ND-18-0179, Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.01.02a (Index Number 91)
| ML18054A121 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/20/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ITAAC 2.2.01.02a, ND-18-0179 | |
| Download: ML18054A121 (15) | |
Text
k Southern Nuclear FEB 2 0 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 Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 cell myox@southernco.com ND-18-0179 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 2.2.01.02a [Index Number 91 ]
Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of February 12, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item2.2.01.02a
[Index Number91] 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 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 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 Direbtor Vogtle 3 &4
U.S. Nuclear Regulatory Commission ND-18-0179 Page 2 of 4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.02a [Index Number 91]
MJY/KJD/amw
U.S. Nuclear Regulatory Commission ND-18-0179 Page 3 of 4 To:
Southern Nuclear Operating Company/ Georgia Power Company D. A. Bost (w/o enclosures)
M. D. Rauckhorst (w/o enclosures)
M. D. Meier D. H. Jones (w/o enclosures)
D. L. McKinney M. J. Vox D. L. Fulton J. D. Williams F. H. Willis M
M M
M M
M M
M M
Ms. A. L. Pugh M
M M
A. 8. Parton W. A. Sparkman
- 0. E. Morrow Ms. K. M. Stacy
. M. K. Washington
. J. P. Redd M
M Ms. A. 0. 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 Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
U.S. Nuclear Regulatory Commission ND-18-0179 Page 4 of 4 Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Orlani (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. Deangells 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-18-0179 Enclosure Page 1 of 11 Southern Nuclear Operating Company ND-18-0179 Enclosure Vogtle Electric Generating Plant (VEGP) Unit3 and Unit4 Completion Plan for Uncompleted ITAAC 2.2.01.02a[Index Number 91]
U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 2 of 11 ITAAC Statement Design Commitment:
2.a) The components identified inTable 2.2.1-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
2.b) The piping identifiedin Table 2.2.1-2 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 inTable 2.2.1-1 as ASME Code Section III meet ASME Code Section III requirements.
3.b) Pressure boundary welds in piping identified in Table 2.2.1-2 as ASME Code Section III meet ASME Code Section III requirements.
4.a) The components identified in Table 2.2.1-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
4.b) The piping identified in Table 2.2.1-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
Inspections. Tests. Analyses:
Inspection will be conducted of the as-built components and pipingas documented inthe ASME design reports.
Inspection of the as-built pressure boundary welds will be performed in accordance with the ASME Code Section III.
i) A hydrostatic or pressure test will be performed on the components required by the ASME Code Section III to be tested.
A hydrostatic or pressure test will be performed on the piping required by the ASME Code Section III to be pressure tested.
Acceptance Criteria:
The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.2.1-1 and 2.2.1-2 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.
i) A report exists and concludes that the results ofthe pressure test of the components identified in Tables 2.2.1-1 as ASME Code Section III conform with the requirements of the ASME Code Section III.
U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 3 of 11 Areport exists and concludes thatthe results ofthe pressuretest ofthe piping identified in Table 2.2.1-2 as ASME Code Section III conform with the requirements of the ASMECode Section III.
ITAAC Completion Description This ITAAC requires inspections, tests, and analyses be performed and documentedto ensure the Containment System (CMS) components and piping listed in the Combined License (COL)
Appendix C, Table 2.2.1-1 (Attachment A) andTable 2.2.1-2 (Attachment B) thatare identified as American Society ofMechanical Engineers (ASME) Code Section III are designedand constructed in accordance with applicable requirements.
2.a) and 2.b) The ASME Code Section III design reoorts exist for the as-built components and oiDino identified in Tables 2.2.1-1 and 2.2.1-2 as ASME Code Section III.
Each component listed in Table 2.2.1-1 as ASME CodeSection III isfabricated in accordance with the VEGP Updated Final SafetyAnalysis Report (UFSAR) and the ASME Code Section III requirements. TheASME 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 Report for each component isdocumented in the component's completed ASME Section III Code Data Report. The individual component ASME Section III Code Data Reports are documented onthe ASME Section III N-5 Code Data Report(s) for the applicable piping system (Reference 1).
The as-built piping listed inTable2.2.1-2 including the componentslisted in Table 2.2.1-1 as ASME Code Section III, are subjectedto a reconciliation process (Reference 2), which verifies thatthe as-built piping are analyzed forapplicable loads(e.g. stress reports) and forcompliance with all designspecification and Code provisions. Design reconciliation ofthe as-built systems, including installed components, validates thatconstruction completion, including field changes andanynonconforming condition dispositions, isconsistent with and bounded by theapproved design. All applicable fabrication, installation andtesting records, as well as, thosefor the related Quality 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 of the certified Design Reports for all the components listed in Table 2.2.1-1 (Attachment A) and piping listed in Table 2.2.1-2 (Attachment B) as ASME CodeSection III, exist and conclude thatthese 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 (Reference3).The N-5 Code Data Reports for the piping system(s) containing the components listed in Table 2.2.1-1 and Table2.2.1-2 are identified in Attachments A and B, respectively.
3.a1 and 3.b1 A reoort exists and concludes that the ASME Code Section III recuirements are met for non-destructive examination of oressure boundarv welds.
Inspections are performed in accordancewith ASME CodeSection III (1998 Edition, 2000 Addenda) to demonstratethat as-built pressure boundary welds in components identified in
U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 4 of 11 Table 2.2.1-1 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 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.
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 in Table 2.2.1-1 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 boundarywelds in piping identified inTable 2.2.1-2 (Attachment B) as ASME Code Section III meet ASME Code Section III requirements (i.e., no unacceptable indications). This portion of the ITAAC is complete when the piping identified inTable 2.2.1-2, whichis encompassed within the respective piping system Code SymbolN-Stampand the corresponding piping system Code N-5 Data Report Form(s) (Reference 1), is complete. The non-destructive examinations (including visual inspection, liquid penetrant, magnetic particle, radiographic, and ultrasonictesting, as required by ASME Code Section III) ofthe piping pressure boundarywelds are documented in the Non-destructive Examination Report(s) withinthe piping system's supporting data package,which supportcompletion ofthe respective CodeStamping and Code N-5 Data Report(s). The completion ofstampingthe respectivepiping system along with the corresponding ASME Code N-5 Data Report Form(s) (certified bythe Authorized Nuclear Inspector) ensure thatthe piping isconstructed in accordance with the designspecification(s) and the ASME Code Section III and that the satisfactory completion of the non-destructive examinationsof piping pressure boundaryweldsforthe pipe lines identified inTable 2.2.1-2 meet ASME Code Section III requirements and are documented inthe Non-destructive Examination Report(s) withinthe supporting data packages.
4.a.n and 4.b1 A report exists and concludes that the results of the pressure test of the comoonents and oiDina identified in Tables 2.2.1-1 and 2.2.1-2 as ASME Code Section III conform with the reouirements of the ASME Code Section III.
A hydrostatic/pressure test is performedbythe vendor to demonstrate that the components identified inTable 2.2.1-1 (Attachment A) as ASME Code Section III retain their pressure boundary integrity at theirdesign pressure. The completion ofthe N-5 Data Reports isgoverned by Reference 2.
Thisportion ofthe ITAAC is complete once each component identified inTable2.2.1 -1 has their individual Code Symbol N-Stamp and corresponding Code Data Report (Reference1) completed, and the componentsare installed into the respectiveCode Symbol N-Stamped piping system and documented on the corresponding N-5 Code Data Report(s) (Reference 1). The hydrostatic/pressure testing results ofthe component's pressure boundary are documented in the
U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 5 of 11 Hydrostatic/Pressure Testing Report(s) within the supporting component's data package, which supportcompletion ofthe respective Code Stamping and Code Data Report(s).
The completion ofstampingthe individual componentsand the respectivepiping system along with the corresponding ASME Code DataReports (certified bythe Authorized Nuclear Inspector) ensures that the componentsare constructed inaccordance with the Design Specifications and the ASMECode Section III and that the satisfactory completion of the hydrostatic/pressure testing ofeach component identified in Table 2.2.1-1 as ASME CodeSection III are documented in the Hydrostatic/Pressure Testing Report(s) within the supporting data packages and meets ASME Code Section III requirements.
This ITAAC also verifies that the piping identified in Table 2.2.1-2 (Attachment B) fully meets all applicable ASME CodeSection III requirements and retains itspressure boundary integrity at its design pressure.
Ahydrostatic/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 2.2.1-2 retains its pressure boundary integrityat its design pressure.
Ahydrostatic/pressure test verifies thatthereare no leaksat welds or piping, and thatthe pressure boundary integrity is retained at its design pressure. Thehydrostatic/pressure testing results ofthe pipelines are documented in the Hydrostatic/Pressure Testing Report(s). The Hydrostatic/Pressure Testing Report(s) supports completion of theASME Section III N-5 Code Data Report(s) for the applicable piping system (i.e., CNS) (Reference1).
Theapplicable ASME Section III N-5 Code Data Report(s) (Reference 1) identified in Attachments A and Bdocuments that the results of the hydrostatic/pressure testing ofthe components and piping identified in Table 2.2.1-1 andTable 2.2.1-2 respectively conform with the requirements ofthe ASME Code (1998 Edition, 2000Addenda),Section III.
Reference1 provides the evidencethat the ITAAC AcceptanceCriteria requirements are met;.
The ASME Code Section III design reportsexistfor the as-built componentsand piping identified in Tables 2.2.1-1 and 2.2.1-2 as ASME Code Section III; Areport exists andconcludes thattheASME Code Section III requirements are met for non destructive examination of pressure boundary welds; Areport exists and concludesthat the results ofthe pressure test ofthe components identified in Table 2.2.1-1 as ASME Code Section III conform with the requirements of the ASME Code Section III, and Areport exists and concludes that the results of thepressure test of the piping identified Table 2.2.1-2 as ASME Code Section III conform withthe requirements of the ASME Code Section III.
Reference 1 is availablefor NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.01.02a Completion Packages (References 4 and 5, respectively).
U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 6 of 11 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 92, 93, 94, 95 and 97 found no relevant ITAAC findings associated with this ITAAC:
References favailable for NRG inspection) 1.
ASME N-5 Code Data Report(s) 2.
APP-GW-GAP-139, "WestinghouseA/VECTEC ASME N-5 Interface Procedure" 3.
VEGP 3&4 Updated Final Safety Analysis Report, Subsection 5.2.1, Compliance with Codes and Code Cases 4.
Completion Package for Unit3 ITAAC 2.2.01.02a [COL Index Number 91]
5.
Completion Package for Unit4 ITAAC 2.2.01.02a [COL Index Number 91]
6.
NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"
U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 7 of 11 Attachment A SYSTEM: Containment System (CNS)
Equipment Name
- Tag No.
- ASME Code Section III
- N-5 Report Service Air Supply Outside Containment Isolation Valve Service Air Supply Inside Containment Isolation Check Valve CAS-PL-V204 CAS-PL-V205 Yes Yes N-5 Code Data Report Instrument AirSupply Outside Containment Isolation Valve Instrument AirSupply Inside Containment Isolation Check Valve CAS-PL-V014 CAS-PL-V015 Yes Yes N-5 Code Data Report Component Cooling Water System (CCS) Containment Isolation Motor-operated Valve (MOV) - Inlet Line Outside Reactor Containment (ORC)
CCS Containment Isolation Check Valve - Inlet Line Inside Reactor Containment (IRC)
CCS-PL-V200 CCS-PL-V201 Yes Yes N-5 Code Data Report CCS Containment Isolation MOV - Outlet Line IRC CCS Containment Isolation MOV - Outlet Line ORC CCS Containment Isolation Relief Valve - Outlet Line IRC CCS-PL-V207 CCS-PL-V208 CCS-PL-V220 Yes Yes Yes N-5 Code Data Report Demlnerallzed Water Supply Containment Isolation Valve ORC Demlnerallzed Water Supply Containment Isolation Check Valve IRC DWS-PL-V244 DWS-PL-V245 Yes Yes N-5 Code Data Report Fuel Transfer Tube FHS-FT-01 Yes N-5 Code Data Report Fuel Transfer Tube Isolation Valve FHS-PL-V001 Yes N-5 Code Data Report Fire Water Containment Supply Isolation Valve - Outside Fire Water Containment Isolation Supply Check Valve -
Inside FPS-PL-V050 FPS-PL-V052 Yes Yes N-5 Code Data Report Spent Fuel Pool Cooling System (SFS) Discharge Line Containment Isolation Check Valve - IRC SFS Discharge Line Containment Isolation MOV-ORC SFS-PL-V037 SFS-PL-V038 Yes Yes N-5 Code Data Report SFS Suction Line Containment Isolation MOV - IRC SFS Suction Line Containment Isolation MOV - ORC SFS Suction Line Containment Isolation Relief Valve - IRC SFS-PL-V034 SFS-PL-V035 SFS-PL-V067 Yes Yes Yes N-5 Code Data Report
U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 8 of 11 Attachment A SYSTEM; Containment System (CNS)
Equipment Name
- Tag No.
- ASME Code Section ill
- N-5 Report Containment Purge Inlet Containment Isolation Valve - ORC Containment Purge Inlet Containment Isolation Valve - IRC VFS-PL-V003 VFS-PL-V004 Yes Yes N-5 Code Data Report Integrated Leak Rate Testing Vent Discharge Containment Isolation Valve - ORC Containment Purge Discharge Containment Isolation Valve -
IRC Containment Purge Discharge Containment Isolation Valve -
ORC VFS-PL-V008 VFS-PL-V009 VFS-PL-V010 Yes Yes Yes N-5 Code Data Report Vacuum Relief Containment Isolation A MOV - ORC Vacuum Relief Containment Isolation B MOV - ORC Vacuum Relief Containment Isolation Check Valve A - IRC Vacuum Relief Containment Isolation Check Valve B - IRC VFS-PL-V800A VFS-PL-V800B VFS-PL-V803A VFS-PL-V803B Yes Yes Yes Yes N-5 Code Data Report Fan Coolers Return Containment Isolation Valve - IRC Fan Coolers Return Containment Isolation Valve - ORC Fan Coolers Return Containment Isolation Relief Valve - IRC VWS-PL-V082 VWS-PL-V086 VWS-PL-V080 Yes Yes Yes N-5 Code Data Report Fan Coolers Supply Containment Isolation Valve - ORC Fan Coolers Supply Containment Isolation Check Valve -
IRC VWS-PL-V058 VWS-PL-V062 Yes Yes N-5 Code Data Report Reactor Coolant Drain Tank (RCDT) Gas Outlet Containment Isolation Valve - IRC RCDT Gas Outlet Containment Isolation Valve - ORC WLS-PL-V067 WLS-PL-V068 Yes Yes N-5 Code Data Report Sump Discharge Containment Isolation Valve - IRC Sump Discharge Containment Isolation Valve - ORC Sump Discharge Containment Isolation Relief Valve - IRC WLS-PL-V055 WLS-PL-V057 WLS-PL-V058 Yes Yes Yes N-5 Code Data Report Spare Penetration CNS-PY-C01 Yes N-5 Code Data Report Spare Penetration CNS-PY-C02 Yes N-5 Code Data Report Spare Penetration CNS-PY-C03 Yes N-5 Code Data Report
U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 9 of 11 Attachment A SYSTEM: Containment System (CNS)
Equipment Name
- Tag No.
- ASME Code Section ill
- N-5 Report Main Equipment Hatch CNS-MY-Y01 Yes N-5 Code Data Report Maintenance Hatch CNS-MY-Y02 Yes N-5 Code Data Report Personnel Hatch CNS-MY-Y03 Yes N-5 Code Data Report Personnel Hatch CNS-MY-Y04 Yes N-5 Code Data Report Containment Vessel CNS-MV-01 Yes N-5 Code Data Report Electrical Penetration P03 DAS-EY-P03Z Yes N-5 Code Data Report Electrical Penetration P01 ECS-EY-P01X Yes N-5 Code Data Report Electrical Penetration P02 ECS-EY-P02X Yes N-5 Code Data Report Electrical Penetration P06 ECS-EY-P06Y Yes N-5 Code Data Report Electrical Penetration P07 ECS-EY-P07X Yes N-5 Code Data Report Electrical Penetration P09 ECS-EY-P09W Yes N-5 Code Data Report Electrical Penetration P10 ECS-EY-P10W Yes N-5 Code Data Report Electrical Penetration P11 IDSA-EY-P11Z Yes N-5 Code Data Report Electrical Penetration P12 IDSA-EY-P12Y Yes N-5 Code Data Report Electrical Penetration P13 IDSA-EY-P13Y Yes N-5 Code Data Report Electrical Penetration P14 IDSD-EY-P14Z Yes N-5 Code Data Report Electrical Penetration P15 IDSD-EY-P15Y Yes N-5 Code Data Report Electrical Penetration P16 IDSD-EY-P16Y Yes N-5 Code Data Report Electrical Penetration P17 ECS-EY-P17X Yes N-5 Code Data Report Electrical Penetration P18 ECS-EY-P18X Yes N-5 Code Data Report
U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 10 of 11 Attachment A SYSTEM; Containment System (CMS)
Equipment Name
- Tag No.
- ASME Code Section III
- N-5 Report Electrical Penetration PI 9 ECS-EY-P19Z Yes N-5 Code Data Report Electrical Penetration P20 ECS-EY-P20Z Yes N-5 Code Data Report Electrical Penetration P21 EDS-EY-P21Z Yes N-5 Code Data Report Electrical Penetration P22 ECS-EY-P22X Yes N-5 Code Data Report Electrical Penetration P23 ECS-EY-P23X Yes N-5 Code Data Report Electrical Penetration P24 ECS-EY-P24 Yes N-5 Code Data Report Electrical Penetration P25 ECS-EY-P25W Yes N-5 Code Data Report Electrical Penetration P26 ECS-EY-P26W Yes N-5 Code Data Report Electrical Penetration P27 IDSC-EY-P27Z Yes N-5 Code Data Report Electrical Penetration P28 IDSC-EY-P28Y Yes N-5 Code Data Report Electrical Penetration P29 IDSC-EY-P29Y Yes N-5 Code Data Report Electrical Penetration P30 IDSB-EY-P30Z Yes N-5 Code Data Report Electrical Penetration P31 IDSB-EY-P31Y Yes N-5 Code Data Report Electrical Penetration P32 IDSB-EY-P32Y Yes N-5 Code Data Report Instrument Penetration P46 PCS-PY-C01 Yes N-5 Code Data Report Instrument Penetration P47 PCS-PY-C02 Yes N-5 Code Data Report Instrument Penetration P48 PCS-PY-C03 Yes N-5 Code Data Report Instrument Penetration P49 PCS-PY-C04 Yes N-5 Code Data Report
'Excerpt from COL Appendix C Table 2.2.1-1
U.S. Nuclear Regulatory Commission ND-18-0179 Enclosure Page 11 of 11 Attachment B SYSTEM: Containment System (CNS)
Line Name*
Line Number*
ASME Code Section III*
N-5 Report Instrument Air In CAS-PL-L015 +
Yes N-5 Code Data Report Service Air In CAS-PL-L204 +
Yes N-5 Code Data Report Component Cooling Water Supply to Containment CCS-PL-L201 Yes N-5 Code Data Report Component Cooling Water Outlet from Containment CCS-PL-L207 Yes N-5 Code Data Report Demineralized Water In DWS-PL-L245 +, L230 Yes N-5 Code Data Report Fire Protection Supply to Containment FPS-PL-L107 Yes N-5 Code Data Report Containment Atmosphere Return Line PSS-PL-L038 +
Yes N-5 Code Data Report Common Primary Sample Line A/B PSS-PL-T005A/B Yes N-5 Code Data Report Containment Atmosphere Sample Line PSS-PL-T031 Yes N-5 Code Data Report Spent Fuel Pool Cooling Discharge SFS-PL-L017 Yes N-5 Code Data Report Spent Fuel Pool Cooling Suction from Containment SFS-PL-L038 Yes N-5 Code Data Report Containment Purge Inlet to Containment VFS-PL-L104, LI 05, LI 06 Yes N-5 Code Data Report Containment Purge Discharge from Containment VFS-PL-L203, L204, L205, L800, L801A/B, L803, L804, L805A/B, L810A/B, L832 Yes N-5 Code Data Report Fan Cooler Supply Line to Containment VWS-PL-L032 Yes N-5 Code Data Report Fan Cooler Return Line from Containment VWS-PL-L055 Yes N-5 Code DataReport RCDT Gas Out WLS-PL-L022 Yes N-5 Code DataReport Waste Sump Out WLS-PL-L073 Yes N-5 Code DataReport
'Excerpt from COLAppendixC, Table 2.2.1-2
+These lines require that dynamic loads in its pipe stressanalysis satisfy the requirements of ASME Code Section III (1989 Edition, 1989 Addenda) for girth fillet welds between piping and socket welded fittings, valves and flanges per VEGP UFSAR Section 5.2.1.1 (Reference 3)