ND-18-0179, Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.01.02a (Index Number 91)

Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.01.02a (Index Number 91)

ML18054A121
Person / Time
Site:	Vogtle
Issue date:	02/20/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.2.01.02a, ND-18-0179
Download: ML18054A121 (15)

Text

Michael J. Yox 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 k Southern Nuclear Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell myox@southernco.com FEB 2 0 2018 Docket Nos.: 52-025 52-026 ND-18-0179 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.01.02a [Index Number 91 ]

Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of February 12, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.01.02a

[Index Number91] 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 prior to plant operation, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

If there are any questions, please contact Tom Petrak at 706-848-1575.

Respectfully submitted,

/ /

Michael J. Yox Regulatory Affairs Direbtor Vogtle 3 &4

U.S. Nuclear Regulatory Commission ND-18-0179 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.02a [Index Number 91]

MJY/KJD/amw

U.S. Nuclear Regulatory Commission ND-18-0179 Page 3 of 4 To:

Southern Nuclear Operating Company/ Georgia Power Company M D. A. Bost (w/o enclosures)

M M. D. Rauckhorst (w/o enclosures)

M M. D. Meier M D. H. Jones (w/o enclosures)

M D. L. McKinney M M. J. Vox M D. L. Fulton M J. D. Williams M F. H. Willis Ms. A. L. Pugh M A. 8. Parton M W. A. Sparkman M 0. E. Morrow Ms. K. M. Stacy M . M. K. Washington M . J. P. Redd Ms. A. 0. Chamberlain Mr. D. R. Culver Mr. T. G. Petrak Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reoulatorv Commission Mr. W. Jones (w/o enclosures)

Ms. J. M. Heisserer Mr. C. P. Patel Mr. M. E. Ernstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E. Temple Ms. P. Braxton Mr. T. C. Brimfield Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Oalethoroe Power Corporation Mr. R. B. Brinkman Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0179 Page 4 of 4 Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Orlani (w/o enclosures)

Mr. D. C. Durham (w/o enclosures)

Mr. M. M. Corletti Ms. L. G. Iller Mr. D. Hawkins Ms. J. Monahan Mr. J. L. Coward Ms. N. E. Deangells Other Mr. J. E. Hesler, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

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

U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 1 of 11 Southern Nuclear Operating Company ND-18-0179 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.02a [Index Number 91]

U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 2 of 11 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 Tables 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-18-0179 Enclosure Page 3 of 11 A report exists and concludes that the results ofthe pressuretest ofthe piping identified in Table 2.2.1-2 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 Containment System (CMS) 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 are designed and constructed in accordance with applicable requirements.

2.a) and 2.b) The ASME Code Section III design reoorts exist for the as-built components and oiDino 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 CodeSection III is fabricated in accordance with the VEGP Updated Final SafetyAnalysis Report (UFSAR) and the ASME Code Section III requirements. TheASME 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) for the applicable piping system (Reference 1).

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, are subjected to a reconciliation process (Reference 2), which verifies that the as-built piping are analyzed forapplicable loads (e.g. stress reports) and forcompliance with all design specification and Code provisions. Design reconciliation ofthe as-built systems, including installed components, validates thatconstruction 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, thosefor 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 2.2.1-1 (Attachment A) and piping listed in Table 2.2.1-2 (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 Table 2.2.1-1 and Table2.2.1-2 are identified in Attachments A and B, respectively.

3.a1 and 3.b1 A reoort exists and concludes that the ASME Code Section III recuirements are met for non-destructive examination of oressure boundarv welds.

Inspections are 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-18-0179 Enclosure Page 4 of 11 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 completion of the 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) (Reference 1) documents satisfactory completion of the required examination and testing of the item, which includes non-destructive examinations of pressure boundary welds. Satisfactory completion of the non-destructive examination of pressure boundary welds ensures that the pressure boundary welds in components identified in Table 2.2.1-1 as ASME Code Section III meet ASME Code Section III requirements.

An inspection is performed in accordance with Reference 2 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 meet ASME Code Section III requirements (i.e., no unacceptable indications). This portion of the ITAAC is complete when the piping identified in Table 2.2.1-2, which is encompassed within the respective piping system Code Symbol N-Stampand 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 ultrasonictesting, as required by ASME Code Section III) of the piping pressure boundary welds are documented in the Non-destructive Examination Report(s) withinthe piping system's supporting data package, which support completion ofthe respective Code Stamping and Code N-5 Data Report(s). The completion of stampingthe 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 is 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 2.2.1-2 meet ASME Code Section III requirements and are documented in the Non-destructive Examination Report(s) within the supporting data packages.

4.a.n and 4.b1 A report exists and concludes that the results of the pressure test of the comoonents and oiDina identified in Tables 2.2.1-1 and 2.2.1-2 as ASME Code Section III conform with the reouirements of the ASME Code Section III.

A hydrostatic/pressure test is performed by the vendor 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 theirdesign pressure. The completion of the N-5 Data Reports is governed by Reference 2.

This portion ofthe ITAAC is complete once each component identified inTable 2.2.1 -1 has their individual Code Symbol N-Stamp and corresponding Code Data Report (Reference 1) completed, and the components are installed into the respective Code Symbol N-Stamped piping system and documented on the corresponding N-5 Code Data Report(s) (Reference 1). The hydrostatic/pressure testing results ofthe component's pressure boundary are documented in the

U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 5 of 11 Hydrostatic/Pressure Testing Report(s) within the supporting component's data package, which supportcompletion of the respective Code Stamping and Code Data Report(s).

The completion of stampingthe individual components and the respective piping system along with the corresponding ASME Code Data Reports (certified bythe Authorized Nuclear Inspector) ensures that the componentsare 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 CodeSection III are 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.

Ahydrostatic/pressure test is performed in accordance with procedure XYZ (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.

Ahydrostatic/pressure test verifies that there are no leaks at welds or piping, and thatthe pressure boundary integrity is 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) (Reference 1).

Theapplicable ASME Section III N-5 Code Data Report(s) (Reference 1) 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 andTable 2.2.1-2 respectively conform with the requirements of the ASME Code (1998 Edition, 2000 Addenda),Section III.

Reference 1 provides the evidence that the ITAAC Acceptance Criteria requirements are met;.

• The ASME Code Section III design reports existfor the as-built components and piping identified in Tables 2.2.1-1 and 2.2.1-2 as ASME Code Section III;

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

• A report exists and concludes that the results ofthe 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

• Areport exists and concludes that the results of the pressure test of the piping identified Table 2.2.1-2 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 2.2.01.02a Completion Packages (References 4 and 5, respectively).

U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 6 of 11 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 92, 93, 94, 95 and 97 found no relevant ITAAC findings associated with this ITAAC:

References favailable for NRG inspection)

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

2. APP-GW-GAP-139, "WestinghouseA/VECTEC 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. Completion Package for Unit 3 ITAAC 2.2.01.02a [COL Index Number 91]

5. Completion Package for Unit 4 ITAAC 2.2.01.02a [COL Index Number 91]

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

U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 7 of 11 Attachment A SYSTEM: Containment System (CNS)

ASME Code Equipment Name

• Tag No.

• N-5 Report Section III

• Service Air Supply Outside Containment Isolation Valve CAS-PL-V204 Yes N-5 Code Data Report Service Air Supply Inside Containment Isolation Check Valve CAS-PL-V205 Yes Instrument Air Supply Outside Containment Isolation Valve CAS-PL-V014 Yes N-5 Code Instrument Air Supply Inside Containment Isolation Check Data Report CAS-PL-V015 Yes Valve Component Cooling Water System (CCS) Containment CCS-PL-V200 Yes Isolation Motor-operated Valve (MOV) - Inlet Line Outside Reactor Containment (ORC) N-5 Code Data Report CCS Containment Isolation Check Valve - Inlet Line Inside Yes CCS-PL-V201 Reactor Containment (IRC)

CCS Containment Isolation MOV - Outlet Line IRC CCS-PL-V207 Yes CCS Containment Isolation MOV - Outlet Line ORC CCS-PL-V208 Yes N-5 Code Data Report CCS Containment Isolation Relief Valve - Outlet Line IRC CCS-PL-V220 Yes Demlnerallzed Water Supply Containment Isolation Valve DWS-PL-V244 Yes ORC N-5 Code Data Report Demlnerallzed Water Supply Containment Isolation Check DWS-PL-V245 Yes Valve IRC N-5 Code Fuel Transfer Tube FHS-FT-01 Yes Data Report N-5 Code Fuel Transfer Tube Isolation Valve FHS-PL-V001 Yes Data Report Fire Water Containment Supply Isolation Valve - Outside FPS-PL-V050 Yes N-5 Code Fire Water Containment Isolation Supply Check Valve - Data Report FPS-PL-V052 Yes Inside Spent Fuel Pool Cooling System (SFS) Discharge Line SFS-PL-V037 Yes Containment Isolation Check Valve - IRC N-5 Code Data Report SFS Discharge Line Containment Isolation MOV- ORC SFS-PL-V038 Yes SFS Suction Line Containment Isolation MOV - IRC SFS-PL-V034 Yes N-5 Code SFS Suction Line Containment Isolation MOV - ORC SFS-PL-V035 Yes Data Report SFS Suction Line Containment Isolation Relief Valve - IRC SFS-PL-V067 Yes

U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 8 of 11 Attachment A SYSTEM; Containment System (CNS)

ASME Code Equipment Name

• Tag No.

• N-5 Report Section ill

• Containment Purge Inlet Containment Isolation Valve - ORC VFS-PL-V003 Yes N-5 Code Data Report Containment Purge Inlet Containment Isolation Valve - IRC VFS-PL-V004 Yes Integrated Leak Rate Testing Vent Discharge Containment VFS-PL-V008 Yes Isolation Valve - ORC Containment Purge Discharge Containment Isolation Valve - VFS-PL-V009 Yes N-5 Code IRC Data Report Containment Purge Discharge Containment Isolation Valve - VFS-PL-V010 Yes ORC Vacuum Relief Containment Isolation A MOV - ORC VFS-PL-V800A Yes Vacuum Relief Containment Isolation B MOV - ORC VFS-PL-V800B Yes N-5 Code Data Report Vacuum Relief Containment Isolation Check Valve A - IRC VFS-PL-V803A Yes Vacuum Relief Containment Isolation Check Valve B - IRC VFS-PL-V803B Yes Fan Coolers Return Containment Isolation Valve - IRC VWS-PL-V082 Yes N-5 Code Fan Coolers Return Containment Isolation Valve - ORC VWS-PL-V086 Yes Data Report Fan Coolers Return Containment Isolation Relief Valve - IRC VWS-PL-V080 Yes Fan Coolers Supply Containment Isolation Valve - ORC VWS-PL-V058 Yes N-5 Code Fan Coolers Supply Containment Isolation Check Valve - VWS-PL-V062 Yes Data Report IRC Reactor Coolant Drain Tank (RCDT) Gas Outlet Containment WLS-PL-V067 Yes Isolation Valve - IRC N-5 Code Data Report RCDT Gas Outlet Containment Isolation Valve - ORC WLS-PL-V068 Yes Sump Discharge Containment Isolation Valve - IRC WLS-PL-V055 Yes N-5 Code Sump Discharge Containment Isolation Valve - ORC WLS-PL-V057 Yes Data Report Sump Discharge Containment Isolation Relief Valve - IRC WLS-PL-V058 Yes N-5 Code Spare Penetration CNS-PY-C01 Yes Data Report N-5 Code Spare Penetration CNS-PY-C02 Yes Data Report N-5 Code Spare Penetration CNS-PY-C03 Yes Data Report

U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 9 of 11 Attachment A SYSTEM: Containment System (CNS)

ASME Code Equipment Name

• Tag No.

• N-5 Report Section ill

• N-5 Code Main Equipment Hatch CNS-MY-Y01 Yes Data Report N-5 Code Maintenance Hatch CNS-MY-Y02 Yes Data Report N-5 Code Personnel Hatch CNS-MY-Y03 Yes Data Report N-5 Code Personnel Hatch CNS-MY-Y04 Yes Data Report N-5 Code Containment Vessel CNS-MV-01 Yes Data Report N-5 Code Electrical Penetration P03 DAS-EY-P03Z Yes Data Report N-5 Code Electrical Penetration P01 ECS-EY-P01X Yes Data Report N-5 Code Electrical Penetration P02 ECS-EY-P02X Yes Data Report N-5 Code Electrical Penetration P06 ECS-EY-P06Y Yes Data Report N-5 Code Electrical Penetration P07 ECS-EY-P07X Yes Data Report N-5 Code Electrical Penetration P09 ECS-EY-P09W Yes Data Report N-5 Code Electrical Penetration P10 ECS-EY-P10W Yes Data Report N-5 Code Electrical Penetration P11 IDSA-EY-P11Z Yes Data Report N-5 Code Electrical Penetration P12 IDSA-EY-P12Y Yes Data Report N-5 Code Electrical Penetration P13 IDSA-EY-P13Y Yes Data Report N-5 Code Electrical Penetration P14 IDSD-EY-P14Z Yes Data Report N-5 Code Electrical Penetration P15 IDSD-EY-P15Y Yes Data Report N-5 Code Electrical Penetration P16 IDSD-EY-P16Y Yes Data Report N-5 Code Electrical Penetration P17 ECS-EY-P17X Yes Data Report N-5 Code Electrical Penetration P18 ECS-EY-P18X Yes Data Report

U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 10 of 11 Attachment A SYSTEM; Containment System (CMS)

ASME Code Equipment Name

• Tag No.

• N-5 Report Section III

• N-5 Code Electrical Penetration PI 9 ECS-EY-P19Z Yes Data Report N-5 Code Electrical Penetration P20 ECS-EY-P20Z Yes Data Report N-5 Code Electrical Penetration P21 EDS-EY-P21Z Yes Data Report N-5 Code Electrical Penetration P22 ECS-EY-P22X Yes Data Report N-5 Code Electrical Penetration P23 ECS-EY-P23X Yes Data Report N-5 Code Electrical Penetration P24 ECS-EY-P24 Yes Data Report N-5 Code Electrical Penetration P25 ECS-EY-P25W Yes Data Report N-5 Code Electrical Penetration P26 ECS-EY-P26W Yes Data Report N-5 Code Electrical Penetration P27 IDSC-EY-P27Z Yes Data Report N-5 Code Electrical Penetration P28 IDSC-EY-P28Y Yes Data Report N-5 Code Electrical Penetration P29 IDSC-EY-P29Y Yes Data Report N-5 Code Electrical Penetration P30 IDSB-EY-P30Z Yes Data Report N-5 Code Electrical Penetration P31 IDSB-EY-P31Y Yes Data Report N-5 Code Electrical Penetration P32 IDSB-EY-P32Y Yes Data Report N-5 Code Instrument Penetration P46 PCS-PY-C01 Yes Data Report N-5 Code Instrument Penetration P47 PCS-PY-C02 Yes Data Report N-5 Code Instrument Penetration P48 PCS-PY-C03 Yes Data Report N-5 Code Instrument Penetration P49 PCS-PY-C04 Yes Data Report

'Excerpt from COL Appendix C Table 2.2.1-1

U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 11 of 11 Attachment B SYSTEM: Containment System (CNS)

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

Instrument Air In CAS-PL-L015 + Yes N-5 Code Data Report Service Air In CAS-PL-L204 + Yes N-5 Code Data Report Component Cooling Water CCS-PL-L201 Yes N-5 Code Data Report Supply to Containment Component Cooling Water CCS-PL-L207 Yes N-5 Code Data Report Outlet from Containment Demineralized Water In DWS-PL-L245 +, L230 Yes N-5 Code Data Report Fire Protection Supply to FPS-PL-L107 Yes N-5 Code Data Report Containment Containment Atmosphere PSS-PL-L038 + Yes N-5 Code Data Report Return Line Common Primary Sample PSS-PL-T005A/B Yes N-5 Code Data Report Line A/B Containment Atmosphere PSS-PL-T031 Yes N-5 Code Data Report Sample Line Spent Fuel Pool Cooling SFS-PL-L017 Yes N-5 Code Data Report Discharge Spent Fuel Pool Cooling SFS-PL-L038 Yes N-5 Code Data Report Suction from Containment Containment Purge Inlet to VFS-PL-L104, LI 05, LI 06 Yes N-5 Code Data Report Containment VFS-PL-L203, L204, L205, Containment Purge Discharge L800, L801A/B, L803, L804, Yes N-5 Code Data Report from Containment L805A/B, L810A/B, L832 Fan Cooler Supply Line to VWS-PL-L032 Yes N-5 Code Data Report Containment Fan Cooler Return Line from VWS-PL-L055 Yes N-5 Code DataReport Containment RCDT Gas Out WLS-PL-L022 Yes N-5 Code DataReport Waste Sump Out WLS-PL-L073 Yes N-5 Code DataReport

'Excerpt from COL Appendix C, Table 2.2.1-2

+ These lines require that dynamic loads in its pipe stressanalysis 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 3)