ND-18-0554, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.07.02a (Index Number 392)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.07.02a (Index Number 392)

ML18117A296
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
ITAAC 2.3.07.02a, ND-18-0554
Download: ML18117A296 (10)

Text

Michael J. Yox 7825 River Road

^ Southern Nuclear Regulatory Affairs Director Waynestraro, GA 30830 706-848-6459 tei Vogtie 3 & 4 410-474-8587 ceii myox@southernco.com APR 2 A 2018 Docket Nos.: 52-025 52-026 ND-18-0554 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.07.02a [Index Number 3921 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, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.07.02a [Index Number 392]

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.

He Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.07.02a [Index Number 392]

MJY/KJD/amw

U.S. Nuclear Regulatory Commission ND-18-0554 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. B. 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. Convert Oalethorpe Power Corporation Mr. R. B. Brinkman Municipal Electric Authoritv of Georgia Mr. J. E. Fuller

U.S. Nuclear Regulatory Commission ND-18-0554 Page 3 of 3 Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (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. Deangells Other Mr. J. E. Hesler, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

Mr. 8. Roetger, Georgia PublicService Commission Ms. 8. W. Kernlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-18-0554 Enclosure Page 1 of 7 Southern Nuclear Operating Company ND-18-0554 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.07.02a [Index Number 392]

U.S. Nuclear Regulatory Commission ND-18-0554 Enclosure Page 2 of 7 ITAAC Statement Deslon Commitment:

2.a) The components identified inTable 2.3.7-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.

2.b) The piping lines identified in Table 2.3.7-2 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.

3. Pressure boundary welds in piping lines identified in Table 2.3.7-2 as ASME Code Section III meet ASME Code Section III requirements.

4. The piping lines identified in Table 2.3.7-2 as ASME Code Section III retain their pressure boundary integrity at their design pressure.

Insoections. Tests. Analyses:

Inspection will be conducted of the ASME as-built components and piping lines 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 ill.

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

Acceotance Criteria:

The ASME Code Section III design reports existfor the as-built components and piping lines identified in Tables 2.3.7-1 and 2.3.7-2 as ASME Code Section III.

Areport exists and concludes 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 piping lines identified in Table 2.3.7-2 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 Spent Fuel Pool Cooling System (SFS) components and piping lines listed in the Combined License (COL) Appendix C, Table 2.3.7-1 (Attachment A) and Table 2.3.7-2 (Attachment B) that are identified as American Society of Mechanical Engineers (ASME) Code Section ill, are designed and constructed in accordance with applicable requirements.

U.S. Nuclear Regulatory Commission ND-18-0554 Enclosure Page 3 of 7 2.a and 2.b) The ASME Code Section III design reports exist for the as-built components and oioina lines identified in Tables 2.3.7-1 and 2.3.7-2 as ASME Code Section III.

Each component listed in Table 2.3.7-1 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 piping lines listed in Table 2.3.7-2 including the components listed in Table 2.3.7-1 as ASME Code Section III, are subjected to a reconciliation process (Reference 2), which verifies that the as-built piping lines 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 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 2.3.7-1 (Attachment A) and piping lines listed in Table2.3.7-2 (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 the Table 2.3.7-1 and Table 2.3.7-2 are identified in Attachments A and B, respectively.

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

An inspection is performed in accordance with Reference 2to demonstrate that the as-built pressure boundary welds in piping lines identified in Table 2.3.7-2 (Attachment B) as ASME Code Section III meet ASME Code Section III requirements (i.e., no unacceptable indications).

This portion of the ITAAC is complete when the piping lines identified in Table 2.3.7-2, 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-destructive examinations (including visual inspection, liquid penetrant, magnetic particle, radiographic, and ultrasonic testing, as required by ASME Code Section III) of the piping lines 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). The completion 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 lines are constructed in accordancewith the design specification(s) andtheASME Code Section III andthat the satisfactory completion

U.S. Nuclear Regulatory Commission ND-18-0554 Enclosure Page 4 of 7 of the non-destructive examinations of piping pressure boundary welds for the pipe lines identified in Table 2.3.7-2 meet ASME Code Section III requirements and are documented in the Non-destructive Examination Report(s) within the supporting data packages.

4. A report exists and concludes that the results of the hvdrostatic test of the pioing lines identified in Table 2.3.7-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.

This ITAAC verifies that the piping lines identified in Table 2.3.7-2 (Attachment B) fully meets all applicable ASME Code,Section III requirements and retains its pressure boundary integrity at its design pressure.

Ahydrostatic test is performed in accordance with procedure XYZ (Reference 4) (asapplicable) thatcomplies with the ASME Code (1998 Edition, 2000 Addenda),Section III requirements to demonstrate that the ASME Code Section III piping lines identified in Table 2.3.7-2 retains its pressure boundary integrity at its design pressure.

Ahydrostatic testverifies that there are no leaks at welds or piping lines, 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., SFS) (Reference 1).

The applicable ASME Section III N-5 Code Data Report(s) (Reference 1) identified in Attachment B documentsthat the results ofthe hydrostatic testing of the piping lines identified in Table 2.3.7-2 conform with the requirements of the Code (1998 Edition, 2000 Addenda),Section III.

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

• TheASME Code Section III design reports exist for the as-built components and piping lines identified in Tables 2.3.7-1 and 2.3.7-2 as ASME Code Section III;

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

• Areport exists and concludes that the results of the hydrostatic test of piping lines identified in Table 2.3.7-2 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 2.3.07.02a 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 393, 394 and 395found no relevant ITAAC findings associated with this ITAAC:

U.S. Nuclear Regulatory Commission ND-18-0554 Enclosure Page 5 of 7 References (available for NRC Inspection)

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

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

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

4. SFS Piping Line ASME Section III Hydrostatic Test Procedure XYZ

5. Completion Package for Unit 3 ITAAC 2.3.07.02a [COL Index Number 392]

6. Completion Package for Unit 4 ITAAC 2.3.07.02a [COL Index Number392]

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

U.S. Nuclear Regulatory Commission ND-18-0554 Enclosure Page 6 of 7 Attachment A SYSTEM: Spent Fuel Pool Cooling System (SFS)

ASME Code Component Name

• Tag No.

• N-5 Report Section ill*

Refueling Cavity Drain to SGS Compartment SFS-PL-V031 Yes SFS N-5 Code Data Report Isolation Valve Refueling Cavity to SFS Pump Suction Isolation SFS-PL-V032 Yes SFS N-5 Code Data Report Valve Refueling Cavity Drain to Containment Sump SFS-PL-V033 Yes SFS N-5 Code Data Report Isolation Valve IRWSTto SFS Pump Suction Line Isolation SFS-PL-V039 Yes SFS N-5 Code Data Report Valve Fuel Transfer Canal to SFS Pump Suction Iso. SFS-PL-V040 Yes SFS N-5 Code Data Report Valve Cask Loading Pit to SFS Pump Suction Isolation SFS-PL-V041 Yes SFS N-5 Code Data Report Valve Cask Loading Pit to SFS Pump Suction Isolation SFS-PL-V042 Yes SFS N-5 Code Data Report Valve SFS Pump Discharge Line to Cask Loading Pit SFS-PL-V045 Yes SFS N-5 Code Data Report Isolation Valve Cask Loading Pit to SFS-PL-V049 Yes SFS N-5 Code Data Report WLS Isolation Valve Spent Fuel Pool to Cask Washdown Pit Isolation SFS-PL-V066 Yes SFS N-5 Code Data Report Valve Cask Washdown Pit Drain Yes SFS N-5 Code Data Report SFS-PL-V068 Isolation Valve Refueling Cavity Drain SFS-PL-V071 Yes SFS N-5 Code Data Report Line Check Valve Refueling Cavity Drain SFS-PL-V072 Yes SFS N-5 Code Data Report Line Check Valve SFS Containment Floodup SFS-PL-V075 Yes SFS N-5 Code Data Report Isolation Valve

'Excerpts from COL Appendix C Table 2.3.7-1

U.S. Nuclear Regulatory Commission ND-18-0554 Enclosure Page 7 of 7 Attachment B SYSTEM: Spent Fuel Pool Cooling System (SFS)

Line ASME Code Piping Line Name* N-5 Report Number* Section III*

Spent Fuel Pool to RNS Pump SFS N-5 Code Data L014 Yes Suction Report Cask Loading Pit to RNS Pump SFS N-5 Code Data L115 Yes Suction Report SFS N-5 Code Data Refueling Cavity Drain L033+ Yes Report PXS IRWST to SFS Pump SFS N-5 Code Data L035 Yes Suction Report Refueling Cavity Skimmer to SFS SFS N-5 Code Data L036 Yes Pump Suction Report SFS N-5 Code Data Refueling Cavity Drain L037 Yes Report SFS N-5 Code Data Refueling Cavity Drain L044+ Yes Report SFS N-5 Code Data Fuel Transfer Canal Drain L047 Yes Report SFS N-5 Code Data Cask Washdown Pit Drain L068 Yes Report SFS N-5 Code Data Cask Loading Pit Drain L043 Yes Report SFS N-5 Code Data Cask Pit Transfer Branch Line L045 Yes Report Spent Fuel Pool Containment SFS N-5 Code Data L052+ Yes Isolation Thermal Relief Line Report SFS N-5 Code Data Refueling Cavity Drain L030 Yes Report SFS N-5 Code Data Upender Pit Drain/Fill Line LI 21 Yes Report SFS N-5 Code Data Spent Fuel Pool Drain L066+ Yes Report SFS N-5 Code Data Cask Loading Pit to WLS L067+ Yes Report SFS N-5 Code Data RNS Return to Spent Fuel Pool LI 00 Yes Report SFS N-5 Code Data SFS Containment Floodup Line LI 20 Yes Report

• Excerpts from COL Appendix C, Table 2.3.7-2

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