ND-18-0545, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.02.02a (Index Number 285)

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Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.02.02a (Index Number 285)
ML18117A305
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 04/24/2018
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ND-18-0545
Download: ML18117A305 (12)


Text

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Southern Nuclear APR 2 4 2018 Docket Nos.:

52-025 52-026 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 cell myox @southernco.com ND-18-0545 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 2.3.02.02a findex Number 2851 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern NuclearOperating Company hereby notifies the NRC that as ofApril 16, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, andAcceptance Criteria (ITAAC) Item 2.3.02.02a [Index Number 285]

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 laterdate, provide additional notifications for ITAAC that have not beencompleted 225-days prior to initial fuel load.

This notification is informed bythe guidance described in NEI 08-01, Industry Guideline forthe ITAAC Closure Process Under 10 CFR Part 52, which was endorsed by the NRC in Regulatory Guide 1.215. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, oranalyses have not been performed orhave 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 supportthe Commission finding that all acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

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

Respectfully submitted, Michael J. Yox Regulatory Affairs DirectorVogtle 3 &4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Planfor Uncompleted ITAAC 2.3.02.02a[Index Number 285]

MJY/KJD/amw

U.S. Nuclear Regulatory Commission ND-18-0545 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. 8. 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 Ms. N. C. Coovert Oalethoroe Power Corporation Mr. R. B. Brinkman

U.S. Nuclear Regulatory Commission ND-18-0545 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Orlani (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., CDS Associates, inc.

Mr. 8. Roetger, GeorgiaPublicSen/ice 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-18-0545 Enclosure Page 1 of 9 Southern Nuclear Operating Company ND-18-0545 Enclosure Vogtle Electric Generating Plant (VEGP) Unit3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.02.02a [Index Number 285]

U.S. Nuclear Regulatory Commission ND-18-0545 Enclosure Page 2 of 9 ITAAC Statement Design Commitment:

2.a) The components identified inTable 2.3.2-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.

2.b) The piping identified inTable 2.3.2-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.

3.a) Pressure boundary welds in components identified in Table 2.3.2-1 as ASME CodeSection III meet ASME Code Section III requirements.

3.b) Pressureboundary welds in piping identified in Table 2.3.2-2 as ASME CodeSection III meet ASME Code Section III requirements.

4.a)The components identified in Table 2.3.2-1 as ASME CodeSection III retain their pressure boundary integrity at their design pressure.

4.b) The piping identified in Table 2.3.2-2 as ASME CodeSection III retains itspressure boundary integrity at its design pressure.

Insoections. Tests. Analyses:

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

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

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

Acceptance Criteria:

The ASME CodeSection III design reports existfor the as-built components and piping identified in Tables 2.3.2-1 and 2.3.2-2 as ASME Code Section III.

Areport exists andconcludes that theASME Code Section III requirements are met for non destructive examination of pressure boundary welds.

Areport exists and concludes that the results of the hydrostatic test of the components and piping identified in Tables 2.3.2-1 and 2.3.2-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.

ITAAC Completion Description This ITAAC requires inspections, tests, andanalyses be performed anddocumented toensure the Chemical and Volume Control System (CVS) components and piping listed in the Combined License (COL) Appendix C, Table 2.3.2-1 (Attachment A) and Table 2.3.2-2 (Attachment B) that

U.S. Nuclear Regulatory Commission ND-18-0545 Enclosure Page 3 of 9 are identified as American Society of Mechanical Engineers (ASME) Code Section III, are designed and constructed in accordance with applicable requirements.

2.a and 2.b) The ASME Code Section III desion reoorts exist for the as-built components and oipino identified in Tables 2.3.2-1 and 2.3.2-2 as ASME Code Section III.

Each component listed in Table 2.3.2-1 as ASME Code Section III is fabricated in accordance withthe VEGP Updated Final Safety Analysis Report (UFSAR) and the ASMECode 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 Reportfor each component is documented inthe component's completed ASMESection 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) forthe applicable piping system (Reference 1).

The as-builtpiping listedinTable 2.3.2-2 including the components listed inTable 2.3.2-1 as ASME Code Section III, are subjected to a reconciliation process (Reference 2), which verifies that the as-built piping are analyzed for applicable loads (e.g. stress reports) and forcompliance with all design specification and Code provisions. Design reconciliation ofthe as-built systems, including installed components, validates that construction completion, including field changes and any nonconforming condition dispositions, isconsistent with and bounded bythe approved design. All applicable fabrication, installation and testing records, as well as, thosefor the relatedQuality Assurance (OA) verification/inspection activities, which confirm adequate construction incompliance with the ASME Code Section III and design provisions, are referenced in the N-5 data report and/or its sub-tier references.

Theapplicable ASME Section III N-5 Code Data Report(s), which include the location ofthe certified Design Reports for all the components listed in Table 2.3.2-1 (Attachment A) and piping listed inTable2.3.2-2 (Attachment B) as ASME Code Section III, existand conclude that these installed componentsare designed and constructed (including theirinstallation 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 forthe piping system(s) containing thecomponents listed in theTable 2.3.2-1 and Table 2.3.2-2 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 pressure boundarv welds.

Inspections are performed in accordancewith ASME Code Section III (1998 Edition, 2000 Addenda) todemonstrate that as-built pressure boundary welds in components identified in Table 2.3.2-1 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 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.

U.S. Nuclear Regulatory Commission ND-18-0545 Enclosure Page 4 of 9 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 that the pressure boundary welds in components identified inTable 2.3.2-1 as ASME Code Section III meet ASME Code Section III requirements.

An inspection is performed in accordance with Reference 2 to demonstrate that the as-built pressure boundary welds in piping identified inTable2.3.2-2 (Attachment B) as ASME Code Section III meet ASME Code Section III requirements (i.e., no unacceptable indications). This portion ofthe ITAAC is complete whenthe piping identified in Table2.3.2-2, which is encompassed within the respective piping system Code Symbol N-Stamp and the corresponding piping systemCode N-5 DataReport Form(s) (Reference 1), is complete. The non-destructiveexaminations (including visual inspection,liquid penetrant, magnetic particle, radiographic, and ultrasonic testing, as required byASME CodeSection III) ofthe 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 andCode N-5 DataReport(s). Thecompletion ofstamping the respective piping system along with thecorresponding ASME Code N-5 Data Report Form(s) (certified by the Authorized Nuclear Inspector) ensure that the piping isconstructed inaccordance with the design specification(s) and theASME Code Section III and that the satisfactory completion of the non-destructive examinations ofpiping pressure boundary weldsforthe pipelinesidentified in Table 2.3.2-2 meet ASMECode Section III requirements and are documented inthe Non-destructive Examination Report(s) within the supporting data packages.

4.a and 4.b1 A reoort exists and concludes that the results of the hvdrostatic test of the components and oipina identified in Tables 2.3.2-1 and 2.3.2-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.

Ahydrostatic testisperformed by thevendor todemonstrate that thecomponents identified in Table 2.3.2-1 (Attachment A) as ASME Code Section III retain their pressure boundary integrity attheir design pressure. The completion of the N-5 Data Reports isgoverned by Reference 2.

This portion of the ITAAC iscomplete once each component identified in Table 2.3.2-1 hastheir individual Code Symbol N-Stamp andcorresponding Code Data Report (Reference 1) completed, and thecomponents areinstalled into therespective Code Symbol N-Stamped piping system and documented on the corresponding N-5 Code Data Report(s) (Reference 1).

The hydrostatic testing results of thecomponent's pressure boundaryaredocumented in the Hydrostatic Testing Report(s) within thesupporting component's datapackage, which support completion ofthe respective CodeStamping and CodeData Report(s).

The completion of stamping theindividual components andthe respective piping system along with the corresponding ASME Code Data Reports (certified by the Authorized Nuclear Inspector) ensures that thecomponents areconstructed in accordance with theDesign Specifications and the ASME Code Section III and that thesatisfactory completion of the hydrostatic testing of each component identified in Table 2.3.2-1 as ASME Code Section III are documented in the Hydrostatic Testing Report(s) within thesupporting datapackages and meets ASME Code Section III requirements.

U.S. Nuclear Regulatory Commission ND-18-0545 Enclosure Page 5 of 9 This ITAACalso verifies that the piping identified in Table 2.3.2-2 (Attachment B) fully meets all applicable ASME Code,Section III requirements and retains its pressure boundary integrity at its design pressure.

A hydrostatic 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 2.3.2-2 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 of the pipe lines are documented in the Hydrostatic Testing Report(s). The Hydrostatic Testing Report(s) supports completion of the ASMESection III N-5 Code Data Report(s) for the applicable piping system (i.e., CVS) (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 inTable 2.3.2-1 and Table 2.3.2-2 respectively conform with the requirements of the Code (1998 Edition, 2000 Addenda), Section 111.

Reference 1 provides 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 2.3.2-1 and 2.3.2-2 as ASME Code Section III; Areport exists and concludesthat the ASME Code Section III requirements are metfor non-destructive examination of pressure boundary welds; and A reportexists and concludes that the results ofthe hydrostatictest of the components and piping identified inTables 2.3.2-1 and 2.3.2-2as ASME Code Section III conform with the requirements of the ASME Code Section III.

Reference 1 is available for NRC inspection as part ofthe Unit 3 and Unit 4 ITAAC 2.3.02.02a Completion Packages (References 5 and 6, respectively).

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

This review, which included now consolidated ITAAC Indexes 286, 287, 288, 289 and 290, found no relevant ITAAC findings associated with this ITAAC.

References (available for NRC inspection) 1.

CVS ASME N-5 Code Data Report(s)

2. APP-GW-GAP-139, "WestinghouseA/VECTEC ASME N-5 Interface Procedure"

U.S. Nuclear Regulatory Commission ND-18-0545 Enclosure Page 6 of 9 3.

VEGP 3&4 Updated Final Safety Analysis Report, Subsection 5.2.1, Compliance witfi Codes and Code Cases 4.

CVS Piping ASME Section III Hydrostatic Test Procedure XYZ 5.

Completion Package for Unit3 ITAAC 2.3.02.02a [COL Index Number 285]

6. Completion Package for Unit 4 ITAAC 2.3.02.02a [COL Index Number 285]

7.

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

U.S. Nuclear Regulatory Commission ND-18-0545 Enclosure Page 7 of 9 Attachment A SYSTEM: Chemical and Volume Control System (CVS)

Equipment Name

  • Tag No.
  • ASME Code Section ill*

N-5 Report RCS Purification Motor-operated Isolation Valve CVS-PL-V001 Yes CVS N-5 Code Data Report RCS Purification Motor-operated Isolation Valve CVS-PL-V002 Yes CVS N-5 Code Data Report RCS Purification Motor-operated Isolation Valve CVS-PL-V003 Yes CVS N-5 Code Data Report CVS Resin Flush Line Containment Isolation Valve CVS-PL-V040 Yes CVS N-5 Code Data Report CVS Resin Flush Line Containment Isolation Valve CVS-PL-V041 Yes CVS N-5 Code Data Report CVS Demineralizer Resin Flush Line Containment Isolation Thermal Relief Valve CVS-PL-V042 Yes CVS N-5 Code Data Report CVS Letdown Containment Isolation Valve CVS-PL-V045 Yes CVS N-5 Code Data Report CVS Letdown Containment Isolation Valve CVS-PL-V047 Yes CVS N-5 Code Data Report CVS Letdown Line Containment Isolation Thermal Relief Valve CVS-PL-V058 Yes CVS N-5 Code Data Report CVS Makeup Return Line Bypass Check Valve CVS-PL-V067 Yes CVS N-5 Code Data Report CVS Purification Return Line Pressure Boundary Check Valve CVS-PL-V080 Yes CVS N-5 Code Data Report CVS Purification Return Line Pressure Boundary Isolation Check Valve CVS-PL-V081 Yes CVS N-5 Code Data Report CVS Purification Return Line Pressure Boundary Check Valve CVS-PL-V082 Yes CVS N-5 Code Data Report CVS Auxiliary Pressurizer Spray Line Pressure Boundary Valve CVS-PL-V084 Yes CVS N-5 Code Data Report CVS Auxiliary Pressurizer Spray Line Pressure Boundary Check Valve CVS-PL-V085 Yes CVS N-5 Code Data Report CVS Makeup Line Containment Isolation Motor-operated Valve CVS-PL-V090 Yes CVS N-5 Code Data Report CVS Makeup Line Containment Isolation Motor-operated Valve CVS-PL-V091 Yes CVS N-5 Code Data Report CVS Zinc Injection Containment Isolation Valve ORC CVS-PL-V092 Yes CVS N-5 Code Data Report CVS Zinc Injection Containment Isolation Valve IRC CVS-PL-V094 Yes CVS N-5 Code Data Report CVS Zinc Addition Line Ctmt Isol Thermal Relief Valve CVS-PL-V098 Yes CVS N-5 Code Data Report

U.S. Nuclear Regulatory Commission ND-18-0545 Enclosure Page 8 of 9 Attachment A SYSTEM: Chemical and Volume Control System (CVS)

Equipment Name

  • Tag No.
  • ASME Code Section ill*

N-5 Report CVS Makeup Line Containment Isolation Thermal Relief Valve CVS-PL-V100 Yes CVS N-5 Code Data Report CVS Demineralized Water Isolatbn Valve CVS-PL-V136A Yes CVS N-5 Code Data Report CVS Demineralized Water Isolation Valve CVS-PL-V136B Yes CVS N-5 Code Data Report CVS Hydrogen InjectionContainment Isolation Check Valve IRC CVS-PL-V217 Yes CVS N-5 Code Data Report CVS Hydrogen Injection Containment Isolation Valve ORC CVS-PL-V219 Yes CVS N-5 Code Data Report

'Excerpts from COLAppendixC Table 2.3.2-1

U.S. Nuclear Regulatory Commission ND-18-0545 Enclosure Page 9 of 9 Attachment B SYSTEM; Chemical and Volume Control System (CVS)

Line Name*

Line Number*

ASMECode Section III*

N-5 Report CVS Purification Line L001 L040 Yes Yes CVS N-5 Code Data Report CVS Resin Flush Containment Penetration Line L026+

Yes CVS N-5 Code Data Report CVS Purification Line Return L038 Yes CVS N-5 Code Data Report CVS Pressurizer AuxiliarySpray Connection L070+

L071 +

Yes Yes CVS N-5 Code Data Report CVS Letdown Containment Penetration Line L051 +

Yes CVS N-5 Code Data Report CVS Makeup Containment Penetratton Line L053 Yes CVS N-5 Code Data Report CVS Hydrogen Injection Containment Penetration Line L213+

L214+

L217+

Yes CVS N-5 Code Data Report CVS Zinc Injection Containment Penetration Line L061 +

Yes CVS N-5 Code Data Report CVS Return Line from Regenerative Heat Exchanger L036 Yes CVS N-5 Code Data Report

  • Excerpts from COL Appendix C, Table 2.3.2-2

+ For girth fillet welds between piping and socket welded fittings, valves andflanges, refer to VEGP UFSAR Section 5.2.1.1 (Reference 3).