ND-18-0552, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.06.02a (Index Number 355)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.06.02a (Index Number 355)

ML18117A341
Person / Time
Site:	Vogtle
Issue date:	04/25/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0552
Download: ML18117A341 (16)

Text

k , fc. I I Michael J. Yox 7825 River Road ilk SOU'tn0rn Nuclssr Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 &4 706-848-6459 tel 410-474-8587 cell APR L 5 201B myox@southernco.com Docket Nos.: 52-025 52-026 ND-18-0552 10 CFR 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 2.3.06.02a findex Number 3551 Ladies and Gentlemen; Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of April 16, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.06.02a [Index Number 355]

has not been completed greater than 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.

HP-Michael J. Yox Regulatory Affairs Director Vogtle 3 &4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.06.02a [Index Number 355]

MJY/KJD/amw

U.S. Nuclear Regulatory Commission ND-18-0552 Page 2 of 3 To:

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

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

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

Mr. D. L. McKinney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. B. Klecha Mr. G. Chick Mr. 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. C. Chamberlain Mr. D. R. Culver Mr. T. G. Petrak Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reaulatorv 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. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Ms. L. A. Kent Mr. P. B. Donnelly Ms. N. C. Coovert Oaiethoroe Power Corporation Mr. R. B. Brinkman

U.S. Nuclear Regulatory Commission ND-18-0552 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson 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. J. Monahan Mr. J. L. Coward Ms. N. E. Deangelis Other Mr. J. E. Hosier, 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, Batch BIngham

U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 1 of 13 Southern Nuclear Operating Company ND-18-0552 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.06.02a [Index Number 355]

U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 2 of 13 ITAAC Statement Design Commitment:

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

2.b) The piping identified in Table 2.3.6-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.

3.a) Pressure boundary welds in components identified in Table 2.3.6-1 as ASME Code Section III meet ASME Code Section III requirements.

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

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

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

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

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

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

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

Inspection will be performed for the existence of an LBB evaluation report oran 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 criteriafor protection from the dynamic effects of pipe rupture.

U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 3 of 13 Acceptance Criteria:

The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.3.6-1 and 2.3.6-2 as ASME Code Section III.

A report exists and concludes that the ASME Code Section III requirements are met for non destructive examination of pressure boundary welds.

A report exists and concludes that the results of the hydrostatic test of the components and piping identified in Tables 2.3.6-1 and 2.3.6-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.

A report exists and concludes that each of the as-built lines identified in Table 2.3.6-2 for which functional capability is required meets the requirements for functional capability.

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

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

2.a and 2.b) The ASME Code Section III desion reports exist for the as-built components and pioing identified in Tables 2.3.6-1 and 2.3.6-2 as ASME Code Section III.

Each component listed in Table 2.3.6-1 as ASME CodeSection III is fabricated in accordance with the VEGP Updated Final Safety Analysis Report (UFSAR) and the ASME CodeSection III requirements. The ASME Code Section III certified Design Reports for these components exist and documentthat the as-built components conform to the approved design details. The ASME Section III Design Report for each component is documented in the component's completed ASME Section III Code Data Report. The individual component ASME Section III Code Data Reports are documented on the ASME Section III N-5 Code Data Report(s) for the applicable piping system (Reference 1).

The as-built piping listed in Table 2.3.6-2 including the components listed in Table 2.3.6-1 as ASME Code Section III, 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 thatconstruction 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, thosefor 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-18-0552 Enclosure Page 4 of 13 The applicable ASME Section III N-5 Code Data Report(s), which include the location of the certified Design Reports for all the components listed in Table 2.3.6-1 (Attachment A) and piping listed in Table 2.3.6-2 (Attachment B) as ASME Code Section III, exist and conclude that these installed components are designed and constructed (including their installation within the applicable as-built piping system) in accordance with the ASME Code (1998 Edition, 2000 Addenda and 1989 Edition, 1989 Addenda),Section III requirements as applicable, as described in UFSAR Subsection 5.2.1 (Reference 3). The N-5 Code Data Reports for the piping system(s) containing the components listed in the Table 2.3.6-1 and Table 2.3.6-2 are identified in Attachments A and B, respectively.

3.a and 3.b1 A reoort exists and concludes that the ASME Code Section III reouirements are met for non-destructive examination of oressure 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 2.3.6-1 as ASME Code Section III meet ASME Code Section III requirements (i.e., no unacceptable indications).

The applicable non-destructive examinations (including liquid penetrant, magnetic particle, radiographic, and ultrasonic testing, as required by ASME Code Section III) of the components' pressure boundary welds are documented in the Non-destructive Examination Report(s), which support completion of the respective ASME Section III N-5 Code Data Report(s) certified by the Authorized Nuclear Inspector, as listed in Attachment A.

Per ASME Code Section III, Subarticle NCA-8300, "Code Symbol Stamps," the N-5 Code Data Report(s) (Reference 1) documents satisfactory completion of the required examination and testing ofthe item, which includes non-destructive examinations of pressure boundary welds. Satisfactory completion of the non-destructive examination of pressure boundary welds ensures thatthe pressure boundary welds in components identified in Table 2.3.6-1 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 2.3.6-2 (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 2.3.6-2, which is encompassed within the respective piping system Code Symbol N-Stamp and the corresponding piping system Code N-5 Data Report Form(s) (Reference 1), 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 in accordance with the design specification(s) and the ASME Code Section III and that the satisfactory completion of the non-destructive examinations of piping pressure boundary welds for the pipe lines identified in Table 2.3.6-2 meet ASME Code Section III requirements and are documentedin the Non-destructive Examination Report(s) within the supporting data packages.

U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 5 of 13 4.a and 4.b1 A report exists and concludes that the results of the hydrostatic test of the components and pioino identified in Tables 2.3.6-1 and 2.3.6-2 as ASME Code Section III conform witfi the reouirements of tfie ASME Code Section III.

A hydrostatic test is performed by the vendor to demonstrate that the components identified in Table 2.3.6-1 (Attachment A) as ASME Code Section III retain their pressure boundary integrity at their design pressure. The completion of the N-5 Data Reports is governed by Reference 2.

This portion of the ITAAC is complete once each component identified in Table 2.3.6-1 has 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 boundaryare documented inthe 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 stampingthe 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 are constructed in accordance with the Design Specificationsand the ASME Code Section III and that the satisfactory completion of the hydrostatic pressure testing of each component identified in Table 2.3.6-1 as ASME Code Section III are documented in the Hydrostatic Testing Report(s) within the supporting data packagesand meets ASME Code Section III requirements.

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

Ahydrostatic test is performed in accordance with procedure XYZ (Reference 4) (as applicable) that complies with the ASME Code (1998 Edition, 2000 Addenda),Section III requirements to demonstrate that the ASME Code Section III piping identified in Table 2.3.6-2 retains its pressure boundary integrityat its design pressure.

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

The applicable ASME Section III N-5 Code Data Report(s) (Reference 1) identified in Attachments A and B documents that the results of the hydrostatic testing of the components and piping identified in Table2.3.6-1 and Table2.3.6-2 respectively conform with the requirements of the Code (1998 Edition, 2000 Addenda),Section III.

U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 6 of 13 5.b1 A report exists and concludes that each of the as-built lines identified in Table 2.3.6-2 for which functional caoabilitv is reouired meets the reouirements 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 RNS piping lines identified in ITAAC Table 2.3.6-2 that requires functional capability is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability. "Functional capability," in this context, refers to the capability of the piping to withstand the effects of earthquakes, without a loss of safety function (to conveyfluids from one location to another). Specific functional capability requirements are defined in the VEGP UFSAR Table 3.9-11 (Reference3).

Piping functional capability is not a specific ASME Code requirement but it is a requirement in the VEGP UFSAR (Reference 3). As such, information demonstrating that UFSAR functional capability requirements are met is included in the ASME Section III As-Built Design Reports for safety class piping prepared in accordance with ASME Section III NCA-3550 under the ASME Boiler & Pressure Vessel Code (1998 Edition, 2000 Addenda)Section III requirements. The as-built piping systems are subjected to a reconciliation process (Reference 2), which verifies that the as-built piping systems are analyzed for functional capability and for compliance with the design specification and ASME Code provisions. Design reconciliation of the as-built systems validates that construction completion, including field changes and any nonconforming condition dispositions, isconsistent with and bounded by the approved design. As required by ASME Code, the As-Built Design Report includes the results of physical inspection ofthe piping and reconciliation to the design pipe stress report.

Inspections of the ASME Code Section III As-Built Piping Design Reports (Reference 5) for the RNS piping lines identified in Table 2.3.6-2 are complete and conclude that each of the as-built RNS piping lines for which functional capability is required meets the requirements for functional capability. The ASME Section III As-Built Piping Design Reports for each of the as-built RNS piping lines inTable 2.3.6-2 are identified in Attachment B.

6. An LBB evaluation reoort exists and concludes that the LBB acceptance criteria are met bv the as-built RNS oioina and oioino materials, or a pipe 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 2.3.6-2 (Attachment B) to verify that each of the as-built lines designed for LBB meets the LBB criteria, or an evaluation is performed of the protection from the dynamic effects of a rupture of the line. VEGP COL Appendix 0, Section 3.3, Nuclear Island Buildings, contains the design descriptions and inspections, tests, analyses, and acceptance criteria for protection from the dynamic effects of pipe rupture.

LBB evaluations are performed as described in UFSAR subsection 3.6.3 to confirm that the as-built RNS 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 RNS piping line in Attachment B cannot meet the LBB acceptance criteria, a pipe break evaluation is performed which concludes that protection from the dynamic effects of a line break isprovided. The pipe break evaluation criteria is discussed in UFSAR, Section 3.6.4.1, Pipe Break Hazards Analysis (Reference3) and is documented as a pipe rupture hazards analysis report (pipe break evaluation report).

U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 7 of 13 Inspections are performed to verify that LBB as-built piping evaluation reports for the RNS piping (and corresponding piping materials) identified in Attachment B conclude that the as-built piping analysis is bounded by the applicable bounding analysis curves provided in Appendix SB of the UFSAR (Reference 3). The results are documented in either the applicable ASME Section III as-built piping design report(s) or in separate LBB evaluation report(s). For cases where an as-built RNS piping line in Attachment B cannot meet the LBB acceptance criteria, inspections are performed to verify that a pipe rupture hazards analysis evaluation report (pipe break evaluation report) exists which concludes that protection from the dynamic effects of a line break is provided.

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 5 provide the evidence that the following ITAAC Acceptance Criteria requirements are met:

• The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.3.6-1 and 2.3.6-2 as ASME Code Section III;

• A report exists and concludes that the ASME Code Section III requirements are met for non-destructive examination of pressure boundary welds;

• A report exists and concludes that the results of the hydrostatic test of the components and piping identified in Tables 2.3.6-1 and 2.3.6-2 as ASME Code Section III conform with the requirements of the ASME Code Section III;

• A report exists and concludes that each ofthe as-built lines identified in Table 2.3.6-2 for which functional capability is required meets the requirements for functional capability; and

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

References 1 and 5 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.3.06.02a Completion Packages (References 6 and 7, respectively).

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 nowconsolidated ITAAC Indexes 356, 357, 358, 359, 360, 364 and 365, found no relevant ITAAC findings associated with this ITAAC.

U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 8 of 13 References (available for NRG inspection^

1. RNS 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. RNS Piping Hydrostatic Test Procedure XYZ

5. RNS ASME III As Built Design Report(s)

6. Completion Package for Unit 3 ITAAC 2.3.06.02a [COL Index Number 355]

7. Completion Packagefor Unit 4 ITAAC 2.3.06.02a [COL Index Number 355]

8. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part52"

U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 9 of 13 Attachment A SYSTEM: Normal Residual Heat Removal System (RNS)

ASME III as-ASME Code Equipment Name* Tag No.* built Design N-5 Report Section III*

Report RNS Pump A (Pressure RNS N-5 Code Data RNS-MP-01A Yes XXX Boundary) Report RNS Pump B (Pressure RNS N-5 Code Data RNS-MP-OIB Yes XXX Boundary) Report RNS Heat Exchanger A RNS N-5 Code Data RNS-ME-01A Yes XXX (Tube Side) Report RNS Heat Exchanger B RNS N-5 Code Data RNS-ME-01B Yes XXX (Tube Side) Report RCS Inner Hot Leg Suction RNS N-5 Code Data Motor-operated Isolation RNS-PL-V001A Yes XXX Report Valve RCS Inner Hot Leg Suction RNS N-5 Code Data Motor-operated Isolation RNS-PL-V001B Yes XXX Report Valve RCS Outer Hot Leg Suction RNS N-5 Code Data Motor-operated Isolation RNS-PL-V002A Yes XXX Report Valve RCS Outer Hot Leg Suction RNS N-5 Code Data Motor-operated Isolation RNS-PL-V002B Yes XXX Report Valve RCS Pressure Boundary RNS N-5 Code Data RNS-PL-V003A Yes XXX Thermal Relief Check Valve Report RCS Pressure Boundary RNS N-5 Code Data RNS-PL-V003B Yes XXX Thermal Relief Check Valve Report RNS Discharge Motor- RNS N-5 Code Data operated Containment RNS-PL-V011 Yes XXX Report Isolation Valve RNS Discharge Containment RNS N-5 Code Data RNS-PL-V012 Yes XXX Isolation Test Connection Report RNS Discharge Header RNS N-5 Code Data Containment Isolation Check RNS-PL-V013 Yes XXX Report Valve RNS Discharge RCS RNS N-5 Code Data Pressure Boundary Check RNS-PL-V015A Yes XXX Report Valve RNS Discharge RCS RNS N-5 Code Data Pressure Boundary Check RNS-PL-V015B Yes XXX Report Valve RNS Discharge RCS RNS N-5 Code Data Pressure Boundary Check RNS-PL-V017A Yes XXX Report Valve

U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 10 of 13 Attachment A SYSTEM: Normal Residual Heat Removal System (RNS)

ASME III as-ASME Code Equipment Name* Tag No.* built Design N-5 Report Section III*

Report RNS Discharge RCS RNS N-5 Code Data Pressure Boundary Check RNS-PL-V017B Yes XXX Report Valve RNS Hot Leg Suction RNS N-5 Code Data RNS-PL-V020 Yes XXX Pressure Relief Valve Report RNS Hot Leg Suction RNS N-5 Code Data RNS-PL-V021 Yes XXX Pressure Relief Valve Report RNS Suction Header Motor- RNS N-5 Code Data operated Containment RNS-PL-V022 Yes XXX Report Isolation Valve RNS Suction from IRWST RNS N-5 Code Data Motor-operated Isolation RNS-PL-V023 Yes XXX Report Valve RNS Discharge to IRWST RNS N-5 Code Data Motor-operated Isolation RNS-PL-V024 Yes XXX Report Valve RNS Pump Discharge Relief RNS N-5 Code Data RNS-PL-V045 Yes XXX Report RNS Suction from Cask RNS N-5 Code Data Loading Pit Motor-operated RNS-PL-V055 Yes XXX Report Isolation Valve RNS Suction from Cask RNS N-5 Code Data RNS-PL-V056 Yes XXX Loading Pit Check Valve Report RNS Pump Miniflow Air- RNS N-5 Code Data RNS-PL-V057A Yes XXX Operated Isolation Valve Report RNS Pump Miniflow Air- RNS N-5 Code Data RNS-PL-V057B Yes XXX Operated Isolation Valve Report RNS Return from Chemical and Volume Control System RNS N-5 Code Data RNS-PL-V061 Yes XXX (CVS) Containment Isolation Report Valve "Excerpts from COL Appendix C Table 2.3.6-1

U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 11 of 13 Attachment B SYSTEM: Normal Residual Heat Removal System (RNS)

ASME ASME III LBB Leak Functional Code As-Built evaluation /

Line Name* Line No.* Before Capability N-5 Section Design pipe break Break* Required* Report ill* Report evaluation RNS Suction Lines, from the RCS Hot Leg N-5 RNS-L001 Connection to the Code RNS-L002A Yes Yes No XXX YYY RCS Side of Valves Data RNS-L002B RNS PL-VOOIAand Report RNS-PL-V001B RNS-L004A Yes RNS Suction Lines, Yes RNS-L004B from the RCS N-5 RNS-L005 Yes Pressure Boundary Yes Code RNS-L006 YYY Valves, RNS-PL- Yes No XXX RNS-007A Yes Data VOOIAand RNS-PL- Report RNS-007B Yes V001B,tothe RNS Yes RNS-009A pumps Yes RNS-009B N-5 RNS Suctton Line Code RNS-L061 Yes No Yes XXX YYY from CVS Data Report N-5 RNS Suction Line Code RNS-L029 Yes No Yes XXX YYY from IRWST Data Report N-5 RNS Suction Line RNS-L040 Code Yes No Yes XXX YYY LTOP Relief RNS-L090 Data Report RNS Discharge Lines, from the RNS Pumps N-5 to the RNS Heat RNS-L011A Code Yes No Yes XXX YYY Exchangers RNS-L011B Data RNS-ME-OIAand Report RNS-ME-01B RNS Discharge Lines, from RNS Heat N-5 Exchanger RNS-ME- RNS-L012A Code Yes No Yes XXX YYY 01A to Containment RNS-L014 Data Isolation Valve RNS- Report PL-V011

U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 12 of 13 Attachment B SYSTEM: Normal Residual Heat Removal System (RNS)

ASME ASME III LBB Leak Functional Code As-Built evaluation /

Line Name* Line No.* Before Capability N-5 Section Design pipe break Break* Required* Report III* Report evaluation RNS Discharge Line, from RNS Heat N-5 Exchanger RNS-ME- Code RNS-L012B Yes No Yes XXX YYY 01B to Common Data Discharge Header Report RNS-L014 RNS Discharge Lines, Containment Isolation N-5 Valve Code RNS-PL-V011 to RNS-L016 Yes No Yes XXX YYY Data Containment Isolation Report Valve RNS-PL-V013 N-5 RNS Suction Line Code RNS-L065 Yes No No XXX YYY from Cask Loading Pit Data Report RNS Discharge Lines, from Containment Isolation Valve RNS- N-5 RNS-L017 Code PL-V013 to RCS XXX YYY RNS-L018A Yes No Yes Pressure Boundary Data RNS-L018B Report Isolation Valves RNS-PL-V015Aand RNS-PL-V015B RNS Discharge Lines, from Direct Vessel Injection (DVI) Line N-5 RNS-BBC-L018Ato Code RNS-L020 Yes No No XXX YYY Passive Core Cooling Data System (PXS) IRWST Report Return Isolafion Valve RNS-PL-V024

U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 13 of 13 Attachment B SYSTEM: Normal Residual Heat Removal System (RNS)

ASME ASME III LBB Leak Functional Code As-Bulit evaluation /

Line Name* Line No.* Before Capability N-5 Section Design pipe break Break* Required* Report ill* Report evaluation RNS Discharge Lines, from RCS Pressure Boundary Isolation Valves RNS-PL- N-5 V015Aand RNS-PL- RNS-L019A Code Yes No Yes XXX YYY V015Bto RCS RNS-L019B Data Pressure Boundary Report Isolation Valves RNS-PL-V017Aand RNS-PL-V017B N-5 RNS Heat Exchanger RNS-L008A Code Yes No No XXX YYY Bypass RNS-L008B Data Report N-5 RNS Suctton from Code RNS-L052 Yes No No XXX YYY Spent Fuel Pool Data Report N-5 RNS Pump Miniflow RNS-L030A Code Yes No No XXX YYY Return RNS-L030B Data Report N-5 RNS Discharge to Code RNS-L051 Yes No No XXX YYY Spent Fuel Pool Data Report N-5 RNS Discharge to Code RNS-L021 Yes No No XXX YYY CVS Purification Data Report "Excerpts from COL Appendix C, Table 2.3.6-2