ND-18-0315, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.02a (Index Number 159)

From kanterella
Jump to navigation Jump to search
Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.02a (Index Number 159)
ML18089A363
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 03/29/2018
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ITAAC 2.2.03.02a, ND-18-0315
Download: ML18089A363 (16)
v • d • e


Text

_ , . . , Michael J.Yox 7825 River Road SOUtnSrn iNUCl0dr Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 &4 706-848-6459 tei 410-474-8587 cell MAR 2 9 2018 myox@southernco.com Docket Nos.: 52-025 52-026 ND-18-0315 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 2.2.03.02a [Index Number 1591 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of March 5, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.02a [Index Number 159]

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.

Michael J. Vox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.02a [Index Number 159]

MJY/KJD/amw

U.S. Nuclear Regulatory Commission ND-18-0315 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. Vox 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 Reoulatorv 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 Oaiethoroe Power Corporation Mr. R. B. Brinkman Munlcioai Eiectric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0315 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinqhouse 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. Hesler, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

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

U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 1 of 13 Southern Nuclear Operating Company ND-18-0315 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.02a [Index Number 159]

U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 2 of 13 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 2.2.3-2as ASME Code Section III meet ASME Code Section III requirements.

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

4.b) The piping identified inTable 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 lossof 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.

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 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 criteria for protection from the dynamic effects of pipe rupture.

U.S. Nuclear Regulatory Commission ND-18-0315 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 2.2.3-1 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 Completion Description This ITAAC requires inspections, tests, and analyses be performed and documented to ensure the Passive Core Cooling System (PXS) components and piping listed inthe 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 Societyof 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 comoonents and oipina 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 isfabricated 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 theapplicable piping system (Reference 1).

The as-built piping listed in Table 2.2.3-2 including the components listed in Table2.2.3-1 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, isconsistent 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 itssub-tier references.

U.S. Nuclear Regulatory Commission ND-18-0315 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 2.2.3-1 (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 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 2.2.3-1 and Table 2.2.3-2 are identified in Attachments A and B, respectively.

3.a and 3.b1 A report exists and concludes that the ASME Code Section III requirements are met for non-destructive examination of pressure boundarv welds.

Inspectionsare 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 2.2.3-1 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, radiographic, and ultrasonic testing, as required by ASME Code Section III) of the components' pressure boundary welds are documented in the Non-destructive Examination Report(s), which support completion of the respective ASME Section III N-5 Code Data Report(s) certified by the Authorized Nuclear Inspector, as listed in Attachment A.

Per ASME Code Section III, Subarticle NCA-8300, "Code Symbol Stamps," the N-5 Code Data Report(s) (Reference 1) documents satisfactory completion of the required examination and testing of the item, which includes non-destructive examinations of pressure boundary welds. Satisfactory completion of the non-destructive examination of pressure boundary welds ensures thatthe pressure boundary welds in components identified in Table 2.2.3-2 as ASME Code Section III meet ASME Code Section III requirements.

An inspection is performed in accordance with Reference 2 to demonstrate thatthe as-built pressure boundary welds in piping identified in Table 2.2.3-2 (Attachment B) as ASME Code Section III meet ASME Code Section III requirements (i.e., no unacceptable indications). This portion of the ITAAC iscomplete when the piping identified in Table 2.2.3-2, which is encompassed within the respective piping systemCode 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). 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 is constructed in accordancewith the design specification(s) and theASME 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 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-18-0315 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 Dioina 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 is 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 Is governed by Reference 2.

This portion of the ITAAC Is complete once each component Identified In Table 2.2.3-1 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) (Reference1).

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 componentsand 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 Specifications and the ASME Code Section III and that the satisfactory completion of the hydrostatic pressuretesting of each component Identified In Table 2.2.3-1 as ASME Code Section III are documented In the HydrostaticTesting Report(s) within the supporting data packages and meets ASME Code Section III requirements.

This ITAAC also verifies that the piping Identified In Table 2.2.3-2 (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 compiles 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 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 ofthe 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.

5.b1 A reoort exists and concludes that each of the as-bullt lines Identified In Table 2.2.3-2 for which functional caoabllltv Is reoulred meets the requirements for functional caoabllltv.

An Inspection Is performed of the ASME Section III as-bullt piping design report XXX to verify that the report demonstratesthat each of the PXS piping lines Identified In ITAAC Table

U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 6 of 13 2.2.3-2 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 inthe 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 (Reference2), 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 by ASME Code, the As-Built Design Report includesthe 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 4) for the PXS piping lines identified in Table 2.2.3-2 are complete and conclude that each of the as-built PXS piping lines for which functional capability is required meetsthe 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 are met bv the as-built PXS Dioino and oioina materials, or a oioe break evaluation report exists and concludes that protection from the dvnamic effects of a line break is orovided.

Inspections are performed for the as-built lines identified in Table 2.2.3-2 (Attachment B) to verify that eachof 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 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 3.6.3to confirm thatthe as-built PXS 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 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 isdocumented as a pipe rupture hazards analysis report (pipe break evaluation report).

Inspections are performed toverify that LBB as-built piping evaluation reports for the PXS piping (and corresponding piping materials) identified in Attachment Bconclude that theas-built piping analysis is bounded by the applicable bounding analysis curves provided in Appendix 3B of the

U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 7 of 13 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 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 2.2.3-1 and 2.2.3-2 as ASME Code Section III;
  • 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 2.2.3-2as ASME Code Section III conform with the requirements of the ASME Code Section III;
  • A report existsand concludes that each ofthe as-built lines identified in Table2.2.3-2 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 bythe 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.

References 1 and 4 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.03.02a Completion Packages (References 5 and 6, respectively).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southem Nuclear Operating Company (SNC) performed a review of all ITAAC findings and associated corrective actions.

This review, which included now consolidated ITAAC Indexes 160,161,162,163,164,168, and 169, found the following relevant ITAAC findings associated with this ITAAC:

1) Noncited Violation (NCV) 05200025/2017004-01/05200026/2017004-01 (Open)
2) Notice of Nonconformance (NGN) 99901431/2013-201-01 (Closed)
3) NGN 99901377/2012-201-02 (Closed)
4) NGN 99901377/2012-201-03 (Closed)

U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 8 of 13

5) NON 99900404/2011-201-02 (Open)

Before submission of tfie IT/\AC Closure Notification (ICN), corrective actions will be completed for relevant findings identified prior to ICN submission.

References favailabie for NRG inspection)

1. PXS ASME N-5 Code Data Report(s)
2. APP-GW-GAP-139, "Westingfiouse/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 API 000 Piping
4. PXS ASME III As Built Design Report(s)
5. Completion Package for Unit 3 ITAAC 2.2.03.02a [COL Index Number 159]
6. Completion Packagefor Unit 4 ITAAC 2.2.03.02a [COL Index Number 159]
7. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10CFR Part 52"

U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 9 of 13 Attachment A SYSTEM: Passive Core Cooling System (PXS)

ASME III as-ASME Code Equipment Name

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

Report Passive Residual Heat Removal PXS-ME-01 Yes XXX N-5 Code Data Report Heat Exchanger (PRHR HX)

Accumulator Tank A PXS-MT-01A Yes XXX N-5 Code Data Report Accumulator Tank B PXS-MT-01B Yes XXX N-5 Code Data Report Core Makeup Tank (CMT) A PXS-MT-02A Yes XXX N-5 Code Data Report CMTB PXS-MT-02B Yes XXX N-5 Code Data Report CMT A Inlet Isolation Motor- XXX N-5 Code Data Report PXS-PL-V002A Yes operated Valve CMT B Inlet Isolation Motor- N-5 Code Data Report PXS-PL-V002B Yes XXX operated Valve CMT A Discharge Isolation Valve PXS-PL-V014A Yes XXX N-5 Code Data Report CMT B Discharge Isolation Valve PXS-PL-V014B Yes XXX N-5 Code Data Report CMT A Discharge Isolation Valve PXS-PL-V015A Yes XXX N-5 Code Data Report CMT B Discharge Isolation Valve PXS-PL-V015B Yes XXX N-5 Code Data Report CMT A Discharge Check Valve PXS-PL-V016A Yes XXX N-5 Code Data Report CMT B Discharge Check Valve PXS-PL-V016B Yes XXX N-5 Code Data Report CMT A Discharge Check Valve PXS-PL-V017A Yes XXX N-5 Code Data Report CMT B Discharge Check Valve PXS-PL-V017B Yes XXX N-5 Code Data Report Accumulator A Pressure Relief XXX N-5 Code Data Report PXS-PL-V022A Yes Valve Accumulator B Pressure Relief XXX N-5 Code Data Report PXS-PL-V022B Yes Valve Accumulator A Discharge Isolation PXS-PL-V027A Yes XXX N-5 Code Data Report Valve Accumulator B Discharge Isolation PXS-PL-V027B Yes XXX N-5 Code Data Report Valve Accumulator A Discharge Check PXS-PL-V028A Yes XXX N-5 Code Data Report Valve Accumulator B Discharge Check PXS-PL-V028B Yes XXX N-5 Code Data Report Valve Accumulator A Discharge Check PX8-PL-V029A Yes XXX N-5 Code Data Report Valve Accumulator B Discharge Check PXS-PL-V029B Yes XXX N-5 Code Data Report Valve Nitrogen Supply Containment PXS-PL-V042 Yes XXX N-5 Code Data Report Isolation Valve

U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 10 of 13 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 Nitrogen Supply Containment PXS-PL-V043 Yes XXX N-5 Code Data Report Isolation Check Valve PRHR HX Inlet Isolation Motor- XXX N-5 Code Data Report PXS-PL-V101 Yes operated Valve PRHR HX Control Valve PXS-PL-V108A Yes XXX N-5 Code Data Report PRHR HX Control Valve PXS-PL-V108B Yes XXX N-5 Code Data Report Containment Recirculation A XXX N-5 Code Data Report PXS-PL-V117A Yes Isolation Motor-operated Valve Containment Recirculation B PXS-PL-V117B Yes XXX N-5 Code Data Report Isolation Motor-operated Valve Containment Recirculation A Squib PXS-PL-V118A Yes XXX N-5 Code Data Report Valve Containment Recirculation B Squib PXS-PL-V118B Yes XXX N-5 Code Data Report Valve Containment Recirculation A Check PXS-PL-V119A Yes XXX N-5 Code Data Report Valve Containment Recirculation B Check PXS-PL-V119B Yes XXX N-5 Code Data Report Valve Containment Recirculation A Squib PXS-PL-V120A Yes XXX N-5 Code Data Report Valve Containment Recirculation B Squib PXS-PL-V120B Yes XXX N-5 Code Data Report Valve IRWST Injection A Check Valve PXS-PL-V122A Yes XXX N-5 Code Data Report IRWST Injection B Check Valve PXS-PL-V122B Yes XXX N-5 Code Data Report IRWST Injection A Squib Valve PXS-PL-V123A Yes XXX N-5 Code Data Report IRWST Injection B Squib Valve PXS-PL-V123B Yes XXX N-5 Code Data Report IRWST Injection A Check Valve PXS-PL-V124A Yes XXX N-5 Code Data Report IRWST Injection B Check Valve PXS-PL-V124B Yes XXX N-5 Code Data Report IRWST Injection A Squib Valve PXS-PL-V125A Yes XXX N-5 Code Data Report IRWST Injection B Squib Valve PXS-PL-V125B Yes XXX N-5 Code Data Report IRWST Gutter Isolation Valve PXS-PL-V130A Yes XXX N-5 Code Data Report IRWST Gutter Isolation Valve PXS-PL-V130B Yes XXX N-5 Code Data Report RNS Suction Leak Test Valve PXS-PL-V208A Yes XXX N-5 Code Data Report "Excerptsfrom COL Appendix C Table 2.2.3-1

U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 11 of 13 Attachment B SYSTEM: Passive Core Cooling System (PXS)

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

[II* Report evaluation RCS-L134, PXS-L102, PXS-L103, N-5 Code PRHR HX inlet PXS-L104A, Yes Yes Yes XXX YYY Data line from hot leg Report PXS-L104B, and outlet line to PXS-L105, steam generator RCS-L113 channel head N-5 Code PXS-L107 Yes Yes No XXX YYY Data Report RCS-L118A, PXS-L007A, CMT A inlet line PXS-L015A, N-5 Code from cold leg C PXS-L016A, YYY Data Yes Yes Yes XXX and outlet line to PXS-L017A, Report reactor vessel PXS-L018A, direct vessei PXS-L020A, injection (DVI) PXS-L021A nozzle A N-5 Code PXS-L070A Yes Yes No XXX YYY Data Report RCS-L118B, PXS-L007B, PXS-L015B, N-5 Code CMT B inlet line PXS-L016B, YYY Data Yes Yes Yes XXX from cold leg D PXS-L017B, Report and outlet line to PXS-L018B, reactor vessel PXS-L020B, DVI nozzle B PXS-L021B N-5 Code PXS-L070B Yes Yes No XXX YYY Data Report RNS A discharge line to PXS from N-5 Code RNS check valve PXS-L019A Yes Yes Yes XXX YYY Data RNS-PL-V017A to Report DVI line A

U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 12 of 13 Attachment B SYSTEM: Passive Core Cooling System (PXS)

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

ill* Report evaluation RNS B discharge line to PXS from N-5 Code RNS check valve PXS-L019B Yes Yes Yes XXX YYY Data RNS-PL-V017B Report to DVI line B Accumulator A PXS-L025A, N-5 Code discharge iine to PXS-L027A, Yes Yes Yes XXX YYY Data DVI line A PXS-L029A Report Accumulator B PXS-L025B, N-5 Code discharge line to PXS-L027B, Yes Yes Yes XXX YYY Data DVI line B PXS-L029B Report PXS-L123A, N-5 Code PXS-L125A, Yes Yes Yes XXX YYY Data PXS-L127A Report PXS-L124A, IRWST injection PXS-L118A, N-5 Code line A to DVI line A PXS-L117A, Yes No Yes XXX YYY Data PXS-L116A, Report PXS-L112A N-5 Code PXS-L133A, XXX YYY Data Yes Yes No PXS-L134A Report PXS-L123B, N-5 Code PXS-L125B, Yes Yes Yes XXX YYY Data PXS-L127B Report PXS-L124B, PXS-L118B, PXS-L117B, N-5 Code IRWST injection PXS-L116B, Yes No Yes XXX N/A Data line B to DVI line B Report PXS-L114, PXS-L112B, PXS-L120 N-5 Code PXS-L133B, XXX YYY Data Yes Yes No PXS-L134B Report N-5 Code IRWST screen PXS-L180A, XXX N/A Data Yes No Yes cross-connect line PXS-L180B Report PXS-L113A, N-5 Code Containment Yes XXX N/A Data PXS-L131A, Yes No recirculation line A Report PXS-L132A

U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 13 of 13 Attachment B SYSTEM: Passive Core Cooling System (PXS)

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

Hi* Report evaluation PXS-L100, PXS-L101, N-5 Code Containment PXS-L106, N/A Data Yes No Yes XXX recirculation line B PXS-L113B, Report PXS-L131B, PXS-L132B N-5 Code PXS-L142A, N/A Data Yes No Yes XXX PXS-L142B IRWST gutter Report drain line N-5 Code PXS-LMIA-", Data Yes No No XXX N/A PXS-LMIB-" Report PXS-L301A, PXS-L302A, Downspout drain PXS-L303A, lines from polar PXS-L304A, N-5 Code crane girder and PXS-L305A, Yes No Yes XXX N/A Data internal stiffener PXS-L306A, PXS-L307A, Report to collection box A PXS-L308A, PXS-L309A"',

PXS-L310A-'

PXS-L301B, PXS-L302B, Downspout drain PXS-L303B, lines from polar PXS-L304B, N-5 Code crane girder and PXS-L305B, Yes No Yes XXX N/A Data internal stiffener PXS-L306B, PXS-L307B, Report to collection box B 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).

Retrieved from "https://kanterella.com/w/index.php?title=ND-18-0315,_Notice_of_Uncompleted_ITAAC_225-days_Prior_to_Initial_Fuel_Load_Item_2.2.03.02a_(Index_Number_159)&oldid=2533474"