ND-22-0231, ITAAC Closure Notification on Completion of ITAAC 2.2.01.02a (Index Number 91)

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ITAAC Closure Notification on Completion of ITAAC 2.2.01.02a (Index Number 91)
ML23131A264
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 05/11/2023
From: Coleman J
Southern Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-22-0231
Download: ML23131A264 (1)
v • d • e


Text

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel May 11, 2023 Docket No.:

52-026 ND-22-0231 10 CFR 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 4 ITAAC Closure Notification on Completion of ITAAC 2.2.01.02a [Index Number 91]

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 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.01.02a [Index Number 91].

This ITAAC verifies that the Containment System (CNS) components listed in the Combined License (COL) Appendix C, Table 2.2.1-1 and Table 2.2.1-2 that are identified as American Society of Mechanical Engineers (ASME) Code Section III were designed and constructed in accordance with applicable requirements. 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 Roberts at 706-848-6991.

Respectfully submitted, Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 4 Completion for ITAAC 2.2.01.02a [Index Number 91]

JMC/TL/sfr

U.S. Nuclear Regulatory Commission ND-22-0231 Page 2 of 2 cc:

Regional Administrator, Region ll Director, Office of Nuclear Reactor Regulation (NRR)

Director, Vogtle Project Office NRR Senior Resident Inspector - Vogtle 3 & 4

U.S. Nuclear Regulatory Commission ND-22-0231 Enclosure Page 1 of 15 Southern Nuclear Operating Company ND-22-0231 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.01.02a [Index Number 91]

U.S. Nuclear Regulatory Commission ND-22-0231 Enclosure Page 2 of 15 ITAAC Statement Design Commitment:

2.a) The components identified in Table 2.2.1-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.

2.b) The piping identified in Table 2.2.1-2 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 2.2.1-1 as ASME Code Section III meet ASME Code Section III requirements.

3.b) Pressure boundary welds in piping identified in Table 2.2.1-2 as ASME Code Section III meet ASME Code Section III requirements.

4.a) The components identified in Table 2.2.1-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.

4.b) The piping identified in Table 2.2.1-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.

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.

i) A hydrostatic or pressure test will be performed on the components required by the ASME Code Section III to be tested.

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

Acceptance Criteria:

The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.2.1-1 and 2.2.1-2 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.

i) A report exists and concludes that the results of the pressure test of the components identified in Table 2.2.1-1 as ASME Code Section III conform with the requirements of the ASME Code Section III.

U.S. Nuclear Regulatory Commission ND-22-0231 Enclosure Page 3 of 15 A report exists and concludes that the results of the pressure test of the piping identified in Table 2.2.1-2 as ASME Code Section III 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 Containment System (CNS) components and piping listed in the Combined License (COL)

Appendix C, Table 2.2.1-1 (Attachment A) and Table 2.2.1-2 (Attachment B) that are identified as American Society of Mechanical Engineers (ASME) Code Section III were 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 2.2.1-1 and 2.2.1-2 as ASME Code Section III.

Each component listed in Table 2.2.11 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 was documented in the components 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 (References 1 through 11, 26).

The as-built piping listed in Table 2.2.1-2 including the components listed in Table 2.2.1-1 as ASME Code Section III, were subjected to a reconciliation process (Reference 12), which verifies that the as-built piping 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, 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 (QA) 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(s), which include the location of the certified Design Reports for all the components listed in Table 2.2.11 (Attachment A) and piping listed in Table 2.2.1-2 (Attachmnet 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 13). The N-5 Code Data Reports for the piping system(s) containing the components listed in the Table 2.2.1-1 and Table 2.2.1-2 are identified in Attachments A and B, respectively.

3.a and 3.b) A report exists and concludes that the ASME Code Section III requirements 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

U.S. Nuclear Regulatory Commission ND-22-0231 Enclosure Page 4 of 15 Table 2.2.1-1 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 the completed 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) (References 1 through 11, 26) 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 2.2.11 as ASME Code Section III met ASME Code Section III requirements.

An inspection was performed in accordance with Reference 12 to demonstrate that the as-built pressure boundary welds in piping identified in Table 2.2.1-2 (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 2.2.12, which was encompassed within the respective piping system Code Symbol N-Stamp and the corresponding piping system Code N-5 Data Report Form(s) (References 1 through 11, 26),

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 systems 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 was 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 welds for the pipe lines identified in Table 2.2.12 meet ASME Code Section III requirements and were documented in the Non-destructive Examination Report(s) within the supporting data packages.

4.a.i and 4.b) A report exists and concludes that the results of the pressure test of the components and piping identified in Tables 2.2.1-1 and 2.2.1-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.

A hydrostatic/pressure test were performed by the manufacturer to demonstrate that the components identified in Table 2.2.1-1 (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 12.

This portion of the ITAAC was completed once each component identified in Table 2.2.11 had their individual Code Symbol N-Stamp and corresponding Code Data Report (References 1 through 11, 26) completed, and the components were installed into the respective Code Symbol N-Stamped piping system and documented on the corresponding N-5 Code Data Report(s)

(References 1 through 11, 26). The hydrostatic/pressure testing results of the components pressure boundary were documented in the Hydrostatic/Pressure Testing Report(s) within the

U.S. Nuclear Regulatory Commission ND-22-0231 Enclosure Page 5 of 15 supporting components 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 were 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 2.2.11 as ASME Code Section III were documented in the Hydrostatic/Pressure Testing Report(s) within the supporting data packages and meets ASME Code Section III requirements.

This ITAAC also verifies that the piping identified in Table 2.2.1-2 (Attachment B) fully meets all applicable ASME Code,Section III requirements and retains its pressure boundary integrity at its design pressure.

Hydrostatic/pressure tests were performed in accordance with procedures identified in References 1 through 11, 26 (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 2.2.1-2 retains its pressure boundary integrity at its design pressure.

The hydrostatic/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 hydrostatic/pressure testing results of the pipe lines are documented in the Hydrostatic/Pressure Testing Report(s).

The Hydrostatic/Pressure Testing Report(s) supports completion of the ASME Section III N-5 Code Data Report(s) for the applicable piping system (i.e., CNS) (References 1 through 11, 26).

The applicable ASME Section III N-5 Code Data Report(s) (References 1 through 11, 26) identified in Attachments A and B documents that the results of the hydrostatic/pressure testing of the components and piping identified in Table 2.2.11 and Table 2.2.1-2, respectively, conform with the requirements of the ASME Code (1998 Edition, 2000 Addenda),Section III.

References 1 through 11, 26 and the supporting as-built design reports (References 14 through

25) 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 2.2.1-1 and 2.2.1-2 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; A report exists and concludes that the results of the pressure test of the components identified in Table 2.2.1-1 as ASME Code Section III conform with the requirements of the ASME Code Section III; and A report exists and concludes that the results of the pressure test of the piping identified in Table 2.2.1-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.

U.S. Nuclear Regulatory Commission ND-22-0231 Enclosure Page 6 of 15 This ITAAC also verified that a Preservice Inspection (PSI) examination for the applicable portions of the Passive Containment Cooling System (PCS) and Spent Fuel Pool Cooling System (SFS) components and piping identified in Tables 2.2.1-1 and 2.2.1-2 were completed (Reference 28) in accordance with the Unit 4 PSI program plan (Reference 27), and that the results of the PSI conforms with the requirements of the ASME B&PV Code. The remaining systems in the scope of this ITAAC [Compressed Air System (CAS), Component Cooling Water System (CCS), Demineralized Water Transfer and Storage System (DWS), Fuel Handling System (FHS), Fire Protection System (FPS), Containment Air Filtration System (VFS), Chilled Water System (VWS), Liquid Radwaste System (WLS), Primary Sampling System (PSS), and Containment System (CNS)] require no PSI examinations per the Unit 4 Preservice Inspection Program Plan (Reference 27).

References 1 through 11, 26, and 14 through 25 are available for NRC inspection as part of the Unit 4 ITAAC 2.2.01.02a Completion Package (Reference 29).

ITAAC Finding Review 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 92, 93, 94, 95 and 97 found no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.2.01.02a (Reference 29) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.01.02a was performed for VEGP Unit 4 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. SV4-CNS-MUR-001, Rev. 0, AP1000 Vogtle Unit 4 ASME Section III System Code Data Report for the Containment System Penetration Assemblies (CNS)
2. SV4-CAS-MUR-001, Rev. 0, AP1000 Vogtle Unit 4 ASME Section III System Code Data Report for the Compressed and Instrument Air System (CAS)
3. SV4-CCS-MUR-001, Rev. 0, AP1000 Vogtle Unit 4 ASME Section III System Code Data Report for the Component Cooling Water System (CCS)
4. SV4-DWS-MUR-001, Rev. 0, AP1000 Vogtle Unit 4 ASME Section III System Code Data Report for the Demineralized Water Transfer and Storage System (DWS)
5. SV4-FHS-MUR-001, Rev. 0, AP1000 Vogtle Unit 4 ASME Section III System Code Data Report for the Fuel Handling System (FHS)

U.S. Nuclear Regulatory Commission ND-22-0231 Enclosure Page 7 of 15

6. SV4-FPS-MUR-001, Rev. 0, AP1000 Vogtle Unit 4 ASME Section III System Code Data Report for the Fire Protection System (FPS)
7. SV4-VFS-MUR-001, Rev. 0, AP1000 Vogtle Unit 4 ASME Section III System Code Data Report for the Containment Air Filtration System (VFS)
8. SV4-VWS-MUR-001, Rev. 0, AP1000 Vogtle Unit 4 ASME Section III System Code Data Report for the Chilled Water System (VWS)
9. SV4-WLS-MUR-002, Rev. 0, AP1000 Vogtle Unit 4 ASME Section III System Code Data Report for the Liquid Radwaste System B (WLS-B)
10. SV4-PSS-MUR-001, Rev. 0, AP1000 Vogtle Unit 4 ASME Section III System Code Data Report for the Primary Sampling System (PSS)
11. SV4-SFS-MUR-001, Rev. 0, AP1000 Vogtle Unit 4 ASME Section III System Code Data Report for the Spent Fuel Pool Cooling System (SFS)
12. APP-GW-GAP-139, Rev. 9, Westinghouse/Stone & Webster ASME Code Data Report As-Built Documentation Interface Procedure
13. VEGP 3&4 Updated Final Safety Analysis Report, Rev. 11.2
a. Subsection 5.2.1 Compliance with Codes and Code Cases,
b. Table 3.9 Piping Functional Capability - ASME Class 1, 2, and 3,
c. Subsection 3.6.4.1-Pipe Break Hazards Analysis
14. SV4-CNS-S3R-001, Rev. 0, Vogtle Unit 4 Containment System Penetration Assemblies (CNS) ASME III As-Built Design Report
15. SV4-CAS-S3R-001, Rev. 0, Vogtle Unit 4 AP 1000 Compressed and Instrument Air (CAS)

Piping System As-Built Design Report

16. SV4-CCS-S3R-001, Rev. 0, Vogtle Unit 4 Component Cooling Water System (CCS) ASME Section III As-Built Piping System Design Report
17. SV4-DWS-S3R-001, Rev. 0, Vogtle Unit 4 Demineralized Water Transfer and Storage System (DWS) ASME Section III As-Built Piping System Design Report
18. SV4-FHS-S3R-001, Rev. 0, Vogtle Unit 4 Fuel Handling System (FHS) As-Built ASME Section III Piping System Design Report
19. SV4-FPS-S3R-001, Rev. 0, Vogtle Unit 4 Fire Protection System (FPS) ASME Section III As-Built Piping System Design Report
20. SV4-VFS-S3R-001, Rev. 0, Vogtle Unit 4 Containment Air Filtration System (VFS) ASME Section III As-Built Piping System Design Report
21. SV4-VWS-S3R-001, Rev. 0, Vogtle Unit 4 Central Chilled Water System (VWS) ASME Section III As-Built Piping System Design Report

U.S. Nuclear Regulatory Commission ND-22-0231 Enclosure Page 8 of 15

22. SV4-WLS-S3R-002, Rev. 0, Vogtle Unit 4 Liquid Radwaste System B (WLS-B) ASME Section III As-Built Piping System Design Report
23. SV4-PSS-S3R-001, Rev. 0, Vogtle Unit 4 Primary Sampling System (PSS) ASME Section III As-Built Piping System Design Report
24. SV4-SFS-S3R-001, Rev. 0, Vogtle Unit 4 Spent Fuel Pool Cooling System (SFS) ASME Section III As-Built Piping System Design Report
25. SV4-MV50-S3R-100, Rev. 0, Vogtle Unit 4 Containment Vessel ASME III As-Built Design Report
26. SV4-MV50-VQQ-004P1P36 Rev. 0, Quality Release & C of C SV4 CV Data package (Note: this document contains CBIs ASME N-1 Code Data Report for CV and supporting ASME Code Data Reports)
27. SV4-GW-GEI-100, Rev. 1, AP1000 Preservice Inspection Program Plan for Vogtle Unit 4
28. APE-10-00026, Completion of Preservice Inspection for the Vogtle Unit 4 PCS and SFS Class 1, 2, and 3 Portions of Systems
29. 2.2.01.02a-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-22-0231 Enclosure Page 9 of 15 Attachment A SYSTEM: Containment System (CNS)

Equipment Name

  • Tag No.
  • ASME Code Section III*

ASME III as-built Design Report N-5 Report Service Air Supply Outside Containment Isolation Valve Service Air Supply Inside Containment Isolation Check Valve CAS-PL-V204 CAS-PL-V205 Yes Yes SV4-CAS-S3R-001 SV4-CAS-MUR-001 Instrument Air Supply Outside Containment Isolation Valve Instrument Air Supply Inside Containment Isolation Check Valve CAS-PL-V014 CAS-PL-V015 Yes Yes SV4-CAS-S3R-001 SV4-CAS-MUR-001 Component Cooling Water System (CCS) Containment Isolation Motor-operated Valve (MOV) -

Inlet Line Outside Reactor Containment (ORC)

CCS Containment Isolation Check Valve - Inlet Line Inside Reactor Containment (IRC)

CCS-PL-V200 CCS-PL-V201 Yes Yes SV4-CCS-S3R-001 SV4-CCS-MUR-001 CCS Containment Isolation MOV

- Outlet Line IRC CCS Containment Isolation MOV

- Outlet Line ORC CCS Containment Isolation Relief Valve - Outlet Line IRC CCS-PL-V207 CCS-PL-V208 CCS-PL-V220 Yes Yes Yes SV4-CCS-S3R-001 SV4-CCS-MUR-001 Demineralized Water Supply Containment Isolation Valve ORC Demineralized Water Supply Containment Isolation Check Valve IRC DWS-PL-V244 DWS-PL-V245 Yes Yes SV4-DWS-S3R-001 SV4-DWS-MUR-001 Fuel Transfer Tube FHS-FT-01 Yes SV4-FHS-S3R-001 SV4-MV50-VQQ-004P1P36

U.S. Nuclear Regulatory Commission ND-22-0231 Enclosure Page 10 of 15 Attachment A SYSTEM: Containment System (CNS)

Equipment Name

  • Tag No.
  • ASME Code Section III*

ASME III as-built Design Report N-5 Report Fuel Transfer Tube Isolation Valve FHS-PL-V001 Yes SV4-FHS-S3R-001 SV4-FHS-MUR-001 Fire Water Containment Supply Isolation Valve - Outside Fire Water Containment Isolation Supply Check Valve - Inside FPS-PL-V050 FPS-PL-V052 Yes Yes SV4-FPS-S3R-001 SV4-FPS-MUR-001 Spent Fuel Pool Cooling System (SFS) Discharge Line Containment Isolation Check Valve - IRC SFS Discharge Line Containment Isolation MOV - ORC SFS-PL-V037 SFS-PL-V038 Yes Yes SV4-SFS-S3R-001 SV4-SFS-MUR-001 SFS Suction Line Containment Isolation MOV - IRC SFS Suction Line Containment Isolation MOV - ORC SFS Suction Line Containment Isolation Relief Valve - IRC SFS-PL-V034 SFS-PL-V035 SFS-PL-V067 Yes Yes Yes SV4-SFS-S3R-001 SV4-SFS-MUR-001 Containment Purge Inlet Containment Isolation Valve -

ORC Containment Purge Inlet Containment Isolation Valve - IRC VFS-PL-V003 VFS-PL-V004 Yes Yes SV4-VFS-S3R-001 SV4-VFS-MUR-001 Integrated Leak Rate Testing Vent Discharge Containment Isolation Valve - ORC Containment Purge Discharge Containment Isolation Valve - IRC Containment Purge Discharge Containment Isolation Valve -

ORC VFS-PL-V008 VFS-PL-V009 VFS-PL-V010 Yes Yes Yes SV4-VFS-S3R-001 SV4-VFS-MUR-001

U.S. Nuclear Regulatory Commission ND-22-0231 Enclosure Page 11 of 15 Attachment A SYSTEM: Containment System (CNS)

Equipment Name

  • Tag No.
  • ASME Code Section III*

ASME III as-built Design Report N-5 Report Vacuum Relief Containment Isolation A MOV - ORC Vacuum Relief Containment Isolation B MOV - ORC Vacuum Relief Containment Isolation Check Valve A - IRC Vacuum Relief Containment Isolation Check Valve B - IRC VFS-PL-V800A VFS-PL-V800B VFS-PL-V803A VFS-PL-V803B Yes Yes Yes Yes SV4-VFS-S3R-001 SV4-VFS-MUR-001 Fan Coolers Return Containment Isolation Valve - IRC Fan Coolers Return Containment Isolation Valve - ORC Fan Coolers Return Containment Isolation Relief Valve - IRC VWS-PL-V082 VWS-PL-V086 VWS-PL-V080 Yes Yes Yes SV4-VWS-S3R-001 SV4-VWS-MUR-001 Fan Coolers Supply Containment Isolation Valve - ORC Fan Coolers Supply Containment Isolation Check Valve - IRC VWS-PL-V058 VWS-PL-V062 Yes Yes SV4-VWS-S3R-001 SV4-VWS-MUR-001 Reactor Coolant Drain Tank (RCDT) Gas Outlet Containment Isolation Valve - IRC RCDT Gas Outlet Containment Isolation Valve - ORC WLS-PL-V067 WLS-PL-V068 Yes Yes SV4-WLS-S3R-002 SV4-WLS-MUR-002 Sump Discharge Containment Isolation Valve - IRC Sump Discharge Containment Isolation Valve - ORC Sump Discharge Containment Isolation Relief Valve - IRC WLS-PL-V055 WLS-PL-V057 WLS-PL-V058 Yes Yes Yes SV4-WLS-S3R-002 SV4-WLS-MUR-002 Spare Penetration CNS-PY-C01 Yes SV4-MV50-S3R-001 SV4-MV50-VQQ-004P1P36

U.S. Nuclear Regulatory Commission ND-22-0231 Enclosure Page 12 of 15 Attachment A SYSTEM: Containment System (CNS)

Equipment Name

  • Tag No.
  • ASME Code Section III*

ASME III as-built Design Report N-5 Report Spare Penetration CNS-PY-C02 Yes SV4-MV50-S3R-001 SV4-MV50-VQQ-004P1P36 Spare Penetration CNS-PY-C03 Yes SV4-MV50-S3R-001 SV4-MV50-VQQ-004P1P36 Main Equipment Hatch CNS-MY-Y01 Yes SV4-MV50-S3R-001 SV4-MV50-VQQ-004P1P36 Maintenance Hatch CNS-MY-Y02 Yes SV4-MV50-S3R-001 SV4-MV50-VQQ-004P1P36 Upper Personnel Hatch CNS-MY-Y03 Yes SV4-MV50-S3R-001 SV4-MV50-VQQ-004P1P36 Lower Personnel Hatch CNS-MY-Y04 Yes SV4-MV50-S3R-001 SV4-MV50-VQQ-004P1P36 Containment Vessel CNS-MV-01 Yes SV4-MV50-S3R-001 SV4-MV50-VQQ-004P1P36 Electrical Penetration P03 DAS-EY-P03Z Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P01 ECS-EY-P01X Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P02 ECS-EY-P02X Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P06 ECS-EY-P06Y Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P07 ECS-EY-P07X Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P09 ECS-EY-P09W Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P10 ECS-EY-P10W Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P11 IDSA-EY-P11Z Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P12 IDSA-EY-P12Y Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P13 IDSA-EY-P13Y Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P14 IDSD-EY-P14Z Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P15 IDSD-EY-P15Y Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001

U.S. Nuclear Regulatory Commission ND-22-0231 Enclosure Page 13 of 15 Attachment A SYSTEM: Containment System (CNS)

Equipment Name

  • Tag No.
  • ASME Code Section III*

ASME III as-built Design Report N-5 Report Electrical Penetration P16 IDSD-EY-P16Y Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P17 ECS-EY-P17X Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P18 ECS-EY-P18X Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P19 ECS-EY-P19Z Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P20 ECS-EY-P20Z Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P21 EDS-EY-P21Z Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P22 ECS-EY-P22X Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P23 ECS-EY-P23X Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P24 ECS-EY-P24 Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P25 ECS-EY-P25W Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P26 ECS-EY-P26W Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P27 IDSC-EY-P27Z Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P28 IDSC-EY-P28Y Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P29 IDSC-EY-P29Y Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P30 IDSB-EY-P30Z Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P31 IDSB-EY-P31Y Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Electrical Penetration P32 IDSB-EY-P32Y Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Instrument Penetration P46 PCS-PY-C01 Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Instrument Penetration P47 PCS-PY-C02 Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001

U.S. Nuclear Regulatory Commission ND-22-0231 Enclosure Page 14 of 15 Attachment A SYSTEM: Containment System (CNS)

Equipment Name

  • Tag No.
  • ASME Code Section III*

ASME III as-built Design Report N-5 Report Instrument Penetration P48 PCS-PY-C03 Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001 Instrument Penetration P49 PCS-PY-C04 Yes SV4-CNS-S3R-001 SV4-CNS-MUR-001

  • Excerpt from COL Appendix C Table 2.2.1-1

U.S. Nuclear Regulatory Commission ND-22-0231 Enclosure Page 15 of 15 Attachment B SYSTEM: Containment System (CNS)

Line Name*

Line Number*

ASME Code Section III*

ASME III As-Built Design Report N-5 Report Instrument Air In CAS-PL-L015+

Yes SV4-CAS-S3R-001 SV4-CAS-MUR-001 Service Air In CAS-PL-L204+

Yes SV4-CAS-S3R-001 SV4-CAS-MUR-001 Component Cooling Water Supply to Containment CCS-PL-L201 Yes SV4-CCS-S3R-001 SV4-CCS-MUR-001 Component Cooling Water Outlet from Containment CCS-PL-L207 Yes SV4-CCS-S3R-001 SV4-CCS-MUR-001 Demineralized Water In DWS-PL-L245+,

L230 Yes SV4-DWS-S3R-001 SV4-DWS-MUR-001 Fire Protection Supply to Containment FPS-PL-L107 Yes SV4-FPS-S3R-001 SV4-FPS-MUR-001 Containment Atmosphere Return Line PSS-PL-L038+

Yes SV4-PSS-S3R-001 SV4-PSS-MUR-001 Common Primary Sample Line A/B PSS-PL-T005A/B Yes SV4-PSS-S3R-001 SV4-PSS-MUR-001 Containment Atmosphere Sample Line PSS-PL-T031 Yes SV4-PSS-S3R-001 SV4-PSS-MUR-001 Spent Fuel Pool Cooling Discharge SFS-PL-L017 Yes SV4-SFS-S3R-001 SV4-SFS-MUR-001 Spent Fuel Pool Cooling Suction from Containment SFS-PL-L038 Yes SV4-SFS-S3R-001 SV4-SFS-MUR-001 Containment Purge Inlet to Containment VFS-PL-L104, L105, L106 Yes SV4-VFS-S3R-001 SV4-FVS-MUR-001 Containment Purge Discharge from Containment VFS-PL-L203, L204, L205, L800, L801A/B, L803, L804, L805A/B, L810A/B, L832 Yes SV4-VFS-S3R-001 SV4-FVS-MUR-001 Fan Cooler Supply Line to Containment VWS-PL-L032 Yes SV4-VWS-S3R-001 SV4-FWS-MUR-001 Fan Cooler Return Line from Containment VWS-PL-L055 Yes SV4-VWS-S3R-001 SV4-FWS-MUR-001 RCDT Gas Out WLS-PL-L022 Yes SV4-WLS-S3R-001 SV4-WLS-MUR-001 Waste Sump Out WLS-PL-L073 Yes SV4-WLS-S3R-001 SV4-WLS-MUR-001

  • Excerpts from COL Appendix C, Table 2.2.1-2

+ These lines require that dynamic loads in its pipe stress analysis satisfy the requirements of ASME Code Section III (1989 Edition, 1989 Addenda) for girth fillet welds between piping and socket welded fittings, valves and flanges per VEGP UFSAR Section 5.2.1.1 (Reference 13)

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