL-L112A that were buried in concrete to verify any deflection in the pipe due to the concrete pour was accounted for in accordance with the acceptance criteria. 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 reviewed a

11 nonconformance report associated with the reviewed records to verify the as-built field conditions aligned with the engineering disposition and was not material to the acceptance criteria of the ITAAC.

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 performed an independent walk-down of these pipe lines and the IRWST and 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 Combined License.

b. Findings No findings were identified.

1A10 (Unit 3) ITAAC Number 2.2.03.08c.iv.03 (185) / Family 03A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.03.08c.iv.03 (185). 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 the maximum elevation of the top inside surface of both Unit 3 core makeup tank (CMT) discharge lines to the direct vessel injection (DVI) connections are less than the elevation of each CMT bottom inside surface to satisfy the ITAAC requirement. The inspectors performed a walkdown of the two piping sections with the licensee and performed an independent assessment to verify the as-built piping elevations were consistent with the as-built elevation drawings. In addition, the inspectors reviewed quality records including the Principal Closure Document, survey results, and as-built elevation drawings to verify the elevation of the top inside surface of the piping remained below the bottom inside CMT surface as specified in Table 2.2.3-4 of Appendix C of the COL.

b. Findings No findings were identified.

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

• 65001.F-02.04-General QA Review The inspectors observed the licensee's in-process receipt inspection of the Division S battery to verify the inspection was performed, and nonconforming items were identified and released in accordance with the receipt inspection procedure.

The inspectors also observed the storage, handling, and installation of a sample of the safety-related DC uninterruptable power supply system (IDS) Division A, C, and S batteries for Unit 3 to verify the activities were in accordance with the procedures, installation specification, and battery design specification. The inspectors observed the installation of battery cell 100 for Division A, battery cells 113 to 116 for Division C, and battery cells 91 to 94 for Division S to verify they were installed in accordance with the wiring and location drawings, rigging and electrical equipment installation, the vendor manuals for the batteries and battery racks, and the electrical installation and battery specifications. For Division S, the inspectors inspected the grease used on the rails of the battery racks to determine whether the type of grease was in accordance with the battery vendor manual.

As part of the installation of the batteries, the inspectors observed the torqueing of bolts for the spacers, posts, and end pieces for cells 101-120 of Division A, cells 91-94 of Division S, and cells 113-116 of Division C to determine whether bolts were torqued by torque wrenches set to the correct value in accordance with the vendor manual and the electrical equipment installation procedure. The inspectors observed the torqueing of bolts for the spacers, posts, and end pieces for cells 101-120 of Division A to determine whether bolts were torqued in the presence of QC in accordance with the electrical equipment installation procedure. The inspectors observed the torqueing of bolts for the spacers, posts, and end pieces for cells 101-120 of Division A to determine whether QC was determining whether the torque wrenches were set to the correct value for torqueing in accordance with the electrical equipment QC instruction.

The inspectors reviewed the torque wrench M&TE to determine whether the individual torque wrench label showed the calibration was current in accordance with procedure MS 01.02, "Calibration Identification Labels, M&TE Identification Numbers, and Inventory," Revisions 1.01 and 1.02.

During the installation, the inspectors reviewed drawings available in the field to determine whether the batteries were in the location specified by the drawings. The inspectors reviewed the drawings in the field and compared them to drawings in the controlled database to determine whether the drawings were the latest revision available in accordance with procedure 26139-00-4MP-T81C-N1204, "Construction Implementation and Closing of Work Packages," Revisions 5 and 6.

13 The inspectors observed the cleaning of terminal posts of the Division A battery cells to determine whether it was performed in accordance with the battery vendor manual. The inspectors also reviewed the battery room conditions after installation to verify that conditions satisfied storage level B requirements.

b. Findings No findings were identified.

1A12 (Unit 3) ITAAC Number 3.3.00.02a.i.a (760) / Family 01F

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

• 65001.02-02.01 - Inspection of Concrete Placement

• 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 The inspectors performed inspection of construction activities associated with the installation of reinforcing steel for the Unit 3 containment operating deck section located above the IRWST at elevation 135'-3". The inspectors observed ongoing reinforcement installation activities, reviewed licensee records including calculations, design specifications, drawings, installation procedures, and E&DCRs.

The inspectors reviewed design drawings to verify the reinforcement's configuration met the requirements of concrete General Notes drawing SV3-0000-C9-001. In addition, the inspectors reviewed design changes and compared them to design calculations to verify approved design changes did not affect the reinforcement configuration in accordance with American Concrete Institute (ACI) 349-01. The inspectors performed in-field measurements of installed top and bottom layers of reinforcing steel to verify they were the right size, met spacing requirements, had minimum concrete clear cover, lap splices met the minimum length, and the floor had the required thickness in accordance with the design drawings.

The inspectors compared design drawings to the installed reinforcement bars in the floor to verify reinforcing steel was installed in accordance with the latest approved design changes and within the requirements of ACI 349-01. Also, the inspectors observed the installation of type 2 Lenton mechanical couplers and reviewed calibration records for torque wrench No. V-N-0096 to verify the installation was performed in accordance with procedure APP-CR01-Z0-010.

b. Findings No findings were identified.

14 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:

• 65001.01-02.01 - Procedures

• 65001.B-02.02-Welding Procedure Qualification

• 65001.B-02.03-Welder Qualification

• 65001.B-02.04-Production Controls

• 65001.F-02.03-Observation of Fabrication Activities The inspectors looked at various stages of construction for the shield building roof module to determine if welding fabrication was being performed in accordance with the requirements of the American Welding Society (AWS) D1.1:2000 for structural steel.

Specifically, inspectors observed the welding area for welding on a crossbeam to determine if the weld area was clean, free of contaminants, and protected from wind and moisture in accordance with the Chicago Bridge and Iron (CB&I) welding procedure. The inspectors reviewed the electrode that was used to verify if its use was in accordance with the CB&I welding procedure. The inspectors also observed welding for weld R17D on a crossbeam to verify if the welding techniques and direction were in accordance with the CB&I welding procedure.

In addition, the inspectors reviewed the traveler spread sheet to determine if fit-up and cleanliness inspection hold points were sequentially signed-off and traceability of weld filler material and welders was maintained in accordance with CB&I welding procedures. The inspectors also reviewed the welder's qualification records to determine if the welder was qualified in accordance with the AWS Code for that specific weld. The inspectors reviewed the WPS and supporting procedure qualification records to determine if it was written and qualified in accordance with the requirements of the AWS Code D1.1, Section 4. The inspectors reviewed the CMTR for the weld filler metal being used to determine if it met the requirements for chemical analysis and mechanical properties in accordance with AWS A5.5 Specification for Low-Alloy Steel Electrodes for Shielded Arc Metal Welding. At the completion of welding, the inspectors performed an independent visual inspection to determine if the weld was of the required size and contour, and free from defects such as cracks, lack of fusion, or excessive porosity.

Finally, the inspectors visually inspected the fit-up and tack portion of crossbeam weld R32D to determine if met the requirements of the detail drawing and procedure. The inspector observed the double-welded joint to determine if the fit-up, cleanliness, tack welds, and root opening were in accordance the requirements of the AWS D1.1 Code.

The inspectors reviewed the traveler spread sheet to determine if fit-up and cleanliness inspection hold points were sequentially signed-off, and traceability of weld filler material and welders were maintained in accordance with the CB&I welding procedures.

15

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:

• 65001.02-02.01 - Inspection of Concrete Placement

• 65001.02-02.02 - Laboratory Testing

• 65001.A.02.01 - Observation of in-Process Installation Activities The inspectors performed inspection of construction activities associated with the Unit 3 shield building between elevations 169'-6" and 189'-6". The inspectors observed in-process concrete placement activities, in-process concrete testing, reviewed calibration records, and reviewed quality control documents.

The inspectors reviewed concrete pour card No. 4504 to determine whether concrete mix design requirements were translated into quality assurance documents in accordance with design specification SV4-CC01-Z0-026. Also, during placement, the inspectors compared the pour card to the batch tickets to verify concrete delivered to the site had the appropriate concrete mix type. The inspectors reviewed the batch tickets during the concrete placement to verify transport time was completed within the time allowed by ACI 349-01 and the delivery was intended for the proper location in accordance with the pour card.

The inspectors observed concrete testing activities to determine if the processes for testing self-consolidated concrete met the requirements of specification SV4-CC01-Z0-027. The inspectors also observed testing of fresh concrete 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. The inspectors observed the sampling of eight concrete cylinders to be tested for compressive strength and evaluated field-sample storage conditions to verify the sampling and curing methods used by the licensee met the requirements of American Society of Testing and Materials (ASTM)

C31 and section 6.1.12 of specification SV4-CC01-Z0-027.

The inspectors observed concrete placement activities to determine whether placement for the safety related structure met requirements of specification SV4-CC01-Z0-031.

The inspectors also observed the use of concrete vibrators to verify they were inserted and withdrawn in a consistent pattern, inserted to penetrate at least 6 inches into the preceding layer before it began to set, and the concrete mix was placed through congested reinforcement to avoid segregation of the aggregate in accordance with Section 4.2.11 of specification SV4-CC01-Z0-031.

The inspectors reviewed calculation CALC-VMD-032 associated with the laboratory mix trials for safety related, self-consolidating concrete mixes. The inspectors reviewed the calculations in order to verify the self-consolidated concrete mixes were able to reach

16 the minimum bulk dry density requirement of 140 pounds per cubic foot as it was described in Section 12.3.2.2 of the UFSAR. The inspectors also reviewed the concrete test report to verify the mix met the 6,000 psi strength requirements for concrete mix Y in accordance with specification SV3-CC01-Z0-026, section 4.2.10.

b. Findings No findings were identified.

1A15 (Unit 3) 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 performed inspections of construction activities associated with the wall on column line 7.3, located between column line I and the shield building, and the wall on column line J, located between 7.3 and 9.2, between elevations 117'-6" and 135'-3" in the auxiliary building. The inspectors observed ongoing reinforcement installation, observed ongoing concrete placement activities, and reviewed licensee records including design drawings, specifications, E&DCRs, and N&Ds.

The inspectors performed independent measurements of installed reinforcement and embed plates. Specifically, the inspectors measured installed reinforcing steel to verify it was the right size, met spacing requirements, met minimum concrete clear cover, and lap splices met the minimum length in accordance with ACI 349-01. Also, the inspectors measured reinforcement around mechanical penetrations to verify the reinforcement configuration was installed in accordance with the latest approved design drawings. The inspectors independently measured reinforcement spacing in congested areas to verify reduced spacing between steel reinforcement met the requirements specified in Section 3.3.2 of ACI 349-01. The inspectors also evaluated the condition of embedments to verify they were secured in the structure, free of concrete or excessive rust, and had the proper clearances in accordance with General Notes drawing SV3-0000-C9-002A.

The inspectors observed reinforcement installation activities to verify they were performed using the latest-approved design changes, design drawings, and design specifications in accordance with ASME Nuclear Quality Assurance Program (NQA-1) 1994, Basic Requirement 3. The inspectors reviewed an N&D report to verify non-conforming items were dispositioned without changing the design basis in accordance with Section 4.6.4 of procedure APP-GW-GAP-428. The inspectors also observed the installation of mechanical couplers and reviewed calibration records of the torque wrench used for the installation to verify the couplers were installed in accordance with Section 12.14.3.6 of ACI 349-01.

17 The inspectors reviewed quality records and observed concrete placement activities associated with walls 7.3 and J. The inspectors reviewed concrete pour card 4419 to determine whether concrete mix design requirements were properly translated into quality assurance documents in accordance with design specification SV3-CC01-Z0-026. Also, during placement, the inspectors compared the pour card to the batch tickets to verify concrete delivered to the site had the appropriate concrete mix type. In addition, the inspectors reviewed the batch tickets to verify transport time was completed within the time allowed by ACI 349-01 and the delivery was intended for the proper location in accordance with the pour card. The inspectors observed concrete placement activities to determine whether placement drop distances met requirements specified in Section 4.2.4 of specification SV3-CC01-Z0-031. The inspectors also observed the use of concrete vibrators to verify they were handled and operated to ensure adequate consolidation of the mix, including vertical operation and penetration into the previous placed concrete layer, in accordance with Section 4.2.9 of specification SV3-CC01-Z0-031.

During the concrete placement, the inspectors observed in-process concrete testing to determine if concrete temperature, slump, and air content were determined at the mix delivery location as required by specification SV3-CC01-Z0-026 and ACI 349-01. The inspectors observed in-process concrete testing to verify the methods used were in accordance with specification SV3-CC01-Z0-027 and required ASTM standards. The inspectors observed the sampling of 12 concrete strength test cylinders to verify sample collection was performed in accordance with specification SV3-CC01-Z0-027 and ASTM C172.

b. Findings No findings were identified.

1A16 (Unit 3) 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

• 65001.A.02.03 - Independent Assessment/Measurement Inspection The inspectors performed an inspection of construction activities associated with the wall on column line K located between column line 11 and the shield building and from elevation 117'-6" to 135-3. The inspectors observed ongoing reinforcement installation, reviewed licensee records including design drawings, specifications, and E&DCRs.

The inspectors performed independent measurements of installed reinforcement and embedment plates. Specifically, the inspectors measured installed reinforcing steel to verify if the size, spacing requirements, minimum concrete clear cover, and lap splices were in accordance with Section 7.5 of ACI 349-01. Also, the inspectors measured the

18 reinforcement around mechanical penetrations to verify if the configuration was in accordance with the latest approved design drawings.

The inspectors independently measured reinforcement spacing in congested areas to verify if the spacing between steel reinforcements met Section 3.3.2 of ACI 349-01. The inspectors also measured the clear cover between permanent form plates and steel reinforcement to verify if they were secured and free of concrete or excessive rust in accordance design drawings and specification SV3-CC01-Z0-031.

The inspectors observed reinforcement installation activities to verify they were performed using the latest-approved design changes and design drawings. The inspectors also reviewed four E&DCRs to verify the design control process was implemented in accordance with APP-GW-GAP-420 and the reinforcement configuration of the wall reflected the approved changes described on the E&DCR's.

b. Findings No findings were identified.

1A17 (Unit 3) 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

• 65001.A.02.03 - Independent Assessment/Measurement Inspection The inspectors performed inspection of construction activities associated with the floor slab located between column lines K, L, 9.2 and the shield building at elevation 117'-6" in the Unit 3 auxiliary building. The inspectors observed ongoing reinforcement installation activities and reviewed licensee documents including design specifications, design drawings, and E&DCRs.

The inspectors performed independent measurements of installed top and bottom layers of reinforcing steel to verify the size, spacing, concrete clear cover, lap splice length, and the floor design thickness field configuration were in accordance with the design drawings and concrete General Notes SV3-0000-C9-001. The inspectors reviewed two E&DCRs to determine whether approved design changes were implemented into the field reinforcement configuration in accordance with design specification SV3-CC01-Z0-031. In addition, the inspectors compared the E&DCRs with design drawings to verify approved design changes were incorporated into final design documents in accordance with ACI 349-01.

The inspectors also observed the installation of mechanical couplers to verify the couplers were installed in accordance with procedure APP-CR01-Z0-010 and Section 12.14.3.6 of ACI 349-01. In addition, the inspectors reviewed calibration records of torque wrench No. V-N 0035 to verify the couplers were installed in accordance with Section 12 of the Bechtel Project Nuclear Quality Assurance Program.

19

b. Findings No findings were identified.

1A18 (Unit 3) 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

• 65001.A.02.03 - Independent Assessment/Measurement Inspection The inspectors performed inspections of construction activities associated with the wall on column line L located between column line 11 and the shield building and from elevation 117'-6" to 135-3 of the Unit 3 auxiliary building. The inspectors observed ongoing reinforcement installation, reviewed licensee records including design drawings, specifications, E&DCRs, and condition reports.

The inspectors performed independent measurements of installed reinforcement and embedment plates. Specifically, the inspectors measured installed reinforcing steel to verify the size, spacing, concrete clear cover, and lap splice length were in accordance with ACI 349-01. The inspectors also measured reinforcement around penetrations to verify the configuration was in accordance with the latest approved design drawings.

The inspectors independently measured rebar spacing in congested areas to verify reduced spacing between steel reinforcement met the requirements specified in Section 3.3.2 of ACI 349-01 and Section 3H.5 of the UFSAR. The inspectors also measured the clear cover between embedment plates and steel reinforcement to verify it met spacing requirements, reinforcement was secured, and it was free of concrete or excessive rust in accordance with General Notes Drawing SV3-0000-C9-002A.

The inspectors observed reinforcement installation activities to verify the activities were performed using the latest-approved design changes and design drawings in accordance with NQA-1 1994, Basic Requirement 3.

b. Findings No findings were identified.

1A19 (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:

20

• 65001.02-02.01 - Inspection of Concrete Placement

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

• 65001.A.02.03 - Independent Assessment/Measurement Inspection The inspectors performed inspections of construction activities associated with the Unit 3 auxiliary building wall on column line I between column lines 4 and 7 and the wall on column line 4.8 between I and the shield building and from elevation 117'-6" to 135-3.

The inspectors observed ongoing reinforcement installation, reviewed licensee records including design specifications, design drawings, calculations, E&DCRs, and N&D's.

The inspectors performed independent measurements of installed reinforcement and embedment plates. Specifically, the inspectors measured installed reinforcing steel to verify it was the right size, met spacing requirements, met minimum concrete clear cover, and lap splices met the minimum lengths in accordance with the design drawings and concrete General Notes SV3-0000-C9-001. The inspectors independently measured reinforcement spacing in congested areas to verify reduced spacing between steel reinforcement bars would not hinder concrete flow nor cause consolidation to be difficult to control during concrete placement as specified on SV3-CC01-Z0-031. Also, the inspectors measured reinforcement around door openings to verify the configuration was in accordance with ACI 349-01.

The inspectors also reviewed design calculations, design drawings, E&DCRs, and N&Ds to verify if the reinforcement configuration was translated into design drawings and steel reinforcement was installed in accordance with the latest approved design changes.

b. Findings No findings were identified.

1A20 (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:

• 65001.03-02.06 - Nondestructive Examination (NDE)

The inspectors observed in-process field activities and performed an independent assessment of the final liquid penetrant examination on the Unit 4 RCS surface of the hot leg RCS-L001B to the reactor vessel inlet nozzle weld SV4-RCS-PL01-FW-BHL01.

The inspectors also observed the final liquid penetrant examination on the Unit 4 RCS cold leg RCS-L002C to the east steam generator field weld SV4-RCS-PL01-FW-BCL04.

The inspectors observed the examinations performed in the field by PCI inspectors to determine if the requirements of procedure GQP 9.7 were adhered to, including surface

21 temperature of the weld, type of penetrant, solvent and developer used, and penetrant dwell time. The inspectors reviewed NDE-PT procedure GQP 9.7, to determine if the procedure met the requirements of ASME Section V, Article 6, and the acceptance criteria met the requirements in the ASME Code,Section III, Subsection NB-5350. The inspectors also performed an independent assessment of the test results to determine if the requirements of the ASME Code,Section III, Subsection NB-5350 were met.

The inspectors reviewed the final computerized radiography results for three stainless steel pipe field welds for the Unit 4 RCS loops to verify NDE-RT was performed in accordance with the requirements of MISTRAS procedure 521-RT-302. Specifically, the inspectors reviewed the following MISTRAS computed radiography examination reports to determine if the source type and size, source to object distance, object to image plate distance, geometric unsharpness, exposure time, and IQI used were in accordance with the procedure:

• NDE-RT report P-18-RT-302-0052 for Cold Leg - RCS - L002D weld-no. SV4-RCS-PL01-FW-BCL05;

• NDE-RT report P-18-RT-302-0053 for Cold Leg - RCS - L002C weld-no. SV4-RCS-PL01-FW-BCL03; and

• NDE-RT report P-18-RT-302-0055 for Hot Leg - RCS - L001B weld-no. SV4-RCS-PL01-FW-BHL02.

In addition, the inspectors reviewed computerized RT images of the welds to determine whether the technique and brightness at the body of the required wire image quality indicator locations in the area of interest were in accordance with the requirements of MISTRAS radiography procedure 521-RT-302 and ASME Code Section V, Article 2.

The inspectors reviewed the computer screen images to determine the acceptance criteria were in accordance with the requirements of the ASME Code,Section III, Subsection NB-5320, Radiographic Acceptance Standards.

Finally, the inspectors reviewed the radiography reports listed above to determine if the results were accurately recorded for acceptance by an American Society of Nondestructive Testing (ASNT-TC-1A) Level II or higher certified examiner in accordance with procedure 521-RT-302 and quality assurance program.

b. Findings No findings were identified.

1A21 (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:

• 65001.03-02.01 - Purchase and Receipt of Materials

• 65001.03-02.03 - Installation and Welding

• 65001.03-02.06 - Nondestructive Examination (NDE)

22

• 65001.03-02.07 - Review of Records

• 65001.03-02.08 - Problem Identification and Resolution

• 65001.B-02.04-Production Controls

• 65001.F-02.02-Fabrication Records Review The inspectors conducted an inspection of the Unit 4 module Q601. This module consists of the ASME piping, valves and supports for the RCS ADS stages 1, 2, and 3.

The inspectors performed this inspection to verify if module Q601 was fabricated in accordance with ASME BPVC,Section III, Westinghouse (WEC) design and fabrication specifications, and UFSAR Chapter 3. Specifically, the inspectors reviewed fabrication records, which included piping pressure boundary welds as well as support welds, for the following piping spools and supports:

• SV4-RCS-PLW-016-1A (RCS-L031A),

• SV4-RCS-PLW-016-1B (RCS-L032A),

• SV4-RCS-PLW-016-1C (RCS-L033A),

• SV4-RCS-PLW-01C-1 (RCS-L006B),

• piping support SV4-RCS-PH-11V0113,

• piping support SV4-RCS-PH-11Y0112,

• piping support SV4-RCS-PH-11R0076, and

• the Q601 module support structure.

The inspectors reviewed fabrication records for MOVs SV4-RCS-PL-V003A and SV4-RCS-PL-V013A.

The inspectors reviewed fabrication records for these components to determine if the module had been fabricated per ASME Code Section III, Subsection NB, NC, ND (for piping and valves) and NF (for the supports). The inspectors reviewed the applicable code data reports and design and fabrication drawings to verify that data reports were signed by the ANI and drawings met the requirements of the design and fabrication specifications. The inspectors also reviewed the code data reports, weld travelers, and design and fabrication drawings to verify if traceability of the fabrication records to the components and their associated welding procedures, welders, NDE reports, and nonconformance reports. The inspectors reviewed the records to determine if they were fully traceable and retrievable per the ASME Code and criterion XVII of 10 CFR Part 50 Appendix B. The inspectors reviewed the weld NDE reports to determine if the welds had been examined by certified examiners and met acceptance requirements in accordance ASME Code Sections III and V. The inspectors reviewed the weld filler metal CMTRs to determine if the weld filler for the selected welds had been manufactured, tested, and certified per the requirements of ASME Code Sections III and II. The inspectors reviewed CMTRs for various components including pipe sections to verify if the materials were properly heat treated and met the specified chemical, mechanical, and nondestructive testing requirements of ASME Section III and ASME Section II. The inspectors reviewed the radiograph film of two welds to verify they were free of rejectable defects and were of sufficient film quality.

The inspectors performed a walkdown of module Q601 to determine if the selected piping spools, valves, and supports were fabricated per the design drawings. The inspectors compared the design drawings to the as built condition to determine if the selected sample of components was of the correct size, length, and installed in the

23 designed location and orientation with the appropriate physical markings and nameplate data. The inspectors observed the weld joint geometry for the piping and supports to verify if clearances between the restraints and piping were as specified in the design drawings. The inspectors also inspected how the module was being stored to determine if it met the storage requirements as specified in the design specifications, site procedures, the MOV vendor manual, and Section 13 of the SNC QAP.

The inspectors reviewed a sample of nonconformances, condition reports, Nonconformance and Disposition Reports, and Engineering and Design Coordination Reports to verify if fabrication issues were captured, initiated, processed, reviewed, dispositioned, and closed per the procedure for the control of nonconforming material and parts. Additionally, the inspectors reviewed these documents to verify if they were dispositioned by engineering as required by the QA Program.

b. Findings No findings were identified.

1A22 (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.B-02.04-Production Controls

• 65001.B-02.05-Inspection The inspectors observed manual GTAW and reviewed the WDS and WMR for field weld-no. SV4-PXS-PLW-02E-11 joining a 10" diameter stainless pipe and tee fitting for line-no. PXS-PL-L120 (IRWST to DVI-B) to determine whether welding activities were in accordance with ASME Code Section III-ND. Specifically, the inspectors observed the weld joint open root spacing to verify compliance with WPS 1-8.8T01 referenced in the WDS. The inspectors also observed the butt joint alignment, and internal tack welds with a partial root pass through the root openings for complete penetration against the bevel edges of the pipe and fitting to verify compliance with the requirement of ND-4200 and ND-4400, respectively. In addition, the inspectors reviewed the S&W WDS to verify the following QC inspection hold points were signed-off:

• material identification markings;

• internal and weld area cleanliness;

• bevel end-preparation and fit-up; and

• internal purge/backing gas.

Finally, the inspectors reviewed WMR 405688 against the WDS entries to verify if traceability of the welder and welding rods were controlled in compliance with ASME III-ND.

24

b. Findings No findings were identified.

1A23 (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.B-02.05-Inspection

• 65001.F-02.02-Fabrication Records Review The inspectors reviewed corrective action documents that were created as a result of NRC identified NCV 2018002-02, Failure to Meet Radiographic Film Requirements on PRHR HX. The CAP documents included the limited cause analysis and the plan for the expanded scope to review radiographic films. The WEC extent of condition review of radiographic films was associated with the fabrication records for the following ASME Class 1 components:

• PRHR HX;

• PZR;

• CMT A & B; and

• ACC A & B.

The inspectors reviewed the extent of condition to verify if the welds of the above components were scoped into the review. The inspectors reviewed a limited sample of NDE-RT to gain reasonable assurance that the extent of condition was adequate to address the previously identified deficiency. Specifically, the inspectors selected weld-nos. CW-033 and CW-035 for the PZR and weld-no. CW-029/1 for the PRHR HX. For each weld, the inspectors reviewed the film package and associated NDE-RT report to verify that the film quality, density, and IQI sensitivity were in accordance with the requirements of the ASME Code,Section V.

b. Findings No findings were identified.

1A24 (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.F-02.02-Fabrication Records Review

25 The inspectors reviewed the quality assurance data package for accumulator A discharge isolation valve PXS-PL-V027A to determine if the pressure boundary aspects of the valve were manufactured in accordance with the ASME Code,Section III, Subsection ND. The inspectors reviewed the CMTR to determine if the materials used for the valve body met the chemical requirements of the ASME Code,Section II, SA351. The inspectors also reviewed the liquid penetrant and radiography reports to determine if the valve body casting had been inspected and found acceptable per the ASME Code,Section III.

b. Findings No findings were identified.

1A25 (Unit 4) ITAAC Number 2.2.03.08c.iv.01 (183) / Family 03A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.03.08c.iv.01 (183). The inspectors used the following NRC IPs/sections to perform this inspection:

• 65001.A.02.03 - Independent Assessment/Measurement Inspection The inspectors performed independent inspections for the PXS DVI lines SV4-PXS-PL-L112A and SV4-PXS-PL-L112B and the IRWST. The inspectors performed an independent walk-down of the IRWST and these pipe lines prior to concrete placement 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 also performed a walk down after concrete was placed to verify the pipe lines did not shift during the concrete placement.

b. Findings No findings were identified.

1A26 (Unit 4) ITAAC Number 2.5.02.11 (550) / Family 10F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.5.02.11 (550). The inspectors used the following NRC IPs/sections to perform this inspection:

• 35007-A13.04.02 - Inspection of QA Program Implementation

• 65001.10-02.02 - Inspection Activities

• 65001.F-02.04-General QA Review The inspectors observed the receipt surveillance of selected Unit 4 PMS cabinets. The inspectors observed the licensee's compliance monitoring program (CMP) to determine if it was in accordance with the surveillance checklist. The inspectors reviewed the

26 qualification records of the CMP representative to verify were qualified in accordance with ND-CA-VNP-021.

The inspectors observed the handling and placement of the PMS cabinets in the warehouse to verify they were handled with no damage to the shipping containers and stored in accordance with the requirements of specification APP-PMS-J0M-003. The sampled cabinets were:

• SV4-PMS-JD-BCCA01, BPL/LCL Cabinet A01

• SV4-PMS-JD-BCCC01, BPL/LCL Cabinet C01

• SV4-PMS-JD-SOEA01, Sequence of Events Cabinet A

• SV4-PMS-JD-QDPB01, QDPS Cabinet Division B

• SV4-PMS-JD-SOEC01, Sequence of Events Cabinet C

• SV4-PMS-JD-BCCC02, BPL/LCL Cabinet C02

• SV4-PMS-JD-BCCD01, BPL/LCL Cabinet D01 The inspectors walked down the warehouse to verify the PMS cabinets were being stored in accordance with the cabinet specification, the onsite storage procedure, and ASME NQA-1 1994, Part II, Subpart 2.2. The inspectors reviewed temperature and humidity records for storage of the cabinets from August 9, 2018 through November 27, 2018 to determine whether the temperature and humidity were within the range specified by specification APP-PMS-J0M-003 and ASME NQA-1 1994, Part II, Subpart 2.2. The inspectors inspected the temperature and humidity data logger to determine whether it was in an appropriate location and whether it had a sticker that indicated it was calibrated.

b. Findings No findings were identified.

1A27 (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.A- As-Built Attributes for SSCs associated with ITAAC

• 65001.A.02.02 - Installation Records Review The inspectors observed in-process concrete placement activities, observed in-process concrete testing, reviewed calibration records, and reviewed quality control documents associated with the containment internal structures for Vogtle Unit 3. This included the following wall and floor sections:

• South, West, North, and East walls of West Steam Generator Compartment from el. 103'-0" to 153'-0";

• South wall of Pressurizer Compartment from el. 103'-0" to 153'-6";

• West and North wall of Pressurizer Compartment from el. 107-2 to 160-0;

27

• East wall of Pressurizer Compartment from el. 118'-6" to 160'-0"; and

• below the In-Containment Refueling Water Storage Tank floor up to el. 102'-11".

The inspectors reviewed concrete pour card No. 4150 to determine whether concrete mix design requirements were properly translated into quality assurance documents in accordance with design specification SV4-CC01-Z0-026. Also, during placement, the inspectors compared the pour card to the batch tickets to verify concrete delivered to the site had the appropriate concrete mix type.

The inspectors reviewed the batch tickets during the concrete placement to verify transport time was completed within the time allowed by ACI 349-01 and the delivery was intended for the proper location in accordance with the pour card. The inspectors observed concrete testing activities to determine if the processes for testing self-consolidated concrete met the requirements of specification SV4-CC01-Z0-027. The inspectors observed testing of fresh concrete 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.

The inspectors observed the sampling of 48 concrete cylinders to be tested for compressive strength, evaluated field-samples storage conditions, and reviewed field curing logs to verify the sampling and curing methods used by the licensee met the requirements of ASTM C31 and section 6.1.12 of specification SV4-CC01-Z0-027.

The inspectors observed concrete placement activities to determine whether placement for safety related components met requirements of specification SV4-CC01-Z0-031.

The inspectors also observed the use of concrete vibrators to verify they were inserted and withdrawn in a consistent pattern, inserted to penetrate at least 6 inches into the preceding layer before it began to set, and the duration of each insertion was sufficient to ensure adequate consolidation of the mix in accordance with Section 4.2.9 of specification SV4-CC01-Z0-031.

The inspectors also reviewed the concrete mix density report to verify the concrete mix used met the minimum dry density requirements of 140 pounds per cubic foot as specified in Section 12.3.2.3 of the UFSAR.

b. Findings No findings were identified.

1A28 (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.A.02.01 - Observation of in-Process Installation Activities

• 65001.A.02.02 - Installation Records Review

28 The inspectors performed concrete placement inspection associated with Unit 3 structural module CA02, which is part of the northeast boundary of the in-containment refueling water storage tank from elevation 103'-0" to 135'-3". The inspectors reviewed licensee documents and observed in-process testing and concrete placement inside the structural module.

The inspectors reviewed the approved concrete pour card to determine if concrete mix design requirements were properly translated in accordance with design specification SV4-CC01-Z0-026. During placement, the inspectors compared the pour placement card against a batch ticket to verify concrete delivered to the site had the proper concrete-mix type. In addition, the inspectors verified transport time was completed within the time allowed by ACI 349-01 and the delivery was intended for the proper location in accordance with the pour card.

During the concrete placement, the inspectors observed in-process concrete testing to determine if concrete temperature, slump size, unit weight, and air content were determined at the mix delivery location as required by the pour card, specification SV4-CC01-Z0-026, and ACI 349-01. The inspectors also observed the sampling of 12 concrete strength test cylinders to verify sample collection and testing techniques were performed in accordance with specification SV4-CC01-Z0-027 and ASTM C172.

The inspectors observed concrete placed at module wall CA02 to determine if the placement did not result in mix segregation and placement-drop distances met requirements specified in SV4-CC01-Z0-031. The inspectors also observed the use of concrete vibrators to verify they were handled and operated to ensure adequate consolidation of the mix, including vertical operation and penetration into the previous placed concrete layer in accordance with design specifications. The inspectors verified quality control inspections during placement were performed by the licensee as required by specification SV4-CC01-Z0-031.

b. Findings No findings were identified.

1A29 (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 performed inspection of construction activities associated with the Unit 4 wall on column line K between column lines 7.3 and 11 and from elevation 100'-0" to 117-6. The inspectors observed in-process concrete placement activities, in-process concrete testing, and reviewed quality control documents.

29 The inspectors reviewed concrete pour card No. 4399 to determine whether concrete mix design requirements were properly translated into quality records in accordance with design specification SV4-CC01-Z0-026. Also, during placement, the inspectors compared the pour card to the batch tickets to verify concrete delivered to the site had the appropriate concrete mix type.

The inspectors reviewed the batch tickets during the concrete placement to verify transport time was completed within the time allowed by ACI 349-01 and the delivery was intended for the proper location in accordance with the pour card. The inspectors observed concrete testing activities to determine if the processes for testing self-consolidated concrete met the requirements of specification SV4-CC01-Z0-027. The inspectors observed testing of fresh concrete 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.

The inspectors observed the sampling of 24 concrete cylinders to be tested for compressive strength and evaluated field-samples storage conditions to verify the sampling and curing methods used by the licensee met the requirements of ASTM C31 and Section 6.1.12 of specification SV4-CC01-Z0-027.

b. Findings No findings were identified.

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

• 35007-A16.04.02 - 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 ensure the CAP appropriately included regulatory required non-safety related SSCs. The inspectors periodically attended the licensee's corrective action program 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 issues were appropriately classified in accordance with the licensee's quality assurance program and CAP implementing procedures. The inspectors reviewed corrective actions associated with conditions entered into the CAP to determine whether appropriate actions to correct the issues were identified and implemented effectively, including immediate or short-term corrective actions, in accordance with the licensee's quality assurance program requirements and 10 CFR 50, Appendix B, Criterion XVI.

30 Additionally, the inspectors reviewed 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 all 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 the 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

a. Inspection Scope The inspectors selected one issue that was entered into the licensee's CAP for additional follow-up inspection. The inspectors reviewed condition report 50005649 and technical evaluation 50005739, which identified the need for revisions to several Unit 3 operating procedures. The operating procedures address instrument channel failures in the protection and safety monitoring system. The inspectors reviewed the licensee's evaluation and corrective actions to verify the following attributes were in accordance with the licensee's corrective action program implementing procedures:

• complete and accurate 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 safety significance; The inspectors discussed the condition report, evaluation, and corrective actions with licensee personnel to determine whether they were aware of different thresholds for classification and had considered the extent of condition in accordance with procedures ND-AD-002 and ND-AD-002-025.

b. Findings No findings were identified.

2. SAFEGUARDS PROGRAMS Cornerstones: Security Programs for Construction Inspection and Operations IMC 2504, Construction Inspection Program - Inspection of Construction and Operational Programs 2P01 Fitness for Duty - Construction

31

a. Inspection Scope This input is security related. See non-public report 05200025/2018413 for details.

b. Findings No findings were identified.

4. OTHER INSPECTION RESULTS 4OA3 Follow-up of Licensee Reports and NOVs

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

a. Inspection Scope The inspectors performed a review of the licensee's corrective actions associated with Non-Cited Violation (NCV)05200025/2015002-002, Spent Fuel Pool Wall Repair without an Approved Procedure, identified in IR 05200025/2015002 (ML15223B074).

The review was to determine whether the corrective actions taken by the licensee were complete and sufficient to address the issue and ensure the acceptance criteria for the related ITAAC could be met. Specifically, this violation was associated with the licensee's failure, through their contractor CB&I, to perform repair activities (i.e. an activity affecting quality) on a seismic category I structural module according to an approved engineering disposition or procedure. The violation represented an ITAAC finding because it was material to the acceptance criteria of Unit 3 ITAAC 3.3.00.02a.i.d (763), in that, if left uncorrected, the licensee would not have been able to show that the acceptance criteria of this ITAAC was met.

The inspectors reviewed SNC CR 10062982, CB&I CAR 2015-1585, and associated corrective actions taken to address this issue. The inspectors also reviewed the apparent cause evaluation which was completed to determine the apparent and contributing causes of the nonconformance. The inspectors concluded that issue was appropriately described in the corrective action documents listed above and that the corrective actions were appropriate. These corrective actions included briefing field engineering disciplines on the appropriate use of the Request for Information (RFI) and Nonconformance and Disposition reports.

The inspectors also reviewed N&D SV3-CA20-GNR-000680, "Volume for Fuel Transfer and Spent Fuel Pool," and N&D SV3-CA20-GNR-000887, "North Wall Repair Spent Fuel Pool Supplemental Information," to determine whether appropriate action was taken to address the nonconforming condition. Based on the information provided, the inspectors concluded that the nonconforming condition was addressed to the extent that the as-built construction did not conflict with regulatory requirements. This review supplemented an earlier inspection that was documented in IR 05200025/2016002 (ML16210A448). During this previous inspection, NRC inspectors observed in-process construction activities associated with the repair of the north wall of the spent fuel pool between elevations 92'-8-1/2" and 135'-3" to determine whether repair activities were being conducted in accordance with applicable codes and standards, including AISC N690-94, AWS D1.1:2000, AWS D1.6:1999, and UFSAR welding requirements.

32 Additionally, the inspectors reviewed N&D SV3-CA20-GNR-000680 and associated structural analysis prepared by Structural Integrity Associates, Inc. to verify that the non-conforming condition and repair activities were appropriately evaluated, approved, and dispositioned in accordance with applicable technical and QA requirements.

Based on the reviews described above, the inspectors determined the licensee took adequate corrective actions to address this violation and the nonconforming condition had been appropriately addressed such that the acceptance criteria of Unit 3 ITAAC 3.3.00.02a.i.d (763) was no longer impacted. No additional findings were identified.

NCV 05200025/2015002-002 is closed.

b. Findings No findings were identified.

4OA5 Other Activities

.1 Review of National Academy for Nuclear Training Operations Training Assessment Report The inspectors reviewed the National Academy for Nuclear Training Operations Training Assessment Report of Vogtle 3&4 operations training programs dated April 19, 2018.

During this review, the inspectors did not identify any new significant training issues.

4OA6 Meetings, Including Exit Exit Meeting.

On January 15, 2019, the inspectors presented the inspection results to Mr. G. Chick, Senior Vice President Vogtle 3 & 4, and other licensee and contractor staff members.

Proprietary information was reviewed during the inspection period, but was not included in the inspection report.

SUPPLEMENTAL INFORMATION KEY POINTS OF CONTACT Licensees and Contractor Personnel R. Calia, WECTEC Performance Improvement Senior Manager C. Castell, SNC Licensing Engineer D. Gardner, SNC Licensing Lead L. Grissom, SNC Licensing Engineer W. Lynn, SNC ITAAC Supervisor M. Newberry, Bechtel, Subcontract Technical Representative A. Pugh, SNC Licensing Manager D. Reddick, Bechtel Area Manager G. Scott, SNC Licensing Engineer K. Stacy, SNC Licensing Supervisor M. Koblansky, WEC ASME Section III Modules Mechanical Lead LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED Item Number Type Status Description 05200025/2015002-002 NCV Closed Spent Fuel Pool Wall Repair without an Approved Procedure (Section 4OA3)

LIST OF DOCUMENTS REVIEWED Section 1A01 Southern Nuclear Development Quality Assurance Manual, Revision 17 WEC Construction Isometric Drawing SV3-PXS-PLW-070-R0, "Passive Core Cooling System Containment Building Room 11305 ADS Piping to Sparger A", Rev. 0 Stone and Webster (S&W) Weld Data Sheet (WDS) SV3-PXS-PLW-070-8 for work package SV3-PXS-P0W-800032, 4-2-18 S&W Welding Material Requisition (WMR) 405686 for welders CSK 8128 and NAH 1357, and GTAW rods for 3/32" and 1/8" dia. with heat-nos. 1030C and 1243V, respectively, 9/24/18 Section 1A02 Specifications APP-GW-P0-008, AP1000 Specification for Field Fabricated Piping and Installation, ASME III, Code Classes 1, 2, and 3 and ASME B31.1 Rev. 7 APP-PL02-Z0-101, AP1000 Class 1 Piping and Non-Class 1 Extensions Design Specification, Rev. 4 APP-PV01-Z0-001, 3 AND Larger Motor Operated Gate and Globe Valves, ASME Boiler and Pressure Vessel Code Section III, Class 1, 2, and 3, Rev. 9 APP-Q601-Z0-001, Design Specification for AP1000 Piping Module 1102-Q6-01, Rev. 1 APP-GW-P0-008-ADD-02, Supplemental QA Requirements for the Pressurizer Upper Lateral Support Assembly (PRZUL)-Ring Girder and ASME III Mechanical Modules KB36, Q223, Q233, Q240, Q305, and Q601 Rev. 9 APP-GW-P0-007, AP1000 Specification for Shop Fabricated Piping Rev. 8 Attachment

2 APP-PL02-Z0-001, AP1000 Standard Piping Specification Class BTA, Rev. 10 QA Document Packages Aecon:

132175-G230.04-404-012-00014 CB&I Laurens:

132175-C601.08-404-012-00096 132175-C601.08-404-012-00064 132175-C601.08-404-012-00090 132175-C601.08-404-012-00066 Flowserve:

SV3-PV01-VQQ-030 SV3-PV01-VQQ-018 RT films Weld W1301 from Aecon Document Package 132175-G230.04-404-012-00014 Weld 7 from CB&I Laurens Document Package 132175-C601.08-404-012-00064 Corrective Actions Documents N&D APP-Q601-GNR-850140-2, Rev. 0 CARs: 260537, 269484, 271111, 50000825, 677254 CRs: 50008557, 50008982, 50008966 N&D SV3-RCS-GNR-000028, ADS 1,2,3 MOV Globe Valves, Rev. 0 E&DCR APP-PV01-GEF-071, PV01 ADS 123 Datasheet 1131 and 132 Changes Rev. 0 E&DCR APP-RCS-GEF-406, Resolution to CAPAL 100487069, Rev. 0 E&DCR APP-PV01-GEF-082, Modify E&DCR APP-PV01-GEF-071, Rev. 0 Drawings SV3-RCS-M6-002, Piping and Instrumentation Diagram Reactor coolant System, Rev. 7 SV3-RCS-PLW-01E, RCS Containment Building Room 11603 Lower Tier 2nd Stage ADS Piping, Rev. 1 Procedures SV0-PV01-VMM-001 , MAINTENANCE MANUAL for AP1000 PV01 Size 3 or Larger Motor Operated Gate Valves,Section III, Class 1, 2 & 3 Rev. 0 Design Calculations for Q601 Piping System & Pipe Supports:

APP-RCS-PLR-010, AP1000 Piping Analysis Report for Pressurizer Safety and Automatic Depressurization System PSADS, Rev. 10 APP-RCS-PHC-11R2103, Pipe Support Calculation for APP-RCS-PH-11R2103, Rev. 1 APP-RCS-PHC-11R2104, Pipe Support Calculation for APP-RCS-PH-11R2104, Rev. 1 Fabrication Records for Q601 Pipe Supports: APP-RCS-PH-11R0075 & APP-RCS-PH-11R0076 QAPD 132175-SMS-014, ASME Section III Div. 1 Safety Related Primary Equipment Supports for Vogtle Unit 3 PO 132175-PH02.01 Miscellaneous Documents Reviewed:

E&DCR APP-RCS-GEF-403, Pipe Support Reconciliation for APP-RCS-PLR-010, Rev. 0 E&DCR APP-RCS-GEF-406, Resolution to CAPAL 100487069, Rev. 0

3 DI 100487069, Slide Plate Required for Variable Spring Supports Section 1A03 NDE Reports:

Doosan Report of Ultrasonic Examination No. U110927-007-001 (25 pages) after intermediate heat treatment in as-ground condition conducted from inside and outside surfaces for upper shell to inlet/outlet/DVI nozzles, 9/26/2011 Doosan Report of Ultrasonic Examination No. U120706-021-001 (108 pages) after hydro for three vessel girth welds, eight nozzle welds, and eight nozzle inner radius sections, 7/19/2012 Doosan Report of Liquid Penetrant Examination No. P110404-021-001 after first layer weld in as-ground condition of transition ring to core support pad, 4/5/11 Doosan Report of Liquid Penetrant Examination No. P110405-005-001 after back gouging in as-ground condition and after first 1/2" level and back groove of transition ring to core support pad, 4/6/11 Doosan Report of Liquid Penetrant Examination No. P110406-018-001 after half layer in as-ground condition on the progressively core support pad weld of transition ring, 4/7/11 Doosan Report of Liquid Penetrant Examination No. P110406-019-001 after half layer in as-ground condition on the progressively core support pad weld of transition ring, 4/7/11 Doosan Report of Liquid Penetrant Examination No. P110407-023-001 after half layer in as-ground condition on the progressively core support pad weld of transition ring, 4/8/11 Doosan Report of Liquid Penetrant Examination No. P110407-024-001 after half layer in as-ground condition on the progressively core support pad weld of transition ring, 4/9/11 Doosan Report of Liquid Penetrant Examination No. P110408-037-001 after half layer in as-ground condition on the progressively core support pad weld of transition ring, 4/11/11 Doosan Report of Liquid Penetrant Examination No. P110411-027-001 after half layer in as-ground condition on the progressively core support pad weld of transition ring, 4/12/11 Doosan Report of Liquid Penetrant Examination No. P110412-011-001 after half layer in as-ground condition on the progressively core support pad weld of transition ring, 4/13/11 Doosan Report of Liquid Penetrant Examination No. P110415-035-001 after back gouging in as-ground condition on the bottom side ground area of transition ring to core support pad, 4/18/11 Doosan Report of Liquid Penetrant Examination No. P110421-022-001 after weld in as-ground condition on the core support pad bottom weld, 4/23/11 Doosan Report of Magnetic Particle Examination No. M120706-018-001 after hydrostatic testing in as-ground condition on the outside surface of vessel, 7/12/12 Japan Steel Works, LTD, Muroran Plant Record of Magnetic Particle Examination No. 7042 16-2 of lower shell with manufacturing stage configuration at delivery (max. 250 microinch Ra surface condition, June 8 to 12, 2009 Section 1A04 WEC Construction Isometric Drawing SV3-CCS-PLW-050-R1, "Component Cooling Water System Containment Building Room 11400 CCS Return Line", Revision 1 WECTEC Weld Data Sheet (WDS) SV3-CCS-PLW-050-1 for work package SV3-CCS-P0W-1002504, 9-7-2018 MISTRAS V-18-RT-302-0546, Computed Radiography Examination Report for SV3-CCS-PLW-050-1, 10/03/2018 (P04A)

4 Section 1A05 WEC Construction Isometric Drawing SV3-CCS-PLW-040-R3, "Component Cooling Water System Containment Building Room 11400 CCS Supply Line", Revision 3 WECTEC Weld Data Sheet (WDC) SV3-CCS-PLW-040-1 for work package SV3-CCS-P0W-800010, 9-4-2018 MISTRAS V-18-RT-302-0528, Computed Radiography Examination Report for SV3-CCS-PLW-040-1, 9/24/2018 (P03)

Section 1A06 Weld Data Sheet for SV3-SFS-PY-C01-1 (P21 Penetration), Revision 0 Weld Data Sheet for SV3-SGS-PY-C01A-2 (P23 Penetration), Revision 0 Welding Procedure Specification No. WPS 1-1.8T01, Revision 4 Procedure Qualification Record A82-3, Revision 1 Procedure Qualification Record J2-17, Revision 3 Welding Procedure Specification No. WPS 1-1.1GT(M)SM-NE-2, Revision 8 with supporting PQRs PQ607A/B APP-ML10-V6-004, "AP1000 Flued Head Detail Drawing for Penetration P21", Revision 1 APP-ML10-V6-101, "AP1000 Containment Vessel Flued Head Bevel Detail Drawing", Revision 2

SV3-SFS-MLK-882135, "Weld Map for SV3-SFS-PY-C01 (P21)", Revision 1 APP-MV50-V8-001, "AP1000 Containment Vessel Penetration Installation Specification", Revision 3 Welding Material Requisition No. 416067 for Filler Metal ER309L, 3/32" dia., Heat No. 1181K, October 25, 2018 Welding Material Requisition No. 415882 for Filler Metal ER70S-6, 1/8" dia., Heat No. 1186G, October 25, 2018 Section 1A07 Q-445-18-11196 Q-445-18-11197 F-Q445-014, "Receipt Inspection: Receipt of WEC Procured ASME III & Non-ASME Items,"

Rev. 07.03 Section 1A08 Procedures:

ND-AD-002, Nuclear Development Corrective Action Program, Version 27 W2-5.1-101, Westinghouse Corrective Action Program, Revision 5.1 and 6 W2-5.1-105, Limited Cause Analysis, Revision 2 CAP items:

CR 10491047 CR 10490570 IR-2018-9616 Drawings:

Mangiarotti Drawing-No. W3-WLM-00-00-001, AP1000 Core Make-up Tank, Weld Location Map (CW-054), Revision 0

5 Mangiarotti Drawing-No. W4-WLM-00-00-001, AP1000 Accumulator Tank, Weld Location Map (NZ-036), Revision 0 Radiographic Reports:

Mangiarotti Vogtle Unit 3 Radiographic Test Report No. N015-RT-W4-PCF-10-09-002-15 for Weld-No. NZ-036 (4 pages), 19/09/2011 Mangiarotti Vogtle Unit 3 Radiographic Test Report No. N021-RT-W3-PCF-10-09-002-65 for Weld-No. CW-054 (4 pages), 21/06/2012 Section 1A09 Drawings:

SV3-1130-CE-045, "Containment Concrete Embedment Drawing at Elevation 103'-0" Detail A3," Revision 1 SV3-1130-CE-061, "Containment Concrete Embedment Drawing at Elevation 103'-0" Detail B3," Revision 2 SV3-PXS-FSK-800183, "As-Built IRWST Injection Lines Top Inside Surface Elevation Comparison to IRWST Bottom Inside Surface," Revision 0 SV3-PXS-MTK-891586, "IRWST Bottom Inside Tank Surface Comparison to DVI Nozzle Centerline Elevation," Revision 0 SV3-PXS-PLW-012, "Passive Core Cooling System Containment Building Room 11206 Common Injection Header to DVI-A," Revision 1 SV3-PXS-PLW-015, "Passive Core Cooling System Containment BLDG Room 11206 Containment Recirc. to DVI-A," Revision 1 SV3-PXS-PLW-016, "Passive Core Cooling System Containment BLDG Room 11206 Common Injection header to DVI-A," Revision 1 SV3-PXS-PLW-017, "Passive Core Cooling System Containment BLDG Room 11206 Common Injection Header to DVI-A," Revision 1 SV3-PXS-PLW-018, "Passive Core Cooling System Containment BLDG Room 11305/11206 from IRWST to DVI-A," Revision 0 SV3-PXS-PLW-019, "Passive Core Cooling System Containment Building Room 11206/11105 DVI-A to Reactor Vessel," Revision 2 SV3-PXS-PLW-01Q, "Passive Core Cooling System Containment BLDG Room 11206 Accumulator MT-01A Discharge Piping," Revision 1 SV3-PXS-PLW-01S, "Passive Core Cooling System Containment Building Room 11206 IRWST to DVI-A," Revision 1 SV3-PXS-PLW-01T, "Passive Core Cooling System Containment Building Room 11206 IRWST to DVI-A," Revision 1 SV3-PXS-PLW-01U, "Passive Core Cooling System Containment BLDG Room 11206 IRWST to DVI-A," Revision 0 SV3-PXS-PLW-022, "Passive Core Cooling System Containment Building Room 11207 Common Injection Header to DVI-B," Revision 0 SV3-PXS-PLW-025, "Passive Core Cooling System Containment Building Rooms 11204/11207 DVI-B to Reactor Vessel," Revision 1 SV3-PXS-PLW-026, "Passive Core Cooling System Containment Building Rooms 11105/11204 DVI-B to Reactor Vessel," Revision 2 SV3-PXS-PLW-027, "Passive Core Cooling System Containment Building Room 11207 IRWST

& Containment Recirc. to DVI-B," Revision 1 SV3-PXS-PLW-029, "Passive Core Cooling System Containment Building Room 11207 from IRWST to DVI-B," Revision 0

6 SV3-PXS-PLW-02E, "Passive Core Cooling System Containment Building Room 11207 IRWST to DVI-B & RNS Pump Suction," Revision 1 SV3-PXS-PLW-02L, "Passive Core Cooling System Containment Building Room 11207 from Containment Recirc. to DVI-B," Revision 1 SV3-PXS-PLW-02N, "Passive Core Cooling System Containment Building Room 11207 IRWST

& Cont. Recirc. to DVI-B," Revision 1 SV3-PXS-PLW-02U, "Passive Core Cooling System Containment Building Room 11207 IRWST

& Cont. Recirc. to DVI-B," Revision 1 SV3-PXS-PLW-02W, "Passive Core Cooling System Containment Building Room 11207 IRWST

& Containment Recirc. to DVI-B," Revision 1 SV3-PXS-PLW-02X, "Passive Core Cooling System Containment Building Room 11207 IRWST

& Cont. Recirc. to DVI-B," Revision 1 SV3-PXS-M6-001, "Piping and Instrumentation Diagram Passive Core Cooling System,"

Revision 4 SV3-PXS-M6-002, "Piping and Instrumentation Diagram Passive Core Cooling System,"

Revision 7 Miscellaneous:

Principle Closure Document 2.2.03.08c.iv.01-U3-PRF, Revision 0 SNC Condition Report 10497430 N&D SV3-CA03-GNR-000100, "IRWST Channels to CA03 / P-Plates," Revision 0 Procedures :

26139-000-4MP-T81C-N3201, "Construction Survey," Revision 1 26139-000-4MP-T81C-N7102, "Control of Measuring and Test Equipment," Revision 0 NCSP 02-24, "ITAAC Support Activities (AP1000)," Revision 02.00 NCSP 03-03, "Construction Engineering," Revision 01.04 NCSP 0 3-24, "Field Surveying," Revision 05.00 SV3-PL02-Z0-001, "Piping Class Sheets and Standard Details," Revision 6 Survey Data:

Data File 3-241, Survey Data Reference NI-3 Field Book 97, Pages 100-101, 1-27/18 Survey Data Obtained from SWR Number 1048162 SV3-MV01-X4D-000001, Excerpt from Survey Book NI3 Book #75, Revision 0 Section 1A10 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 - 1047046 SV3-PXS-PLW-019, "Passive Core Cooling System Containment Building Room 11206/11105 DVI-A To Reactor Vessel," Revision 2 SV3-PXS-PLW-012, "Passive Core Cooling System Containment Building Room 11206 Common Injection Header To DVI-A," Revision 1 SV3-PXS-PLW-010, "Passive Core Cooling System Containment BLDG Room 11206 Module Q2-33 CMT-A Discharge Piping," Revision 0 SV3-PXS-PLW-01K, "Passive Core Cooling System Containment BLDG Room 11206 CMT-A Discharge Piping," Revision 1 SV3-PXS-PLW-01V, "Passive Core Cooling System Containment Building Room 11206 CMT-A Discharge Piping," Revision 1

7 SV3-PXS-PLW-011, "Passive Core Cooling System Containment BLDG Room 11206 CMT-A Discharge Piping," Revision 1 SV3-PXS-PLW-026, "Passive Core Cooling System Containment Building Rooms 11105/11204 DVI-B To Reactor Vessel," Revision 2 SV3-PXS-PLW-025, "Passive Core Cooling System Containment Building Rooms 11204/11207 DVI-B To Reactor Vessel," Revision 1 SV3-PXS-PLW-022, "Passive Core Cooling System Containment Building Room 11207 Common Injection Header To DVI-B," Revision 0 SV3-PXS-PLW-02Y, "Passive Core Cooling System Containment Building Room 11207 RNS Connection To DVI-B Connection," Revision 0 SV3-PXS-PLW-02P, "Passive Core Cooling System Containment Building Room 11207 Common Injection HOR To RNS Connection," Revision 1 SV3-PXS-PLW-020, "Passive Core Cooling System Containment Building Room 11207 ISOL Valves To Common Injection HDR," Revision 2 SV3-PXS-PLW-021, "Passive Core Cooling System Containment Building Room 11207 CMT B Injection HDR To ISOL Valves," Revision 2 Section 1A11 Drawings SV3-IDSA-E5-DB101, Wiring Diagram Class 1E 250 VDC Battery IDSA-DB-1, Rev. 0 SV3-IDSS-E5-DB101, Wiring Diagram Class 1E 250 VDC Battery IDSS-DB-1, Rev. 0 SV3-IDSC-E5-DB101-R0, Wiring Diagram Class 1E 250 VDC Battery IDSC-DB-1, Rev. 0 SV3-1210-P3-001, Auxiliary Building Equipment Location Plan EL 666 Areas 1 & 2, Rev. 2 SV3-1010-P2-0011, Nuclear Island Auxiliary BldG Area 1 &2 General Arrangement Plan at Elev 66-6, Rev. 1 Work Orders SV3-IDS-DBW-860172, Install IDS Div. A battery racks in Room 12101 el. 666, Rev. 0 SV3-1212-DBW-1004270, U3 Aux Install IDSS-DB-1A/1B Spare Batteries Rm 12103 El 666 SV3-1212-DBW-1003989, U3 Install IDS 24 Hr Battery Division C Battery Room 12102 El 66-6 SV3-1212-DBW-1001929, U3 Aux Install IDS 24 Hr Battery Division A battery Room 12101 El.

666, Rev. 0 Specifications SV3-G1-V8-001, AP1000 Electrical Installation specification, Rev. 6 SV3-DB01-Z0-001, Design Specification for Class 1E 250 VDC Batteries and Racks, Rev. 7 Procedures F-Q445-014, Receipt inspection: Receipt of WEC procured ASME III and Non-ASME ITEMS, Rev. 07.02 26139-000-4MP-T81C-N6201, Field Material Storage Control, Rev. 4 26139-000-4MP-T81C-N1903, Construction Rigging Work Operations, Rev. 1 26139-000-FMP-T81C-N3301, Electrical Equipment Installation, Rev. 0 26139-000-2QI-Q07C-N3301, QC instruction for Electrical Equipment Installation Rev. 0 Vendor Manuals SV3-DB01-V2-001, AP1000 Class 1E 250 VDC Battery System Assembly Drawings: Two Step Rack Assembly Drawing High Seismic 132 for Type G Batteries, Rev. 0 SV3-DB01-V0M-700, AP1000 Class 1E 250 VDC Battery Multipurpose Manual: Safety, Storage, Installation, Operation & Maintenance Manual, Rev. 1

8 SV3-DB01-V8M-001, AP1000 Class 1E 250 VDC Battery Assembly Drawings: Instruction for Assembling 1E Racks, Rev. 0 Miscellaneous APP-DB01-GEF-850001, Safety related battery terminal exposed copper vendor letter, Rev. 0 26139-J132175-MRR-18-03460-000, Material Receiving Report for IDSS 1E Batteries, Rev. 0 SV3-DB01-VQQ-006, Conditional Quality Release and Final QA document package for IDSS 1E batteries, Rev. 0 SVC-2018-1087, Risk Release for IDSS-DB-1A Batteries, Rev.0 APP-IDSS-GEF-850000, IDSS 250V Spare Class 1E Battery Orientation, Rev. 0 SVC-2018-1080, Risk Release for IDSC-DB-1B 24 Hour Batteries, Rev. 0 APP-DB01-GEF-004, Battery Storage Classification Change, Rev. 0 Section 1A12 Design Specifications SV3-CC01-Z0-031, Safety Related Placing Concrete & Reinforcing Steel, Rev. 8 Design Calculations APP-CA55-S3C-008, AP1000 CA55 Structural Module Design Evaluation, Rev.0 APP-CA55-S3C-009, AP1000 CA55 Structural Module Design Evaluation, Rev.0 APP-CA56-S3C-007, AP1000 CA56 Structural Module Design Evaluation, Rev.0 APP-CA56-S3C-008, AP1000 CA56 Structural Module Connection Evaluation, Rev.0 APP-CA57-S3C-008, AP1000 CA57 Structural Module Connection Evaluation, Rev.0 APP-CA57-S3C-007, AP1000 CA57 Structural Module Design Evaluation, Rev.0 Drawings SV3-0000-C9-001, AP1000 Concrete General Notes, Rev. 7 SV3-1150-CR-013, Containment Concrete Reinforcement CA55 Top, Rev. 2 SV3-1150-CR-045, Containment Concrete Reinforcement CA55 Bottom, Rev.0 SV3-1150-CR-030, Containment Concrete Reinforcement Drawing CA56 & CA57 Top, Rev. 1 SV3-1150-CR-030, Containment Concrete Reinforcement Drawing CA56 & CA57 Bottom, Rev.0 SV3-1150-CR-029, Containment Concrete Reinforcement Drawing Sections U & V Floor at El.

135'-3", Rev.1 SV3-1150-CR-024, Containment Concrete Reinforcement Drawing Section G Floor at EL. 135'-

3", Rev.1 SV3-1150-CR-021, Containment Concrete Reinforcement Drawing Sections A&B Floor at EL.

135'-3", Rev.1 SV3-1150-CR-047, Containment Concrete Reinforcement CA55, CA56, CA57 & CA58 Type Details, Rev.0 SV3-1150-CR-011, Containment Concrete Reinforcement CA55, CA56, CA57 Bottom, Rev.1 APP-1150-CE-010, Containment Concrete Embedment AT EL. 135'-3" General Plan View, Rev.1 Engineering & Design Coordination Reports SV3-CA55-GEF-000016, CA55 Slab Blockout (ESR), Rev.0 APP-1150-GEF-850033, CA55/56/57 Reinforcement Details, Rev.0 APP-CA55-GEF-850032, CA55 FB07 Unachievable Welds, Rev0 APP-1150-GEF-174, E&DCR for Modifying Base Plate on IRWST Tower, Rev, 0 APP-CA00-GEF-130, Stiffness Study CA55, CA56, CA57, and CA58 Floor Modules, Rev. 0 APP-CA01-GEF-077, Couplers on CA01 for Connection of CA55 and CA56, Rev. 0

9 SV3-CA57-GEF-000002, CA57 Clip Angle Alternative (ESR # 50000605), Rev.0 Procedures APP-CR01-Z0-010, Specification for Supply and Installation of Mechanical Splices for Reinforcing Steel, Rev. 8 Calibration Records Torque Wrench V-N-0096, Calibration Date: 7/3/218; Calibration Due Date: 1/3/2019.

Section 1A13 Welding Procedures 181816-000-WS-SP-E71T1, Rev 1 181816-000-WS-SP-E8018, Rev. 2 Welding Procedure Qualification Records 1304 2/13/15, 13869 3/15/18, 13863 2/23/18, 13408 6/3/15, 13849 11/17/17, 13857 2/23/18 Miscellaneous CMTR for Lot 1332R, 3/16/18 Welder qualification record for welder ID DLR6697 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", Rev. 2 Section 1A14 Design Specifications SV3-CC01-Z0-031, Safety Related Placing Concrete and Reinforcing Steel, Rev. 8.

SV3-CC01-Z0-026, Safety Related Mixing and Delivering Concrete, Revision 7.

SV3-CC01-Z0-027, Safety Related Concrete Testing Services, Revision 6.

Calculation CALC-VMD-032, Mix Y Recommended Mix Proportions, Date Issued: 1/28/12 Pour Card 4504, Unit 3 Shield Building Course 9 & 10, Date: 05/12/2018 Batch Tickets 51068 51056 51075 51084 51096 51105 51117 51125 51134 Concrete Compression Test Results Wood Lab/Ref. # 2018VEGP8017T. Sample Date: 12/5/2018

10 Section 1A15 Design Specifications SV3-CC01-Z0-031, "Safety Related Placing Concrete and Reinforcing Steel," Rev. 8 SV3-CC01-Z0-026, "Safety Related Mixing and Delivering Concrete," Rev. 7 SV3-CC01-Z0-027, "Safety Related Concrete Testing Services," Rev. 6 APP-CR01-Z0-010, "Specification for Supply and Installation of Mechanical Splices for Reinforcing Steel", Rev. 8 Procedure APP-GW-GAP-428, Nonconformance and Disposition Report (N&D), Rev. 15 Drawings SV3-0000-C9-001, AP1000 Concrete General Notes, Rev. 8 SV3-0000-C9-002A, AP1000 Concrete General Notes, Rev. 2 APP-1200-CR-931, Auxiliary Building Areas 2 & 3 Concrete Reinforcement Wall 7.3 Elevation, Rev. 19 APP-1240-CR-931, Auxiliary Building Areas 2 & 3 Concrete Reinforcement Wall 7.3 Section &

Details Elevation 117'-6", Rev. 6 APP-1200-CR-912, Auxiliary Building Area 2 Concrete Reinforcement Walls J & K Elevations, Rev. 18 APP-1240-CR-912, Auxiliary Building Area 2 Concrete Reinforcement Wall J Sections & Details Elevation 117'-6", Rev. 5 SV3-1200-CR-992, Auxiliary Building Concrete Reinforcement Typical Detail Opening (sheet 2),

Rev. 10 E&DCRs APP-1240-GEF-850044, Wall 7.3 Reinforcement and Penetrations, Rev, 1 APP-1240-GEF-850074, Wall 7.3 Reinforcement and Penetrations, Rev. 0 SV3-1240-GEF-000003, Hold on Formwork Installation on Wall 7.3 between El. 117'-6" and El.

135'-3" SV3-CR01-GNR-000993, 7.3 Line Elevation 117'-6" Doorway Details, Rev. 0 APP-1200-GEF-1019, Wall J Drawing Modificationsper APP-1240-E0-912, Rev. 6_ADL APP-CR01-GEF-850514, Wall J Added SPLC Location for Add'l Steel Elevation 117'-6" APP-1200-GEF-1020, Modifications to Auxiliary Building Rebar Placement EL. 117'-6" & El.

135'-3", Rev. 0 Non-conformance and Disposition Report SV3-CR01-GNR-000994, J-Line Elevation 117'-6" Doorway Details, Rev. 0 Pour Card 4419, Unit 3 Auxiliary Building Interior Wall Placement #131 on 7.3 Line Batch Tickets 50734 50735 50738 50751 50756 Torque Wrench Calibration Records V-N-0126, Calibration Date: 06/09/18 through 12/09/18

11 Condition Report 50007586, Date: 10/29/18 Section 1A16 Specifications SV3-CC01-Z0-031, Safety Related Placing Concrete and Reinforcing Steel, Rev. 8 Drawings SV3-0000-C9-001, AP1000 Concrete General Notes, Rev. 9 SV3-0000-C9-002A, AP1000 Concrete General Notes, Rev. 2 SV3-1200-CR-992, Auxiliary Building Concrete Typical Reinforcement Typical Detail Opening (sheet 2), Rev. 6 SV3-0000-C9-002, AP1000 Concrete General Notes, Rev. 7 APP-1240-CR-918, Auxiliary Building Area 2 Concrete Reinforcement Wall K Sections & Details EL. 117'-6", Rev. 6 APP-1200-CR-912, Auxiliary Building Area 2 Concrete Reinforcement Walls J & K Elevations, Rev. 18 E&DCR's APP-1232-GEF-115, Horizontal Construction Joints at EL. 115'-8 ", Rev. 0 APP-CR01-GEF-850158, Wedge at Wall K EL 117'-6", Rev. 0 APP-CR01-GEF-850419, Wall K Rebar Details EL. 117'-6", Rev. 0 SV0-CR01-GEF-000873, Allowance to Field Bend Reinforcing Bars and Hairpin Requirements, Rev. 0 Procedures APP-GW-GAP-420, Engineering and Design Coordination Reports, Rev. 12 Section 1A17 Design Specification SV3-CC01-Z0-031, Safety Related Placing Concrete and Reinforcing Steel, Rev. 8 Drawings SV3-000-C9-001, Concrete General Notes, Rev. 8 SV3-1242-CR-204, Auxiliary Building Area 2 Concrete Reinforcement Floor EL. 117'-6" Plan, Rev. 4 SV3-1040-CR-101, Auxiliary Building Concrete Reinforcement Slab Joint Rebar to connect the Shield Building EL. 117'-6" Detail (Sheet 2), Rev. 2 SV3-1242-CR-264, Auxiliary Building Area 2 Concrete Reinforcement Floor EL. 117'-6" Details (sheet 5), Rev. 2 SV3-1242-CR-204, Auxiliary Building Concrete Outline Area 2 Floor EL. 117'-6", Rev. 8 Condition Report 70000127, Bars off elevation on SP34A Slab, Date, 11/26/18 Engineering & Design Coordination Reports APP-1242-GEF-850014, Area2 El. 117'-6" Slab Reinforcement & Drawings Clean up, Rev. 0 APP-1240-GEF-375, Relocation of Embedments Supporting DK-1 and Localized Conduits, Rev.

0

12 Procedure APP-CR01-Z0-010, Specification for Supply and Installation of Mechanical Splices for Reinforcing Steel, Rev. 8 Bechtel Project Quality Assurance Manual, Rev. 0 Calibration Records Torque Wrench No. V-N 0035, Calibration Date: 08/11/18. Calibration Due Date: 02/14/19.

Section 1A18 Specifications SV3-CC01-Z0-031, Safety Related Placing Concrete and Reinforcing Steel, Rev. 8 Drawings SV3-0000-C9-001, AP1000 Concrete General Notes, Rev. 9 SV3-0000-C9-002A, AP1000 Concrete General Notes, Rev. 2 SV3-1200-CR-913, Auxiliary Building Areas 1 & 2 Concrete Reinforcement Walls L & M Elevations, Rev. 12 SV3-1252-CR-215, Auxiliary Building Area 2 Concrete Reinforcement Floor EL. 135'-3" Details (Sheet 1), Rev. 2 SV3-1250-CR-913, Auxiliary Building Areas 1 & 2 Concrete Reinforcement Walls L & M Sections and Details, Rev. 3 SV3-1240-CR-913, Auxiliary Building Areas 1 & 2 Concrete Reinforcement Walls L & M Sections and Details, Rev. 5 SV3-1200-CR-991, Auxiliary Building Concrete Reinforcement Typical Opening Detail, Rev.5 Engineering & Design Coordination Reports APP-1240-GEF-364, Horizontal Construction Joint at EL. 133'-3" for Wall L, Rev. 0 SV0-CR01-GEF-001164, SPLC Locations on Walls L, M, P, and Q, Rev. 0 Nonconformance and Disposition Report SV3-CR01-GNR-000949, Reinforcement in Wall L, Rev. 0 Section 1A19 Design Specifications SV3-CC01-Z0-031, Safety Related Placing concrete and Reinforcement Steel, Rev. 8 Calculations APP-1240-S3C-123, Auxiliary Building Secondary (Small) Walls Between EL. 100'-0" & EL.

135'-3", Reinforced Concrete Design, Rev. 1 Drawings SV3-0000-C9-001, AP1000 Concrete General Notes, Rev. 8 SV3-1200-CR-932, Auxiliary Building Areas 3&4 Concrete Reinforcement Wall I Elevation, Rev.

11 SV3-1240-CR-932, Auxiliary Building Areas 3&4 Concrete Reinforcement Wall I Sections &

Details EL. 117'-6" (Sheet 1), Rev. 6 SV3-1240-CR-937, Auxiliary Building Areas 3&4 Concrete Reinforcement Wall I Sections &

Details EL. 117'-6" (Sheet 2), Rev.4

13 SV3-1230-CR-937, Auxiliary Building Areas 3&4 Concrete Reinforcement Wall I Section &

Detail EL. 100'-0", 105'-0", & 107'-2" (Sheet 2), Rev.6 APP-1240-CR-990, Auxiliary Building Concrete Reinforcement Secondary Walls Elevation EL.

117'-6", Rev.6 APP-1240-CR-992, Auxiliary Building Concrete Reinforcement Secondary Walls Sections &

details EL. 117'-6" (Sheet 2), Rev. 5 Engineering & Design Coordination Reports APP-1240-GEF-286, Block Out Addressed on Drawings for Wall 4.8, Rev. 0 APP-1240-GEF-850021, Wall 4.8 Embedded Plate PL13, Rev. 0 APP-1240-GEF-850040, Wall 4.8 Reinforcement and CJs, Rev.0 Nonconformance & Disposition Report SV3-CR01-GNR-001048, Wall #120 @ I-Line Crack Control Bars at Equipment Door Corner, Rev. 0 Section 1A20 SV0-RCS-M0P-800315, GQ P 9.7, "Solvent Removable Liquid Penetrant Examination and Acceptance Standards for Welds, Base Materials, and Cladding", Revision 19 MISTRAS Computed Radiography Examination Report P-18-RT-302-0052 for Cold Leg - RCS -

L002D weld-no. SV4-RCS-PL01-FW-BCL05 (all film), 10/01/2018 MISTRAS Computed Radiography Examination Report P-18-RT-302-0053 for Cold Leg - RCS -

L002C weld-no. SV4-RCS-PL01-FW-BCL03 (all film), 10/01/2018 MISTRAS Computed Radiography Examination Report P-18-RT-302-0055 for Hot Leg - RCS -

L001B weld-no. SV4-RCS-PL01-FW-BHL02 (all film), 10/01/2018 MISTRAS 521-RT-302, "Radiographic Examination using Computed Radiography in Accordance with ASME Section V, Article 2", Revision 0 Section 1A21 Specifications APP-GW-P0-008, AP1000 Specification for Field Fabricated Piping and Installation, ASME III, Code Classes 1, 2, and 3 and ASME B31.1 Rev. 7 APP-PL02-Z0-101, AP1000 Class 1 Piping and Non-Class 1 Extensions Design Specification, Rev. 4 APP-PV01-Z0-001, 3 AND Larger Motor Operated Gate and Globe Valves, ASME Boiler and Pressure Vessel Code Section III, Class 1, 2, and 3, Rev. 9 APP-Q601-Z0-001, Design Specification for AP1000 Piping Module 1102-Q6-01, Rev. 1 APP-GW-P0-008-ADD-02, Supplemental QA Requirements for the Pressurizer Upper Lateral Support Assembly (PRZUL)-Ring Girder and ASME III Mechanical Modules KB36, Q223, Q233, Q240, Q305, and Q601 Rev. 9 APP-GW-P0-007, AP1000 Specification for Shop Fabricated Piping Rev. 8 APP-PL02-Z0-001, AP1000 Standard Piping Specification Class BTA, Rev. 10 QA Document Packages Aecon:

132176-G230.04-404-012-00007 CB&I Laurens:

132176-C601.08-404-012-00089

14 132176-C601.08-404-012-00072 132176-C601.08-404-012-00038 132176-C601.08-404-012-00094 Flowserve:

SV4-PV01-VQQ-010 SV4-PV01-VQQ-024 RT film Weld W1064 from Aecon Document Package 132176-G230.04-404-012-00007 Weld #9 from CB&I Laurens Document Package 132176-C601.08-404-012-00072 Corrective Actions Documents N&D APP-Q601-GNR-850140-2, Rev. 0 CARs: 260537, 269484, 271111, 50000825, 677254 CRs: 50008557, 50008982, 50008966 N&D SV3-RCS-GNR-000028, ADS 1,2,3 MOV Globe Valves, Rev. 0 E&DCR APP-PV01-GEF-071, PV01 ADS 123 Datasheet 1131 and 132 Changes Rev. 0 E&DCR APP-RCS-GEF-406, Resolution to CAPAL 100487069, Rev. 0 E&DCR APP-PV01-GEF-082, Modify E&DCR APP-PV01-GEF-071, Rev. 0 Drawings SV4-RCS-M6-002, Piping and Instrumentation Diagram Reactor coolant System, Rev. 7 SV4-RCS-PLW-016, RCS Containment Building Room 11703 Upper Tier 3rd Stage ADS Piping, Rev. 1 SV4-PLW-01C, RCS Containment Building Rm 11603 PZR to Lower Tier ADS Piping, Rev. 1 Procedures SV0-PV01-VMM-001 , MAINTENANCE MANUAL for AP1000 PV01 Size 3 or Larger Motor Operated Gate Valves,Section III, Class 1, 2 & 3 Rev. 0 Design Calculations for Q601 Piping System & Pipe Supports APP-RCS-PLR-010, AP1000 Piping Analysis Report for Pressurizer Safety and Automatic Depressurization System PSADS, Rev. 10 APP-RCS-PHC-11R0075, Pipe Support Calculation for APP-RCS-PH-11R0075, Rev. 0 APP-RCS-PHC-11R0076, Pipe Support Calculation for APP-RCS-PH-11R0076, Rev. 2 APP-RCS-PHC-11V0113, Pipe Support Calculation for APP-RCS-PH-11V0113, Rev. 1 APP-RCS-PHC-11Y0112, Pipe Support Calculation for APP-RCS-PH-11Y0112, Rev. 1 Fabrication Records for Q601 Pipe Supports: APP-RCS-PH-11R2103, APP-RCS-PH-11R2104, APP-RCS-PH-11V0113 & APP-RCS-PH-11Y0112 QAPD 132176-SMS-011, ASME Section III Div. 1 Safety Related Primary Equipment Supports for Vogtle Unit 4 PO 132176-PH02.01 Section 1A22 WEC Isometric Drawing APP-PXS-PLW-02E, "Passive Core Cooling System Containment Building Room 11207 IRWST to DVI-B & RNS Pump Suction", Rev. 4 Stone and Webster (S&W) Weld Data Sheet (WDC) SV4-PXS-PLW-02E-11 for work package SV4-PXS-P0W-800006, 1-29-18 S&W Welding Material Requisition (WMR) 405688 for welder MAJ 2161 and welding rods 3/32" and 1/8" dia. with heat-nos.1203F and 1203E, respectively, 9/25/18

15 Section 1A23 Procedures:

ND-AD-002, Nuclear Development Corrective Action Program, Version 27 W2-5.1-101, Westinghouse Corrective Action Program, Revision 5.1 and 6 W2-5.1-105, Limited Cause Analysis, Revision 2 CAP items:

CR 10491047 CR 10490570 IR-2018-9616 Drawings:

Mangiarotti Drawing-No. W2-WLM-00-00-001, AP1000 Pressurizer, Weld Location Map (CW-033 and CW-035), Revision 0 Mangiarotti Drawing-No. W1-DWF-11-00-025, AP1000 Passive Heat Removal Heat Exchanger, Weld Location Map (CW-029/1), Revision 7 Radiographic Reports:

Mangiarotti Vogtle Unit 4 Radiographic Test Report No. N016-RT-W2-PCF-10-11-003-16.2 for Weld-No. CW-033 (4 pages), 22/11/2013 Mangiarotti Vogtle Unit 4 Radiographic Test Report No. N016-RT-W2-PCF-10-11-003-16.3 for Weld-No. CW-035 (4 pages), 22/11/2013 Mangiarotti Vogtle Unit 4 Radiographic Test Report No. N024-RT-W1-PCF-00-11-001-6 for Weld-No. CW-029/1 (4 pages), 25/5/2014 Section 1A24 CMTR for heat Number K5684 APP-PV01-Z0D-106, "PV01 Datasheet 106", Rev. 4 Drawing 09-91175-07 Sheets 1-5, Rev. 0 NDE Reports ARE3958, ABD00172 Section 1A25 Drawings:

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-PLW-018, "Passive Core Cooling System Containment BLDG Room 11305/11206 from IRWST to DVI-A," Revision 0 SV4-PXS-PLW-029, "Passive Core Cooling System Containment Building Room 11207 from IRWST to DVI-B," Revision 0 SV4-PXS-M6-001, "Piping and Instrumentation Diagram Passive Core Cooling System,"

Revision 4 SV4-PXS-M6-002, "Piping and Instrumentation Diagram Passive Core Cooling System,"

Revision 7 Section 1A26 CMP-RSHT-2018-5-13614, PMS Digital Cabinets/Receipt Inspection and Storage Compliance for Units 4 PMS Digital Cabinets, May 17, 2018 Qualification and Curriculum for Surveillance Representatives

16 ND-CA-VNP-013, Nuclear Development Compliance Monitoring Program (CMP) Surveillance Program, Rev. 13 ND-CA-VNP-021, Management of the Compliance Monitoring Program, Rev. 18 APP-PMS-J0M-003, AP1000 Protection and Safety Monitoring System Technical Manual, Rev.

1 26139-000-4MP-T81C-N6201, Field Material Storage Control, Rev. 4 V-U-0092-Oct_Summary, August 9, 2018 through October 23, 2018 V-U-0092_Summary-Nov, October 23, 2018 through November 27,2018 V-U-0193-Oct_Summary, August 9, 2018 through October 23, 2018 V-U-0193_Summary-Nov, October 23, 2018 through November 27, 2018 Section 1A27 Design Specifications SV3-CC01-Z0-031, Safety Related Placing Concrete and Reinforcing Steel, Rev. 8.

SV3-CC01-Z0-026, Safety Related Mixing and Delivering Concrete, Revision 7.

SV3-CC01-Z0-027, Safety Related Concrete Testing Services, Revision 6.

Concrete Mix Dry Density Report 132175-102-006-04-000004 - Mix E(r1)

Concrete Pour Card Concrete Placement/Order Pour Card, Pour Number 4150, Batch Tickets Pump No. 1 50296 77212 50339 77226 77235 77246 77310 (Correlation Test)

Pump No. 2 50307 50330 50338 77223 50364 (Correlation Test) 50374 50398 50409 77292 (Correlation Test)

Pump No. 3 50317 77209 50331 50388 (Correlation Test) 77256 77269 77280 77302 77330 (Correlation Test)

17 77333 (Correlation Test)

Condition Reports 50005968, Date 10/01/18 50006023, Date 10/02/18 50006091, Date 10/03/18 50006684, Date 10/03/18 Miscellaneous Concrete Specimen Initial Curing Log, Pour 4150, Date: 9/26/2018 Curing Box Logs, Pour 4150, Date: 9/26/2018 Vibrator Serial No. 9-1100980, Calibration Date 9/01/18 through 11/30/18 Section 1A28 Specifications SV4-CC01-Z0-026, Safety Related Mixing and Delivering Concrete, Rev. 8 SV4-CC01-Z0-027, Safety Related Concrete Testing Services, Rev. 7 SV4-CC01-Z0-031, Safety Related Placing Concrete and Reinforcement Steel, Rev. 8 Pour Card 4422, Unit 4 CA01/CA02 Concrete Placement to Elevation 135'-3", Date: 7/12/18 Batch Tickets 51147 51157 51189 51217 Section 1A29 Design Specifications SV3-CC01-Z0-031, Safety Related Placing Concrete and Reinforcing Steel, Rev. 8.

SV3-CC01-Z0-026, Safety Related Mixing and Delivering Concrete, Revision 7.

SV3-CC01-Z0-027, Safety Related Concrete Testing Services, Revision 6.

Pour Card 4399, Unit 4 Aux. EL. 100-0 to 117-6 (Wall 98), Date: 12/19/2018 Batch Ticket 51332 Section 1P01 ND-AD-002, Nuclear Development Program Corrective Action Program, Rev. 28.0 APP-GW-GAP-428, "Nonconformance and Disposition Report," Revision 15 APP-GW-GAP-420, "Engineering and Design Coordination Reports," Revision 16 CAPAL 100497762 Quality Inspection Report S511-17-11031, "Mechanical Rebar Splices: Threaded Lenton Coupler Splices/Weldable Couplers," 10/16/17 Quality Inspection Plan F-S511-001, "Mechanical Rebar Splices: Threaded Lenton Splices/Weldable Couplers," Revision 14.01 N&D SV3-CR01-GNR-000905, "Sister Splices not taken per required frequency," Revision 0

18 Quality Inspection Report S511-17-12279, "Mechanical Rebar Splices: Threaded Lenton Coupler Splices/Weldable Couplers," 09/24/17 E&DCR SV0-CR01-GEF-001010, "Revision of Taper Threaded Mechanical Splice Testing &

Inspection Requirements," Revision 0 CAPAL 100501995 Quality Inspection Report C114-17-10189, "Post Placement: Concrete Repair," 11/01/17 N&D SV4-CR01-GNR-000306, "Form Saver with No Internal Threads," Revision 0 CAPAL 100502331 Quality Inspection Report C114-17-10212, "Post Placement: Concrete Repair," 11/17/17 N&D SV4-CC01-GNR-000242, "Voids Below Horizontal Construction Joint of N-Line/13M Interface," Revision 0 E&DCR SV4-CC01-GEF-000056, "NI4 SBW Optional horizontal construction joint," Revision 0 Quality Inspection Report C113-17-10152, "Placing Safety Related Concrete (See Gen. Inst.

1. 6)," 11/16/17 N&D SV4-CR01-GNR-000317, "13M U-Bar Splice/Development Issue," Revision 0 CAPAL 100494292 N&D SV4-CA20-GNR-000217, "Cracked weld in SV4-CA20 room 12264," Revision 0 Request For Information SV4-CA20-GF-000084, "[Part 21 RFI] Cracked weld in SV4-CA20 room 12264," 10/09/2017 WDS 870522-120 Record Of Magnetic Particle Examination NDE Report No. V-17-MT-302-1933, 08/22/17 Record Of Magnetic Particle Examination NDE Report No. V-17-MT-963-0023, 10/17/17 CAPAL 100497412 N&D SV4-CC01-GNR-000221, "U4-Aux Bldg. Wall Placement # 48 South Face Consolidation,"

Revision 0 Quality Inspection Report C114-18-10030, "Post Placement: Concrete Repair," 02/03/18 Quality Inspection Report C114-18-10018, "Post Placement: Concrete Repair," 02/01/18 Section 1P02 ND-AD-002, "Nuclear Development Corrective Action Program," Version 28.0 ND-AD-002-025, "Issue Identification, Screening, and Dispatching", Version 1.0 3-AOP-404, "Instrument Failure PMS Division B", Version C 3-AOP-405, "Instrument Failure PMS Division C", Version C 3-AOP-406, "Instrument Failure PMS Division D", Version C SV3-1030-P2-0011-R1, "Nuclear island Auxiliary Bldg Area 1 & 2 General Arrangement Plan at EL 100'-0" & 107'-2", Rev. 1 CR 50005649, "3-AOP-404, 405, and 406 need revisions", 9/26/18 TE 50005739, "3-AOP-404, 405, and 406 need revisions", 9/26/18 Section 2P01 This input is security related. See non-public report 05200025/2018413 for details.

4. OTHER INSPECTION RESULTS 4OA3 Corrective Action Documents SNC CR 10062982 CB&I CAR 2015-1585

19 Nonconformance and Disposition Reports (N&Ds)

N&D SV3-CA20-GNR-000680, Volume for Fuel Transfer and Spent Fuel Pool, Revision 0 N&D SV3-CA20-GNR-000887, North Wall Repair Spent Fuel Pool Supplemental Information, Revision 0

20 LIST OF ACRONYMS ACC accumulator ACI American Concrete Institute ADS automatic depressurization system ANI authorized nuclear inspector ASME BPVC American Society of Mechanical Engineers Boiler & Pressure Vessel Code ASNT American Society of Nondestructive Testing ASTM American Society of Testing and Materials AWS American Welding Society CB&I Chicago Bridge and Iron CFR Code of Federal Regulations CMP compliance monitoring program CMT core makeup tank CMTR certified material test report DVI direct vessel injection E&DCR engineering and design coordination report GTAW gas tungsten arc welding IDS uninterruptable power supply system IMC inspection manual chapter IQI image quality indicator ITAAC Inspections, Tests, Analysis, and Acceptance Criteria IRWST in-containment refueling water storage tank MOV motor operated valve MT magnetic particle test N&D nonconformance and disposition NDE nondestructive examination NQA-1 ASME Nuclear Quality Assurance Program PCD principle closure document PRHR HX passive residual heat removal heat exchanger PT liquid penetrant test PXS passive core cooling system PZR pressurizer QAP Quality Assurance Program QC quality control RCS reactor coolant system RT radiographic test SNC Southern Nuclear Company UFSAR Updated Final Safety Analysis Report UT ultrasonic test WDS weld data sheet WEC Westinghouse WMR welding material requisition

21 ITAAC INSPECTED 13 2.1.02.02a 2.a) The components Inspection will be The ASME Code identified in Table conducted of the as- Section III design 2.1.2-1 as ASME built components 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 Section met for non-constructed in III. A hydrostatic destructive accordance with test will be examination of ASME Code Section performed on the pressure boundary III requirements. 3.a) components and welds. A report exists Pressure boundary piping required by and concludes that welds in components 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 for Table 2.1.21 and III requirements. 3.b) the existence of a Table 2.1.22 as Pressure boundary report verifying that ASME Code Section welds in piping the as-built piping III conform with the identified in Table meets the requirements of the 2.1.2-2 as ASME requirements for ASME Code Section Code Section III meet functional capability. III. A report exists ASME Code Section Inspection will be and concludes that III requirements. 4.a) performed for the each of the as-built The components existence of an LBB lines identified in identified in Table evaluation report or Table 2.1.2-2 for 2.1.2-1 as ASME an evaluation report which functional Code Section III on the protection capability is required retain their pressure from dynamic effects meets the boundary integrity at of a pipe break.

requirements for their design pressure. Section 3.3, Nuclear functional capability.

4.b) The piping Island Buildings, An LBB evaluation identified in Table contains the design report exists and 2.1.2-2 as ASME descriptions and concludes that the Code Section III inspections, tests, LBB acceptance retains its pressure analyses, and criteria are met by the boundary integrity at acceptance criteria as-built RCS piping its design pressure. for protection from and piping materials, 5.b) Each of the lines the dynamic effects or a pipe break identified in Table of pipe rupture.

evaluation report 2.1.2-2 for which exists and concludes functional capability is that protection from

22 required is designed the dynamic effects of to withstand a line break is combined normal and provided.

seismic 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.

72 2.1.03.03 3. The components Inspection will be The ASME Code identified in Table conducted of the as- Section III design 2.1.3-1 as ASME built components as reports exist for the Code Section III are documented in the as-built components designed and ASME design 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 welds in components ASME Code Section III requirements are identified in Table III. A hydrostatic met for non-2.1.3-1 as ASME test will be destructive Code Section III meet performed on the examination of ASME Code Section components of the pressure boundary III requirements. 5. RXS required by the welds. A report exists The pressure ASME Code Section and concludes that boundary III to be the results of the components (RV, hydrostatically hydrostatic test of the CRDMs, and incore tested. pressure boundary instrument QuickLoc components (RV, assemblies) identified CRDMs, and incore in Table 2.1.3-1 as instrument QuickLoc ASME Code Section assemblies) conform III retain their with the requirements pressure boundary of the ASME Code integrity at their Section III.

design pressure.

23 91 2.2.01.02a 2.a) The components Inspection will be The ASME Code identified in Table conducted of the as- Section III design 2.2.1-1 as ASME built components 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 Section met for non constructed in III. i) A hydrostatic destructive accordance with or pressure test will examination of ASME Code Section be performed on the pressure boundary III requirements. 3.a) components welds. i) A report Pressure boundary required by the exists and concludes welds in components ASME Code Section that the results of the identified in Table III to be tested. A pressure test of the 2.2.1-1 as ASME hydrostatic or components identified Code Section III meet pressure test will be in Table 2.2.1-1 as ASME Code Section performed on the ASME Code Section III requirements. 3.b) piping required by III conform with the Pressure boundary the ASME Code requirements of the welds in piping Section III to be ASME Code Section identified in Table pressure tested. III. A report exists 2.2.1-2 as ASME and concludes that Code Section III meet the results of the ASME Code Section pressure test of the III requirements. 4.a) piping identified in The components Table 2.2.1-2 as identified in Table ASME Code Section 2.2.1-1 as ASME III conform with the Code Section III requirements of the retain 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.

24 159 2.2.03.02a 2.a) The components Inspection will be The ASME Code identified in Table conducted of the as- Section III design 2.2.3-1 as ASME built components 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 ASME Code Section accordance with the III requirements are III is designed and ASME Code Section met for non-constructed in III. A hydrostatic destructive accordance with test will be examination of ASME Code Section performed on the pressure boundary III requirements. 3.a) components and welds. A report Pressure boundary piping required by exists and concludes welds in components 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 for Table 2.2.31 and III requirements. 3.b) the existence of a 2.2.3-2 as ASME Pressure boundary report verifying that Code Section III welds in piping the as-built piping conform with the identified in Table meets the requirements of the 2.2.3-2 as ASME requirements for ASME Code Section Code Section III meet functional capability. III. A report exists ASME Code Section Inspection will be and concludes that III requirements. 4.a) performed for the each of the as-built The components existence of an LBB lines identified in identified in Table evaluation report or Table 2.2.3-2 for 2.2.3-1 as ASME an evaluation report which functional Code Section III on the protection capability is required retain their pressure from dynamic effects meets the boundary integrity at of a pipe break. requirements for their design pressure. Section 3.3, Nuclear functional capability.

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

25 combined normal and a line break is seismic design basis provided.

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

183 2.2.03.08c.iv.01 8.c) The PXS iv) Inspections of iv) The maximum provides RCS the elevation of the elevation of the top makeup, boration, following pipe lines inside surface of and safety injection will be conducted: 1. these lines is less during design basis IRWST injection than the elevation of:

events. lines; IRWST 1. IRWST bottom connection to DVI inside surface v) nozzles v) The elevation of the Inspections of the bottom inside tank elevation of the surface is higher than following tanks will the direct vessel be conducted: 2. injection nozzle IRWST centerline by the following: 2. IRWST 3.4 ft 185 2.2.03.08c.iv.03 8.c) The PXS iv) Inspections of iv) The maximum provides RCS the elevation of the elevation of the top makeup, boration, following pipe lines inside surface of and safety injection will be conducted: 3. these lines is less during design basis CMT discharge lines than the elevation of:

events. to DVI connection 3. CMT bottom inside surface

26 550 2.5.02.11 11. The PMS Inspection will be A report exists and hardware and performed of the concludes that the software is developed process used to process defines the using a planned design the hardware organizational design process which and software. responsibilities, provides for specific activities, and design configuration documentation and management controls reviews during the for the following: a) following life cycle Not used. b) stages: a) Not used Specification of b) System definition functional phase c) Hardware requirements. c) and software Documentation and development phase, review of hardware consisting of and software. d) hardware and Performance of software design and system tests and the implementation d) documentation of System integration system test results, and test phase e) including a response Installation phase time test performed under maximum CPU loading to demonstrate that the PMS can fulfill its response time criteria. e)

Performance of installation tests and inspections.

27 597 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 report seismically bounded verifying that the as- by the tested or built equipment analyzed conditions.

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

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

28 761 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 Design Description and 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 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 design basis loads and the safety-related specified in the functions. Design Description without loss of structural integrity or the safety-related functions.

29 763 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 design basis loads and the safety-related specified in the functions. Design Description without loss of structural integrity or the safety-related functions.