ND-18-0554, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.07.02a (Index Number 392)
| ML18117A296 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/24/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ITAAC 2.3.07.02a, ND-18-0554 | |
| Download: ML18117A296 (10) | |
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Southern Nuclear APR 2 A2018 Docket Nos.:
52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtie 3 &4 7825 River Road Waynestraro, GA 30830 706-848-6459 tei 410-474-8587 ceii myox@southernco.com ND-18-0554 10CFR 52.99(c)(3)
Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.07.02a [Index Number 3921 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of April 16, 2018, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.07.02a [Index Number 392]
has not been completed greater than 225-days priorto initial fuel load. The Enclosure describes the plan forcompleting 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 ITAACfor 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.
He Michael J. Yox Regulatory Affairs Director Vogtie 3 &4
Enclosure:
Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit4 Completion Plan for Uncompleted ITAAC 2.3.07.02a [Index Number 392]
MJY/KJD/amw
U.S. Nuclear Regulatory Commission ND-18-0554 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)
Mr. M. D. Rauckhorst (w/o enclosures)
Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)
Mr. D. L. McKinney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. B. Klecha Mr. G. Chick Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. C. Chamberlain Mr. D. R. Culver Mr. T. G. Petrak Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:
Nuclear 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. Convert Oalethorpe Power Corporation Mr. R. B. Brinkman Municipal Electric Authoritv of Georgia Mr. J. E. Fuller
U.S. Nuclear Regulatory Commission ND-18-0554 Page 3 of 3 Mr. 8. M. Jackson 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. Deangells 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, GeorgiaPublicService Commission Ms. 8. W. Kernlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham
U.S. Nuclear Regulatory Commission ND-18-0554 Enclosure Page 1 of 7 Southern Nuclear Operating Company ND-18-0554 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.07.02a [Index Number 392]
U.S. Nuclear Regulatory Commission ND-18-0554 Enclosure Page 2 of 7 ITAAC Statement Deslon Commitment:
2.a) The componentsidentified inTable 2.3.7-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
2.b)The piping linesidentified in Table2.3.7-2 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
- 3. Pressure boundary welds in piping lines identified in Table2.3.7-2 as ASME CodeSection III meet ASME Code Section III requirements.
- 4. The piping lines identified in Table 2.3.7-2 as ASME CodeSection III retain theirpressure boundary integrity at their design pressure.
Insoections. Tests. Analyses:
Inspection will beconducted of the ASME as-built components and piping lines as documented in the ASME design reports.
Inspection of theas-built pressure boundary welds will be performed in accordance with the ASME Code Section ill.
Ahydrostatic testwill beperformed on thepiping lines required by theASME Code Section III to be hydrostatically tested.
Acceotance Criteria:
The ASME Code Section III design reports existfor the as-built components and piping lines identified in Tables 2.3.7-1 and 2.3.7-2 as ASME Code Section III.
Areport exists and concludes that the ASME 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 piping lines identified inTable 2.3.7-2 as ASME Code Section III conform with the requirements ofthe ASME Code Section III.
ITAAC Completion Description This ITAAC requires inspections, tests, andanalyses be performed anddocumented toensure the Spent Fuel Pool Cooling System (SFS) components and piping lines listed in the Combined License (COL) Appendix C, Table 2.3.7-1 (Attachment A) and Table 2.3.7-2 (Attachment B) that are identified as American Society of Mechanical Engineers (ASME) CodeSection ill, are designed and constructed in accordancewith applicable requirements.
U.S. Nuclear Regulatory Commission ND-18-0554 Enclosure Page 3 of 7 2.a and 2.b) The ASME Code Section III design reports exist for the as-built components and oioina lines identified in Tables 2.3.7-1 and 2.3.7-2 as ASME Code Section III.
Each component listed inTable 2.3.7-1 as ASME Code Section III is fabricated 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 Reportsforthese components exist and document that the as-built components conformto the approved design details. The ASME Section III Design Report foreach component is documented inthe component's completed ASMESection III Code Data Report. The individual component ASME Section III Code Data Reportsare documentedon the ASME Section III N-5 Code Data Report(s) forthe applicable piping system (Reference 1).
The as-built piping lines listed in Table 2.3.7-2 including the components listed in Table 2.3.7-1 as ASME Code Section III, are subjected to a reconciliation process (Reference 2), which verifies that the as-built piping lines are analyzedforapplicable loads (e.g. stress reports) and for compliance with all design specification and Codeprovisions. Design reconciliation ofthe as-built systems, including installed components, validates that construction completion, including field changes and anynonconforming condition dispositions, isconsistent with and bounded by the approved design. All applicable fabrication, installation andtesting records, as well as, those for the related Quality Assurance (OA) verification/inspection activities, which confirm adequate construction in compliance with the ASME CodeSection III and design provisions, are referenced in the N-5 data report and/oritssub-tierreferences.
Theapplicable ASME Section III N-5 Code Data Report(s), which include the location of the certified Design Reports for all thecomponents listed in Table 2.3.7-1 (Attachment A) and piping lines listed in Table2.3.7-2 (Attachment B) as ASME CodeSection 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 Reportsforthe piping system(s) containing the components listed in the Table 2.3.7-1 and Table 2.3.7-2 areidentified in Attachments A and B, respectively.
- 3. A report exists and concludes that the ASME Code Section III requirements are met for non destructive examination of pressure boundarv welds.
An inspection isperformed in accordance with Reference 2todemonstrate that theas-built pressure boundary welds in piping lines identified in Table 2.3.7-2 (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 lines identified in Table 2.3.7-2, which is encompassed within the respective piping system Code 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 lines pressure boundary welds are documented in the Non-destructive Examination Report(s) within thepiping system's supporting data package, which support completion of the respective Code Stamping andCode 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) ensurethatthe piping lines are constructed in accordancewith thedesign specification(s) andtheASME Code Section III andthat thesatisfactory completion
U.S. Nuclear Regulatory Commission ND-18-0554 Enclosure Page 4 of 7 of the non-destructive examinations of piping pressure boundary welds for the pipe lines identifiedinTable 2.3.7-2 meet ASME Code Section III requirements and are documented inthe Non-destructive Examination Report(s) within the supporting data packages.
- 4. A report exists and concludes that the results of the hvdrostatic test of the pioing lines identified in Table 2.3.7-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.
This ITAAC verifies thatthe piping lines identified in Table 2.3.7-2 (Attachment B) fully meets all applicable ASME Code,Section III requirements and retains its pressure boundary integrity at its design pressure.
Ahydrostatic test is performed in accordance with procedure XYZ (Reference 4) (asapplicable) thatcomplies with theASME Code (1998 Edition, 2000 Addenda),Section III requirements to demonstrate that the ASME Code Section III piping linesidentified in Table 2.3.7-2 retains its pressure boundary integrity at its design pressure.
Ahydrostatic testverifies that there are no leaks atwelds orpiping lines, and that the pressure boundary integrity isretained at its design pressure. The hydrostatic testing results of the pipe lines aredocumented in the Hydrostatic Testing Report(s). The Hydrostatic Testing Report(s) supports completion of the ASME Section III N-5 Code Data Report(s) for the applicable piping system (i.e., SFS) (Reference 1).
The applicable ASME Section III N-5 Code Data Report(s) (Reference 1) identified in Attachment Bdocumentsthat the resultsofthe hydrostatic testingofthe piping linesidentified in Table 2.3.7-2 conform with the requirements of the Code (1998 Edition, 2000 Addenda),Section III.
Reference 1 provides theevidence thatthefollowing ITAAC Acceptance Criteria requirements are met:
TheASME Code Section III design reports exist for the as-built components and piping lines identified in Tables 2.3.7-1 and 2.3.7-2 as ASME Code Section III; Areport exists and concludes that the ASME Code Section III requirements are met for non-destructive examination of pressure boundary welds; and Areport exists and concludes that the results of the hydrostatic test of piping lines identified inTable 2.3.7-2as ASME Code Section III conform with the requirementsof the ASME Code Section III.
Reference1 is available for NRC inspection as part ofthe Unit 3 and Unit 4 ITAAC 2.3.07.02a Completion Packages(References 5 and 6, respectively).
List of ITAAC Findings In accordance with plant procedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings and associated corrective actions.
This review, which included now consolidated ITAAC Indexes 393, 394and 395found no relevant ITAAC findings associated with this ITAAC:
U.S. Nuclear Regulatory Commission ND-18-0554 Enclosure Page 5 of 7 References (available for NRC Inspection) 1.
SFS ASME N-5 Code Data Report(s) 2.
APP-GW-GAP-139, "Westinghouse/WECTEC ASME N-5 Interface Procedure"
- 3. VEGP 3&4 Updated FinalSafety Analysis Report, Subsection 5.2.1, Compliance with Codes and Code Cases
- 4. SFS Piping Line ASME Section III Hydrostatic Test Procedure XYZ
- 5. Completion Package for Unit 3 ITAAC 2.3.07.02a [COLIndex Number 392]
- 6. Completion Package for Unit 4 ITAAC 2.3.07.02a [COL Index Number392]
7.
NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"
U.S. Nuclear Regulatory Commission ND-18-0554 Enclosure Page 6 of 7 Attachment A SYSTEM: Spent Fuel Pool Cooling System (SFS)
Component Name
- Tag No.
- ASME Code Section ill*
N-5 Report Refueling Cavity Drain to SGS Compartment Isolation Valve SFS-PL-V031 Yes SFS N-5 Code Data Report Refueling Cavity to SFS Pump Suction Isolation Valve SFS-PL-V032 Yes SFS N-5 Code Data Report Refueling Cavity Drain to Containment Sump Isolation Valve SFS-PL-V033 Yes SFS N-5 Code Data Report IRWSTto SFS Pump Suction Line Isolation Valve SFS-PL-V039 Yes SFS N-5 Code Data Report Fuel Transfer Canal to SFS Pump Suction Iso.
Valve SFS-PL-V040 Yes SFS N-5 Code Data Report Cask Loading Pit to SFS Pump Suction Isolation Valve SFS-PL-V041 Yes SFS N-5 Code Data Report Cask Loading Pit to SFS Pump Suction Isolation Valve SFS-PL-V042 Yes SFS N-5 Code Data Report SFS Pump Discharge Line to Cask Loading Pit Isolation Valve SFS-PL-V045 Yes SFS N-5 Code Data Report Cask Loading Pit to WLS Isolation Valve SFS-PL-V049 Yes SFS N-5 Code Data Report Spent Fuel Pool to Cask Washdown Pit Isolation Valve SFS-PL-V066 Yes SFS N-5 Code Data Report Cask Washdown Pit Drain Isolation Valve SFS-PL-V068 Yes SFS N-5 Code Data Report Refueling Cavity Drain Line Check Valve SFS-PL-V071 Yes SFS N-5 Code Data Report Refueling Cavity Drain Line Check Valve SFS-PL-V072 Yes SFS N-5 Code Data Report SFS Containment Floodup Isolation Valve SFS-PL-V075 Yes SFS N-5 Code Data Report
'Excerpts from COL Appendix C Table 2.3.7-1
U.S. Nuclear Regulatory Commission ND-18-0554 Enclosure Page 7 of 7 Attachment B SYSTEM: Spent Fuel Pool Cooling System (SFS)
Piping Line Name*
Line Number*
ASME Code Section III*
N-5 Report Spent Fuel Pool to RNS Pump Suction L014 Yes SFS N-5 Code Data Report Cask Loading Pit to RNS Pump Suction L115 Yes SFS N-5 Code Data Report Refueling Cavity Drain L033+
Yes SFS N-5 Code Data Report PXS IRWST to SFS Pump Suction L035 Yes SFS N-5 Code Data Report Refueling Cavity Skimmer to SFS Pump Suction L036 Yes SFS N-5 Code Data Report Refueling Cavity Drain L037 Yes SFS N-5 Code Data Report Refueling Cavity Drain L044+
Yes SFS N-5 Code Data Report Fuel Transfer Canal Drain L047 Yes SFS N-5 Code Data Report Cask Washdown Pit Drain L068 Yes SFS N-5 Code Data Report Cask Loading Pit Drain L043 Yes SFS N-5 Code Data Report Cask Pit Transfer Branch Line L045 Yes SFS N-5 Code Data Report Spent Fuel Pool Containment Isolation Thermal Relief Line L052+
Yes SFS N-5 Code Data Report Refueling Cavity Drain L030 Yes SFS N-5 Code Data Report Upender Pit Drain/Fill Line LI 21 Yes SFS N-5 Code Data Report Spent Fuel Pool Drain L066+
Yes SFS N-5 Code Data Report Cask Loading Pit to WLS L067+
Yes SFS N-5 Code Data Report RNS Return to Spent Fuel Pool LI 00 Yes SFS N-5 Code Data Report SFS Containment Floodup Line LI 20 Yes SFS N-5 Code Data Report
- Excerpts from COLAppendixC, Table 2.3.7-2
+ For girth fillet welds between piping and socket welded fittings, valves and flanges, refer to VEGP UFSAR Section 5.2.1.1 (Reference 3).