ND-18-0545, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.02.02a (Index Number 285)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.02.02a (Index Number 285)

ML18117A305
Person / Time
Site:	Vogtle
Issue date:	04/24/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0545
Download: ML18117A305 (12)

Text

Michael J. Yox 7825 River Road

^ Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 cell APR 2 4 2018 myox @southernco.com Docket Nos.: 52-025 52-026 ND-18-0545 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.02.02a findex Number 2851 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of April 16, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.02.02a [Index Number 285]

has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern Nuclear Operating Company will, at a laterdate, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.

This notification is informed by the guidance described in NEI 08-01, Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52, which was endorsed by the NRC in Regulatory Guide 1.215. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, oranalyses have not been performed or have been only partially completed. All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

If there are any questions, please contact Tom Petrak at 706-848-1575.

Respectfully submitted, Michael J. Yox Regulatory Affairs Director Vogtle 3 &4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Planfor Uncompleted ITAAC 2.3.02.02a [Index Number 285]

MJY/KJD/amw

U.S. Nuclear Regulatory Commission ND-18-0545 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)

Mr. M. D. Rauckhorst (w/o enclosures)

Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)

Mr. D. L. McKinney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. 8. Klecha Mr. G. Chick Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. C. Chamberlain Mr. D. R. Culver Mr. T. G. Petrak Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reoulatorv Commission Mr. W. Jones (w/o enclosures)

Ms. J. M. Heisserer Mr. C. P. Patel Mr. M. E. Ernstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E. Temple Ms. P. Braxton Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Ms. L. A. Kent Mr. P. B. Donnelly Ms. N. C. Coovert Oalethoroe Power Corporation Mr. R. B. Brinkman

U.S. Nuclear Regulatory Commission ND-18-0545 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Orlani (w/o enclosures)

Mr. D. 0. Durham (w/o enclosures)

Mr. M. M. CorlettI Ms. L. G. Iller Mr. D. Hawkins Ms. J. Monahan Mr. J. L. Coward Ms. N. E. Deangelis Other Mr. J. E. Hosier, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., CDS Associates, inc.

Mr. 8. Roetger, Georgia PublicSen/ice Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-18-0545 Enclosure Page 1 of 9 Southern Nuclear Operating Company ND-18-0545 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.02.02a [Index Number 285]

U.S. Nuclear Regulatory Commission ND-18-0545 Enclosure Page 2 of 9 ITAAC Statement Design Commitment:

2.a) The components identified in Table 2.3.2-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.

2.b) The piping identified in Table 2.3.2-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.

3.a) Pressure boundary welds in components identified in Table 2.3.2-1 as ASME Code Section III meet ASME Code Section III requirements.

3.b) Pressure boundary welds in piping identified in Table 2.3.2-2 as ASME CodeSection III meet ASME Code Section III requirements.

4.a) The components identified in Table 2.3.2-1 as ASME CodeSection III retain their pressure boundary integrity at their design pressure.

4.b) The piping identified in Table 2.3.2-2 as ASME CodeSection III retains its pressure boundary integrity at its design pressure.

Insoections. Tests. Analyses:

Inspection will be conducted of the as-built components and piping as documented in the ASME design reports.

Inspection of the as-built pressure boundary welds will be performed in accordance with the ASME Code Section III.

Ahydrostatic test will be performed on the components and piping required by the ASME Code Section III to be hydrostatically tested.

Acceptance Criteria:

The ASME Code Section III design reports existfor the as-built components and piping identified in Tables 2.3.2-1 and 2.3.2-2 as ASME Code Section III.

Areport exists andconcludes that the ASME Code Section III requirements are met for non destructive examination of pressure boundary welds.

Areport exists and concludes that the results of the hydrostatic test of the components and piping identified in Tables 2.3.2-1 and 2.3.2-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.

ITAAC Completion Description This ITAAC requires inspections, tests, and analyses be performed and documented to ensure the Chemical and Volume Control System (CVS) components and piping listed in the Combined License (COL) Appendix C, Table 2.3.2-1 (Attachment A) and Table 2.3.2-2 (Attachment B) that

U.S. Nuclear Regulatory Commission ND-18-0545 Enclosure Page 3 of 9 are identified as American Society of Mechanical Engineers (ASME) Code Section III, are designed and constructed in accordance with applicable requirements.

2.a and 2.b) The ASME Code Section III desion reoorts exist for the as-built components and oipino identified in Tables 2.3.2-1 and 2.3.2-2 as ASME Code Section III.

Each component listed in Table 2.3.2-1 as ASME Code Section III is fabricated in accordance with the VEGP Updated Final Safety Analysis Report (UFSAR) and the ASME Code Section III requirements. The ASME Code Section III certified Design Reports for these components exist and document that the as-built components conform to the approved design details. The ASME Section III Design Report for each component is documented in the component's completed ASME Section III Code Data Report. The individual component ASME Section III Code Data Reports are documented on the ASME Section III N-5 Code Data Report(s) for the applicable piping system (Reference 1).

The as-built piping listed in Table 2.3.2-2 including the components listed in Table 2.3.2-1 as ASME Code Section III, are subjected to a reconciliation process (Reference 2), which verifies that the as-built piping are analyzed for applicable loads (e.g. stress reports) and for compliance with all design specification and Code provisions. Design reconciliation ofthe as-built systems, including installed components, validates that construction completion, including field changes and any nonconforming condition dispositions, is consistent with and bounded bythe approved design. All applicable fabrication, installation and testing records, as well as, those for the related Quality Assurance (OA) verification/inspection activities, which confirm adequate construction in compliance with the ASME Code Section III and design provisions, are referenced in the N-5 data report and/or its sub-tier references.

The applicable ASME Section III N-5 Code Data Report(s), which include the location ofthe certified Design Reports for all the components listed in Table 2.3.2-1 (Attachment A) and piping listed inTable 2.3.2-2 (Attachment B) as ASME Code Section III, exist and conclude that these installed components are designed and constructed (including their installation within the applicable as-built piping system) in accordance with the ASME Code (1998 Edition, 2000 Addenda and 1989 Edition, 1989 Addenda),Section III requirements as applicable, as described in UFSAR Subsection 5.2.1 (Reference 3). The N-5 Code Data Reports for the piping system(s) containing the components listed in theTable 2.3.2-1 and Table 2.3.2-2 are identified in Attachments A and B, respectively.

3.a and 3.b1 A reoort exists and concludes that the ASME Code Section III reouirements are met for non-destructive examination of pressure boundarv welds.

Inspections are performed in accordance with ASME Code Section III (1998 Edition, 2000 Addenda) to demonstrate that as-built pressure boundary welds in components identified in Table 2.3.2-1 as ASME Code Section III meet ASME Code Section III requirements (i.e., no unacceptable indications).

The applicable non-destructive examinations (including liquid penetrant, magnetic particle, radiographic, and ultrasonic testing, as required by ASME Code Section III) of the components' pressure boundary welds are documented in the Non-destructive Examination Report(s), which support completion of the respective ASME Section III N-5 Code Data Report(s) certified by the Authorized Nuclear Inspector, as listed in Attachment A.

U.S. Nuclear Regulatory Commission ND-18-0545 Enclosure Page 4 of 9 Per ASME Code Section III, Subarticle NCA-8300, "Code Symbol Stamps," the N-5 Code Data Report(s) (Reference 1) documents satisfactory completion of the required examination and testing of the item, which includes non-destructive examinations of pressure boundary welds. Satisfactory completion of the non-destructive examination of pressure boundary welds ensures that the pressure boundary welds in components identified in Table 2.3.2-1 as ASME Code Section III meet ASME Code Section III requirements.

An inspection is performed in accordance with Reference 2 to demonstrate that the as-built pressure boundary welds in piping identified inTable 2.3.2-2 (Attachment B) as ASME Code Section III meet ASME Code Section III requirements (i.e., no unacceptable indications). This portion ofthe ITAAC is complete when the piping identified in Table 2.3.2-2, which is encompassed within the respective piping system Code Symbol N-Stamp and the corresponding piping system Code N-5 Data Report Form(s) (Reference 1), is complete. The non-destructiveexaminations (including visual inspection, liquid penetrant, magnetic particle, radiographic, and ultrasonic testing, as required byASME CodeSection III) ofthe piping pressure boundary welds are documented in the Non-destructive Examination Report(s) within the piping system's supporting data package, which support completion of the respective Code Stamping and Code N-5 Data Report(s). Thecompletion of stamping the respective piping system along with the corresponding ASME Code N-5 Data Report Form(s) (certified by the Authorized Nuclear Inspector) ensure that the piping is constructed in accordance with the design specification(s) and the ASME Code Section III and that the satisfactory completion of the non-destructive examinations of piping pressure boundary weldsforthe pipe linesidentified in Table 2.3.2-2 meet ASME Code Section III requirements and are documented in the Non-destructive Examination Report(s) within the supporting data packages.

4.a and 4.b1 A reoort exists and concludes that the results of the hvdrostatic test of the components and oipina identified in Tables 2.3.2-1 and 2.3.2-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.

Ahydrostatic test is performed by the vendor to demonstrate that the components identified in Table 2.3.2-1 (Attachment A) as ASME Code Section III retain their pressure boundary integrity at their design pressure. The completion of the N-5 Data Reports is governed by Reference 2.

This portion of the ITAAC iscomplete once each component identified in Table 2.3.2-1 hastheir individual Code Symbol N-Stamp andcorresponding Code Data Report (Reference 1) completed, and thecomponents are installed into the respective Code Symbol N-Stamped piping system and documented on the corresponding N-5 Code Data Report(s) (Reference 1).

The hydrostatic testing results of thecomponent's pressure boundary are documented in the Hydrostatic Testing Report(s) within thesupporting component's datapackage, which support completion ofthe respective Code Stamping and Code Data Report(s).

The completion of stamping the individual components andthe respective piping system along with the corresponding ASME Code Data Reports (certified by the Authorized Nuclear Inspector) ensures that the components are constructed in accordance with the Design Specifications and the ASME Code Section III and that the satisfactory completion of the hydrostatic testing of each component identified in Table 2.3.2-1 as ASME Code Section III are documented in the Hydrostatic Testing Report(s) within the supporting data packages and meets ASME Code Section III requirements.

U.S. Nuclear Regulatory Commission ND-18-0545 Enclosure Page 5 of 9 This ITAAC also verifies that the piping identified in Table 2.3.2-2 (Attachment B) fully meets all applicable ASME Code,Section III requirements and retains its pressure boundary integrity at its design pressure.

A hydrostatic test is performed in accordance with procedure XYZ (Reference 4) (as applicable) that complies with the ASME Code (1998 Edition, 2000 Addenda),Section III requirements to demonstrate that the ASME Code Section III piping identified in Table 2.3.2-2 retains its pressure boundary integrity at its design pressure.

A hydrostatic test verifies that there are no leaks at welds or piping, and that the pressure boundary integrity is retained at its design pressure. The hydrostatic testing results of the pipe lines are documented in the Hydrostatic Testing Report(s). The Hydrostatic Testing Report(s) supports completion of the ASME Section III N-5 Code Data Report(s) for the applicable piping system (i.e., CVS) (Reference 1).

The applicable ASME Section III N-5 Code Data Report(s) (Reference 1) identified in Attachments A and B documents that the results of the hydrostatic testing of the components and piping identified in Table 2.3.2-1 and Table 2.3.2-2 respectively conform with the requirements of the Code (1998 Edition, 2000 Addenda), Section 111.

Reference 1 provides the evidence that the ITAAC Acceptance Criteria requirements are met:

• The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.3.2-1 and 2.3.2-2 as ASME Code Section III;

• A report exists and concludes that the ASME Code Section III requirements are met for non-destructive examination of pressure boundary welds; and

• A report exists and concludes that the results of the hydrostatic test of the components and piping identified in Tables 2.3.2-1 and 2.3.2-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.

Reference 1 is available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.3.02.02a Completion Packages (References 5 and 6, respectively).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings and associated corrective actions.

This review, which included now consolidated ITAAC Indexes 286, 287, 288, 289 and 290, found no relevant ITAAC findings associated with this ITAAC.

References (available for NRC inspection)

1. CVS ASME N-5 Code Data Report(s)

2. APP-GW-GAP-139, "WestinghouseA/VECTEC ASME N-5 Interface Procedure"

U.S. Nuclear Regulatory Commission ND-18-0545 Enclosure Page 6 of 9

3. VEGP 3&4 Updated Final Safety Analysis Report, Subsection 5.2.1, Compliance witfi Codes and Code Cases

4. CVS Piping ASME Section III Hydrostatic Test Procedure XYZ

5. Completion Package for Unit 3 ITAAC 2.3.02.02a [COL Index Number 285]

6. Completion Package for Unit 4 ITAAC 2.3.02.02a [COL Index Number 285]

7. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-18-0545 Enclosure Page 7 of 9 Attachment A SYSTEM: Chemical and Volume Control System (CVS)

ASME Code Equipment Name

• Tag No.

• N-5 Report Section ill*

RCS Purification Motor-operated Isolation CVS N-5 Code CVS-PL-V001 Yes Valve Data Report RCS Purification Motor-operated Isolation CVS N-5 Code CVS-PL-V002 Yes Valve Data Report RCS Purification Motor-operated Isolation CVS N-5 Code CVS-PL-V003 Yes Valve Data Report CVS N-5 Code CVS Resin Flush Line Containment CVS-PL-V040 Yes Isolation Valve Data Report CVS N-5 Code CVS Resin Flush Line Containment CVS-PL-V041 Yes Isolation Valve Data Report CVS Demineralizer Resin Flush Line CVS N-5 Code Containment Isolation Thermal Relief CVS-PL-V042 Yes Data Report Valve CVS N-5 Code CVS-PL-V045 Yes CVS Letdown Containment Isolation Valve Data Report CVS N-5 Code CVS-PL-V047 Yes CVS Letdown Containment Isolation Valve Data Report CVS Letdown Line Containment Isolation CVS N-5 Code CVS-PL-V058 Yes Thermal Relief Valve Data Report CVS Makeup Return Line Bypass Check CVS N-5 Code CVS-PL-V067 Yes Valve Data Report CVS Purification Return Line Pressure CVS N-5 Code CVS-PL-V080 Yes Boundary Check Valve Data Report CVS Purification Return Line Pressure CVS N-5 Code CVS-PL-V081 Yes Boundary Isolation Check Valve Data Report CVS Purification Return Line Pressure CVS N-5 Code CVS-PL-V082 Yes Boundary Check Valve Data Report CVS Auxiliary Pressurizer Spray Line CVS N-5 Code CVS-PL-V084 Yes Pressure Boundary Valve Data Report CVS Auxiliary Pressurizer Spray Line CVS N-5 Code CVS-PL-V085 Yes Pressure Boundary Check Valve Data Report CVS N-5 Code CVS Makeup Line Containment Isolation CVS-PL-V090 Yes Motor-operated Valve Data Report CVS N-5 Code CVS Makeup Line Containment Isolation CVS-PL-V091 Yes Motor-operated Valve Data Report CVS Zinc Injection Containment Isolation CVS N-5 Code CVS-PL-V092 Yes Valve ORC Data Report CVS Zinc Injection Containment Isolation CVS N-5 Code CVS-PL-V094 Yes Valve IRC Data Report CVS Zinc Addition Line Ctmt Isol Thermal CVS N-5 Code CVS-PL-V098 Yes Relief Valve Data Report

U.S. Nuclear Regulatory Commission ND-18-0545 Enclosure Page 8 of 9 Attachment A SYSTEM: Chemical and Volume Control System (CVS)

ASME Code Equipment Name

• Tag No.

• N-5 Report Section ill*

CVS Makeup Line Containment Isolation CVS N-5 Code CVS-PL-V100 Yes Thermal Relief Valve Data Report CVS N-5 Code CVS Demineralized Water Isolatbn Valve CVS-PL-V136A Yes Data Report CVS N-5 Code CVS Demineralized Water Isolation Valve CVS-PL-V136B Yes Data Report CVS Hydrogen InjectionContainment CVS N-5 Code CVS-PL-V217 Yes Isolation Check Valve IRC Data Report CVS Hydrogen Injection Containment CVS N-5 Code CVS-PL-V219 Yes Isolation Valve ORC Data Report

'Excerpts from COL Appendix C Table 2.3.2-1

U.S. Nuclear Regulatory Commission ND-18-0545 Enclosure Page 9 of 9 Attachment B SYSTEM; Chemical and Volume Control System (CVS)

ASMECode Line Name* Line Number* N-5 Report Section III*

L001 Yes CVS N-5 Code Data Report CVS Purification Line L040 Yes CVS Resin Flush Containment L026+ Yes CVS N-5 Code Data Report Penetration Line CVS Purification Line Return L038 Yes CVS N-5 Code Data Report CVS Pressurizer Auxiliary Spray L070+ Yes CVS N-5 Code Data Report Connection L071 + Yes CVS Letdown Containment CVS N-5 Code Data Report L051 + Yes Penetration Line CVS Makeup Containment L053 Yes CVS N-5 Code Data Report Penetratton Line CVS Hydrogen Injection L213+

Containment Penetration L214+ Yes CVS N-5 Code Data Report Line L217+

CVS Zinc Injection Containment L061 + Yes CVS N-5 Code Data Report Penetration Line CVS Return Line from Regenerative Heat L036 Yes CVS N-5 Code Data Report Exchanger

• Excerpts from COL Appendix C, Table 2.3.2-2

+ For girth fillet welds between piping and socket welded fittings, valves and flanges, refer to VEGP UFSAR Section 5.2.1.1 (Reference 3).