ND-18-0065, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.02a (Index Number 13)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.02a (Index Number 13)

ML18032A511
Person / Time
Site:	Vogtle
Issue date:	01/30/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.1.02.02a, ND-18-0065
Download: ML18032A511 (16)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell myox @southernco.com JAN 3 2018 Docket Nos.: 52-025 52-026 ND-18-0065 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.1.02.02a [Index Number 131 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of January 29, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02.02a

[Index Number 13] has not been completed greaterthan 225-days prior to initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.

This notification is informed by the guidance described in NEI 08-01, Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52, which was endorsed by the NRC in Regulatory Guide 1.215. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, or analyses have not been performed or have been only partially completed. All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

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

Respectfully submitted.

Michael J. Yox Regulatory Affairs Director Vogtle 3 &4

U.S. Nuclear Regulatory Commission ND-18-0065 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.02a [Index Number 13]

MJY/KJD/amw

U.S. Nuclear Regulatory Commission ND-18-0065 Page 3 of 4 To:

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

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

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

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

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

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

U.S. Nuclear Regulatory Commission ND-18-0065 Page 4 of 4 Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. 0. Durham (w/o enclosures)

Mr. M. M. Corletti Ms. L. G. Iller Mr. D. Hawkins Ms. 8. DiTommaso Mr. J. L. Coward Ms. N. E. Deangelis Other Mr. J. E. Hesler, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

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

U.S. Nuclear Regulatory Commission ND-18-0065 Enclosure Page 1 of 12 Southern Nuclear Operating Company ND-18-0065 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.02a [index Number 13]

U.S. Nuclear Regulatory Commission ND-18-0065 Enclosure Page 2 of 12 ITAAC Statement Design Commitment:

2.a) The components identified in Table 2.1.2-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.

2.b) The piping identified in Table 2.1.2-2 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 2.1.2-1 as ASME Code Section III meet ASME Code Section III requirements.

3.b) Pressure boundarywelds in piping identified in Table 2.1.2-2 as ASME Code Section III meet ASME Code Section III requirements.

4.a) The components identified inTable 2.1.2-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.

4.b) The piping identified in Table 2.1.2-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.

5.b) Each ofthe lines identified in Table 2.1.2-2 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 2.1.2-2 as designed for LBB meets the LBB criteria, or an evaluation is performed ofthe protection from the dynamic effects of a rupture of the line.

Insoections. Tests. Analyses:

Inspection will be conducted of the as-built components and piping as documented in theASME design reports.

Inspection of the as-built pressure boundary welds will be performed in accordance with the ASME Code Section III.

Ahydrostatic 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 oran evaluation report onthe protection from dynamic effects of a pipe break. Section 3.3, Nuclear Island Buildings, contains the design descriptions and inspections, tests, analyses, and acceptance criteriafor protection from the dynamic effects of pipe rupture.

U.S. Nuclear Regulatory Commission ND-18-0065 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 2.1.2-1 and 2.1.2-2 as ASME Code Section III.

A report exists and concludesthat 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 2.1.2-1 and 2.1.2-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.

Areport exists and concludes that each of the as-built lines identified in Table 2.1.2-2 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 bythe as-built RCS piping and piping materials ora pipe break evaluation report exists and concludes that protection from the dynamic effects of a line break is provided.

ITAAC Completion Description This ITAAC requires inspections, tests, and analyses be performed and documented to ensure the Reactor Coolant System (RCS) components and piping listed in the Combined License (COL) Appendix C, Table 2.1.2-1 (Attachment A) and Table 2.1.2-2 (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.b1 The ASME Code Section III desion reports exist for the as-built components and pipina identified in Tables 2.1.2-1 and 2.1.2-2 as ASME Code Section III.

Each component listed in Table 2.1.2-1 as ASME Code Section III is 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 thatthe as-built components conform to the approved design details. TheASME 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 2.1.2-2 including the components listed in Table 2.1.2-1 as ASME Code Section III, are subjected to a reconciliation process (Reference 2), which verifies that the as-built piping are 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 confirtri 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-18-0065 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 2.1.2-1 (Attachment A) and piping listed in Table 2.1.2-2 (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 2.1.2-1 and Table 2.1.2-2 are identified in Attachments A and B, respectively.

S.a and S.bl A report exists and concludes that the ASME Code Section III reouirements are met for non-destructive examination of pressure boundary welds.

Inspections are performed in accordance with ASME Code Section III (1998 Edition, 2000 Addenda) to demonstrate that as-built pressure boundary welds in components identified in Table 2.1.2-1 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) ofthe components' pressure boundary welds are documented in the Non-destructive Examination Report(s), which support completion ofthe respective ASME Section III N-5 Code Data Report(s) certified bythe 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 ofthe required examination and testing ofthe item, which includes non-destructive examinations of pressure boundary welds. Satisfactory completion ofthe non-destructive examination of pressure boundary welds ensures thatthe pressure boundary welds in components identified in Table 2.1.2-1 as ASME Code Section III meet ASME Code Section III requirements.

An inspection is performed in accordance with Reference 2 to demonstrate that the as-built pressure boundary welds in piping identified in Table 2.1.2-2 (Attachment B) as ASME Code Section III meet ASME Code Section III requirements (i.e., no unacceptable indications). This portion of the ITAAC is complete when the piping identified in Table 2.1.2-2, 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), is complete. 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). Thecompletion 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 is constructed inaccordance with the design specification(s) and theASME Code Section III and that the satisfactory compietion of the non-destructive examinations of piping pressure boundaryweldsfor the pipe lines identified in Table 2.1.2-2 meet ASME Code Section III requirements and are documented in the Non destructive Examination Report(s) within the supporting data packages.

U.S. Nuclear Regulatory Commission ND-18-0065 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 pioina identified in Tables 2.1.2-1 and 2.1.2-2 as ASME Code Section III conform with tfie reouirements of the ASME Code Section III.

A hydrostatic test is performed by the vendor to demonstrate that the components identified in Table 2.1.2-1 (Attachment A) as ASME Code Section III retain their pressure boundary integrity at their design pressure. The completion of the N-5 Data Reports is governed by Reference 2.

This portion of the ITAAC is complete once each component identified in Table 2.1.2-1 has their individual Code Symbol N-Stampand corresponding Code Data Report (Reference 1) completed, and the components are installed intothe respective Code Symbol N-Stamped piping system and documented on the corresponding N-5 Code Data Report(s) (Reference1).

The hydrostatic testing results of the component's pressure boundaryare documented in the Hydrostatic Testing Report(s) within the supporting component'sdata package, which support completion of the respectiveCode Stampingand Code Data Report(s).

The completion of stamping the individual components and the respective piping systemalong with the corresponding ASME Code Data Reports (certified by the Authorized Nuclear Inspector) ensures that the components are constructed in accordancewith the Design Specifications andthe ASME Code Section III andthatthe satisfactory completion of the hydrostatic pressure testing of eachcomponent identified in Table 2.1.2-1 as ASME Code Section III are documented in the Hydrostatic Testing Report(s) within the supporting data packages and meets ASME Code Section III requirements.

This ITAAC also verifies that the piping identified in Table 2.1.2-2 (Attachment B) fully meets all applicable ASME Code,Section III requirements and retains its pressure boundary integrity at its design pressure.

Ahydrostatic test is performed in accordance with procedure XYZ (as applicable) that complies with the ASME Code (1998 Edition, 2000 Addenda),Section III requirements to demonstrate that the ASME Code Section III piping identified in Table 2.1.2-2 retains its pressure boundary integrity at its design pressure.

Ahydrostatic 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., RCS) (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 2.1.2-1 andTable 2.1.2-2 respectively conform with the requirements of the Code (1998 Edition, 2000 Addenda),Section III.

U.S. Nuclear Regulatory Commission ND-18-0065 Enclosure Page 6 of 12 5.b) A report exists and concludes that each of the as-built lines identified in Table 2.1.2-2 for which functional capability is required meets the requirements for functional capability.

An inspection is performed of the ASME Section III as-built piping design report XXX to verify that the report demonstrates that each of the RCS piping lines identified in ITAAC Table 2.1.2-2 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).

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 Reportsfor 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 bythe approved design. As required byASME 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 RCS piping lines identified in Table 2.1.2-2 are complete and conclude that each of the as-built RCS piping lines for which functional capability is required meetsthe requirements for functional capability. TheASME Section III As-Built Piping Design Reports for each of the as-built RCS piping lines in Table 2.1.2-2 are identified in Attachment B.

6. An LBB evaluation report exists and concludes that the LBB acceptance criteria are met bv the as-built RCS Dioino and pioina materials or a oioe break evaluation reoort exists and concludes that orotection from the dvnamic effects of a line break is orovided.

Inspections are performed for the as-built lines identified in Table 2.1.2-2 (Attachment B) to verify that each of the as-built lines designed for LBB meets the LBB criteria, oran 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 are performed as described in UFSAR subsection 3.6.3 to confirm thatthe as-built RCS piping (and corresponding piping materials) identified in Attachment Ameet the LBB acceptance criteria described in the UFSAR, Appendix 3B, Leak-Before-Break Evaluation of the API 000 Piping (Reference 3). In cases where an as-built RCS piping line in Attachment B cannot meetthe 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-18-0065 Enclosure Page 7 of 12 Inspections are performed to verify that LBB as-built piping evaluation reports for the RGB 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 RCS 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 and 4 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 2.1.2-1 and 2.1.2-2 as ASME Code Section III;

• Areport 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 ofthe hydrostatic test of the components and piping identified in Tables 2.1.2-1 and 2.1.2-2 as ASME Code Section III conform with the requirements of the ASME Code Section III;

• Areport exists and concludes that each of the as-built lines identified in Table 2.1.2-2 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 RCS piping and piping materials ora pipe break evaluation report exists and concludes that protection from the dynamic effects of a line break is provided.

References 1 and 4 are available for NRC inspection as part ofthe Unit 3 and Unit 4 ITAAC 2.1.02.02a Completion Packages (References 5 and 6, respectively).

U.S. Nuclear Regulatory Commission ND-18-0065 Enclosure Page 8 of 12 List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings and associated corrective actions.

This review, which included now consolidated ITAAC Indexes 14,15,16,17,18, 22 and 23, found the following relevant ITAAC findings associated with this ITAAC:

1) Noncited violation 05200025/2017002-01 (Unit 3 Open) and 05200026/2017002-01 (Unit 4 Open)

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

Before submission of the ICN, corrective actions will be complete for relevant findings identified prior to ICN submission.

References (available for NRC inspection)

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

2. APP-GW-GAP-139, "Westinghouse/WECTEC ASME N-5 Interface Procedure"

3. VEGP 3&4 Updated Final Safety Analysis Report

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. RCS ASME III As Built Design Report(s)

5. Completion Package for Unit 3 ITAAC 2.1.02.02a [COL Index Number 13]

6. Completion Packagefor Unit 4 ITAAC 2.1.02.02a [COL Index Number 13]

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

U.S. Nuclear Regulatory Commission ND-18-0065 Enclosure Page 9 of 12 Attachment A SYSTEM: Reactor Coolant System (RCS)

ASME ill as-ASME Code Equipment Name

• Tag No.

• built Design N-5 Report Section iii*

Report XXX RCS N-5 Code Data Steam Generator 1 RCS-MB-01 Yes Report XXX RCS N-5 Code Data Steam Generator 2 RCS-MB-02 Yes Report XXX RCS N-5 Code Data RCP1A RCS-MP-01A Yes Report XXX RCS N-5 Code Data RCP1B RCS-MP-01B Yes Report XXX RCS N-5 Code Data RCP2A RCS-MP-02A Yes Report XXX RCS N-5 Code Data RCP2B RCS-MP-02B Yes Report XXX RCS N-5 Code Data Pressurizer RCS-MV-02 Yes Report Automatic XXX RCS N-5 Code Data Depressurization Report PXS-MW-01A Yes System (ADS)

Sparger A XXX RCS N-5 Code Data ADS Sparger B PXS-MW-01B Yes Report Pressurizer Safety XXX RCS N-5 Code Data RCS-PL-V005A Yes Valve Report Pressurizer Safety XXX RCS N-5 Code Data RCS-PL-V005B Yes Valve Report First-stage ADS XXX RCS N-5 Code Data Motor-operated Valve RCS-PL-V001A Yes Report (MOV)

XXX RCS N-5 Code Data First-stage ADS MOV RCS-PL-V001B Yes Report Second-stage ADS XXX RCS N-5 Code Data RCS-PL-V002A Yes MOV Report Second-stage ADS XXX RCS N-5 Code Data RCS-PL-V002B Yes MOV Report Third-stage ADS XXX RCS N-5 Code Data RCS-PL-V003A Yes MOV Report Third-stage ADS XXX RCS N-5 Code Data RCS-PL-V003B Yes MOV Report Fourth-stage ADS XXX RCS N-5 Code Data RCS-PL-V004A Yes Report Squib Valve Fourth-stage ADS XXX RCS N-5 Code Data RCS-PL-V004B Yes Squib Valve Report

U.S. Nuclear Regulatory Commission ND-18-0065 Enclosure Page 10 of 12 Attachment A SYSTEM: Reactor Coolant System (RCS)

ASME III as-ASME Code Equipment Name

• Tag No.

• built Design N-5 Report Section iii*

Report Fourtfi-stage ADS XXX RCS N-5 Code Data RCS-PL-V004C Yes Squib Valve Report Fourth-stage ADS XXX RCS N-5 Code Data RCS-PL-V004D Yes Squib Valve Report ADS Discharge XXX RCS N-5 Code Data Header A Vacuum RCS-PL-V010A Yes Report Relief Valve ADS Discharge XXX RCS N-5 Code Data Header B Vacuum RCS-PL-V010B Yes Report Relief Valve First-stage ADS Yes XXX RCS N-5 Code Data RCS-PL-V011A Isolation MOV Report First-stage ADS RCS-PL-V011B Yes XXX RCS N-5 Code Data Isolation MOV Report Second-stage ADS XXX RCS N-5 Code Data RCS-PL-V012A Yes Isolation MOV Report Second-stage ADS XXX RCS N-5 Code Data RCS-PL-V012B Yes Isolation MOV Report Third-stage ADS XXX RCS N-5 Code Data RCS-PL-V013A Yes Isolation MOV Report Third-stage ADS XXX RCS N-5 Code Data RCS-PL-V013B Yes Isolation MOV Report Fourth-stage ADS XXX RCS N-5 Code Data RCS-PL-V014A Yes MOV Report Fourth-stage ADS XXX RCS N-5 Code Data RCS-PL-V014B Yes MOV Report Fourth-stage ADS XXX RCS N-5 Code Data RCS-PL-V014C Yes MOV Report Fourth-stage ADS XXX RCS N-5 Code Data RCS-PL-V014D Yes MOV Report Reactor Vessel Head XXX RCS N-5 Code Data RCS-PL-V150A Yes Vent Valve Report Reactor Vessel Head XXX RCS N-5 Code Data RCS-PL-V150B Yes Vent Valve Report Reactor Vessel Head XXX RCS N-5 Code Data RCS-PL-V150C Yes Vent Valve Report Reactor Vessel Head XXX RCS N-5 Code Data RCS-PL-V150D Yes Vent Valve Report

'Excerpts from COL Appendix C Table 2.1.2-1

U.S. Nuclear Regulatory Commission ND-18-0065 Enclosure Page 11 of 12 Attachment B SYSTEM: Reactor Coolant System (RCS)

ASME ASME Mi LBB Leak Functional Code As-Buiit evaluation / N-5 Line Name* Line Number* Before Capability Section Design pipe break Report Break* Required*

Hi* Report evaluation N-5 Code RCS-L001A Hot Legs Yes Yes Yes XXX YYY Data RCS-L001B Report RCS-L002A N-5 Code RCS-L002B Cold Legs Yes Yes Yes XXX YYY Data RCS-L002C Report RCS-L002D N-5 Code Pressurizer YYY Data RCS-L003 Yes Yes Yes XXX Surge Line Report RCS-L004A/B N-5 Code ADS Inlet RCS-L006A/B Data Yes Yes Yes XXX YYY Headers RCS-L030A/B Report RCS-L020A/B N-5 Code Safety Valve RCS-L005A Yes Yes Yes XXX YYY Data Inlet Piping RCS-L005B Report N-5 Code RCS-L050A/B YYY Data Yes No Yes XXX Safety Valve RCS-L051A/B Report Discharge N-5 Code Piping No No XXX YYY Data RCS-L064A/B Yes Report ADS First- N-5 Code RCS-L010A/B YYY Data stage Valve Yes No Yes XXX RCS-L011A/B Report Inlet Piping ADS Second- N-5 Code RCS-L021A/B Yes Data stage Yes Yes XXX YYY RCS-L022A/B No Report Valve Inlet Piping l_ £Z ADS Third- RCS-L131 Yes N-5 Code RCS-L031A/B Yes Yes XXX YYY Data stage Valve Yes Inlet Piping RCS-L032A/B No Report

U.S. Nuclear Regulatory Commission ND-18-0065 Enclosure Page 12 of 12 Attachment B SYSTEM: Reactor Coolant System (RCS)

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

III* Report evaluation RCS-L012A/B RCS-L023A/B RCS-L033A/B N-5 Code RCS-L061A/B Yes No Yes XXX YYY Data RCS-L063A/B Report RCS-L200 ADS Outlet RCS-L069A/B +

Piping PXS-L130A/B N-5 Code RCS-L240A/B Yes No No XXX YYY Data Report ADS RCS-L133A/B N-5 Code Fourth- RCS-L135A/B Yes Yes Yes XXX YYY Data stage Inlet RCS-L136A/B Report Piping RCS-L137A/B RCS-L106 Pressurizer RCS-L110A/B N-5 Code Spray RCS-L212A/B Yes No No XXX YYY Data Piping RCS-L213 Report RCS-L215 RMS N-5 Code RCS-L139 Suction Yes Yes No XXX YYY Data RCS-L140 Piping Report CVS N-5 Code RCS-L111 Purification Yes No No XXX YYY Data RCS-L112 Piping Report

• Excerpts from COL Appendix C, Table 2.1.2-2

+ RCS-L069A/B requires that dynamic loads in its pipe stress analysis satisfy the requirements of ASME Code Section III (1989 Edition, 1989 Addenda) for girth fillet welds between piping and socket welded fittings, valves and flanges perVEGP UFSAR Section 5.2.1.1 (Reference 3)