ND-21-0723, ITAAC Closure Notice on Completion of ITAAC 2.2.03.02a (Index Number 159)

ITAAC Closure Notice on Completion of ITAAC 2.2.03.02a (Index Number 159)

ML22053A307
Person / Time
Site:	Vogtle
Issue date:	02/22/2022
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 2.2.03.02a, ND-21-0723
Download: ML22053A307 (20)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel FEB 2 2 2022 Docket No.: 52-025 ND-21-0723 10CFR 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 Notice on Completion of ITAAC 2.2.03.02a [Index Number 1591 Ladies and Gentiemen:

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 2.2.03.02a [Index Number 159]. This ITAAC requires inspections, tests, and analyses be performed and documented to ensure the Passive Core Cooling System (PXS) components and piping listed in the Combined License (COL) Appendix C, Table 2.2.3-1 and Table 2.2.3-2 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 Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.2.03.02a [Index Number 159]

MJY/JRV/sfr

U.S. Nuclear Regulatory Commission ND-21-0723 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. 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 Reoulatorv Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil Mr. C. P. Patel Mr. G. J. Khouri 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. Fanelli Ms. K. McCurry Mr. J. Parent Mr. B. Griman Mr. V. Hall

U.S. Nuclear Regulatory Commission ND-21-0723 Page 3 of 3 Qqlethorpe 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 Westinqhouse Electric Company. LLC Dr. L. Oriani Mr. D. 0. Durham Mr. M. M. CorlettI Mr. Z.S. 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, Baich Bingham

U.S. Nuclear Regulatory Commission ND-21-0723 Enclosure Page 1 of 17 Southern Nuclear Operating Company ND-21-0723 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.2.03.02a [Index Number 159]

U.S. Nuclear Regulatory Commission ND-21-0723 Enclosure Page 2 of 17 ITAAC Statement Desion Commitment:

2.a) The components identified in Table 2.2.3-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.

2.b) The piping identified in Table 2.2.3-2 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 2.2.3-1 as ASME Code Section III meet ASME Code Section III requirements.

3.b) Pressure boundary welds in piping identified in Table 2.2.3-2 as ASME Code Section III meet ASME Code Section III requirements.

4.a) The components identified in Table 2.2.3-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.

4.b) The piping identified in Table 2.2.3-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.

5.b) Each of the lines identified in Table 2.2.3-2 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 2.2.3-2 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. Analvses:

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 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-21-0723 Enclosure Page 3 of 17 Acceptance Criteria:

The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.2.3-1 and 2.2.3-2 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 2.2.3-1 and 2.2.3-2 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 2.2.3-2 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 PXS 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 Passive Core Cooling System (PXS)components and piping listed in the Combined License (COL) Appendix C, Table 2.2.3-1 (Attachment A) and Table 2.2.3-2 (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 2.2.3-1 and 2.2.3-2 as ASME Code Section III.

Each component listed in Table 2.2.3-1 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 2.2.3-2 including the components listed in Table 2.2.3-1 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-21-0723 Enclosure Page 4 of 17 The applicable ASME Section III N-5 Code Data Report(s)(Reference 1), which Include the location of the certified Design Reports for all the components listed In Table 2.2.3-1 (Attachment A)and piping listed In Table 2.2.3-2 (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-bullt 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 (Reference 1)for the piping system(s) containing the components listed In the Table 2.2.3-1 and Table 2.2.3-2 are Identified In Attachments A and 8, 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-bullt pressure boundary welds In components Identlifled In Table 2.2.3-1 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 completion of the respective ASME Section III N-5 Code Data Report(Reference 1) certified by the Authorized Nuclear Inspector (ANI), as listed In Attachment A.

Per ASME Code Section III, Subartlcle 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 ensured that the pressure boundary welds In components Identified In Table 2.2.3-1 as ASME Code Section III meets ASME Code Section III requirements.

An Inspection was performed In accordance with Reference 2to demonstrate that the as-bullt pressure boundary welds In piping Identified In Table 2.2.3-2(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 2.2.3-2, 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, radlographic, 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 2.2.3-2 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-21-0723 Enclosure Page 5 of 17 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 2.2.3-1 and 2.2.3-2 as ASME Code Section III conform with the reouirements of the ASME Code Section III.

A hydrostatic test was performed by the vendor to demonstrate that the components identified in Table 2.2.3-1 (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 2.2.3-1 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(s)(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 2.2.3-1 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 verified that the piping identified in Table 2.2.3-2 (Attachment B)fully meets all applicable ASME Code,Section III requirements and retains its pressure boundary integrity at its design pressure.

A hydrostatic test was 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 2.2.3-2 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 was 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) support completion of the ASME Section III N-5 Code Data Report(s)for the applicable piping system (i.e., PXS)(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 2.2.3-1 and Table 2.2.3-2 respectively conform with the requirements of the Code (1998 Edition, 2000 Addenda),Section III.

U.S. Nuclear Regulatory Commission ND-21-0723 Enclosure Page 6 of 17 5.b) A report exists and concludes that each of the as-built lines identified in Table 2.2.3-2 for which functional capability is required meets tfie 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 PXS piping lines identified in ITAAC Table 2.2.3-2 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 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 was 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 PXS piping lines identified in Table 2.2.3-2 are completed and concluded that each of the as-built PXS 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 PXS piping lines in Table 2.2.3-2 are identified in Attachment B.

6. An LBB evaluation report exists and concludes that the LBB acceptance criteria was met bv the as-built PXS piping and piping materials, or a pipe break evaluation report 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 2.2.3-2(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 PXS 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 PXS 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).

U.S. Nuclear Regulatory Commission ND-21-0723 Enclosure Page 7 of 17 Inspections were performed to verify that LBB as-built piping evaluation reports for the PXS piping (and corresponding piping materials) identified in Attachment B conclude that the as-built piping analysis is bounded by the applicable bounding analysis curves provide 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 PXS 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.

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 7 through 14 provide the evidence that the ITAAC Acceptance Criteria requirements are met:

• The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.2.3-1 and 2.2.3-2 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 2.2.3-1 and 2.2.3-2 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 2.2.3-2 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 PXS 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 the required inspections for Preservice Inspection (PSI) have been completed (Reference 5)for the applicable portions of the Passive Core Cooling System (PXS) identified in Tables 2.2.3-1 and 2.2.3-2 of the Vogtle COL, Appendix C, and concludes that the results of the PSI examinations meet the acceptance standards specified in the applicable Boiler and Pressure Vessel(B&PV) Codes for the examinations performed.

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 for ITAAC 2.2.03.02a

[Index Number 159].

References 1, 4, and 7 through 14 are available for NRC inspection as part of the Unit 3 ITAAC 2.2.03.02a Completion Packages (Reference 6).

U.S. Nuclear Regulatory Commission ND-21-0723 Enclosure Page 8 of 17 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 160, 161, 162, 163, 164,168 and 169,found seven (7) relevant ITAAC findings associated with this ITAAC.

1) Noncited Violation (NCV)05200025/2017004-01 (Closed - ML19135A691)

2) Notice of Nonconformance(NON)99901431/2013-201-01 (Closed - ML18152B785)

3) NON 99901377/2012-201-02(Closed - ML18152B785)

4) NON 99901377/2012-201-03(Closed - ML18152B785)

5) NON 99900404/2011-201-02(Closed - ML18152B785)

6) NCV 05200025/2018002-02 (Closed - ML18226A348)

7) NCV 05200025/2019001-01 (Closed - ML19135A691)

The corrective actions for each finding have been completed and each finding is closed. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.2.03.02a (Reference 6) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.02a 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 favallable for NRC inspection)

1. SV3-PXS-MUR-001, Rev. 0,"API000 Vogtle Unit 3 ASME Section III System Code Data Report for the Passive Core Cooling System (PXS)"

2. APP-GW-GAP-139, Rev. 8,"Westinghouse/Stone & Webster ASME Code Data Report As-Built Documentation Interface Procedure"

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

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

U.S. Nuclear Regulatory Commission ND-21-0723 Enclosure Page 9 of 17

4. SV3-PXS-S3R-001, Rev. 2,"Vogtle Unit 3 Passive Core Cooling System (PXS) ASME III As-Built Piping System Design Reporf'

5. APE-10-00022,"Unit 3 - Completion of Preservice Inspection for PXS Class 1, 2 and 3 Portions of Systems"

6. 2.2.03.02a-U3-CP-Rev0, ITAAC Completion Package

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

8. SV3-PXS-P0R-0202, Rev. 1,"API000 Piping for APP-PXS-PLR-020 - Vogtle Unit 3 ASME III As-Built Design Report"

9. SV3-PXS-P0R-0302, Rev. 1,"API000 Piping for APP-PXS-PLR-030 - Vogtle Unit 3 ASME III As-Built Design Report"

10. SV3-PXS-P0R-0402, Rev. 1,"API000 Piping for APP-PXS-PLR-040 - Vogtle Unit 3 ASME III As-Built Design Report"

11. SV3-PXS-P0R-0502, Rev. 1,"API000 Piping for APP-PXS-PLR-050 - Vogtle Unit 3 ASME III As-Built Design Report"

12. SV3-PXS-P0R-0602, Rev. 1,"API000 Piping for APP-PXS-PLR-060 - Vogtle Unit 3 ASME III As-Built Design Report"

13. SV3-RCS-MUR-001, Rev. 0,"API000 Vogtle Unit 3 ASME Section III System Code Data Report for the Reactor Coolant System (RCS)"

14. SV3-RCS-S3R-001, Rev. 1,"Vogtle Unit 3 Reactor Coolant System (RCS) ASME III As-Built Piping System Design Reporf'

U.S. Nuclear Regulatory Commission ND-21-0723 Enclosure Page 10 of 17 Attachment A SYSTEM: Passive Core Cooling System (PXS)

ASME ill As-ASME Code Equipment Name

• Tag No.* Bullt Design N-5 Report Section III*

Report Passive Residual Heat SV3-PXS-S3R- SV3-PXS-MUR-Removal Heat Exchanger PXS-ME-01 Yes 001 001 (PRHR HX)

SV3-PXS-S3R- SV3-PXS-MUR-Accumulator Tank A PXS-MT-01A Yes 001 001 SV3-PXS-S3R- SV3-PXS-MUR-Accumulator Tank B PXS-MT-01B Yes 001 001 Core Makeup Tank(CMT) SV3-PXS-S3R- SV3-PXS-MUR-PXS-MT-02A Yes A 001 001 SV3-PXS-S3R- SV3-PXS-MUR-CMTB PXS-MT-02B Yes 001 001 CMT A Inlet Isolation SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V002A Yes Motor-Operated Valve 001 001 CMT B Inlet Isolation SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V002B Yes Motor-Operated Valve 001 001 CMT A Discharge Isolation SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V014A Yes Valve 001 001 CMT B Discharge Isolation SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V014B Yes Valve 001 001 CMT A Discharge Isolation SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V015A Yes Valve 001 001 CMT B Discharge Isolation SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V015B Yes Valve 001 001 CMT A Discharge Check SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V016A Yes Valve 001 001 CMT B Discharge Check SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V016B Yes Valve 001 001 CMT A Discharge Check SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V017A Yes Valve 001 001 CMT B Discharge Check SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V017B Yes Valve 001 001 Accumulator A Pressure SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V022A Yes Relief Valve 001 001 Accumulator B Pressure SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V022B Yes Relief Valve 001 001

U.S. Nuclear Regulatory Commission ND-21-0723 Enclosure Page 11 of 17 Attachment A SYSTEM: Passive Core Cooling System (PXS)

ASME III As-ASME Code Equipment Name

• Tag No.* Bullt Design N-5 Report Section III*

Report Accumulator A Discharge SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V027A Yes Isolation Valve 001 001 Accumulator B Discharge SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V027B Yes Isolation Valve 001 001 Accumulator A Discharge SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V028A Yes Check Valve 001 001 Accumulator B Discharge SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V028B Yes Check Valve 001 001 Accumulator A Discharge SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V029A Yes Check Valve 001 001 Accumulator B Discharge SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V029B Yes Check Valve 001 001 Nitrogen Supply SV3-PXS-S3R- SV3-PXS-MUR-Containment Isolation PXS-PL-V042 Yes 001 001 Valve Nitrogen Supply SV3-PXS-S3R- SV3-PXS-MUR-Containment Isolation PXS-PL-V043 Yes 001 001 Check Valve PRHR HX Inlet Isolation SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V101 Yes Motor-operated Valve 001 001 SV3-PXS-S3R- SV3-PXS-MUR-PRHR HX Control Valve PXS-PL-V108A Yes 001 001 SV3-PXS-S3R- SV3-PXS-MUR-PRHR HX Control Valve PXS-PL-V108B Yes 001 001 Containment Recirculation SV3-PXS-S3R- SV3-PXS-MUR-A Isoiation Motor-operated PXS-PL-V117A Yes 001 001 Valve Containment Recirculation SV3-PXS-S3R- SV3-PXS-MUR-B Isolation Motor-operated PXS-PL-V117B Yes 001 001 Valve Containment Recirculation SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V118A Yes A Squib Valve 001 001 Containment Recirculation SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V118B Yes B Squib Valve 001 001

U.S. Nuclear Regulatory Commission ND-21-0723 Enclosure Page 12 of 17 Attachment A SYSTEM: Passive Core Cooling System (PXS)

ASME III As-ASME Code Equipment Name

• Tag No.* Bullt Design N-5 Report Section III*

Report Containment Recirculation SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V119A Yes A Check Valve 001 001 Containment Recirculation SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V119B Yes B Check Valve 001 001 Containment Recirculation SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V120A Yes A Squib Valve 001 001 Containment Recirculation SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V120B Yes B Squib Valve 001 001 IRWST Injection A Check SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V122A Yes Valve 001 001 IRWST Injection B Check SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V122B Yes Valve 001 001 IRWST Injection A Squib SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V123A Yes Valve 001 001 IRWST Injection B Squib SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V123B Yes Valve 001 001 IRWST Injection A Check SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V124A Yes Valve 001 001 IRWST Injection B Check SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V124B Yes Valve 001 001 IRWST Injection A Squib SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V125A Yes Valve 001 001 IRWST Injection B Squib SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V125B Yes Valve 001 001 IRWST Gutter Isolation SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V130A Yes Valve 001 001 IRWST Gutter Isolation SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V130B Yes Valve 001 001 RNS Suction Leak Test SV3-PXS-S3R- SV3-PXS-MUR-PXS-PL-V208A Yes Valve 001 001 "Excerpts from COL Appendix C Table 2.2.3-1

U.S. Nuclear Regulatory Commission ND-21-0723 Enclosure Page 13 of 17 Attachment B SYSTEM: Passive Core Cooling System (PXS)

ASME LBB ASME III Leak Functional Line Code Evaluation/ As-Built N-5 Line Name* Before Capability Number* Section Pipe Break Design Report Break* Required*

III* Evaluation Report RCS-L134, PXS-L102, PRHR HX SV3-RCS- SV3-RCS-PXS-L103, Inlet line from SV3-PXS- S3R-001 MUR-001 PXS-hot leg and POR-0302, L104A, Yes Yes Yes outlet line to & SV3-PXS-PXS-steam POR-0402 SV3-PXS- SV3-PXS-L104B, generator S3R-001 MUR-001 PXS-L105, channel RCS-L113 head SV3-PXS- SV3-PXS- SV3-PXS-PXS-L107 Yes Yes No POR-0302 S3R-001 MUR-001 RCS-L118A, PXS-L007A, SV3-RCS- SV3-RCS-CMT A Inlet PXS-S3R-001 MUR-001 line from cold L015A, leg C and PXS-outlet line to L016A, SV3-PXS-Yes Yes Yes reactor PXS- POR-0102, vessel direct L017A, & SV3-PXS-vessel PXS- POR-0502 SV3-PXS- SV3-PXS-Injection L018A, S3R-001 MUR-001 (DVI) nozzle PXS-A L020A, PXS-L021A PXS- SV3-PXS- SV3-PXS- SV3-PXS-Yes Yes No L070A POR-0602 S3R-001 MUR-001 RCS-L118B, SV3-RCS- SV3-RCS-PXS-CMT 8 Inlet S3R-001 MUR-001 L007B, SV3-PXS-line from cold PXS- POR-0202, leg D and L015B, SV3-PXS-outlet line to Yes Yes Yes PXS- POR-0302, reactor L016B, & SV3-PXS-vessel DVI PXS- POR-0602 nozzle B SV3-PXS- SV3-PXS-L017B, S3R-001 MUR-001 PXS-L018B,

U.S. Nuclear Regulatory Commission ND-21-0723 Enclosure Page 14 of 17 Attachment B SYSTEM: Passive Core Cooling System (PXS)

ASME LBB ASME III Leak Functional Line Code Evaluation/ As-Built N-5 Line Name* Before Capability Number* Section Pipe Break Design Report Break* Required*

Ml* Evaluation Report PXS-L020B, PXS-L021B PXS- SV3-PXS- SV3-PXS- SV3-PXS-Yes Yes No L070B POR-0602 S3R-001 MUR-001 RNS A discharge line to PXS from RNS SV3-PXS- SV3-PXS- SV3-PXS-check valve PXS- Yes Yes Yes POR-0102 S3R-001 MUR-001 RNS-PL- L019A V017Ato DVI line A RNSB discharge line to PXS from RNS PXS- SV3-PXS- SV3-PXS- SV3-PXS-Yes Yes Yes check valve L019B POR-0202 S3R-001 MUR-001 RNS-PL-V017B to DVI line B PXS-Accumulator L025A, A discharge PXS- SV3-PXS- SV3-PXS- SV3-PXS-Yes Yes Yes Line to DVI L027A, POR-0202 S3R-001 MUR-001 line A PXS-L029A PXS-Accumulator L025B, B discharge PXS- SV3-PXS- SV3-PXS- SV3-PXS-Yes Yes Yes line to DVI L027B, POR-0202 S3R-001 MUR-001 line B PXS-L029B PXS-IRWST L123A, injection line PXS- SV3-PXS- SV3-PXS- SV3-VES-Yes Yes Yes A to DVI line L125A, POR-0102 S3R-001 MUR-001 A PXS-L127A

U.S. Nuclear Regulatory Commission ND-21-0723 Enclosure Page 15 of 17 Attachment B SYSTEM; Passive Core Cooling System (PXS)

ASME LBB ASME III Leak Functional Line Code Evaluation/ As-Built N-5 Line Name* Before Capability Number* Section Pipe Break Design Report Break* Required*

III* Evaluation Report PXS-L124A, PXS-L118A, PXS- SV3-PXS- SV3-PXS-Yes No Yes N/A L117A, S3R-001 MUR-001 PXS-L116A, PXS-L112A PXS-L133A, SV3-PXS- SV3-PXS- SV3-PXS-Yes Yes No PXS- POR-0102 S3R-001 MUR-001 L134A PXS-L123B, PXS- Yes Yes Yes SV3-PXS- SV3-PXS- SV3-PXS-L125B, POR-0202 S3R-001 MUR-001 PXS-L127B PXS-L124B, PXS-IRWST L118B, injection line PXS-B to DVI line L117B, SV3-PXS- SV3-PXS-Yes No Yes N/A 8 PXS- S3R-001 MUR-001 L116B, PXS-L114, PXS-L112B, PXS-L120 PXS-L133B, SV3-PXS- SV3-PXS- SV3-PXS-Yes Yes No PXS- POR-0202 S3R-001 MUR-001 L134B IRWST PXS-screen L180A, SV3-PXS- SV3-PXS-Yes No Yes N/A cross- PXS- S3R-001 MUR-001 connect line L180B

U.S. Nuclear Regulatory Commission ND-21-0723 Enclosure Page 16 of 17 Attachment B SYSTEM: Passive Core Cooling System (PXS)

ASME LBB ASME ill Leak Functional Line Code Evaluation/ As-Bullt N-5 Line Name* Before Capability Number* Section Pipe Break Design Report Break* Required*

III* Evaluation Report PXS-L113A, Containment PXS- SV3-PXS- SV3-PXS-recirculation Yes No Yes N/A L131A, S3R-001 MUR-001 line A PXS-L132A PXS-L100, PXS-L101, PXS-L106, Containment PXS-SV3-PXS- SV3-PXS-recirculation L113B, Yes No Yes N/A S3R-001 MUR-001 line B PXS-L131B, PXS-L132B PXS-L142A, PXS-L142B PXS-L183A, PXS-L183B, SV3-PXS- SV3-PXS-Yes No Yes N/A PXS- S3R-001 MUR-001 IRWST L184A, gutter drain PXS-line L184B, PXS-L185A, PXS-L185B PXS-L141A*, SV3-PXS- SV3-PXS-Yes No No N/A PXS- S3R-001 MUR-001 L141B*

Downspout PXS-drain lines L301A, from polar PXS- SV3-PXS- SV3-PXS-Yes No Yes N/A crane girder L302A, S3R-001 MUR-001 and internal PXS-stiffener to L303A,

U.S. Nuclear Regulatory Commission ND-21-0723 Enclosure Page 17 of 17 Attachment B SYSTEM: Passive Core Cooling System (PXS)

ASME LBB ASME Iii Leak Functionai Line Code Evaiuation/ As-Buiit N-5 Line Name* Before Capabiiity Number* Section Pipe Break Design Report Break* Required*

iii* Evaiuation Report collection PXS-box A L304A, PXS-L305A, PXS-L306A, PXS-L307A, PXS-L308A, PXS-L309A*,

PXS-L310A*

PXS-L301B, PXS-L302B, PXS-L303B, Downspout PXS-drain lines L304B, from polar PXS-crane girder L305B, SV3-PXS- SV3-PXS-Yes No Yes N/A and internal PXS- S3R-001 MUR-001 stiffener to L306B, collection PXS-box 8 L307B, PXS-L308B, PXS-L309B*,

PXS-L310B*

"Excerpts from COL Appendix C, Table 2.2.3-2

+For girth fillet welds between piping and socket welded fittings, valves and flanges, refer to VEGP UFSAR Section 5.2.1.1 (Reference 3).