ND-21-0802, ITAAC Closure Notification on Completion of ITAAC 2.2.01.02a (Index Number 91)

ITAAC Closure Notification on Completion of ITAAC 2.2.01.02a (Index Number 91)

ML21355A376
Person / Time
Site:	Vogtle
Issue date:	12/21/2021
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-0802
Download: ML21355A376 (18)

Text

Michael J. Yox 7825 River Road hk. Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel DEC 2 1 2021 Docket No.: 52-025 ND-21-0802 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 3 ITAAC Closure Notification on Completion of ITAAC 2.2.01.02a [Index Number 911 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 2.2.01.02a [Index Number 91].

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 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 A. Roberts at 706-848-6991.

Respectfully submitted.

Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 Completion for ITAAC 2.2.01.02a [Index Number 91]

MJY/JRV/sfr

U.S. Nuclear Regulatory Commission ND-21-0802 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. Vox 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 Regulatory Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil M C. P. Patel 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. Eargle M T. Fanelli Ms. K. McCurry M J. Parent M B. Griman M V. Hall

U.S. Nuclear Regulatory Commission ND-21-0802 Page 3 of 3 Oqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros Westinahouse Eiectric 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., 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-21-0802 Enclosure Page 1 of 15 Southern Nuclear Operating Company ND-21-0802 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.2.01.02a [Index Number 91]

U.S. Nuclear Regulatory Commission ND-21-0802 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-21-0802 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 2.2.1-1 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 was 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)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(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(s), which include the location of the certified Design Reports for all the components listed in Table 2.2.1-1 (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 reauirements 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

U.S. Nuclear Regulatory Commission ND-21-0802 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, radlographic, 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, Subartlcle 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 2.2.1-1 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-bullt 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 2.2.1-2, 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, radlographic, 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(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 speclflcatlon(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 2.2.1-2 meet ASME Code Section III requirements and were documented In the Non-destructive Examination Report(s) within the supporting data packages.

4.a.l and 4.b) A report exists and concludes that the results of the pressure test of the components and plplno 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 2.2.1-1 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 component's pressure boundary were documented In the Hydrostatic/Pressure Testing Report(s) within the

U.S. Nuclear Regulatory Commission ND-21-0802 Enclosure Page 5 of 15 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 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 2.2.1-1 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 2.2.1-1 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) provides 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-21-0802 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 (References 28 and 29) in accordance with the Unit 3 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 3 Preservice Inspection Program Plan (Reference 27).

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.

References 1 through 11, 26 and 14 through 25 are available for NRC inspection as part of the Unit 3 ITAAC 2.2.01.02a Completion Package (Reference 30).

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 through 95, 97 and found one relevant ITAAC NRC finding associated with this ITAAC.

1. LIV 05200025/2021003-03(Closed - ML21314A277)

The corrective actions for this finding has been completed and the finding is closed. The IT/\AC completion review is documented in the ITAAC Completion Package for ITAAC 2.2.01.02a (Reference 30) and is available for NRC review.

ITAAC Compietion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.01.02a 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 favaliabie for NRC inspection)

1. SV3-CNS-MUR-001, Rev. 1,"API000 Vogtle Unit 3 ASME Section III System Code Data Report for the Containment System Penetration Assemblies(CNS)"

2. SV3-CAS-MUR-001, Rev. 0,"API000 Vogtle Unit 3 ASME Section III System Code Data Report for the Compressed and Instrument Air System (CAS)"

3. SV3-CCS-MUR-001, Rev. 0,"API000 Vogtle Unit 3 ASME Section III System Code Data Report for the Component Cooling Water System (CCS)"

U.S. Nuclear Regulatory Commission ND-21-0802 Enclosure Page 7 of 15

4. SV3-DWS-MUR-001, Rev. 0,"API000 Vogtle Unit 3 ASME Section III System Code Data Report for the Demineralized Water Transfer and Storage System (DWS)"

5. SV3-FHS-MUR-001, Rev. 1,"API000 Vogtle Unit 3 ASME Section III System Code Data Report for the Fuel Handling System (FHS)"

6. SV3-FPS-MUR-001, Rev. 1,"API000 Vogtle Unit 3 ASME Section III System Code Data Report for the Fire Protection System (FPS)"

7. SV3-VFS-MUR-001, Rev. 0,"API000 Vogtle Unit 3 ASME Section III System Code Data Report for the Containment Air Filtration System (VFS)"

8. SV3-VWS-MUR-001, Rev. 1,"API000 Vogtle Unit 3 ASME Section III System Code Data Report for the Chilled Water System (VWS)"

9. SV3-WLS-MUR-001, Rev. 1,"API000 Vogtle Unit 3 ASME Section III System Code Data Report for the Liquid Radwaste System (WLS-A)"

10. SV3-PSS-MUR-001, Rev. 0,"API000 Vogtle Unit 3 ASME Section III System Code Data Report for the Primary Sampling System (PSS)"

11. SV3-SFS-MUR-001, Rev. 0,"API000 Vogtle Unit 3 ASME Section III System Code Data Report for the Spent Fuel Pool Cooling System (SFS)"

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

13. VEGP 3&4 Updated Final Safety Analysis Report, Rev. 10.0

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. SV3-CNS-S3R-001, Rev. 1,"Vogtle Unit 3 Containment System Penetration Assemblies (CNS)ASME III As-Built Design Report"

15. SV3-CAS-S3R-001, Rev. 0,"Vogtle Unit 3 AP 1000 Compressed and Instrument Air(CAS)

Piping System As-Built Design Report"

16. SV3-CCS-S3R-001, Rev. 1,"Vogtle Unit 3 Component Cooling Water System (CCS) ASME Section III As-Built Piping System Design Report"

17. SV3-DWS-S3R-001, Rev. 0,"Vogtle Unit 3 Demineralized Water Transfer and Storage System (DWS)ASME Section III As-Built Piping System Design Report"

18. SV3-FHS-S3R-001, Rev. 0,"Vogtle Unit 3 Fuel Handling System (FHS) As-Built ASME Section III Piping System Design Report"

19. SV3-FPS-S3R-001, Rev. 0,"Vogtle Unit 3 Fire Protection System (FPS) ASME Section III As-Built Piping System Design Report"

U.S. Nuclear Regulatory Commission ND-21-0802 Enclosure Page 8 of 15

20. SV3-VFS-S3R-001, Rev. 1,"Vogtle Unit 3 Containment Air Filtration System (VFS) ASME Section III As-Built Piping System Design Report"

21. SV3-VWS-S3R-001, Rev. 2,"Vogtle Unit 3 Central Chilled Water System (VWS)ASME Section III As-Built Piping System Design Reporf'

22. SV3-WLS-S3R-002, Rev. 1,"Vogtle Unit 3 Liquid Radwaste System B(WLS-B) ASME Section III As-Built Piping System Design Report"

23. SV3-PSS-S3R-001, Rev. 0,"Vogtle Unit 3 Primary Sampling System (PSS) ASME Section III As-Built Piping System Design Report"

24. SV3-SFS-S3R-001, Rev. 0,"Vogtle Unit 3 Spent Fuel Pool Cooling System (SFS) ASME Section III As-Built Piping System Design Reporf'

25. SV3-MV50-S3R-001, Rev. 0,"Vogtle Unit 3 Containment Vessel ASME III As-Built Design Report"

26. SV3-MV3-VQQ-003P1P25, Ver 1.0 "Quality Release & C of C SV3 CV Data package" (Note: this document contains CBI's ASME N-1 Code Data Report for CV and supporting ASME Code Data Reports)

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

28. APE-10-00016,"Unit 3 - Completion of Preservice Inspection for SFS Class 1, 2, and 3 Portions of Systems"

29. APE-10-00018,"Unit 3- Completion of Preservice Inspection for PCS Class 1, 2, and 3 Portions" 30.2.2.01.02a-U3-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-21-0802 Enclosure Page 9 of 15 Attachment A SYSTEM: Containment System (CNS)

ASME ill as-bullt ASME Code Design Report Equipment Name

• Tag No.

• N-5 Report Section III*

Service Air Supply Outside Containment Isolation Valve CAS-PL-V204 Yes SV3-CAS-S3R- SV3-CAS-MUR-Service Air Supply Inside 001 001 Containment Isolation Check CAS-PL-V205 Yes Valve Instrument Air Supply Outside CAS-PL-V014 Yes Containment Isolation Valve SV3-CAS-S3R- SV3-CAS-MUR-Instrument Air Supply Inside CAS-PL-V015 Yes 001 001 Containment Isolation Check Valve Component Cooling Water System (CCS) Containment Isolation Motor-operated Valve(MOV)- CCS-PL-V200 Yes Inlet Line Outside Reactor SV3-CCS-S3R- SV3-CCS-MUR-Containment(ORC) 001 001 CCS Containment Isolation CCS-PL-V201 Yes Check Valve - Inlet Line Inside Reactor Containment(IRC)

CCS Containment Isolation MOV CCS-PL-V207 Yes

- Outlet Line IRC CCS Containment Isolation MOV SV3-CCS-S3R- SV3-CCS-MUR-CCS-PL-V208 Yes

- Outlet Line ORC 001 001 CCS Containment Isolation Relief CCS-PL-V220 Yes Valve - Outlet Line IRC Demineralized Water Supply DWS-PL-V244 Yes Containment Isolation Valve ORC SV3-DWS-S3R- SV3-DWS-MUR-Demineralized Water Supply DWS-PL-V245 Yes 001 001 Containment Isolation Check Valve IRC Fuel Transfer Tube FHS-FT-01 Yes SV3-FHS-S3R-001 SV3-MV3-VQQ-003P1P25

U.S. Nuclear Regulatory Commission ND-21-0802 Enclosure Page 10 of 15 Attachment A SYSTEM: Containment System (CMS)

ASME III as-bullt ASME Code Design Report Equipment Name

• Tag No.* N-5 Report Section ill*

Fuel Transfer Tube Isolation FHS-PL-V001 Yes SV3-FHS-S3R-001 SV3-FHS-MUR-Valve 001 Fire Water Containment Supply Isolation Valve - Outside FPS-PL-V050 Yes SV3-FPS-S3R-001 SV3-FPS-MUR-Fire Water Containment Isolation FPS-PL-V052 Yes 001 Supply Check Valve - Inside Spent Fuel Pool Cooling System SFS-PL-V037 Yes (SFS) Discharge Line Containment Isolation Check Valve - IRC SV3-SFS-S3R-001 SV3-SFS-MUR-001 SFS Discharge Line Containment SFS-PL-V038 Yes Isolation MOV - ORC SFS Suction Line Containment SFS-PL-V034 Yes Isolation MOV - IRC SFS Suction Line Containment SFS-PL-V035 Yes SV3-SFS-S3R-001 SV3-SFS-MUR-Isolation MOV - ORC 001 SFS Suction Line Containment SFS-PL-V067 Yes Isolation Relief Valve - IRC Containment Purge Inlet VFS-PL-V003 Yes Containment Isolation Valve -

ORC SV3-VFS-S3R-001 SV3-VFS-MUR-Containment Purge Inlet VFS-PL-V004 Yes 001 Containment Isolation Valve - IRC Integrated Leak Rate Testing Vent VFS-PL-V008 Yes Discharge Containment Isolation Valve - ORC Containment Purge Discharge VFS-PL-V009 Yes SV3-VFS-S3R-001 SV3-VFS-MUR-Containment Isolation Valve - IRC 001 Containment Purge Discharge VFS-PL-V010 Yes Containment Isolation Valve -

ORC

U.S. Nuclear Regulatory Commission ND-21-0802 Enclosure Page 11 of 15 Attachment A SYSTEM: Containment System (CNS)

ASME ill as-built ASME Code Design Report Equipment Name

• Tag No.* N-5 Report Section lir Vacuum Relief Containment VFS-PL-V800A Yes Isolation A MOV - ORC Vacuum Relief Containment VFS-PL-V800B Yes Isolation B MOV - ORC SV3-VFS-S3R-001 SV3-VFS-MUR-Vacuum Relief Containment VFS-PL-V803A Yes 001 Isolation Check Valve A - IRC Vacuum Relief Containment VFS-PL-V803B Yes Isolation Check Valve B - IRC Fan Coolers Return Containment VWS-PL-V082 Yes Isolation Valve - IRC Fan Coolers Return Containment VWS-PL-V086 Yes SV3-VWS-S3R- SV3-VWS-MUR-Isolation Valve - ORC 001 001 Fan Coolers Return Containment VWS-PL-V080 Yes Isolation Relief Valve - IRC Fan Coolers Supply Containment VWS-PL-V058 Yes Isolation Valve - ORC SV3-VWS-S3R- SV3-VWS-MUR-Fan Coolers Supply Containment VWS-PL-V062 Yes 001 001 Isolation Check Valve - IRC Reactor Coolant Drain Tank WLS-PL-V067 Yes (RCDT) Gas Outlet Containment Isolation Valve - IRC SV3-WLS-S3R- SV3-WLS-MUR-001 001 RCDT Gas Outlet Containment WLS-PL-V068 Yes Isolation Valve - ORC Sump Discharge Containment WLS-PL-V055 Yes Isolation Valve - IRC Sump Discharge Containment WLS-PL-V057 Yes SV3-WLS-S3R- SV3-WLS-MUR-Isolation Valve - ORC 001 001 Sump Discharge Containment WLS-PL-V058 Yes Isolation Relief Valve - IRC SV3-MV50-S3R- SV3-MV3-VQQ-Spare Penetration CNS-PY-C01 Yes 003P1P25 001

U.S. Nuclear Regulatory Commission ND-21-0802 Enclosure Page 12 of 15 Attachment A SYSTEM: Containment System (CMS)

ASME lii as-built ASME Code Design Report Equipment Name

• Tag No.* N-5 Report Section lir SV3-MV50-S3R- SV3-MV3-VQQ-Spare Penetration CNS-PY-C02 Yes 001 003P1P25 SV3-MV50-S3R- SV3-MV3-VQQ-Spare Penetration CNS-PY-C03 Yes 001 003P1P25 SV3-MV50-S3R- SV3-MV3-VQQ-Main Equipment Hatch CNS-MY-Y01 Yes 001 003P1P25 SV3-MV50-S3R- SV3-MV3-VQQ-Maintenance Hatch CNS-MY-Y02 Yes 001 003P1P25 SV3-MV50-S3R- SV3-MV3-VQQ-Upper Personnel Hatch CNS-MY-Y03 Yes 001 003P1P25 SV3-MV50-S3R- SV3-MV3-VQQ-Lower Personnel Hatch CNS-MY-Y04 Yes 001 003P1P25 SV3-MV50-S3R- SV3-MV3-VQQ-Containment Vessel CNS-MV-01 Yes 001 003P1P25 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P03 DAS-EY-P03Z Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P01 ECS-EY-P01X Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P02 ECS-EY-P02X Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P06 ECS-EY-P06Y Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P07 ECS-EY-P07X Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P09 ECS-EY-P09W Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P10 ECS-EY-P10W Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P11 IDSA-EY-P11Z Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration PI2 IDSA-EY-P12Y Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration PI3 IDSA-EY-P13Y Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration PI4 IDSD-EY-P14Z Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration PI5 IDSD-EY-P15Y Yes 001 001

U.S. Nuclear Regulatory Commission ND-21-0802 Enclosure Page 13 of 15 Attachment A SYSTEM: Containment System (CMS)

ASME ill as-bullt ASME Code Design Report Equipment Name

• Tag No.

• N-5 Report Section III*

SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration PI6 IDSD-EY-P16Y Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration PI7 ECS-EY-P17X Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration PI8 ECS-EY-P18X Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration PI9 ECS-EY-P19Z Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P20 ECS-EY-P20Z Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P21 EDS-EY-P21Z Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P22 ECS-EY-P22X Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P23 ECS-EY-P23X Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P24 ECS-EY-P24 Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P25 ECS-EY-P25W Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P26 ECS-EY-P26W Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P27 IDSC-EY-P27Z Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P28 IDSC-EY-P28Y Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P29 IDSC-EY-P29Y Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P30 IDSB-EY-P30Z Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P31 IDSB-EY-P31Y Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Electrical Penetration P32 IDSB-EY-P32Y Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Instrument Penetration P46 PCS-PY-C01 Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Instrument Penetration P47 PCS-PY-C02 Yes 001 001

U.S. Nuclear Regulatory Commission ND-21-0802 Enclosure Page 14 of 15 Attachment A SYSTEM: Containment System (CMS)

ASME ili as-buiit ASME Code Design Report Equipment Name

• Tag No.* N-5 Report Section ili*

SV3-CNS-S3R- SV3-CNS-MUR-Instrument Penetration P48 PCS-PY-C03 Yes 001 001 SV3-CNS-S3R- SV3-CNS-MUR-Instrument Penetration P49 PCS-PY-C04 Yes 001 001 "Excerpt from COL Appendix C Table 2.2.1-1

U.S. Nuclear Regulatory Commission ND-21-0802 Enclosure Page 15 of 15 Attachment B SYSTEM: Containment System (CMS)

ASME Code ASME III As-Built Line Name* Line Number* Section ill* Design Report N-5 Report Instrument Air In CAS-PL-L015* Yes SV3-CAS-S3R-001 SV3-CAS-MUR-001 Service Air In CAS-PL-L204* Yes SV3-CAS-S3R-001 SV3-CAS-MUR-001 Component Cooling Water CCS-PL-L201 Yes SV3-CCS-S3R-001 SV3-CCS-MUR-001 Supply to Containment Component Cooling Water CCS-PL-L207 Yes SV3-CCS-S3R-001 SV3-CCS-MUR-001 Outlet from Containment DWS-PL-L245*,

Demineralized Water In Yes SV3-DWS-S3R-001 SV3-DWS-MUR-001 L230 Fire Protection Supply to FPS-PL-L107 Yes SV3-FPS-S3R-001 SV3-FPS-MUR-001 Containment Containment Atmosphere PSS-PL-L038* Yes SV3-PSS-S3R-001 SV3-PSS-MUR-001 Return Line Common Primary Sample PSS-PL-T005A/B Yes SV3-PSS-S3R-001 SV3-PSS-MUR-001 Line A/B Containment Atmosphere PSS-PL-T031 Yes SV3-PSS-S3R-001 SV3-PSS-MUR-001 Sample Line Spent Fuel Pool Cooling SFS-PL-L017 Yes SV3-SFS-S3R-001 SV3-SFS-MUR-001 Discharge Spent Fuel Pool Cooling SFS-PL-L038 Yes SV3-SFS-S3R-001 SV3-SFS-MUR-001 Suction from Containment Containment Purge Inlet VFS-PL-L104, Yes SV3-VFS-S3R-001 SV3-FVS-MUR-001 to Containment LI 05, LI06 VFS-PL-L203, Containment Purge L204, L205, L800, Discharge from L801A/B, L803, Yes SV3-VFS-S3R-001 SV3-FVS-MUR-001 Containment L804, L805A/B, L810A/B, L832 Fan Cooler Supply Line to VWS-PL-L032 Yes SV3-VWS-S3R-001 SV3-FWS-MUR-001 Containment Fan Cooler Return Line VWS-PL-L055 Yes SV3-VWS-S3R-001 SV3-FWS-MUR-001 from Containment RCDT Gas Out WLS-PL-L022 Yes SV3-WLS-S3R-001 SV3-WLS-MUR-001 Waste Sump Out WLS-PL-L073 Yes SV3-WLS-S3R-001 SV3-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)