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

From kanterella
(Redirected from ND-18-0315)
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 Unit4 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 performedor have been onlypartially completed. All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRCto support the Commission finding that all acceptance criteria are met priorto 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 PublicService 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 incomponents identified inTable 2.2.3-1 as ASME Code Section III meet ASME Code Section III requirements.

3.b) Pressure boundary welds in piping identified inTable2.2.3-2as ASME Code Section III meet ASME Code Section III requirements.

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

4.b)The piping identified inTable2.2.3-2as ASME Code Section III retainsits 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 towithstand combined normal andseismic design basis loads without a lossof its functional capability.

6. Each of the as-built lines identified inTable 2.2.3-2 as designed for LBB meets the LBB criteria, oran evaluation is performed ofthe protection from the dynamic effects ofa rupture of the line.

Inspections. Tests. Analvses:

Inspection will be conducted 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 test will be performed on thecomponents and piping required by theASME Code Section III to be hydrostatically tested.

Inspection will be performed verifying that theas-built piping meets therequirements for functional capability.

Inspection will be performed for theexistence 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 fromthe 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 inTables 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 ofthe as-built lines identified inTable 2.2.3-2 for which functional capability is required meets the requirements for functional capability.

An LBB evaluation reportexists and concludes that the LBB acceptance criteria are met bythe as-built PXS piping and piping materials, or a pipe break evaluation reportexists and concludes that protection fromthe dynamic effects of a line break is provided.

ITAAC Completion Description This ITAAC requiresinspections, tests, and analyses be performed and documentedto ensure the Passive Core Cooling System (PXS) componentsand piping listed inthe Combined License (COL) Appendix C, Table 2.2.3-1 (Attachment A) andTable 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 designedand 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 theVEGP Updated Final Safety Analysis Report (UFSAR) andtheASME Code Section III requirements. The ASME Code Section III certified Design Reports for these components exist and document thatthe as-built components conform tothe approved designdetails. TheASME Section III Design Report for each component isdocumented in thecomponent's completed ASME Section III Code Data Report. The individual component ASME Section III Code Data Reports aredocumented 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 CodeSection III, are subjected to a reconciliation process (Reference 2), which verifies thatthe as-built piping are analyzed for applicable loads (e.g., stress reports) andfor 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 theapproved 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 anddesign 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 inthe Table 2.2.3-1 and Table2.2.3-2 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 demonstratethat 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).

Theapplicable non-destructive examinations (including liquid penetrant, magnetic particle, radiographic, and ultrasonic testing, as required by ASME Code Section III) of thecomponents' 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 andtesting of the item, which includes non-destructive examinations ofpressure boundary welds. Satisfactory completion of the non-destructive examination of pressure boundary welds ensuresthatthe 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 isperformed in accordance with Reference 2todemonstrate thattheas-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 unacceptableindications). This portion of the ITAAC iscomplete when thepiping identified in Table 2.2.3-2, which is encompassed within the respective piping systemCode 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 data package, which support completion of the respective Code Stamping and Code N-5 Data Report(s).

The completion of stamping therespective piping system along with the corresponding ASME Code N-5 Data Report Form(s) (certified by the Authorized Nuclear Inspector) ensure thatthe piping isconstructed in accordancewith the design specification(s) and theASME Code Section III and that the satisfactory completion of the non-destructive examinations ofpiping pressure boundary welds for the pipelines identified in Table 2.2.3-2 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-18-0315 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 completionofthe N-5 Data Reports Is governed by Reference 2.

This portion ofthe 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 InstalledInto the respective Code Symbol N-Stamped piping system and documented on the corresponding N-5 Code Data Report(s) (Reference1).

The hydrostatic testing results ofthe component's pressure boundaryare 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 ofstamping the Individual componentsand the respective piping system along with the correspondingASME Code Data Reports (certified by the Authorized Nuclear Inspector) ensures that the componentsare constructed In accordance with the Design Specifications and the ASME CodeSection III and that the satisfactory completion ofthe hydrostatic pressuretesting ofeach 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 pressureboundary 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 InTable 2.2.3-2 retains Its pressure boundary Integrity at Itsdesign pressure.

Ahydrostatic test verifies thatthere are no leaksat welds or piping, and thatthe pressure boundary Integrity Isretained at Its design pressure. The hydrostatic testing results ofthe pipe lines are documented In the Hydrostatic Testing Report(s). TheHydrostatic Testing Report(s) supports completion ofthe ASME Section III N-5 CodeData Report(s) for the applicable piping system (I.e., PXS) (Reference 1).

Theapplicable 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 andTable 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 InTable 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 toverify thatthe report demonstratesthat each ofthe 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,"inthis context, refers to the capability of the piping to withstand the effects of earthquakes, without a loss of safety function (to convey fluidsfrom one locationto another). Specific functional capability requirements are defined inthe VEGP UFSAR Table 3.9-11 (Reference 3).

Piping functional capability is not a specific ASME 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 Reports for 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 subjectedto a reconciliation process (Reference2), 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 systemsvalidates thatconstruction completion, including field changes and any nonconforming condition dispositions, isconsistent with and bounded bythe approved design. As required by ASME Code, the As-Built Design Reportincludesthe 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 andconclude that each of theas-built PXS 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 PXSpiping linesinTable 2.2.3-2 are identified in Attachment B.

6. An LBBevaluation 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 theas-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 theline. VEGP COL Appendix 0, 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 3.6.3toconfirm 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 API000 Piping (Reference 3). In cases where an as-built PXS piping line in Attachment Bcannot meet the LBB acceptance criteria, a pipebreak evaluation is performed which concludes that protection from thedynamic 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).

Inspections are performed toverify that LBB as-built piping evaluation reports for thePXS 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 ineither 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 lineinAttachment Bcannot 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 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; Areport existsand concludesthat the ASME Code Section III requirements are metfor non-destructive examination of pressure boundary welds; A reportexists and concludes that the results of the hydrostatictest 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; Areport existsand concludes that each ofthe as-built lines identified in Table2.2.3-2 for which functional capability is required meets the requirements forfunctional capability; and An LBB evaluation report exists and concludes that the LBB acceptance criteria are met bythe as-built PXS piping and piping materials, ora pipebreakevaluation report exists and concludes that protection from the dynamic effects ofa line break is provided.

References 1 and 4 are availablefor NRC inspectionas part ofthe 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 proceduresfor ITAAC completion, Southem Nuclear Operating Company (SNC) performed a review ofall ITAAC findings and associated corrective actions.

This review, which includednowconsolidated 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 ofthe 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)

Equipment Name

  • Tag No.
  • ASME Code Section III*

ASME III as-built Design Report N-5 Report Passive Residual Heat Removal Heat Exchanger (PRHR HX)

PXS-ME-01 Yes XXX N-5 Code Data Report 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-operated Valve PXS-PL-V002A Yes XXX N-5 Code Data Report CMT B Inlet Isolation Motor-operated Valve PXS-PL-V002B Yes XXX N-5 Code Data Report 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 Valve PXS-PL-V022A Yes XXX N-5 Code Data Report Accumulator B Pressure Relief Valve PXS-PL-V022B Yes XXX N-5 Code Data Report Accumulator A Discharge Isolation Valve PXS-PL-V027A Yes XXX N-5 Code Data Report Accumulator B Discharge Isolation Valve PXS-PL-V027B Yes XXX N-5 Code Data Report Accumulator A Discharge Check Valve PXS-PL-V028A Yes XXX N-5 Code Data Report Accumulator B Discharge Check Valve PXS-PL-V028B Yes XXX N-5 Code Data Report Accumulator A Discharge Check Valve PX8-PL-V029A Yes XXX N-5 Code Data Report Accumulator B Discharge Check Valve PXS-PL-V029B Yes XXX N-5 Code Data Report Nitrogen Supply Containment Isolation Valve PXS-PL-V042 Yes XXX N-5 Code Data Report

U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 10 of 13 Attachment A SYSTEM: Passive Core Cooling System (PXS)

Equipment Name

  • Tag No.
  • ASME Code Section III*

ASME III as-bullt Design Report N-5 Report Nitrogen Supply Containment Isolation Check Valve PXS-PL-V043 Yes XXX N-5 Code Data Report PRHR HX Inlet Isolation Motor-operated Valve PXS-PL-V101 Yes XXX N-5 Code Data Report 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 Isolation Motor-operated Valve PXS-PL-V117A Yes XXX N-5 Code Data Report Containment Recirculation B Isolation Motor-operated Valve PXS-PL-V117B Yes XXX N-5 Code Data Report Containment Recirculation A Squib Valve PXS-PL-V118A Yes XXX N-5 Code Data Report Containment Recirculation B Squib Valve PXS-PL-V118B Yes XXX N-5 Code Data Report Containment Recirculation A Check Valve PXS-PL-V119A Yes XXX N-5 Code Data Report Containment Recirculation B Check Valve PXS-PL-V119B Yes XXX N-5 Code Data Report Containment Recirculation A Squib Valve PXS-PL-V120A Yes XXX N-5 Code Data Report Containment Recirculation B Squib Valve PXS-PL-V120B Yes XXX N-5 Code Data Report IRWSTInjectionA 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 COLAppendix 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)

Line Name*

Line Number*

ASME Code Section

[II*

Leak Before Break*

Functional Capability Required*

ASME ill As-Bullt Design Report LBB evaluation/

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

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

Line Name*

Line Number*

ASME Code Section ill*

Leak Before Break*

Functionai Capability Required*

ASME III As-Built Design Report LBB evaluation/

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

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

Line Name*

Line Number*

ASME Code Section Hi*

Leak Before Break*

Functional Capability Required*

ASME ill As-Built Design Report LBB evaluation/

pipe break evaluation N-5 Report Containment recirculation line B PXS-L100, PXS-L101, PXS-L106, PXS-L113B, PXS-L131B, PXS-L132B Yes No Yes XXX N/A N-5 Code Data Report IRWST gutter drain line PXS-L142A, PXS-L142B Yes No Yes XXX N/A N-5 Code Data Report PXS-LMIA-",

PXS-LMIB-"

Yes No No XXX N/A N-5 Code Data Report Downspout drain lines from polar crane girder and internal stiffener to collection box A

PXS-L301A, PXS-L302A, PXS-L303A, PXS-L304A, PXS-L305A, PXS-L306A, PXS-L307A, PXS-L308A, PXS-L309A"',

PXS-L310A-'

Yes No Yes XXX N/A N-5 Code Data Report Downspout drain lines from polar crane girder and internal stiffener to collection box B

PXS-L301B, PXS-L302B, PXS-L303B, PXS-L304B, PXS-L305B, PXS-L306B, PXS-L307B, PXS-L308B, PXS-L309B"',

PXS-L310B'-

Yes No Yes XXX N/A N-5 Code Data Report

  • Excerpts from COL Appendix C, Table 2.2.3-2

+ For girth fillet welds between piping and socket welded fittings, valves andflanges, 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=5009358"