ND-21-0621, Vogtie Electric Generating Plant, Unit 3 - ITAAC Closure Notification on Completion of ITAAC 2.2.05.02a (Index Number 253)

Vogtie Electric Generating Plant, Unit 3 - ITAAC Closure Notification on Completion of ITAAC 2.2.05.02a (Index Number 253)

ML21217A285
Person / Time
Site:	Vogtle
Issue date:	08/05/2021
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-0621
Download: ML21217A285 (12)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Vogtie 3 & 4 Waynesboro, GA 30830 706-848-6459 tel Docket Nos.: 52-025 AU6 0 5 2021 ND-21-0621 10 CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.2.05.02a [Index Number 2531 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 Vogtie Electric Generating Plant(VEGP)

Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.05.02a [Index Number 253]. This ITAAC verifies the following for the Main Control Room Emergency Flabitability System (VES): (1) American Society of Mechanical Engineers(ASME) Code Section III design reports exist for the as-built components and piping identified in the Combined License (COL) Appendix C, Tables 2.2.5-1 and 2.2.5-2 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. (3) A report exists and concludes that the results of the pressure test of the components and piping identified in Tables 2.2.5-1 and 2.2.5-2 as ASME Code Section III conform with the requirements of the ASME Code Section III, and (4) a report exists and concludes that each of the as-built lines identified in Table 2.2.5-2 for which functional capability is required meets the requirements for functional capability. 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. Yox Regulatory Affairs Director Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.2.05.02a [Index Number 253]

MJY/JRV/sfr

U.S. Nuclear Regulatory Commission ND-21-0621 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKinney Mr. M. D. Meier Mr. G. Chick Mr. 8. Stimac Mr. P. Martino Mr. M. J. Yox Mr. A. 8. Parton Ms. K. A. Roberts Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. M. Fisher Mr. R. L. Belike Mr. 8. 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 M . C. P. Patei M . G. J. Khouri M . C. J. Even M B. J. Kemker Ms. N. C. Coovert M . C. Welch M . J. Gaslevic M . O. Lopez-Santiago M G. Armstrong M M. Webb M T. Fredette M C. Santos M B. Davis M . J. Vasquez M J. Eargie M E. Davidson M . T. Faneiii Ms. K. McCurry M . J. Parent M . B. Griman

U.S. Nuclear Regulatory Commission ND-21-0621 Page 3 of 3 Qqlethorpe 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 Westinqhouse Electric Company. LLC Dr. L. Oriani Mr. D. 0. Durham Mr. M. M. Corletti Mr. Z.S. 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., GDS 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-21-0621 Enclosure Page 1 of 9 Southern Nuclear Operating Company ND-21-0621 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.2.05.02a [Index Number 253]

U.S. Nuclear Regulatory Commission ND-21-0621 Enclosure Page 2 of 9 ITAAC Statement Design Commitment:

2.a) The components identified in Table 2.2.5-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.

2.b) The piping identified in Table 2.2.5-2 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 2.2.5-1 as ASME Code Section III meet ASME Code Section III requirements.

3.b) Pressure boundary welds in piping identified in Table 2.2.5-2 as ASME Code Section III meet ASME Code Section III requirements.

4.a) The components identified in Table 2.2.5-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.

4.b) The piping identified in Table 2.2.5-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.

5.b) Each of the lines identified in Table 2.2.5-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability.

Inspections. 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.

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

Inspection will be performed for the existence of a report verifying that the as-built piping meets the requirements for functional capability.

Acceptance Criteria:

The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.2.5-1 and 2.2.5-2 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.

U.S. Nuclear Regulatory Commission ND-21-0621 Enclosure Page 3 of 9 A report exists and concludes that the results of the pressure test of the components and piping identified in Tables 2.2.5-1 and 2.2.5-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.

A report exists and concludes that each of the as-built lines identified in Table 2.2.5-2 for which functional capability is required meets the requirements for functional capability.

ITAAC Determination Basis This ITAAC requires inspections, tests, and analyses be performed and documented to ensure the Main Control Room Emergency Habitability System (VES)components and piping listed in the Combined License(COL) Appendix C, Table 2.2.5-1 (Attachment A)and Table 2.2.5-2 (Attachment B)that are identified as American Society of Mechanical Engineers(ASME)Code Section III or Functional Capability Required are designed and constructed in accordance with applicable requirements.

2.a and 2.b) The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.2.5-1 and 2.2.5-2 as ASME Code Section III.

Inspection of each component listed in Table 2.2.5-1 as ASME Code Section III is performed to demonstrate they are designed and constructed 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 for the applicable piping system (Reference 1).

The as-built piping listed in Table 2.2.5-2 including the components listed in Table 2.2.5-1 as ASME Code Section III, were subjected to a reconciliation process (Reference 2), which verified that the as-built piping was 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, were 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 confirmed 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, which include the location of the certified Design Reports for all the components listed in Table 2.2.5-1 (Attachment A) and piping listed in Table 2.2.5-2 (Attachment B) as ASME Code Section III, exist and conclude that these installed components were 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 Report (Reference 1) for the piping systems containing the components listed in the Table 2.2.5-1 and Table 2.2.5-2 are identified in Attachments A and B, respectively.

U.S. Nuclear Regulatory Commission ND-21-0621 Enclosure Page 4 of 9 3.a and 3.b) A report exists and concludes that the ASME Code Section III reouirements are met for non-destructive examination of pressure boundary 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 2.2.5-1 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 certified by the Authorized Nuclear Inspector (ANI), as listed in Attachment A.

Per ASME Code Section III, Subarticle NCA-8300,"Code Symbol Stamps," the ASME Section III N-5 Code Data Report(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 ensured that the pressure boundary welds in components identified in Table 2.2.5-1 as ASME Code Section III met ASME Code Section III requirements.

An inspection was performed in accordance with Reference 2 to demonstrate that the as-built pressure boundary welds in piping identified in Table 2.2.5-2(Attachment B) as ASME Code Section III met ASME Code Section III requirements (i.e., no unacceptable indications). This portion of the ITAAC was completed when the piping identified in Table 2.2.5-2, which is encompassed within the respective piping system Code Symbol N-Stamp and the corresponding piping system ASME Section III Code N-5 Data Report(Reference 1), was completed.

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 pressure boundary welds were 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.

The completion of stamping the respective piping system along with the corresponding ASME Code N-5 Data Report Forms (certified by the ANI)ensure that the piping was constructed in accordance with the design specifications and the ASME Code Section III, and that the satisfactory completion of the non-destructive examinations of piping pressure boundary welds for the pipe lines identified in Table 2.2.5-2 met ASME Code Section III requirements and were documented in the Non-destructive Examination Report(s) within the supporting data packages.

4.a and 4.b) A report exists and concludes that the results of the pressure test of the components and pipinc identified in Tables 2.2.5-1 and 2.2.5-2 as ASME Code Section III conform with the reouirements of the ASME Code Section III.

Pressure tests were performed by the vendor to demonstrate that the components identified in Table 2.2.5-1 (Attachment A) as ASME Code Section III retain their pressure boundary integrity at their design pressure. The completion of the N-5 Data Reports was governed by Reference 2.

U.S. Nuclear Regulatory Commission ND-21-0621 Enclosure Page 5 of 9 This portion of the ITAAC was complete once each component identified in Table 2.2.5-1 had their individual Code Symbol N-Stamp and corresponding ASME Section III Code Data Report (Reference 1) completed, and the components were installed into the respective Code Symbol N-Stamped piping system and documented on the corresponding ASME Section III N-5 Code Data Report (Reference 1). The pressure testing results of the component's pressure boundary were documented in the Pressure Testing Report(s) within the supporting component's quality data package, which support completion of the respective Code Stamping and Code Data Report.

The completion of stamping the individual components and the respective piping system along with the corresponding ASME Code Data Reports (certified by the AMI) ensures that the components were constructed in accordance with the Design Specifications and the ASME Code Section III and that the satisfactory completion of the pressure testing of each component identified in Table 2.2.5-1 as ASME Code Section III were documented in the Pressure Testing Report(s) within the supporting data packages and met ASME Code Section III requirements.

This ITAAC also verified that the piping identified in Table 2.2.5-2 (Attachment B)fully met all applicable ASME Code,Section III requirements and retains its pressure boundary integrity at its design pressure.

Pressure tests were performed that complied with the ASME Code (1998 Edition, 2000 Addenda),Section III requirements to demonstrate that the ASME Code Section III piping identified in Table 2.2.5-2 retains its pressure boundary integrity at its design pressure.

The pressure tests verified that there were no leaks at welds or piping, and that the pressure boundary integrity was retained at its design pressure. The pressure testing results of the pipe lines are documented in Pressure Testing Reports. The Pressure Testing Report(s)support completion of the ASME Section III N-5 Code Data Report for the applicable piping system (i.e.,

VES)(Reference 1).

The ASME Section III N-5 Code Data Report(Reference 1) identified in Attachments A and B documents that the results of the pressure testing of the components and piping identified in Table 2.2.5-1 and Table 2.2.5-2 respectively conform with the requirements of the Code (1998 Edition, 2000 Addenda),Section III.

5.b) A report exists and concludes that each of the as-built lines identified in Table 2.2.5-2 for which functional caoabilitv is required meets the reouirements for functional caoabilitv.

An inspection was performed of the ASME Section III as-built piping design reports to verify that the report demonstrates that each of the VES piping lines identified in ITAAC Table 2.2.5-2 that requires functional capability was designed to withstand combined normal and seismic design basis loads without a loss of its functional capability. "Functional capability," in this context, refers to the capability of the piping to withstand the effects of earthquakes, without a loss of safety function (to convey fluids from one location to another). Specific functional capability requirements are defined in the VEGP UFSAR Table 3.9-11 (Reference 3).

U.S. Nuclear Regulatory Commission ND-21-0621 Enciosure Page 6 of 9 Piping functional capability is not a specific ASME Code requirement but it is a requirement in the VEGP UFSAR (Reference 3). As such, information demonstrating that UFSAR functional capability requirements were met is included in the ASME Section III As-Built Design Reports for safety class piping prepared in accordance with ASME Section III NCA-3550 under the ASME Boiler & Pressure Vessel Code (1998 Edition, 2000 Addenda)Section III requirements.

The as-built piping systems were subjected to a reconciliation process (Reference 2), which verified that the as-buiit piping systems were analyzed for functional capability and for compliance with the design specification and ASME Code provisions. Design reconciliation of the as-built systems validates that construction completion, including field changes and any nonconforming condition dispositions, was consistent with and bounded by the approved design. As required by ASME Code, the As-Buiit Design Report (Reference 4) includes the results of physical inspection of the piping and reconciiiation to the design pipe stress report.

Inspections of the ASME Code Section III As-Built Piping Design Report(Reference 4)for the VES piping lines identified in Table 2.2.5-2 were completed and concluded that each of the as-built VES piping iines for which functionai capabiiity was required meets the requirements for functional capability. The ASME Section ill As-Built Piping Design Report(Reference 4)for each of the as-built VES piping lines in Table 2.2.5-2 are identified in Attachment B.

References 1 and 4 provide the evidence that the ITAAC Acceptance Criteria requirements were met:

• The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.2.5-1 and 2.2.5-2 as ASME Code Section III; A report exists and conciudes that the ASME Code Section III requirements were met for non-destructive examination of pressure boundary welds;

• A report exists and concludes that the results of the pressure test of the components and piping identified in Tables 2.2.5-1 and 2.2.5-2 as ASME Code Section III conform with the requirements of the ASME Code Section III; and

• A report exists and conciudes that each of the as-built lines identified in Tabie 2.2.5-2 for which functional capability are required meets the requirements for functional capability.

This ITAAC required no Preservice Inspections (PSI) examinations for the VES per the Unit 3 Preservice Inspection Program Plan (Reference 5).

References 1 and 4 are available for NRC inspection as part of the Unit 3 ITAAC 2.2.05.02a Completion Package (Reference 6).

U.S. Nuclear Regulatory Commission ND-21-0621 Enclosure Page 7 of 9 ITAAC Finding Review In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company(SNC) performed a review of all findings pertaining to the subject ITAAC and associated corrective actions. This review, which included now consolidated ITAAC Indexes 254, 255, 256, 257, 258 and 262,found no relevant ITAAC findings associated with this ITAAC.

The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.2.05.02a (Reference 6) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.05.02a 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 favallable for NRC inspection)

1. SV3-VES-MUR-001, Rev. 0,"AP1000 Vogtle Unit 3 ASME Section III System Code Data Report for the Main Control Room Emergency Habitability System (VES)"

2. APP-GW-GAP-139, Rev. 7,"Westinghouse/Stone & Webster ASME Code Data Report As-Built Documentation Interface Procedure"

3. VEGP 3&4 Updated Final Safety Analysis Report, Rev. 10.0, Subsection 5.2.1,"Compliance with Codes and Code Cases" & Table 3.9-11,"Piping Functional Capability - ASME Class 1, 2, and 3"

4. SV3-VES-S3R-001, Rev. 1, "Vogtle Unit 3 Main Control Room Emergency Habitability System (VES)ASME III As-Built Piping System Design Report"

5. SV3-GW-GEI-100, Rev. 2,"API000 Preservice Inspection Program Plan for Vogtle Unit 3"

6. 2.2.05.02a-U3-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-21-0621 Enclosure Page 8 of 9 Attachment A SYSTEM: Main Control Room Emergency Habitability System (VES)

ASME lil As-ASME Code Equipment Name

• Tag No.* Bullt Design N-5 Report Section lil*

Report Air Delivery Alternate SV3-VES-S3R- SV3-VES-MUR-VES-PL-V001 Yes Isolation Valve 001 001 Eductor Flow Path SV3-VES-S3R- SV3-VES-MUR-VES-PL-V045 Yes Isolation Valve 001 001 Eductor Bypass Isolation SV3-VES-S3R- SV3-VES-MUR-VES-PL-V046 Yes Valve 001 001 Pressure Regulating SV3-VES-S3R- SV3-VES-MUR-VES-PL-V002A Yes Valve A 001 001 Pressure Regulating SV3-VES-S3R- SV3-VES-MUR-VES-PL-V002B Yes Valve B 001 001 MCR Air Delivery SV3-VES-S3R- SV3-VES-MUR-VES-PL-V005A Yes Isolation Valve A 001 001 MCR Air Delivery SV3-VES-S3R- SV3-VES-MUR-VES-PL-V005B Yes Isolation Valve B 001 001 Temporary Instrument SV3-VES-S3R- SV3-VES-MUR-VES-PL-V018 Yes Isolation Valve A 001 001 Temporary Instrument SV3-VES-S3R- SV3-VES-MUR-VES-PL-V019 Yes Isolation Valve B 001 001 MCR Pressure Relief SV3-VES-S3R- SV3-VES-MUR-VES-PL-V022A Yes Isolation Valve A 001 001 MCR Pressure Relief SV3-VES-S3R- SV3-VES-MUR-VES-PL-V022B Yes Isolation Valve B 001 001 Air Tank Safety Relief SV3-VES-S3R- SV3-VES-MUR-VES-PL-V040A Yes Valve A 001 001 Air Tank Safety Relief SV3-VES-S3R- SV3-VES-MUR-VES-PL-V040B Yes Valve B 001 001 Air Tank Safety Relief SV3-VES-S3R- SV3-VES-MUR-VES-PL-V040C Yes Valve C 001 001 Air Tank Safety Relief SV3-VES-S3R- SV3-VES-MUR-VES-PL-V040D Yes Valve D 001 001 Main Air Flow Path SV3-VES-S3R- SV3-VES-MUR-VES-PL-V044 Yes Isolation Valve 001 001 MCR Air Filtration Line SV3-VES-S3R- SV3-VES-MUR-VES-PY-N01 Yes Eductor 001 001

'Excerpts from COL Appendix C Table 2.2.5-1

U.S. Nuclear Regulatory Commission ND-21-0621 Enclosure Page 9 of 9 Attachment B SYSTEM: Main Control Room Emergency Habitability System (VES)

ASME III Functional Line ASME Code As-Built N-5 Report Line Name* Capability Number* Section III* Design Required*

Report SV3-VES- SV3-VES-MUR-MCR Relief Line VES-PL-022A Yes Yes S3R-001 001 SV3-VES- SV3-VES-MUR-MCR Relief Line VES-PL-022B Yes Yes S3R-001 001

'Excerpts from COL Appendix C, Table 2.2.5-2