ND-18-0178, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.13.02 (Index Number 459)
| ML18051A717 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/19/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ND-18-0178 | |
| Download: ML18051A717 (10) | |
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Southern Nuclear FES 1J2018 Docket Nos.:
52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 cell myox @southernco.com ND-18-0178 10CFR 52.99(c)(3)
Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.13.02 [Index Number 4591 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern NuclearOperating Company hereby notifies the NRC that as of February 16, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.13.02 [Index Number 459] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern NuclearOperating 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 Guidelinefor 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 allSection 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteriaare 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. Yox Regulatory Affairs Director Vogtle 3 &4
U.S. Nuclear Regulatory Commission ND-18-0178 Page 2 of 4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.13.02 [Index Number 459]
MJY/KJD/amw
U.S. Nuclear Regulatory Commission ND-18-0178 Page 3 of 4 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. D. Williams Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. 0. E. Morrow Ms. K. M. Stacy Mr. M. K. Wastiington 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. T. C. Brimfield Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Oalethoroe Power Corporation Mr. R. B. Brinkman Municipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros
U.S. Nuclear Regulatory Commission ND-18-0178 Page 4 of 4 Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)
Mr. D. C. 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., GDS Associates, Inc.
Mr. 8. Roetger, Georgia Public Service Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham
U.S. Nuclear Regulatory Commission ND-18-0178 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-18-0178 Enclosure Vogtle Electric Generating Plant (VEGP) Unit3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.13.02 [Index Number 459]
U.S. Nuclear Regulatory Commission ND-18-0178 Enclosure Page 2 of 6 ITAAC Statement Desion Commitment:
- 2. The components identified InTable 2.3.13-1 as ASME Code Section ill are designed and constructed in accordance with ASME Code Section ill requirements.
- 3. Pressure boundary welds in components identified in Table 2.3.13-1 as ASME Code Section III meet ASME Code Section III requirements.
- 4. The components identified inTable 2.3.13-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
Inspections. Tests. Analyses:
Inspection will be conducted ofthe as-built components as documented inthe ASME design reports.
Inspection ofthe as-built pressure boundary weldswill be performed in accordance with the ASME Code Section III.
Ahydrostatic test wili be performed on the components required bythe ASME Code Section ili to be hydrostatically tested.
Acceptance Criteria:
The ASME Code Section Ili design reports exist for the as-built components identified inTable 2.3.13-1 as ASME Code Section lil.
Areport existsand concludes thatthe ASME CodeSection III requirements are metfor non destructive examination of pressure boundary welds.
Areport existsand concludes thatthe results ofthe hydrostatic test ofthe components identified in Table 2.3.13-1 as ASME Code Section III conform with the requirements of the ASME Code Section III.
ITAAC Completion Description This ITAAC requires inspections, tests, and anaiyses be performed and documented to ensure the Primary Sampling System (PSS) componentsiisted in the Combined License (COL)
Appendix C,Tabie2.3.13-1 (Attachment A) that are identified as American Society of Mechanicai Engineers (ASME) Code Section ill are designed and constructed in accordance with applicable requirements.
U.S. Nuclear Regulatory Commission ND-18-0178 Enclosure Page 3 of 6
- 2. The ASME Code Section III design reoorts exist for the as-built components Identified in Table 2.3.13-1 as ASME Code Section III.
Each component listed inTable 2.3.13-1 as ASME Code Section III is fabricated in accordance with the VEGP Updated FinalSafety Analysis Report (UFSAR) and the ASME Code Section III requirements. The ASME Code Section III certified Design Reports forthese 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 Reportsare documented on the ASME Section III N-5 Code Data Report(s) forthe applicable piping system (Reference 1).
The as-built components listed in Table 2.3.13-1 as ASME Code Section III, are subjected to a reconciliation process (Reference2), which verifies that the as-built componentsare analyzed for applicable loads(e.g., stress reports) and for compliance with all designspecification and Code provisions. Design reconciliation ofthe as-built systems, including installed components, validates that constructioncompletion, 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, 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/orits sub-tier references.
Theapplicable ASME Section III N-5 Code Data Report(s), which include the location ofthe certified Design Reports for all thecomponents listed in Table 2.3.13-1 (Attachment A) as ASME Code Section III, exist and conclude that these installedcomponents are designed and constructed (including their installation within the applicable as-built piping system) in accordance with the ASME Code Section III (1998 Edition, 2000 Addenda) requirements. The N-5 Code Data Reports for the the components listed in the Table 2.3.13-1 are identified in Attachment A.
- 3. A reoort exists and concludes that the ASME Code Section III requirements are met for non destructive examination of pressure boundarv welds.
Inspections are performed in accordance with ASME CodeSection III (1998 Edition, 2000 Addenda) to demonstrate that as-built pressureboundary welds in components identified in Table 2.3.13-1 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.
U.S. Nuclear Regulatory Commission ND-18-0178 Enclosure Page 4 of 6 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 incomponents identified inTable 2.3.13-1 as ASME Code Section III meet ASME Code Section III requirements.
- 4. A report exists and concludes that the results of the hvdrostatic test of the components identified in Table 2.3.13-1 as ASME Code Section III conform with the reouirements of the ASME Code Section III.
Ahydrostatic test is performed bythe vendor to demonstrate thatthe components identified in Table 2.3.13-1 (Attachment A) as ASME Code Section III retain theirpressure boundaryintegrity at theirdesign pressure. The completion ofthe N-5 Data Reports is governedby Reference2.
This ITAAC is complete once each component identified inTable2.3.13-1 has theirindividual CodeSymbol N-Stamp and corresponding CodeDataReport (Reference 1)completed, and the components are installed into the respective CodeSymbol N-Stamped piping systemand documentedon the corresponding N-5 Code Data Report(s) (Reference 1). The hydrostatic testing results ofthe component's pressure boundary are documented in the Hydrostatic Testing Report(s) within thesupporting component's datapackage, which support completion of the respective Code Stamping and Code Data Report(s).
Thecompletion of stamping the individual components andthe respective piping system along with the corresponding ASME Code Data Reports (certified by theAuthorized Nuclear Inspector) ensures thatthe components are constructed in accordancewith the Design Specifications and the ASME Code Section III and that the satisfactory completion of the hydrostatic pressure testing of each component identified in Table 2.3.13-1 as ASME CodeSection III are documented in the Hydrostatic Testing Report(s) within the supporting data packagesand meets ASME Code Section III requirements.
Reference 1 provides the evidence that the ITAAC Acceptance Criteria requirementsare met:
The ASME Code Section III design reportsexistfor the as-built componentsidentified in Table 2.3.13-1 as ASME Code Section III; Areport exists andconcludes thatthe ASME Code Section III requirements are met for non-destructive examination of pressure boundary welds; and A reportexists and concludes that the results ofthe hydrostatic test ofthe components identified in Table 2.3.13-1 as ASME Code Section III conform with the requirements of the ASME Code Section III.
Reference 1 is availablefor NRC inspection as part ofthe Unit 3 and Unit 4 ITAAC 2.3.13.02 Completion Packages (References 3 and 4, respectively).
U.S. Nuclear Regulatory Commission ND-18-0178 Enclosure Page 5 of 6 List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a reviewof all ITAAC findings and associated corrective actions.
This review, which included now consolidated ITAAC Indexes 460 and 461 found no relevant ITAAC findings associated with this ITAAC.
References (available for NRC inspection) 1.
PSS ASME N-5 Code Data Report(s)
- 2. APP-GW-GAP-139, "Westinghouse/WECTEC ASME N-5 Interface Procedure"
- 3. Completion Package for Unit 3 ITAAC 2.3.13.02 [COL Index Number 459]
- 4. Completion Package for Unit 4 ITAAC 2.3.13.02 [COL Index Number 459]
- 5. NEI 08-01, "Industry Guideline forthe ITAAC ClosureProcess Under 10CFR Part 52"
U.S. Nuclear Regulatory Commission ND-18-0178 Enclosure Page 6 of 6 ATTACHMENT A SYSTEM: Primary Sampling System (PSS)
Equipment Name
- Tag No.
- ASME Code Section III
- N-5 Report Containment Air Sample Containment Isolation Valve Inside Reactor Containment (IRC)
PSS-PL-V008 Yes N-5 Code Data Report Liquid Sample Line Containment Isolation Valve IRC PSS-PL-V010A Yes N-5 Code Data Report Liquid Sample Line Containment Isolation Valve IRC PSS-PL-V010B Yes N-5 Code Data Report Liquid Sample Line Containment Isolation Valve Outside Reactor Containment (ORC)
PSS-PL-V011A Yes N-5 Code Data Report Liquid Sample Line Containment Isolation Valve ORC PSS-PL-V011B Yes N-5 Code Data Report Sample Return Line Containment Isolation Valve ORC PSS-PL-V023 Yes N-5 Code Data Report Sample Return Containment Isolation Valve IRC PSS-PL-V024 Yes N-5 Code Data Report Air Sample Line Containment Isolation Valve ORC PSS-PL-V046 Yes N-5 Code Data Report
'Excerpt from COL Appendix C Table 2.3.13-1