ND-21-0796, ITAAC Closure Notification on Completion of ITAAC 2.1.03.03 (Index Number 72)

ITAAC Closure Notification on Completion of ITAAC 2.1.03.03 (Index Number 72)

ML22047A309
Person / Time
Site:	Vogtle
Issue date:	02/16/2022
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-0796
Download: ML22047A309 (9)

Text

Michael J, Vox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel Docket No.: 52-025 FEB 1 6 2022 ND-21-0796 10CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.1.03.03 [Index Number 721 Ladies and Gentlemen:

In accordance with 10 CFR 52.99(c)(1), the purpose of this letter Is to notify the Nuclear Regulatory Commission (NRC)of the completion of Vogtle Electric Generating Plant(VEGP) Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.03.03 [Index Number 72].

This ITAAC verifies the following for the Reactor System:(1) that the American Society of Mechanical Engineers(ASME) Code Section III design reports exist for the as-built components identified in the Combined Operating License (COL) Appendix C, Table 2.1.3-1 Reactor System (RXS) as ASME Code Section III. (2) A report exists and concludes that the ASME Code Section III requirements are met for nondestructive examination of pressure boundary welds, and (3) a report exists and concludes that the results of the hydrostatic test of the pressure boundary components (Reactor Vessel, Control Rod Drive Mechanisms, and incore instrument QuickLoc assemblies) conform with the requirements of the ASME Code Section III. The closure process for this ITAAC is based on the guidance described in Nuclear Energy Institute (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.

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99.

If there are any questions, please contact Kelli A. Roberts at 706-848-6991.

Respectfully submitted.

Michael J. Vox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.1.03.03 [Index Number 72]

MJY/JRV/sfr

U.S. Nuclear Regulatory Commission ND-21-0796 Enclosure Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKinney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. J.B. Williams Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Ms. J.M. Coleman Mr. C. T. Defnall Mr. C. E. Morrow Mr. K. J. Drudy Mr. J. M. Fisher Mr. R. L. Beiike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reoulatorv Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil Mr. C. P. Patel Mr. G. J. Khouri Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. O. Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Mr. T. Fanelli Ms. K. McCurry Mr. J. Parent Mr. B. Griman Mr. V. Hall

U.S. Nuclear Regulatory Commission ND-21-0796 Enclosure Page 3 of 3 Oqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani Mr. D. C. Durham Mr. M. M. Corletti Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. 8. W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

Mr. 8. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-21-0796 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-21-0796 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.1.03.03[Index Number 72]

U.S. Nuclear Regulatory Commission ND-21-0796 Enclosure Page 2 of 6 ITAAC Statement Design Commitment:

3. The components identified in Table 2.1.3-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.

4. Pressure boundary welds in components identified in Table 2.1.3-1 as ASME Code Section III meet ASME Code Section III requirements.

5. The pressure boundary components(RV, CRDMs,and incore instrument QuickLoc assemblies) identified in Table 2.1.3-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.

Inspections. Tests. Analyses:

Inspection will be conducted of the as-built components 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.

A hydrostatic test will be performed on the components of the RXS required by the ASME Code Section III to be hydrostatically tested.

Acceptance Criteria:

The ASME Code Section III design reports exist for the as-built components identified in Table 2.1.3-1 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.

A report exists and concludes that the results of the hydrostatic test of the pressure boundary components(RV, CRDMs, and incore instrument QuickLoc assemblies) conform with the requirements of the ASME Code Section III.

ITAAC Determination Basis This ITAAC requires inspections, tests, and analyses be performed and documented to ensure the Reactor System (RXS)components listed in the Combined License(COL) Appendix C, Table 2.1.3-1 (Attachment A)that are identified as American Society of Mechanical Engineers (ASME)Code Section III are designed and constructed in accordance with applicable requirements.

3. The ASME Code Section III design reports exist for the as-built components identified in Table 2.1.3-1 as ASME Code Section III.

Each component listed in Table 2.1.3-1 as ASME Code Section III was 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

U.S. Nuclear Regulatory Commission ND-21-0796 Enclosure Page 3 of 6 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 components listed in Table 2.1.3-1 as ASME Code Section III, were subjected to a reconciliation process(Reference 2), which verifies that the as-built components were analyzed for applicable loads (e.g. stress reports) and for compliance with all design specification and Code provisions. Design reconciliation of the as-built systems, including installed components, validates that construction completion, including field changes and any nonconforming condition dispositions, are consistent with and bounded by the 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 of the certified Design Reports for all the components listed in Table 2.1.3-1 (Attachment A) 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),Section III requirements as described in subsection 5.2.1 of the UFSAR (Reference 3). The N-5 Code Data Reports for the components listed in the Table 2.1.3-1 are identified in Attachment A.

4. A report exists and concludes that the ASME Code Section III requirements are met for non-destructive examination of pressure boundarv welds.

Inspections were 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 2.1.3-1 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 were 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.

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 2.1.3-1 as ASME Code Section III met ASME Code Section III requirements.

5. A report exists and concludes that the results of the hvdrostatic test of the pressure boundarv components(RV. CRDMs. and incore instrument QuickLoc assemblies) conform with the reouirements of the ASME Code Section III.

A hydrostatic test was performed by the vendor to demonstrate that the components(RV, CRDMs, and incore instrument QuickLoc assemblies) identified in Table 2.1.3-1 (Attachment A) as ASME Code Section III retain their pressure boundary integrity at their design pressure. A

U.S. Nuclear Regulatory Commission ND-21-0796 Enclosure Page 4 of 6 hydrostatic test verifies that there were no leaks at welds and that the pressure boundary Integrity was retained at Its design pressure. The completion of the N-5 Data Reports Is governed by Reference 2.

This portion of the ITAAC was complete once each component identified In Table 2.1.3-1 has their Individual Code Symbol N-Stamp and corresponding Code Data Report(Reference 1) completed, and the components are Installed Into the respective Code Symbol N-Stamped system and documented on the corresponding N-5 Code Data Report(s)(Reference 1). The hydrostatic testing results of the component's pressure boundary were documented In the Hydrostatic Testing Report(s) within the supporting component's data package, which support completion of the respective Code Stamping and Code Data Report(s).

The completion of stamping the Individual components 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 pressure testing of each component Identified In Table 2.1.3-1 as ASME Code Section III were documented In the Hydrostatic Testing Report(s) within the supporting data packages and met ASME Code Section III requirements.

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

• The ASME Code Section III design reports exist for the as-bullt components Identified In Table 2.1.3-1 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 weld; and A report exists and concludes that the results of the hydrostatic test of the pressure boundary components(RV, CRDMs,and Incore Instrument QuIckLoc assemblies) conform with the requirements of the ASME Code Section III.

This ITAAC also verified that the required Inspections for Preservlce Inspection (PSI) have been completed (Reference 5)for the applicable portions of the Reactor System (RXS) Identified In Tables 2.T3-1 of the Vogtle COL, Appendix C, and concludes that the results of the PSI examinations meet the acceptance standards specified In the applicable Boiler and Pressure Vessel(B&PV) Codes for the examinations performed.

Examinations are conducted for each system In accordance with Section XI of the ASME B&PV Code, Subsections IWB, IWC, and IWD to satisfy the requirements for PSI for ITAAC 2.1.03.03

[Index Number 72].

References 1 and 4 are available for NRC Inspection as part of the Unit 3 ITAAC 2.1.03.03 Completion Package (Reference 6).

ITAAC Finding Review In accordance with plant procedures for ITAAC completion. Southern Nuclear Operating Company(SNC) performed a review of all ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This review, which Included now consolidated ITAAC Indexes 73 and 74,found no relevant ITAAC findings associated with this ITAAC. The ITAAC completion

U.S. Nuclear Regulatory Commission ND-21-0796 Enclosure Page 5 of 6 review is documented in the ITAAC Completion Package for ITAAC 2.1.03.03(Reference 6) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.1.03.03 was performed for VEGP Unit 3 and that the prescribed acceptance criteria were met.

Systems,structures, and components verified as part of this ITAAC are being maintained in their as designed, ITAAC compliant condition in accordance with approved plant programs and procedures.

References(available for NRC Inspection)

1. SV3-RCS-MUR-001, Rev. 0,"API000 Vogtle Unit 3 ASME Section III System Code Data Report for the Reactor Coolant System (RCS)"

2. APP-GW-GAP-139, Rev. 8,"Westinghouse/Stone & Webster ASME Code Data Report and As-Built Documentation Interface Procedure"

3. VEGP 3&4 Updated Final Safety Analysis Report, Rev. 10.1, Subsection 5.2.1, Compliance with Codes and Code Cases

4. SV3-RCS-S3R-001, Rev. 0,"Vogtle Unit 3 Reactor Coolant System (RCS) ASME Section III As-Built Piping System Design Reporf

5. APE-10-00020,"Unit 3 - Completion of Preservice Inspection for RXS Class 1, 2, and 3 Portions of Systems"

6. 2.1.03.03-U3-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-21-0796 Enclosure Page 6 of 6 Attachment A SYSTEM: Reactor System (RXS)

ASME Section III ASME Code Equipment As-Built Piping Tag No. Section iii N-5 Report Name

• System Design Classification' Report RV RXS-MV-01 Yes SV3-RCS-S3R-001 SV3-RCS-MUR-001 Reactor Upper Internals RXS-MI-01 Yes SV3-RCS-S3R-001 SV3-RCS-MUR-001 Assembly Reactor Lower Internals RXS-MI-02 Yes SV3-RCS-S3R-001 SV3-RCS-MUR-001 Assembly RXS-MV-11806/11B08/11810

/11C05/11C07/11C09/11C11/

11D04/11D06/11D08/11D10/

11D12/11E03/11E05/11E07/

11E09/11E11/11E13/11F02/

11F04/11F06/11F08/11F10/

11F12/11F14/11G03/11G05/

Control Rod Drive 11G07/11G09/11G11/11G13/

Mechanisms 11H02/11H04/11H06/11H08/

Yes SV3-RCS-S3R-001 SV3-RCS-MUR-001 (CRDMs) 11H10/11H12/11H14/11J03/

(69 Locations) 11J05/11J07/11J09/11J11/

11J13/11K02/11K04/11K06/

11K08/11K10/11K12/11K14/

11L03/11L05/11L07/11L09/

11L11/11L13/11M04/11M06/

11M08/11 Ml0/11 Ml2/11N05/

11N07/11N09/11N11/11P06/

11P08/11P10 Incore Instrument QuickLoc RXS-MY-Y11 through Y18 Yes SV3-RCS-S3R-001 SV3-RCS-MUR-001 Assemblies (8 Locations)

'Excerpt from COL Appendix C Table 2.1.3-1