ND-23-0476, ITAAC Closure Notification on Completion of ITAAC 2.3.06.02a (Index Number 355)

ITAAC Closure Notification on Completion of ITAAC 2.3.06.02a (Index Number 355)

ML23196A002
Person / Time
Site:	Vogtle
Issue date:	07/15/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-23-0476, ITAAC 2.3.06.02a
Download: ML23196A002 (1)

Text

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel July 15, 2023 Docket No.:

52-026 ND-23-0476 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 2.3.06.02a [Index Number 355]

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 2.3.06.02a [Index Number 355]. This ITAAC verifies that the Normal Residual Heat Removal System (RNS) components listed in the Combined License (COL) Appendix C, Tables 2.3.6-1 and 2.3.6-2 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 of ITAAC 2.3.06.02a [Index Number 355]

JMC/TL/sfr

U.S. Nuclear Regulatory Commission ND-23-0476 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-23-0476 Enclosure Page 1 of 12 Southern Nuclear Operating Company ND-23-0476 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.3.06.02a [Index Number 355]

U.S. Nuclear Regulatory Commission ND-23-0476 Enclosure Page 2 of 12 ITAAC Statement Design Commitment:

2.a) The components identified in Table 2.3.6-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.

2.b) The piping identified in Table 2.3.6-2 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 2.3.6-1 as ASME Code Section III meet ASME Code Section III requirements.

3.b) Pressure boundary welds in piping identified in Table 2.3.6-2 as ASME Code Section III meet ASME Code Section III requirements.

4.a) The components identified in Table 2.3.6-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.

4.b) The piping identified in Table 2.3.6-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.

5.b) Each of the lines identified in Table 2.3.6-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability.

6. Each of the as-built lines identified in Table 2.3.6-2 as designed for LBB meets the LBB criteria, or an evaluation is performed of the protection from the dynamic effects of a rupture of the line.

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

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

Inspection will be performed for the existence of an LBB evaluation report or an evaluation report on the protection from dynamic effects of a pipe break. Section 3.3, Nuclear Island Buildings, contains the design descriptions and inspections, tests, analyses, and acceptance criteria for protection from the dynamic effects of pipe rupture.

U.S. Nuclear Regulatory Commission ND-23-0476 Enclosure Page 3 of 12 Acceptance Criteria:

The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.3.6-1 and 2.3.6-2 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 hydrostatic test of the components and piping identified in Tables 2.3.6-1 and 2.3.6-2 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 2.3.6-2 for which functional capability is required meets the requirements for functional capability.

An LBB evaluation report exists and concludes that the LBB acceptance criteria are met by the as-built RNS piping and piping materials, or a pipe break evaluation report exists and concludes that protection from the dynamic effects of a line break is provided.

ITAAC Determination Basis This ITAAC requires inspections, tests, and analyses be performed and documented to ensure the Normal Residual Heat Removal System (RNS) components and piping listed in the Combined License (COL) Appendix C, Table 2.3.6-1 (Attachment A) and Table 2.3.6-2 (Attachment B) that are identified as American Society of Mechanical Engineers (ASME) Code Section III, Leak Before Break (LBB), 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 2.3.6-1 and 2.3.6-2 as ASME Code Section III.

Each component listed in Table 2.3.6-1 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 is 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 (Reference 1).

The as-built piping listed in Table 2.3.6-2 including the components listed in Table 2.3.6-1 as ASME Code Section III, were subjected to a reconciliation process (Reference 2), which verifies 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, is consistent with and bounded by the approved design. All applicable fabrication, installation and testing records, as well as, those for the related Quality Assurance (QA) 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.

U.S. Nuclear Regulatory Commission ND-23-0476 Enclosure Page 4 of 12 The applicable ASME Section III N-5 Code Data Report(s), which include the location of the certified Design Reports for all the components listed in Table 2.3.6-1 (Attachment A) and piping listed in Table 2.3.6-2 (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 Reports for the piping system(s) containing the components listed in the Table 2.3.6-1 and Table 2.3.6-2 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 Table 2.3.6-1 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(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 (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 2.3.6-1 as ASME Code Section III meets 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 2.3.6-2 (Attachment B) as ASME Code Section III met ASME Code Section III requirements (i.e., no unacceptable indications). This portion of the ITAAC was complete when the piping identified in Table 2.3.6-2, which is encompassed within the respective piping system Code Symbol N-Stamp and the corresponding piping system Code N-5 Data Report Form(s) (Reference 1), 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 are 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 2.3.6-2 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 hydrostatic test of the components and piping identified in Tables 2.3.6-1 and 2.3.6-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.

U.S. Nuclear Regulatory Commission ND-23-0476 Enclosure Page 5 of 12 A hydrostatic test was performed by the vendor to demonstrate that the components identified in Table 2.3.6-1 (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.

This portion of the ITAAC was complete once each component identified in Table 2.3.6-1 had 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 (Reference 1). The hydrostatic testing results of the components pressure boundary are documented in the Hydrostatic Testing Report(s) within the 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 2.3.6-1 as ASME Code Section III were documented in the Hydrostatic Testing Report(s) within the supporting data packages and met ASME Code Section III requirements.

This ITAAC also verifies that the piping identified in Table 2.3.6-2 (Attachment B) fully meets all applicable ASME Code,Section III requirements and retains its pressure boundary integrity at its design pressure.

Hydrostatic tests were performed in accordance with procedures identified in Reference 1 (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 2.3.6-2 retains its pressure boundary integrity at its design pressure.

A hydrostatic test verifies that there are no leaks at welds or piping, and that the pressure boundary integrity is retained at its design pressure. The hydrostatic testing results of the pipe lines are documented in the Hydrostatic Testing Report(s). The Hydrostatic Testing Report(s) supports completion of the ASME Section III N-5 Code Data Report(s) for the applicable piping system (i.e., RNS) (Reference 1).

The applicable ASME Section III N-5 Code Data Report(s) (Reference 1) identified in Attachments A and B documents that the results of the hydrostatic testing of the components and piping identified in Table 2.3.6-1 and Table 2.3.6-2 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 2.3.6-2 for which functional capability is required meets the requirements for functional capability.

An inspection was performed of the ASME Section III as-built piping design report (Reference 4) to verify that the report demonstrates that each of the RNS piping lines identified in ITAAC Table 2.3.6-2 that requires functional capability is 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-23-0476 Enclosure Page 6 of 12 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 are 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 are subjected to a reconciliation process (Reference 2), which verifies that the as-built piping systems are 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, is consistent with and bounded by the approved design. As required by ASME Code, the As-Built Design Report includes the results of physical inspection of the piping and reconciliation to the design pipe stress report.

Inspections of the ASME Code Section III As-Built Piping Design Reports (Reference 4) for the RNS piping lines identified in Table 2.3.6-2 are complete and conclude that each of the as-built RNS piping lines for which functional capability is required meets the requirements for functional capability. The ASME Section III As-Built Piping Design Reports for each of the as-built RNS piping lines in Table 2.3.6-2 are identified in Attachment B.

6. An LBB evaluation report exists and concludes that the LBB acceptance criteria are met by the as-built RNS piping and piping materials, or a pipe break evaluation report exists and concludes that protection from the dynamic effects of a line break is provided.

Inspections were performed for the as-built lines identified in Table 2.3.6-2 (Attachment B) to verify that each of the as-built lines designed for LBB meets the LBB criteria, or an evaluation is performed of the protection from the dynamic effects of a rupture of the line. VEGP COL Appendix C, Section 3.3, Nuclear Island Buildings, contains the design descriptions and inspections, tests, analyses, and acceptance criteria for protection from the dynamic effects of pipe rupture.

LBB evaluations were performed as described in UFSAR subsection 3.6.3 to confirm that the as-built RNS piping (and corresponding piping materials) identified in Attachment A meet the LBB acceptance criteria described in the UFSAR, Appendix 3B, Leak-Before-Break Evaluation of the AP1000 Piping (Reference 3). In cases where an as-built RNS piping line in Attachment B cannot meet the LBB acceptance criteria, a pipe break evaluation is performed which concludes that protection from the dynamic effects of a line break is provided. The pipe break evaluation criteria is discussed in UFSAR, Section 3.6.4.1, Pipe Break Hazards Analysis (Reference 3) and is documented as a pipe rupture hazards analysis report (pipe break evaluation report).

Inspections were performed to verify that LBB as-built piping evaluation reports for the RNS piping (and corresponding piping materials) identified in Attachment B conclude that the as-built piping analysis is bounded by the applicable bounding analysis curves provided in Appendix 3B of the UFSAR (Reference 3). The results are documented in either the applicable ASME Section III as-built piping design report(s) or in separate LBB evaluation report(s). For cases where an as-built RNS piping line in Attachment B cannot meet the LBB acceptance criteria, inspections are performed to verify that a pipe rupture hazards analysis evaluation report (pipe break evaluation report) exists which concludes that protection from the dynamic effects of a line break is provided.

U.S. Nuclear Regulatory Commission ND-23-0476 Enclosure Page 7 of 12 The applicable ASME Section III as-built piping design report(s), LBB evaluation report(s), or pipe rupture hazards analysis report(s) (pipe break evaluation report(s)) exist and are identified in Attachment B.

References 1,4 and 8 provide the evidence that the following ITAAC Acceptance Criteria requirements are met:

The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.3.6-1 and 2.3.6-2 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 hydrostatic test of the components and piping identified in Tables 2.3.6-1 and 2.3.6-2 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 2.3.6-2 for which functional capability is required meets the requirements for functional capability; and An LBB evaluation report exists and concludes that the LBB acceptance criteria are met by the as-built RNS piping and piping materials, or a pipe break evaluation report exists and concludes that protection from the dynamic effects of a line break is provided.

This ITAAC also verified that a Preservice Inspection (PSI) for the applicable portions of the Normal Residual Heat Removal System (RNS) identified in Tables 2.3.6-1 and 2.3.6-2 were completed (Reference 7), in accordance with the Unit 4 PSI program plan (Reference 5), and that the results of the PSI conforms with the requirements of the ASME Boiler and Pressure Vessel (B&PV) Code.

Examinations are conducted for each system in accordance with Section XI of the ASME B&PV Code, Subsections IWB, IWC, and IWD-2200 to satisfy the requirements for PSI.

References 1, 4 and 8 are available for NRC inspection as part of the Unit 4 ITAAC 2.3.06.02a Completion Package (Reference 6).

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 356, 357, 358, 359, 360, 364 and 365, found no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.3.06.02a (Reference 6) and is available for NRC review.

U.S. Nuclear Regulatory Commission ND-23-0476 Enclosure Page 8 of 12 ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.3.06.02a 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-RNS-MUR-001, Rev. 0, AP1000 Vogtle Unit 4 ASME Section III System Code Data Report for the Normal Residual Heat Removal System (RNS)

2. APP-GW-GAP-139, Rev. 9, Westinghouse/Stone & Webster ASME Code Data Report and As-Built Documentation Interface Procedure

3. VEGP 3&4 Updated Final Safety Analysis Report, Rev. 12, Subsection 5.2.1, Compliance with Codes and Code Cases

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 3.6.3 - Leak before Break Evaluation Procedures

d. Subsection 3.6.4.1-Pipe Break Hazards Analysis

e. Appendix 3B - Leak-Before-Break Evaluation of the AP1000 Piping

4. SV4-RNS-S3R-001, Rev. 0, Vogtle Unit 4 Normal Residual Heat Removal System (RNS)

ASME Section III As-Built Piping System Design Report

5. SV4-GW-GEI-100, Rev. 1, AP1000 Preservice Inspection Program Plan for Vogtle Unit 4

6. 2.3.06.02a-U4-CP-Rev0, ITAAC Completion Package

7. APE-10-00027, Completion of Preservice Inspection for the Vogtle Unit 4 PXS, SGS, and RNS Class 1, 2 and 3 Portions of Systems

8. SV4-RNS-P0R-0102, Rev 1, AP1000 Piping for APP-RNS-PLR-010 - Vogtle Unit 4 ASME III As-Built Design Report

U.S. Nuclear Regulatory Commission ND-23-0476 Enclosure Page 9 of 12 Attachment A SYSTEM: Normal Residual Heat Removal System (RNS)

Equipment Name*

Tag No.*

ASME Code Section III*

ASME III as-built Design Report N-5 Report RNS Pump A (Pressure Boundary)

RNS-MP-01A Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Pump B (Pressure Boundary)

RNS-MP-01B Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Heat Exchanger A (Tube Side)

RNS-ME-01A Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Heat Exchanger B (Tube Side)

RNS-ME-01B Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RCS Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001A Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RCS Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001B Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RCS Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002A Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RCS Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002B Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RCS Pressure Boundary Thermal Relief Check Valve RNS-PL-V003A Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RCS Pressure Boundary Thermal Relief Check Valve RNS-PL-V003B Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Discharge Motor-operated Containment Isolation Valve RNS-PL-V011 Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Discharge Containment Isolation Test Connection RNS-PL-V012 Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Discharge Header Containment Isolation Check Valve RNS-PL-V013 Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Discharge RCS Pressure Boundary Check Valve RNS-PL-V015A Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Discharge RCS Pressure Boundary Check Valve RNS-PL-V015B Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Discharge RCS Pressure Boundary Check Valve RNS-PL-V017A Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001

U.S. Nuclear Regulatory Commission ND-23-0476 Enclosure Page 10 of 12 Attachment A SYSTEM: Normal Residual Heat Removal System (RNS)

Equipment Name*

Tag No.*

ASME Code Section III*

ASME III as-built Design Report N-5 Report RNS Discharge RCS Pressure Boundary Check Valve RNS-PL-V017B Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Hot Leg Suction Pressure Relief Valve RNS-PL-V020 Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Hot Leg Suction Pressure Relief Valve RNS-PL-V021 Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Suction Header Motor-operated Containment Isolation Valve RNS-PL-V022 Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Suction from IRWST Motor-operated Isolation Valve RNS-PL-V023 Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Discharge to IRWST Motor-operated Isolation Valve RNS-PL-V024 Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Pump Discharge Relief RNS-PL-V045 Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Suction from Cask Loading Pit Motor-operated Isolation Valve RNS-PL-V055 Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Suction from Cask Loading Pit Check Valve RNS-PL-V056 Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Pump Miniflow Air-Operated Isolation Valve RNS-PL-V057A Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Pump Miniflow Air-Operated Isolation Valve RNS-PL-V057B Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001 RNS Return from Chemical and Volume Control System (CVS) Containment Isolation Valve RNS-PL-V061 Yes SV4-RNS-S3R-001 SV4-RNS-MUR-001

• Excerpts from COL Appendix C Table 2.3.6-1

U.S. Nuclear Regulatory Commission ND-23-0476 Enclosure Page 11 of 12 Attachment B SYSTEM: Normal Residual Heat Removal System (RNS)

Line Name*

Line No.*

ASME Code Section III*

Leak Before Break*

Functional Capability Required*

ASME III As-Built Design Report LBB evaluation /

pipe break evaluation N-5 Report RNS Suction Lines, from the RCS Hot Leg Connection to the RCS Side of Valves RNS PL-V001A and RNS-PL-V001B RNS-L001 RNS-L002A RNS-L002B Yes Yes No SV4-RNS-S3R-001 SV4-RNS-P0R-0102 No Impact on Archived Analysis SV4-RNS-MUR-001 RNS Suction Lines, from the RCS Pressure Boundary Valves, RNS-PL-V001A and RNS-PL-V001B, to the RNS pumps RNS-L004A RNS-L004B RNS-L005 RNS-L006 RNS-L007A RNS-L007B RNS-L009A RNS-L009B Yes No Yes Yes Yes Yes Yes Yes Yes Yes SV4-RNS-S3R-001 N/A SV4-RNS-MUR-001 RNS Suction Line from CVS RNS-L061 Yes No Yes SV4-RNS-S3R-001 N/A SV4-RNS-MUR-001 RNS Suction Line from IRWST RNS-L029 Yes No Yes SV4-RNS-S3R-001 N/A SV4-RNS-MUR-001 RNS Suction Line LTOP Relief RNS-L040 RNS-L090 Yes No Yes SV4-RNS-S3R-001 N/A SV4-RNS-MUR-001 RNS Discharge Lines, from the RNS Pumps to the RNS Heat Exchangers RNS-ME-01A and RNS-ME-01B RNS-L011A RNS-L011B Yes No Yes SV4-RNS-S3R-001 N/A SV4-RNS-MUR-001 RNS Discharge Lines, from RNS Heat Exchanger RNS-ME-01A to Containment Isolation Valve RNS-PL-V011 RNS-L012A RNS-L014 Yes No Yes SV4-RNS-S3R-001 N/A SV4-RNS-MUR-001 RNS Discharge Line, from RNS Heat Exchanger RNS-ME-01B to Common Discharge Header RNS-L014 RNS-L012B Yes No Yes SV4-RNS-S3R-001 N/A SV4-RNS-MUR-001 RNS Discharge Lines, Containment Isolation Valve RNS-PL-V011 to Containment Isolation Valve RNS-PL-V013 RNS-L016 Yes No Yes SV4-RNS-S3R-001 N/A SV4-RNS-MUR-001 RNS Suction Line from Cask Loading Pit RNS-L065 Yes No No SV4-RNS-S3R-001 N/A SV4-RNS-MUR-001 RNS Discharge Lines, from Containment Isolation Valve RNS-PL-V013 to RCS Pressure Boundary Isolation RNS-L017 RNS-L018A RNS-L018B Yes No Yes SV4-RNS-S3R-001 N/A SV4-RNS-MUR-001

U.S. Nuclear Regulatory Commission ND-23-0476 Enclosure Page 12 of 12 Attachment B SYSTEM: Normal Residual Heat Removal System (RNS)

Line Name*

Line No.*

ASME Code Section III*

Leak Before Break*

Functional Capability Required*

ASME III As-Built Design Report LBB evaluation /

pipe break evaluation N-5 Report Valves RNS-PL-V015A and RNS-PL-V015B RNS Discharge Lines, from Direct Vessel Injection (DVI)

Line RNS-BBC-L018A to Passive Core Cooling System (PXS) IRWST Return Isolation Valve RNS-PL-V024 RNS-L020 Yes No No SV4-RNS-S3R-001 N/A SV4-RNS-MUR-001 RNS Discharge Lines, from RCS Pressure Boundary Isolation Valves RNS-PL-V015A and RNS-PL-V015B to RCS Pressure Boundary Isolation Valves RNS-PL-V017A and RNS-PL-V017B RNS-L019A RNS-L019B Yes No Yes SV4-RNS-S3R-001 N/A SV4-RNS-MUR-001 RNS Heat Exchanger Bypass RNS-L008A RNS-L008B Yes No No SV4-RNS-S3R-001 N/A SV4-RNS-MUR-001 RNS Suction from Spent Fuel Pool RNS-L052 Yes No No SV4-RNS-S3R-001 N/A SV4-RNS-MUR-001 RNS Pump Miniflow Return RNS-L030A RNS-L030B Yes No No SV4-RNS-S3R-001 N/A SV4-RNS-MUR-001 RNS Discharge to Spent Fuel Pool RNS-L051 Yes No No SV4-RNS-S3R-001 N/A SV4-RNS-MUR-001 RNS Discharge to CVS Purification RNS-L021 Yes No No SV4-RNS-S3R-001 N/A SV4-RNS-MUR-001

• Excerpts from COL Appendix C, Table 2.3.6-2