ML18089A349
| ML18089A349 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/29/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ITAAC 2.7.01.02a, ND-18-348 | |
| Download: ML18089A349 (11) | |
Text
Southern Nuclear MAR 2 9 2018 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 Waynesboro, GA 30830 706-848-6459 tei 410-474-8587 ceii myox@southernco.com ND-18-0348 10CFR 52.99(c)(3)
Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncomoleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.7.01.02a [Index Number 6781 Ladies and Gentlemen:
Pursuantto 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of March 19,2018, Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, andAcceptance Criteria (ITAAC) Item 2.7.01.02a [Index Number 678]
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 bythe guidance described in NEI 08-01, Industry Guideline forthe ITAACClosure 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 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.
7^1 Michael J. Yox.
Regulatory Affairs t)irector Vogtie 3 &4
Enclosure:
Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Planfor Uncompleted ITAAC 2.7.01.02a[Index Number 678]
MJY/LBP/amw
U.S. Nuclear Regulatory Commission ND-18-0348 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 Reouiatorv 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 Ooiethorpe Power Corporation Mr. R. B. Brinkman Municioai Eiectric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
U.S. Nuclear Regulatory Commission ND-18-0348 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinahouse 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-18-0348 Enclosure Page 1 of 8 Southern Nuclear Operating Company ND-18-0348 Enclosure Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.7.01.02a [Index Number 678]
U.S. Nuclear Regulatory Commission ND-18-0348 Enclosure Page 2 of 8 ITAAC Statement Design Commitment:
2.a) The components identifiedin Table 2.7.1-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
2.b) The piping identified inTable 2.7.1-2 as ASME Code Section Hi is designed and constructed in accordance with ASME Code Section ill requirements.
3.a) Pressure boundary welds in components identified in Tabie 2.7.1-1 as ASME CodeSection III meet ASME Code Section III requirements.
3.b) Pressure boundary welds in piping identified in Table 2.7.1-2 as ASME Code Section III meet ASME Code Section III requirements.
4.a)Thecomponents identified in Table 2.7.1-1 as ASME Code Section Hi retain their pressure boundary integrity at their design pressure.
4.b) Thepiping identified in Tabie 2.7.1-2 as ASME Code Section HI retains its pressure boundary integrityat its design pressure.
Inspections. Tests. Analyses:
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 beperformed in accordance with the ASME Code Section HI.
Apressure test will be performed on the components and piping required by the ASME Code Section HI to be pressure tested.
Acceptance Criteria:
TheASME CodeSection HI design reports exist for the as-built components and piping identified in Tables 2.7.1-1 and 2.7.1-2 as ASME Code Section Hi.
Areport exists and concludes that the ASME Code Section HI requirements are met for nondestructive examination of pressure boundary welds.
Areport exists and concludes that the results of the pressure test of the components and piping identified in Tables 2.7.1-1 and 2.7.1-2as ASME Code Section HI conform with the requirements ofthe ASME Code Section HI.
ITAAC Completion Description This iTAAC requires inspections, tests, and analyses be performed anddocumented toensure the Nuclear Island Nonradioactive Ventilation System (VBS) components and piping listed in the Combined License (COL) Appendix C,Tabie 2.7.1-1 (Attachment A) andTable 2.7.1-2
U.S. Nuclear Regulatory Commission ND-18-0348 Enclosure Page 3 of 8 (Attachment B)that 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.bf The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.7.1-1 and 2.7.1-2 as ASME Code Section III.
Each component listed inTable 2.7.1-1 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 conform to the approved design details. The ASME Section III Design Report foreach component isdocumentedinthe component'scompleted ASME Section III Code Data Report. The individual component ASME Section III Code Data Reports are documented on the ASME Section III N-5 CodeData Report(s) for the applicable pipingsystem (Reference 1).
The as-built piping listed inTable2.7.1-2including the componentslisted in Table 2.7.1-1 as ASME Code Section III, are subjectedto a reconciliation process (Reference 2), which verifies thatthe as-built piping are analyzed for applicable loads (e.g. stress reports) and for compliance with all design specification andCode 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. Ail applicable fabrication, installation and testing records, as well as, those for the related Quality Assurance (OA) verification/inspection activities, which confirrn adequate construction in compliance witfi the ASME CodeSection III and designprovisions, are referenced in the N-5data report and/or its sub-tier references.
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 2.7.1-1 (Attachment A) and piping listed in Table 2.7.1-2 (Attachment B) as ASME Code Section III, exist andconclude thatthese installed components aredesigned 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, 1989Addenda),Section III requirementsas 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 2.7.1-1 and Table 2.7.1-2 are identified in Attachments A and B, respectively.
3.a and 3.b1 A report exists and concludes that the ASME Code Section III reouirements are met for nondestructive examination of pressure boundarv welds.
Inspections areperformed in accordance with ASME Code Section III (1998 Edition, 2000 Addenda) to demonstrate that as-built pressure boundary welds in components identified in Table2.7.1-1 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 componerits' 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 inAttachmentA.
U.S. Nuclear Regulatory Commission ND-18-0348 Enclosure Page 4 of 8 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 2.7.1-1 as ASME Code Section III meet ASME Code Section III requirements.
An inspection is performed in accordance with Reference2 to demonstratethat the as-built pressureboundary welds in piping identified in Table 2.7.1-2 (Attachment B) as ASME Code Section III meet ASME Code Section III requirements (i.e., no unacceptable indications). This portion ofthe ITAAC iscomplete when the piping identified in Table2.7.1-2, which is encompassedwithin the respective piping systemCodeSymbol N-Stamp and the 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, andultrasonic testing, as required by ASME Code Section III) of the piping 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 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) ensurethatthe piping isconstructed in accordance with the design specification(s) and the ASME Code Section III and that the satisfactory completion of the non-destructive examinations of piping pressure boundary welds for the pipe lines identified inTable 2.7.1-2 meet ASME Code Section III requirements and are documented inthe Non-destructive Examination Report(s) within the supportingdata packages.
4.a and 4.b) A reoort exists and concludes that the results of the pressure test of the components and pioino identified in Tables 2.7.1-1 and 2.7.1-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.
Apressure test is performed by the vendor to demonstrate that the components identified in Table 2.7.1-1 (Attachment A) as ASME Code Section III retain their pressure boundary integrity attheir 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 2.7.1-1 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) (Reference 1).
The pressure testing results of the component's pressure boundary are documented in the Pressure (i.e. hydrostatic) Testing Report(s) within the supporting component's data package, which support completion of the respective Code Stamping and Code Data Reporl(s).
The completion of stamping the individual components and 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 pressure testing of each component identified in Table 2.7.1-1 as ASME Code Section III are documented in the Pressure(i.e. hydrostatic) Testing Report(s) within the supporting data packagesand meetsASME CodeSection III requirements.
U.S. Nuclear Regulatory Commission ND-18-0348 Enclosure Page 5 of 8 This ITAAC also verifies that the piping identified in Table 2.7.1-2 (Attachment B)fully meets all applicable ASME Code,Section III requirements and retains its pressure boundary integrity at its design pressure.
A pressure test is performed in accordance with procedure XYZ (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 2.7.1-2 retains its pressure boundary integrity at its design pressure.
A pressure test verifies that there are no leaks at welds or piping, and that the pressure boundary integrityis retained at its design pressure. The pressure testing results of the pipe lines are documented inthe Pressure Testing Report(s). The Pressure Testing Report(s) supports completion of the ASME Section III N-5Code Data Report(s) for the applicable piping system (i.e., VBS) (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 pressure testing of the components and piping identified in Table2.7.1-1 and Table2.7.1-2 respectively conform with the requirements of the Code (1998 Edition, 2000 Addenda),Section III.
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 2.7.1-1 and 2.7.1-2 as ASME Code Section III; Areport exists and concludes thatthe ASME Code Section III requirements are metfor nondestructive examination of pressure boundary welds; and Areport exists and concludes thatthe results ofthe pressuretest of the components and piping identified in Tables 2.7.1-1 and 2.7.1-2 as ASME CodeSection III conform with the requirements of the ASME Code Section III.
Reference 1 is availablefor NRC inspectionas part of the Unit 3 and Unit 4 ITAAC 2.7.01.02a Completion Packages (References4 and 5, respectively).
List of ITAAC Findings In accordance with plant proceduresfor ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review ofall ITAAC findings and associatedcorrective actions.
This review, which included nowconsolidated ITAAC Indexes 679, 680, 681, 682 and 683, found no relevant ITAAC findings associated withthis ITAAC:
References favailabie for NRC inspection) 1.
VBS ASME N-5 Code Data Report(s)
- 2. APP-GW-GAP-139, "Westinghouse/WECTEC ASME N-5 Interface Procedure"
U.S. Nuclear Regulatory Commission ND-18-0348 Enclosure Page 6 of 8
- 3. VEGP3&4Updated Final Safety Analysis Report, Subsection 5.2.1, Compliancewith Codes and Code Cases
- 4. Completion Package for Unit 3 ITAAC 2.7.01.02a [COL Index Number678]
- 5. Completion Package for Unit 4 ITAAC 2.7.01.02a [COL Index Number 678]
- 6. NEI 08-01, "Industry Guideline forthe ITAAC ClosureProcess Under 10 CFR Part 52"
U.S. Nuclear Regulatory Commission ND-18-0348 Enclosure Page 7 of 8 Attachment A SYSTEM: Nuclear Island Nonradioactive Ventilation System (VBS)
Equipment Name
- Tag No.
- ASME Code Section Hi*
N-5 Report MCR Supply Air Isolation Valve VBS-PL-V186 Yes VBS N-5 Code Data Report MCR Supply Air Isolation Valve VBS-PL-V187 Yes VBS N-5 Code Data Report MCR Return Air Isolation Valve VBS-PL-V188 Yes VBS N-5 Code Data Report MCR Return Air Isolation Valve VBS-PL-V189 Yes VBS N-5 Code Data Report MCR Exhaust Air Isolation Valve VBS-PL-V190 Yes VBS N-5 Code Data Report MCR Exhaust Air Isolation Valve VBS-PL-V191 Yes VBS N-5 Code Data Report PWS MCR Isolation Valve PWS-PL-V418 Yes VBS N-5 Code Data Report PWS MCR Isolation Valve PWS-PL-V420 Yes VBS N-5 Code Data Report PWS MCR Vacuum Relief PWS-PL-V498 Yes VBS N-5 Code Data Report MCR SDS (Vent)
Isolation Valve SDS-PL-V001 Yes VBS N-5 Code Data Report MCR SDS (Vent)
Isolation Valve SDS-PL-V002 Yes VBS N-5 Code Data Report MCR WWS Isolation Valve WWS-PL-V506 Yes VBS N-5 Code Data Report "Excerpts from COL Appendix C Table 2.7.1-1
U.S. Nuclear Regulatory Commission ND-18-0348 Enclosure Page 8 of 8 Attachment B SYSTEM: Nuclear Island Nonradioactive Ventilation System (VBS)
Line Name*
Line Number*
ASME Code Section III*
N-5 Report Main Control Room Supply VBS-L311 Yes VBS N-5 Code Data Report Main Control Room Exhaust VBS-L312 Yes VBS N-5 Code Data Report Main Control Room Toilet Exhaust VBS-L313 Yes VBS N-5 Code Data Report Main Control Room Sanitary Vent Line SDS-PL-L016 Yes VBS N-5 Code Data Report Main Control Room Sanitary Drain Line SDS-PL-L179 Yes VBS N-5 Code Data Report Main Control Room Sanitary Drain Line SDS-PL-L182 Yes VBS N-5 Code Data Report Main Control Room Water Line PWS-PL-L319'^
Yes VBS N-5 Code Data Report Main Control Room Water Line PWS-PL-L320'^
Yes VBS N-5 Code Data Report Main Control Room Waste Water Line WWS-PL-L808 Yes VBS N-5 Code Data Report Main Control Room Water Line WWS-PL-L851 Yes VBS N-5 Code Data Report
- Excerpts from COL Appendix C, Table 2.7.1-2
+ For girth fillet welds between piping andsocket welded fittings, valves and flanges, refer to VEGP UFSAR Section 5.2.1.1 (Reference 3).