ND-18-0178, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.13.02 (Index Number 459)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.13.02 (Index Number 459)

ML18051A717
Person / Time
Site:	Vogtle
Issue date:	02/19/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0178
Download: ML18051A717 (10)

Text

Michael J. Yox 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830

^ Southern Nuclear Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell myox @southernco.com FES 1J2018 Docket Nos.: 52-025 52-026 ND-18-0178 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 2.3.13.02 [Index Number 4591 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of February 16, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.13.02 [Index Number 459] 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 later date, 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, or analyses 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 priorto 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

U.S. Nuclear Regulatory Commission ND-18-0178 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.13.02 [Index Number 459]

MJY/KJD/amw

U.S. Nuclear Regulatory Commission ND-18-0178 Page 3 of 4 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. Vox Mr. D. L. Fulton Mr. J. D. Williams Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. 0. E. Morrow Ms. K. M. Stacy Mr. M. K. Wastiington 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. T. C. Brimfield Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Oalethoroe Power Corporation Mr. R. B. Brinkman Municipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros

U.S. Nuclear Regulatory Commission ND-18-0178 Page 4 of 4 Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. C. 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. Hesler, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

Mr. 8. Roetger, Georgia Public Service Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-18-0178 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-18-0178 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.13.02 [Index Number 459]

U.S. Nuclear Regulatory Commission ND-18-0178 Enclosure Page 2 of 6 ITAAC Statement Desion Commitment:

2. The components identified In Table 2.3.13-1 as ASME Code Section ill are designed and constructed in accordance with ASME Code Section ill requirements.

3. Pressure boundary welds in components identified in Table 2.3.13-1 as ASME Code Section III meet ASME Code Section III requirements.

4. The components identified in Table 2.3.13-1 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 inthe 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 wili be performed on the components required bythe ASME Code Section ili to be hydrostatically tested.

Acceptance Criteria:

The ASME Code Section Ili design reports exist for the as-built components identified in Table 2.3.13-1 as ASME Code Section lil.

A report existsand concludes that the ASME Code Section III requirements are met for non destructive examination of pressure boundary welds.

A report existsand concludes that the results ofthe hydrostatic test ofthe components identified in Table 2.3.13-1 as ASME Code Section III conform with the requirements of the ASME Code Section III.

ITAAC Completion Description This ITAAC requires inspections, tests, and anaiyses be performed and documented to ensure the Primary Sampling System (PSS) components iisted in the Combined License (COL)

Appendix C, Tabie2.3.13-1 (Attachment A) that are identified as American Society of Mechanicai Engineers (ASME) Code Section ill are designed and constructed in accordance with applicable requirements.

U.S. Nuclear Regulatory Commission ND-18-0178 Enclosure Page 3 of 6

2. The ASME Code Section III design reoorts exist for the as-built components Identified in Table 2.3.13-1 as ASME Code Section III.

Each component listed in Table 2.3.13-1 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) forthe applicable piping system (Reference 1).

The as-built components listed in Table 2.3.13-1 as ASME Code Section III, are subjected to a reconciliation process (Reference2), which verifies that the as-built components 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 2.3.13-1 (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 Section III (1998 Edition, 2000 Addenda) requirements. The N-5 Code Data Reports for the the components listed in the Table 2.3.13-1 are identified in Attachment A.

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

Inspections are performed in accordance with ASME CodeSection III (1998 Edition, 2000 Addenda) to demonstrate that as-built pressure boundary welds in components identified in Table 2.3.13-1 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-18-0178 Enclosure Page 4 of 6 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 2.3.13-1 as ASME Code Section III meet ASME Code Section III requirements.

4. A report exists and concludes that the results of the hvdrostatic test of the components identified in Table 2.3.13-1 as ASME Code Section III conform with the reouirements of the ASME Code Section III.

Ahydrostatic test is performed bythe vendor to demonstrate that the components identified in Table 2.3.13-1 (Attachment A) as ASME Code Section III retain their pressure boundaryintegrity at theirdesign pressure. The completion ofthe N-5 Data Reports is governed by Reference 2.

This ITAAC is complete once each component identified inTable 2.3.13-1 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 piping systemand documented on the corresponding N-5 Code Data Report(s) (Reference 1). The hydrostatic testing results of the component's pressure boundary are 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 and the respective piping system along with the corresponding ASME Code Data Reports (certified by the Authorized Nuclear Inspector) ensures that the components are constructed in accordancewith 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 2.3.13-1 as ASME CodeSection III are documented in the Hydrostatic Testing Report(s) within the supporting data packages and meets ASME Code Section III requirements.

Reference 1 provides the evidence that the ITAAC Acceptance Criteria requirementsare met:

The ASME Code Section III design reports existfor the as-built components identified in Table 2.3.13-1 as ASME Code Section III;

• Areport exists and concludes thatthe ASME Code Section III requirements are met for non-destructive examination of pressure boundary welds; and

• A reportexists and concludes that the results of the hydrostatic test of the components identified in Table 2.3.13-1 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 2.3.13.02 Completion Packages (References 3 and 4, respectively).

U.S. Nuclear Regulatory Commission ND-18-0178 Enclosure Page 5 of 6 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 460 and 461 found no relevant ITAAC findings associated with this ITAAC.

References (available for NRC inspection)

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

2. APP-GW-GAP-139, "Westinghouse/WECTEC ASME N-5 Interface Procedure"

3. Completion Package for Unit 3 ITAAC 2.3.13.02 [COL Index Number 459]

4. Completion Package for Unit 4 ITAAC 2.3.13.02 [COL Index Number 459]

5. NEI 08-01, "Industry Guideline forthe ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-18-0178 Enclosure Page 6 of 6 ATTACHMENT A SYSTEM: Primary Sampling System (PSS)

ASME Code Equipment Name

• Tag No.

• N-5 Report Section III

• Containment Air Sample Containment Isolation Valve Inside PSS-PL-V008 Yes N-5 Code Data Report Reactor Containment (IRC)

Liquid Sample Line Containment PSS-PL-V010A Yes N-5 Code Data Report Isolation Valve IRC Liquid Sample Line Containment PSS-PL-V010B Yes N-5 Code Data Report Isolation Valve IRC Liquid Sample Line Containment Isolation Valve Outside Reactor PSS-PL-V011A Yes N-5 Code Data Report Containment (ORC)

Liquid Sample Line Containment PSS-PL-V011B Yes N-5 Code Data Report Isolation Valve ORC Sample Return Line Containment PSS-PL-V023 Yes N-5 Code Data Report Isolation Valve ORC Sample Return Containment Isolation PSS-PL-V024 Yes N-5 Code Data Report Valve IRC Air Sample Line Containment PSS-PL-V046 Yes N-5 Code Data Report Isolation Valve ORC

'Excerpt from COL Appendix C Table 2.3.13-1