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

Southern Nuclear JAN 3 2018 Docket Nos.:

52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 cell myox@southernco.com ND-18-0065 10CFR 52.99(c)(3)

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 CFR52.99(c)(3), Southern Nuclear Operating Companyhereby notifies the NRC that as ofJanuary 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 planforcompleting this ITAAC. Southern Nuclear Operating Company will, at a laterdate, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.

This notification is informed bythe guidance described in NEI 08-01, Industry Guideline forthe 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, oranalyses 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 plantoperation, 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) Unit3 and Unit4 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

M M

M M

M M

M M

D. A. Bost (w/o enclosures)

M. D. Rauckhorst (w/o enclosures)

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

D. L. McKinney M. J. Vox D. L. Fulton

. J. D. Williams 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 boundarywelds incomponents identified inTable 2.1.2-1 as ASME Code Section III meet ASME Code Section III requirements.

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

4.a) The components identified inTable2.1.2-1 as ASME Code Section III retain theirpressure boundary integrity at their design pressure.

4.b) The piping identified in Table 2.1.2-2as 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 towithstand combined normal and seismic design basis loads without a loss of its functional capability.

6. Each of the as-built lines identifiedin Table 2.1.2-2 as designed for LBB meets the LBB criteria, oran evaluation is performed ofthe protection from the dynamic effects ofa rupture of the line.

Insoections. Tests. Analyses:

Inspection will beconducted of theas-built components andpiping as documented in theASME design reports.

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

Ahydrostatic testwill be performed on thecomponents and piping required by theASME Code Section III to be hydrostatically tested.

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

Inspection will be performed for the existence of an LBB evaluation report oran evaluation report ontheprotection from dynamic effects of a pipe break. Section 3.3, Nuclear Island Buildings, contains thedesign descriptions and inspections, tests, analyses, andacceptance criteriafor protection from the dynamiceffects 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.

Areport existsand concludesthat the ASME Code Section III requirements are metfor non destructive examination of pressure boundary welds.

Areport exists and concludes thatthe results ofthe hydrostatic test ofthe components and piping identified in Tables 2.1.2-1 and 2.1.2-2 as ASME CodeSection III conform with the requirements of the ASME Code Section III.

Areport exists andconcludes that eachof theas-built lines identified in Table 2.1.2-2 for which functional capability is required meets the requirements forfunctional capability.

An LBB evaluation report exists and concludes thatthe LBB acceptance criteria are metbythe as-built RCS piping and piping materials ora pipe break evaluation report exists andconcludes that protection from the dynamic effectsofa line break is provided.

ITAAC Completion Description This ITAAC requires inspections, tests, andanalyses be performed anddocumented 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), orFunctional Capability Required aredesigned and constructed in accordance with applicable requirements.

2.a and 2.b1 The ASME Code Section III desion reports exist forthe as-builtcomponents 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 anddocument thattheas-built components conform tothe approved design details. TheASME Section III Design Report for each component is documented in the component's completed ASME Section III Code Data Report. Theindividual component ASME Section III Code Data Reports are documented on the ASME Section III N-5 Code Data Report(s) for the applicable pipingsystem (Reference 1).

The as-built piping listed in Table 2.1.2-2 including thecomponents listed in Table 2.1.2-1 as ASME Code Section III, are subjected toa reconciliation process (Reference 2), which verifies that the as-built piping areanalyzed 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 anddesign provisions, are referenced inthe N-5 data report and/or itssub-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 inthe 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-builtpressure boundary welds incomponents 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-destructiveexaminations (including liquid penetrant, magnetic particle, radiographic, and ultrasonic testing, as required byASME 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 ASMECode Section III, Subarticle NCA-8300, "Code Symbol Stamps," the N-5 Code Data Report(s) (Reference 1)documents satisfactory completion ofthe required examination andtesting ofthe item, which includes non-destructive examinations ofpressureboundary welds. Satisfactory completion ofthe non-destructive examination of pressure boundary welds ensures thatthe pressureboundary welds in components identified in Table 2.1.2-1 as ASME Code Section III meet ASME Code Section III requirements.

An inspection isperformed in accordance with Reference 2todemonstrate that theas-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 theITAAC iscomplete when the piping identified in Table 2.1.2-2, which is encompassed within the respective piping system Code Symbol N-Stamp andthe corresponding piping system Code N-5 Data Report Form(s) (Reference 1), iscomplete. 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 datapackage, which support completion of the respective Code Stamping andCode N-5 Data Report(s). Thecompletion of stamping the respective piping system along with thecorresponding ASME Code N-5 Data Report Form(s) (certified by the Authorized Nuclear Inspector) ensure that the piping isconstructed inaccordance with the design specification(s) and theASME Code Section III and that the satisfactory compietion of the non-destructive examinations of piping pressure boundaryweldsforthe pipe linesidentified inTable 2.1.2-2 meet ASME Code Section III requirements and are documented inthe 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 completionofthe N-5 Data Reports is governed by Reference 2.

This portion ofthe ITAAC is complete once each component identified inTable 2.1.2-1 has their individual Code SymbolN-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 resultsofthe component's pressure boundaryare documented in the Hydrostatic Testing Report(s) within the supporting component'sdata package, which support completion ofthe respectiveCode Stampingand Code Data Report(s).

The completion ofstamping the individual components and the respective piping systemalong with the corresponding ASME Code Data Reports(certified bythe Authorized Nuclear Inspector) ensures thatthe components are constructed in accordancewith the Design Specifications andtheASME Code Section III andthatthesatisfactory 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.

ThisITAAC also verifies thatthe 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 isperformed in accordance with procedure XYZ (asapplicable) that complies with the ASME Code (1998 Edition, 2000 Addenda),Section III requirements to demonstrate that the ASME Code Section III piping identified inTable 2.1.2-2 retains its pressure boundary integrity at its design pressure.

Ahydrostatic testverifies that there are no leaks at welds orpiping, and that thepressure boundary integrity isretained at its design pressure. The hydrostatic testing results of the pipe lines aredocumented 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 XXXto 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 inthe VEGP UFSAR Table 3.9-11 (Reference 3).

Piping functional capability is not a specificASME Code requirement but itis a requirement in the VEGP UFSAR (Reference 3). As such, information demonstrating that UFSAR functional capability requirements are met is included inthe ASME Section III As-Built Design Reportsfor safety class piping prepared in accordance with ASME Section III NCA-3550 underthe 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 forfunctional capability and forcompliance with the design specification and ASME Code provisions. Design reconciliation ofthe as-built systems validates that constructioncompletion, including field changes and any nonconforming condition dispositions, isconsistent with and bounded bythe approved design. Asrequired byASME Code,the As-Built Design Report includes the results ofphysical inspection ofthe 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 andconclude thateach of theas-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 2.1.2-2are 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 theas-built lines identified in Table 2.1.2-2 (Attachment B) to verify that each of the as-built lines designed for LBB meets theLBB criteria, oranevaluation is performed of theprotection from the dynamic effects of a rupture of theline. VEGP COL Appendix C, Section 3.3, Nuclear Island Buildings, contains thedesign 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 toconfirm 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 API000 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 isprovided. The pipe break evaluation criteria is discussed in UFSAR, Section 3.6.4.1, Pipe Break Hazards Analysis (Reference 3) and isdocumented 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 LBBas-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 performedto 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)) existand 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 existforthe as-builtcomponents and piping identified in Tables 2.1.2-1 and 2.1.2-2 as ASME Code Section III; Areport exists andconcludes that theASME Code Section III requirements are met for non-destructive examination of pressure boundary welds; Areport exists and concludes thatthe results ofthe hydrostatic test ofthe components and piping identified in Tables 2.1.2-1 and2.1.2-2 as ASME Code Section III conform with the requirements ofthe ASME Code Section III; Areport exists andconcludes that eachof theas-built lines identified in Table 2.1.2-2 for which functional capability is required meetsthe requirements for functional capability; and An LBB evaluation report existsand concludes thatthe LBB acceptance criteria are met by the as-built RCS piping and piping materials ora pipe break evaluation report exists andconcludes that protection from thedynamic 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 2.1.02.02aCompletion 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 ITAACcompletion, 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 ofthe API000 Piping 4.

RCS ASME III As BuiltDesign 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)

Equipment Name

• Tag No.

• ASME Code Section iii*

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

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

RCS-PL-V001A Yes XXX RCS N-5 Code Data Report First-stage ADS MOV RCS-PL-V001B Yes XXX RCS N-5 Code Data Report Second-stage ADS MOV RCS-PL-V002A Yes XXX RCS N-5 Code Data Report Second-stage ADS MOV RCS-PL-V002B Yes XXX RCS N-5 Code Data Report Third-stage ADS MOV RCS-PL-V003A Yes XXX RCS N-5 Code Data Report Third-stage ADS MOV RCS-PL-V003B Yes XXX RCS N-5 Code Data Report Fourth-stage ADS Squib Valve RCS-PL-V004A Yes XXX RCS N-5 Code Data Report Fourth-stage ADS Squib Valve RCS-PL-V004B Yes XXX RCS N-5 Code Data Report

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

Equipment Name

• Tag No.

• ASME Code Section iii*

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

Line Name*

Line Number*

ASME Code Section Hi*

Leak Before Break*

Functional Capability Required*

ASME Mi As-Buiit Design Report LBB evaluation /

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

£Z ADS Third-stage Valve Inlet Piping RCS-L131 RCS-L031A/B RCS-L032A/B Yes Yes Yes No Yes XXX YYY N-5 Code Data Report

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

Line Name*

Line Number*

ASME Code Section III*

Leak Before Break*

Functional Capability Required*

ASME III As-Built Design Report LBB evaluation /

pipe break evaluation N-5 Report ADS Outlet Piping RCS-L012A/B RCS-L023A/B RCS-L033A/B RCS-L061A/B RCS-L063A/B RCS-L200 RCS-L069A/B +

PXS-L130A/B Yes No Yes XXX YYY N-5 Code Data Report RCS-L240A/B Yes No No XXX YYY N-5 Code Data Report ADS Fourth-stage Inlet Piping RCS-L133A/B RCS-L135A/B RCS-L136A/B RCS-L137A/B Yes Yes Yes XXX YYY N-5 Code Data Report Pressurizer Spray Piping RCS-L106 RCS-L110A/B RCS-L212A/B RCS-L213 RCS-L215 Yes No No XXX YYY N-5 Code Data Report RMS Suction Piping RCS-L139 RCS-L140 Yes Yes No XXX YYY N-5 Code Data Report CVS Purification Piping RCS-L111 RCS-L112 Yes No No XXX YYY N-5 Code Data 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 ofASME Code Section III (1989 Edition, 1989 Addenda) for girthfillet welds between piping and socket welded fittings, valves and flanges perVEGP UFSAR Section 5.2.1.1 (Reference 3)