ND-21-0744, Vogtie Electric Generating Plant, Unit 3, ITAAC Closure Notification on Completion of ITAAC 2.3.06.02a (Index Number 355)

Vogtie Electric Generating Plant, Unit 3, ITAAC Closure Notification on Completion of ITAAC 2.3.06.02a (Index Number 355)

ML22021B574
Person / Time
Site:	Vogtle
Issue date:	01/21/2022
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-0744
Download: ML22021B574 (15)

Text

Michael J. Yox 7825 River Road Sk. Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtie 3 & 4 706-848-6459 tel JAN 2 1 2022 Docket No.: 52-025 ND-21-0744 10CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.3.06.02a [Index Number 3551 Ladies and Gentlemen:

In accordance with 10 CFR 52.99(c)(1), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the completion of Vogtie Electric Generating Plant(VEGP) Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.06.02a [Index Number 355]. 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 and Table 2.3.6-2 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. The closure process for this ITAAC is based on the guidance described in Nuclear Energy Institute (NEI) 08-01, Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52, which was endorsed by the NRC in Regulatory Guide 1.215.

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99.

If there are any questions, please contact Kelli A. Roberts at 706-848-6991.

Respectfully submitted.

Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.3.06.02a [Index Number 355]

MJY/JRV/sfr

U.S. Nuclear Regulatory Commission ND-21-0744 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKlnney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. J.B. Williams Mr. M. J. Yox 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. Belike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Requlatorv Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil Mr. C. P. Patel Mr. G. J. Khourl Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. O. Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Mr. T. Fanelll Ms. K. McCurry Mr. J. Parent Mr. B. Griman Mr. V. Hall

U.S. Nuclear Regulatory Commission ND-21-0744 Page 3 of 3 Ogiethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinghouse Electric Company. LLC Dr. L. Oriani Mr. D. C. Durham Mr. M. M. Corletti Mr. J. L. Coward Other Mr. S.W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., CDS Associates, inc.

Mr. 8. Roetger, Georgia Public Service Commission Ms. R.L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-21-0744 Enclosure Page 1 of 12 Southern Nuclear Operating Company ND-21-0744 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.3.06.02a [Index Number 355]

U.S. Nuclear Regulatory Commission ND-21-0744 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-bullt 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-21-0744 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 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 2.3.6-2 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(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.

U.S. Nuclear Regulatory Commission ND-21-0744 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 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 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 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 2.3.6-1 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 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 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.

U.S. Nuclear Regulatory Commission ND-21-0744 Enclosure Page 5 of 12 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.

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 component's pressure boundary are documented in the Hydrostatic Testing Report(s) within the 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 2.3.6-1 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 capabilitv is required meets the reouirements for functional caoabilitv.

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 was designed to withstand combined normal and seismic design basis loads without a loss of its functional capability. "Functional capability," in

U.S. Nuclear Regulatory Commission ND-21-0744 Enclosure Page 6 of 12 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).

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 were 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 bv the as-built RNS Dioing and piping materials, or a oioe break evaluation reoort exists and concludes that protection from the dvnamic 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 0, 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 API000 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

U.S. Nuclear Regulatory Commission ND-21-0744 Enclosure Page 7 of 12 break evaluation report) exists which concludes that protection from the dynamic effects of a line break is provided.

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 3 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 3 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-21-0744 Enclosure Page 8 of 12 ITAAC Completion Statement Based on the above Information, SNC hereby notifies the NRG that ITAAC 2.3.06.02a 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(available for NRG inspection)

1. SV3-RNS-MUR-001, Rev. 0,"API000 Vogtle Unit 3 ASME Section III System Code Data Report for the Normal Residual Heat Removal System (RNS)"

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

3. VEGP 3&4 Updated Final Safety Analysis Report, Rev. 10.1, 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 API000 Piping

4. SV3-RNS-S3R-001, Rev. 1,"Vogtle Unit 3 Normal Residual Heat Removal System (RNS)

ASME III As-Built Piping System Design Report"

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

6. 2.3.06.02a-U3-CP-Rev0, ITAAC Completion Package

7. APE-10-00019,"Unit 3 - Completion of Preservice Inspection for RNS Class 2 and 3 Portions of Systems"

8. SV3-RNS-P0R-0102, Rev, 1,"API000 Piping for APP-RNS-PLR-010 - Vogtle Unit 3 ASME III As-Built Design Report"

U.S. Nuclear Regulatory Commission ND-21-0744 Enclosure Page 9 of 12 Attachment A SYSTEM: Normal Residual Heat Removal System (RNS)

ASME Code ASME ill as-bufit Equipment Name* Tag No.* Section ill* Design Report N-5 Report RNS Pump A RNS-MP-01A Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 (Pressure Boundary)

RNS Pump B RNS-MP-01B Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 (Pressure Boundary)

RNS Heat Exchanger A RNS-ME-01A Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 (Tube Side)

RNS Heat Exchanger B RNS-ME-01B Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 (Tube Side)

RCS Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001A Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 RCS Inner Hot Leg Suction RNS-PL-V001B Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Motor-operated Isolation Valve RCS Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002A Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 RCS Outer Hot Leg Suction RNS-PL-V002B Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Motor-operated Isolation Valve RCS Pressure Boundary RNS-PL-V003A Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Thermal Relief Check Valve RCS Pressure Boundary RNS-PL-V003B Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Thermal Relief Check Valve RNS Discharge Motor-operated RNS-PL-V011 Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Containment Isolation Valve RNS Discharge Containment RNS- PL-V012 Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Isolation Test Connection RNS Discharge Header Containment Isolation RNS-PL-V013 Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Check Valve RNS Discharge RCS Pressure RNS-PL-V015A Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Boundary Check Valve RNS Discharge RCS Pressure RNS-PL-V015B Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Boundary Check Valve RNS Discharge RCS Pressure Boundary RNS-PL-V017A Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Check Valve

U.S. Nuclear Regulatory Commission ND-21-0744 Enclosure Page 10 of 12 Attachment A ASME Code ASME III as-bullt Equipment Name* Tag No.* Section III* Design Report N-5 Report RNS Discharge RCS Pressure Boundary RNS-PL-V017B Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Check Valve RNS Hot Leg Suction RNS-PL-V020 Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Pressure Relief Valve RNS Hot Leg Suction RNS-PL-V021 Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Pressure Relief Valve RNS Suction Header Motor-operated RNS-PL-V022 Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Containment Isolation Valve RNS Suction from IRWST RNS-PL-V023 Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Motor-operated Isolation Valve RNS Discharge to IRWST RNS-PL-V024 Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Motor-operated Isolation Valve RNS Pump Discharge Relief RNS-PL-V045 Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 RNS Suction from Cask Loading Pit RNS-PL-V055 Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Motor-operated Isolation Valve RNS Suction from Cask RNS-PL-V056 Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Loading Pit Check Valve RNS Pump Miniflow RNS-PL-V057A Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Air-Operated Isolation Valve RNS Pump Miniflow RNS-PL-V057B Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 Air-Operated Isolation Valve RNS Return from Chemical and Volume Control System RNS-PL-V061 Yes SV3-RNS-S3R-001 SV3-RNS-MUR-001 (CVS) Containment Isolation Valve

• Excerpts from COL Appendix C Table 2.3.6-1

U.S. Nuclear Regulatory Commission ND-21-0744 Enclosure Page 11 of 12 Attachment B SYSTEM: Normal Residual Heat Removal System (RNS)

ASME III LBB ASME Leak Functional Line Name* As-Bullt evaluation /

Line No.* Code Before Capability N-5 Report Design pipe break Section ill* Break* Required*

Report evaluation RNS Suction Lines, from the RCS Hot Leg SV3-RNS-RNS-L001 POR-0102 Connection to the RCS SV3-RNS- SV3-RNS-Side of Valves RNS PL-RNS-L002A Yes Yes No No Impact S3R-001 MUR-001 RNS-L002B on Archived VOOIAand RNS-PL-V001B Analysis RNS-L004A Yes RNS-L004B Yes RNS Suction Lines, from RNS-L005 Yes the RCS Pressure RNS-L006 Yes SV3-RNS- SV3-RNS-Boundary Valves, RNS- Yes No N/A RNS-L007A Yes S3R-001 MUR-001 PL-V001A and RNS-PL-RNS-L007B Yes V001B, to the RNS pumps RNS-L009A Yes RNS-L009B Yes RNS Suction Line from SV3-RNS- SV3-RNS-RNS-L061 Yes No Yes N/A CVS S3R-001 MUR-001 RNS Suction Line from SV3-RNS- SV3-RNS-RNS-L029 Yes No Yes N/A IRWST S3R-001 MUR-001 RNS Suction Line LTOP RNS-L040 SV3-RNS- SV3-RNS-Yes No Yes N/A Relief RNS-L090 S3R-001 MUR-001 RNS Discharge Lines, from the RNS Pumps to RNS-L011A SV3-RNS- SV3-RNS-the RNS Heat Exchangers Yes No Yes N/A RNS-L011B S3R-001 MUR-001 RNS-ME-OIAand RNS-ME-01B RNS Discharge Lines, from RNS Heat Exchanger RNS-L012A SV3-RNS- SV3-RNS-RNS-ME-OIAto Yes No Yes N/A RNS-L014 S3R-001 MUR-001 Containment Isolation Valve RNS-PL-V011 RNS Discharge Line, from RNS Heat Exchanger SV3-RNS- SV3-RNS-RNS-ME-01B to Common RNS-L012B Yes No Yes N/A S3R-001 MUR-001 Discharge Header RNS-L014 RNS Discharge Lines, Containment Isolation SV3-RNS- SV3-RNS-Valve RNS-PL-V011 to RNS-L016 Yes No Yes N/A S3R-001 MUR-001 Containment Isolation Valve RNS-PL-V013

U.S. Nuclear Regulatory Commission ND-21-0744 Enclosure Page 12 of 12 Attachment B SYSTEM: Normal Residual Heat Removal System (RNS)

ASME III LBB ASME Leak Functional Line Name* Line No.* As-Buiit evaluation /

Code Before Capability N-5 Report Section iil* Break* Required*

Design pipe break Report evaluation RNS Suction Line from SV3-RNS- SV3-RNS-RNS-L065 Yes No No N/A Cask Loading Pit S3R-001 MUR-001 RNS Discharge Lines, from Containment Isolation Valve RNS-PL-V013to RNS-L017 RCS Pressure Boundary SV3-RNS- SV3-RNS-RNS-L018A Yes No Yes N/A Isolation Valves RNS-PL- S3R-001 MUR-001 RNS-L018B VOISAand RNS-PL-V015B RNS Discharge Lines, from Direct Vessel Injection (DVI) Line RNS-BBC-L018A to Passive SV3-RNS- SV3-RNS-RNS-L020 Yes No No N/A Core Cooling System S3R-001 MUR-001 (PXS)IRWST Return Isolation Valve RNS-PL-V024 RNS Discharge Lines, from RCS Pressure Boundary Isolation Valves RNS-PL-V015Aand RNS-RNS-L019A SV3-RNS- SV3-RNS-PL-V015BtoRCS Yes No Yes N/A RNS-L019B S3R-001 MUR-001 Pressure Boundary Isolation Valves RNS-PL-V017Aand RNS-PL-V017B RNS Heat Exchanger RNS-L008A SV3-RNS- SV3-RNS-Yes No No N/A Bypass RNS-L008B S3R-001 MUR-001 RNS Suction from Spent SV3-RNS- SV3-RNS-RNS-L052 Yes No No N/A Fuel Pool S3R-001 MUR-001 RNS Pump Miniflow RNS-L030A SV3-RNS- SV3-RNS-Yes No No N/A Return RNS-L030B S3R-001 MUR-001 RNS Discharge to Spent SV3-RNS- SV3-RNS-RNS-L051 Yes No No N/A Fuel Pool S3R-001 MUR-001 RNS Discharge to CVS SV3-RNS- SV3-RNS-RNS-L021 Yes No No N/A Purification S3R-001 MUR-001

'Excerpts from COL Appendix C, Table 2.3.6-2