ML18081A220
| ML18081A220 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/22/2018 |
| From: | NRC |
| To: | NRC/NRO/DNRL/LB4 |
| References | |
| Download: ML18081A220 (18) | |
Text
1 Vogtle PEmails From:
Hoellman, Jordan Sent:
Thursday, March 22, 2018 10:42 AM To:
Vogtle PEmails
Subject:
Draft Uncompleted ITAAC Notification (UIN) for ITAAC Index No. 159 Attachments:
final ND-18-0315 ITAAC 159.pdf Please see the attached draft UIN for ITAAC Index No. 159 for discussion at the public meeting on March 22, 2018.
Hearing Identifier:
Vogtle_COL_Docs_Public Email Number:
239 Mail Envelope Properties (SN6PR09MB2608820F85AD05022A72205FD5A90)
Subject:
Draft Uncompleted ITAAC Notification (UIN) for ITAAC Index No. 159 Sent Date:
3/22/2018 10:42:08 AM Received Date:
3/22/2018 10:42:19 AM From:
Hoellman, Jordan Created By:
Jordan.Hoellman2@nrc.gov Recipients:
"Vogtle PEmails" <Vogtle.PEmails@nrc.gov>
Tracking Status: None Post Office:
SN6PR09MB2608.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 134 3/22/2018 10:42:19 AM final ND-18-0315 ITAAC 159.pdf 279998 Options Priority:
Standard Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date:
Recipients Received:
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 Docket Nos.: 52-025 52-026 ND-18-0315 10 CFR 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-days Prior to Initial Fuel Load Item 2.2.03.02a [Index Number 159]
Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of March 5, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.02a [Index Number 159]
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 Guideline for 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 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, Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.02a [Index Number 159]
MJY/KJD/amw
U.S. Nuclear Regulatory Commission ND-18-0315 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. F. H. Willis Ms. A. L. Pugh Mr. A. S. 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 Regulatory 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 Oglethorpe Power Corporation Mr. K. T. Haynes Mr. R. B. Brinkman Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson
U.S. Nuclear Regulatory Commission ND-18-0315 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinghouse 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. S. DiTommaso 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. S. Roetger, Georgia Public Service Commission Ms. S. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Balch Bingham
U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 1 of 13 Southern Nuclear Operating Company ND-18-0315 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.02a [Index Number 159]
U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 2 of 13 ITAAC Statement Design Commitment:
2.a) The components identified in Table 2.2.3-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
2.b) The piping identified in Table 2.2.3-2 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 2.2.3-1 as ASME Code Section III meet ASME Code Section III requirements.
3.b) Pressure boundary welds in piping identified in Table 2.2.3-2 as ASME Code Section III meet ASME Code Section III requirements.
4.a) The components identified in Table 2.2.3-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
4.b) The piping identified in Table 2.2.3-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
5.b) Each of the lines identified in Table 2.2.3-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability.
- 6. Each of the as-built lines identified in Table 2.2.3-2 as designed for LBB meets the LBB criteria, or an evaluation is performed of the protection from the dynamic effects of a rupture of the line.
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 be performed in accordance with the ASME Code Section III.
A hydrostatic test will be performed on the components and piping required by the ASME Code Section III to be hydrostatically tested.
Inspection will be performed verifying that the as-built piping meets the requirements for functional capability.
Inspection will be performed for the existence of an LBB evaluation report or an evaluation report on the protection from dynamic effects of a pipe break. Section 3.3, Nuclear Island Buildings, contains the design descriptions and inspections, tests, analyses, and acceptance criteria for protection from the dynamic effects of pipe rupture.
U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 3 of 13 Acceptance Criteria:
The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.2.3-1 and 2.2.3-2 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.
A report exists and concludes that the results of the hydrostatic test of the components and piping identified in Tables 2.2.3-1 and 2.2.3-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.
A report exists and concludes that each of the as-built lines identified in Table 2.2.3-2 for which functional capability is required meets the requirements for functional capability.
An LBB evaluation report exists and concludes that the LBB acceptance criteria are met by the as-built PXS piping and piping materials, or a pipe break evaluation report exists and concludes that protection from the dynamic effects of a line break is provided.
ITAAC Completion Description This ITAAC requires inspections, tests, and analyses be performed and documented to ensure the Passive Core Cooling System (PXS) components and piping listed in the Combined License (COL) Appendix C, Table 2.2.3-1 (Attachment A) and Table 2.2.3-2 (Attachment B) that are identified as American Society of Mechanical Engineers (ASME) Code Section III, Leak Before Break (LBB), or Functional Capability Required are designed and constructed in accordance with applicable requirements.
2.a and 2.b) The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.2.3-1 and 2.2.3-2 as ASME Code Section III.
Each component listed in Table 2.2.3-1 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 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 is documented in the components completed ASME Section 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) for the applicable piping system (Reference 1).
The as-built piping listed in Table 2.2.3-2 including the components listed in Table 2.2.3-1 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 for compliance with all design specification and Code provisions. Design reconciliation of the as-built systems, including installed components, validates that construction completion, including field changes and any nonconforming condition dispositions, is consistent with and bounded by the approved design. All applicable fabrication, installation and testing records, as well as, those for the related Quality Assurance (QA) 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/or its sub-tier references.
U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 4 of 13 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 2.2.3-1 (Attachment A) and piping listed in Table 2.2.3-2 (Attachment B) as ASME Code Section 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 Reports for the piping system(s) containing the components listed in the Table 2.2.3-1 and Table 2.2.3-2 are identified in Attachments A and B, respectively.
3.a and 3.b) A report exists and concludes that the ASME Code Section III requirements are met for non-destructive examination of pressure boundary welds.
Inspections are performed in accordance with ASME Code Section III (1998 Edition, 2000 Addenda) to demonstrate that as-built pressure boundary welds in components identified in Table 2.2.3-1 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 2.2.3-2 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 in Table 2.2.3-2 (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 in Table 2.2.3-2, which is encompassed within the respective piping system Code Symbol N-Stamp and 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 ultrasonic testing, as required by ASME Code Section III) of the piping pressure boundary welds are documented in the Non-destructive Examination Report(s) within the piping systems supporting data package, which support completion of the respective Code Stamping and Code 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) ensure that the piping is constructed 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 in Table 2.2.3-2 meet ASME Code Section III requirements and are documented in the Non-destructive Examination Report(s) within the supporting data packages.
U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 5 of 13 4.a and 4.b) A report exists and concludes that the results of the hydrostatic test of the components and piping identified in Tables 2.2.3-1 and 2.2.3-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.
A hydrostatic test is performed by the vendor to demonstrate that the components identified in Table 2.2.3-1 (Attachment A) as ASME Code Section III retain their pressure boundary integrity at their 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 2.2.3-1 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 hydrostatic testing results of the components pressure boundary are documented in the Hydrostatic Testing Report(s) within the supporting components data package, which support completion of the respective Code Stamping and Code Data Report(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 hydrostatic pressure testing of each component identified in Table 2.2.3-1 as ASME Code Section III are documented in the Hydrostatic 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 2.2.3-2 (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 (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 2.2.3-2 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 ASME Section III N-5 Code Data Report(s) for the applicable piping system (i.e., PXS) (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 in Table 2.2.3-1 and Table 2.2.3-2 respectively conform with the requirements of the Code (1998 Edition, 2000 Addenda),Section III.
5.b) A report exists and concludes that each of the as-built lines identified in Table 2.2.3-2 for which functional capability is required meets the requirements for functional capability.
An inspection is performed of the ASME Section III as-built piping design report XXX to verify that the report demonstrates that each of the PXS piping lines identified in ITAAC Table
U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 6 of 13 2.2.3-2 that requires functional capability is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability. Functional capability, in this context, refers to the capability of the piping to withstand the effects of earthquakes, without a loss of safety function (to convey fluids from one location to another). Specific functional capability requirements are defined in the VEGP UFSAR Table 3.9-11 (Reference 3).
Piping functional capability is not a specific ASME Code requirement but it is a requirement in the VEGP UFSAR (Reference 3). As such, information demonstrating that UFSAR functional capability requirements are met is included in the ASME Section III As-Built Design Reports for safety class piping prepared in accordance with ASME Section III NCA-3550 under the ASME Boiler & Pressure Vessel Code (1998 Edition, 2000 Addenda)Section III requirements. The as-built piping systems are subjected to a reconciliation process (Reference 2), which verifies that the as-built piping systems are analyzed for functional capability and for compliance with the design specification and ASME Code provisions. Design reconciliation of the as-built systems validates that construction completion, including field changes and any nonconforming condition dispositions, is consistent with and bounded by the approved design. As required by ASME Code, the As-Built Design Report includes the results of physical inspection of the piping and reconciliation to the design pipe stress report.
Inspections of the ASME Code Section III As-Built Piping Design Reports (Reference 4) for the PXS piping lines identified in Table 2.2.3-2 are complete and conclude that each of the as-built PXS piping lines for which functional capability is required meets the requirements for functional capability. The ASME Section III As-Built Piping Design Reports for each of the as-built PXS piping lines in Table 2.2.3-2 are identified in Attachment B.
- 6. An LBB evaluation report exists and concludes that the LBB acceptance criteria are met by the as-built PXS piping and piping materials, or a pipe break evaluation report exists and concludes that protection from the dynamic effects of a line break is provided.
Inspections are performed for the as-built lines identified in Table 2.2.3-2 (Attachment B) to verify that each of the as-built lines designed for LBB meets the LBB criteria, or an evaluation is performed of the protection from the dynamic effects of a rupture of the line. VEGP COL Appendix C, Section 3.3, Nuclear Island Buildings, contains the design descriptions and inspections, tests, analyses, and acceptance criteria for protection from the dynamic effects of pipe rupture.
LBB evaluations are performed as described in UFSAR subsection 3.6.3 to confirm that the as-built PXS piping (and corresponding piping materials) identified in Attachment A meet the LBB acceptance criteria described in the UFSAR, Appendix 3B, Leak-Before-Break Evaluation of the AP1000 Piping (Reference 3). In cases where an as-built PXS piping line in Attachment B cannot meet the LBB acceptance criteria, a pipe break evaluation is performed which concludes that protection from the dynamic effects of a line break is provided. The pipe break evaluation criteria is discussed in UFSAR, Section 3.6.4.1, Pipe Break Hazards Analysis (Reference 3) and is documented as a pipe rupture hazards analysis report (pipe break evaluation report).
Inspections are performed to verify that LBB as-built piping evaluation reports for the PXS piping (and corresponding piping materials) identified in Attachment B conclude that the as-built piping analysis is bounded by the applicable bounding analysis curves provided in Appendix 3B of the
U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 7 of 13 UFSAR (Reference 3). The results are documented in either the applicable ASME Section III as-built piping design report(s) or in separate LBB evaluation report(s). For cases where an as-built PXS piping line in Attachment B cannot meet the LBB acceptance criteria, inspections are performed to verify that a pipe rupture hazards analysis evaluation report (pipe break evaluation report) exists which concludes that protection from the dynamic effects of a line break is provided.
The applicable ASME Section III as-built piping design report(s), LBB evaluation report(s), or pipe rupture hazards analysis report(s) (pipe break evaluation report(s)) exist and are identified in Attachment B.
References 1 and 4 provide the evidence that the ITAAC Acceptance Criteria requirements are met:
x The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.2.3-1 and 2.2.3-2 as ASME Code Section III; x
A report exists and concludes that the ASME Code Section III requirements are met for non-destructive examination of pressure boundary welds; x
A report exists and concludes that the results of the hydrostatic test of the components and piping identified in Tables 2.2.3-1 and 2.2.3-2 as ASME Code Section III conform with the requirements of the ASME Code Section III; x
A report exists and concludes that each of the as-built lines identified in Table 2.2.3-2 for which functional capability is required meets the requirements for functional capability; and x
An LBB evaluation report exists and concludes that the LBB acceptance criteria are met by the as-built PXS piping and piping materials, or a pipe break evaluation report exists and concludes that protection from the dynamic effects of a line break is provided.
References 1 and 4 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.03.02a 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 160, 161, 162, 163, 164, 168, and 169, found the following relevant ITAAC findings associated with this ITAAC:
- 1) Noncited Violation (NCV) 05200025/2017004-01/05200026/2017004-01 (Open)
- 2) Notice of Nonconformance (NON) 99901431/2013-201-01 (Closed)
- 3) NON 99901377/2012-201-02 (Closed)
- 4) NON 99901377/2012-201-03 (Closed)
U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 8 of 13
- 5) NON 99900404/2011-201-02 (Open)
Before submission of the ITAAC Closure Notification (ICN), corrective actions will be completed for relevant findings identified prior to ICN submission.
References (available for NRC inspection)
- 1. PXS ASME N-5 Code Data Report(s)
- 2. APP-GW-GAP-139, Westinghouse/WECTEC ASME N-5 Interface Procedure
- a. Subsection 5.2.1 - Compliance with Codes and Code Cases,
- b. Table 3.9 Piping Functional Capability - ASME Class 1, 2, and 3,
- c. Subsection 3.6.3 - Leak before Break Evaluation Procedures
- d. Subsection 3.6.4.1-Pipe Break Hazards Analysis
- e. Appendix 3B - Leak-Before-Break Evaluation of the AP1000 Piping
- 4. PXS ASME III As Built Design Report(s)
- 5. Completion Package for Unit 3 ITAAC 2.2.03.02a [COL Index Number 159]
- 6. Completion Package for Unit 4 ITAAC 2.2.03.02a [COL Index Number 159]
U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 9 of 13 Attachment A SYSTEM: Passive Core Cooling System (PXS)
Equipment Name
- Tag No.
- ASME Code Section III*
ASME III as-built Design Report N-5 Report Passive Residual Heat Removal Heat Exchanger (PRHR HX)
PXS-ME-01 Yes XXX N-5 Code Data Report Accumulator Tank A PXS-MT-01A Yes XXX N-5 Code Data Report Accumulator Tank B PXS-MT-01B Yes XXX N-5 Code Data Report Core Makeup Tank (CMT) A PXS-MT-02A Yes XXX N-5 Code Data Report CMT B PXS-MT-02B Yes XXX N-5 Code Data Report CMT A Inlet Isolation Motor-operated Valve PXS-PL-V002A Yes XXX N-5 Code Data Report CMT B Inlet Isolation Motor-operated Valve PXS-PL-V002B Yes XXX N-5 Code Data Report CMT A Discharge Isolation Valve PXS-PL-V014A Yes XXX N-5 Code Data Report CMT B Discharge Isolation Valve PXS-PL-V014B Yes XXX N-5 Code Data Report CMT A Discharge Isolation Valve PXS-PL-V015A Yes XXX N-5 Code Data Report CMT B Discharge Isolation Valve PXS-PL-V015B Yes XXX N-5 Code Data Report CMT A Discharge Check Valve PXS-PL-V016A Yes XXX N-5 Code Data Report CMT B Discharge Check Valve PXS-PL-V016B Yes XXX N-5 Code Data Report CMT A Discharge Check Valve PXS-PL-V017A Yes XXX N-5 Code Data Report CMT B Discharge Check Valve PXS-PL-V017B Yes XXX N-5 Code Data Report Accumulator A Pressure Relief Valve PXS-PL-V022A Yes XXX N-5 Code Data Report Accumulator B Pressure Relief Valve PXS-PL-V022B Yes XXX N-5 Code Data Report Accumulator A Discharge Isolation Valve PXS-PL-V027A Yes XXX N-5 Code Data Report Accumulator B Discharge Isolation Valve PXS-PL-V027B Yes XXX N-5 Code Data Report Accumulator A Discharge Check Valve PXS-PL-V028A Yes XXX N-5 Code Data Report Accumulator B Discharge Check Valve PXS-PL-V028B Yes XXX N-5 Code Data Report Accumulator A Discharge Check Valve PXS-PL-V029A Yes XXX N-5 Code Data Report Accumulator B Discharge Check Valve PXS-PL-V029B Yes XXX N-5 Code Data Report Nitrogen Supply Containment Isolation Valve PXS-PL-V042 Yes XXX N-5 Code Data Report
U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 10 of 13 Attachment A SYSTEM: Passive Core Cooling System (PXS)
Equipment Name
- Tag No.
- ASME Code Section III*
ASME III as-built Design Report N-5 Report Nitrogen Supply Containment Isolation Check Valve PXS-PL-V043 Yes XXX N-5 Code Data Report PRHR HX Inlet Isolation Motor-operated Valve PXS-PL-V101 Yes XXX N-5 Code Data Report PRHR HX Control Valve PXS-PL-V108A Yes XXX N-5 Code Data Report PRHR HX Control Valve PXS-PL-V108B Yes XXX N-5 Code Data Report Containment Recirculation A Isolation Motor-operated Valve PXS-PL-V117A Yes XXX N-5 Code Data Report Containment Recirculation B Isolation Motor-operated Valve PXS-PL-V117B Yes XXX N-5 Code Data Report Containment Recirculation A Squib Valve PXS-PL-V118A Yes XXX N-5 Code Data Report Containment Recirculation B Squib Valve PXS-PL-V118B Yes XXX N-5 Code Data Report Containment Recirculation A Check Valve PXS-PL-V119A Yes XXX N-5 Code Data Report Containment Recirculation B Check Valve PXS-PL-V119B Yes XXX N-5 Code Data Report Containment Recirculation A Squib Valve PXS-PL-V120A Yes XXX N-5 Code Data Report Containment Recirculation B Squib Valve PXS-PL-V120B Yes XXX N-5 Code Data Report IRWST Injection A Check Valve PXS-PL-V122A Yes XXX N-5 Code Data Report IRWST Injection B Check Valve PXS-PL-V122B Yes XXX N-5 Code Data Report IRWST Injection A Squib Valve PXS-PL-V123A Yes XXX N-5 Code Data Report IRWST Injection B Squib Valve PXS-PL-V123B Yes XXX N-5 Code Data Report IRWST Injection A Check Valve PXS-PL-V124A Yes XXX N-5 Code Data Report IRWST Injection B Check Valve PXS-PL-V124B Yes XXX N-5 Code Data Report IRWST Injection A Squib Valve PXS-PL-V125A Yes XXX N-5 Code Data Report IRWST Injection B Squib Valve PXS-PL-V125B Yes XXX N-5 Code Data Report IRWST Gutter Isolation Valve PXS-PL-V130A Yes xxx N-5 Code Data Report IRWST Gutter Isolation Valve PXS-PL-V130B Yes xxx N-5 Code Data Report RNS Suction Leak Test Valve PXS-PL-V208A Yes xxx N-5 Code Data Report
- Excerpts from COL Appendix C Table 2.2.3-1
U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 11 of 13 Attachment B SYSTEM: Passive Core Cooling System (PXS)
Line Name*
Line Number*
ASME Code Section III*
Leak Before Break*
Functional Capability Required*
ASME III As-Built Design Report LBB evaluation/
pipe break evaluation N-5 Report PRHR HX inlet line from hot leg and outlet line to steam generator channel head RCS-L134, PXS-L102, PXS-L103, PXS-L104A, PXS-L104B, PXS-L105, RCS-L113 Yes Yes Yes XXX YYY N-5 Code Data Report PXS-L107 Yes Yes No XXX YYY N-5 Code Data Report CMT A inlet line from cold leg C and outlet line to reactor vessel direct vessel injection (DVI) nozzle A RCS-L118A, PXS-L007A, PXS-L015A, PXS-L016A, PXS-L017A, PXS-L018A, PXS-L020A, PXS-L021A Yes Yes Yes XXX YYY N-5 Code Data Report PXS-L070A Yes Yes No XXX YYY N-5 Code Data Report CMT B inlet line from cold leg D and outlet line to reactor vessel DVI nozzle B RCS-L118B, PXS-L007B, PXS-L015B, PXS-L016B, PXS-L017B, PXS-L018B, PXS-L020B, PXS-L021B Yes Yes Yes XXX YYY N-5 Code Data Report PXS-L070B Yes Yes No XXX YYY N-5 Code Data Report RNS A discharge line to PXS from RNS check valve RNS-PL-V017A to DVI line A PXS-L019A Yes Yes Yes XXX YYY N-5 Code Data Report
U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 12 of 13 Attachment B SYSTEM: Passive Core Cooling System (PXS)
Line Name*
Line Number*
ASME Code Section III*
Leak Before Break*
Functional Capability Required*
ASME III As-Built Design Report LBB evaluation/
pipe break evaluation N-5 Report RNS B discharge line to PXS from RNS check valve RNS-PL-V017B to DVI line B PXS-L019B Yes Yes Yes XXX YYY N-5 Code Data Report Accumulator A discharge line to DVI line A PXS-L025A, PXS-L027A, PXS-L029A Yes Yes Yes XXX YYY N-5 Code Data Report Accumulator B discharge line to DVI line B PXS-L025B, PXS-L027B, PXS-L029B Yes Yes Yes XXX YYY N-5 Code Data Report IRWST injection line A to DVI line A PXS-L123A, PXS-L125A, PXS-L127A Yes Yes Yes XXX YYY N-5 Code Data Report PXS-L124A, PXS-L118A, PXS-L117A, PXS-L116A, PXS-L112A Yes No Yes XXX YYY N-5 Code Data Report PXS-L133A, PXS-L134A Yes Yes No XXX YYY N-5 Code Data Report IRWST injection line B to DVI line B PXS-L123B, PXS-L125B, PXS-L127B Yes Yes Yes XXX YYY N-5 Code Data Report PXS-L124B, PXS-L118B, PXS-L117B, PXS-L116B, PXS-L114, PXS-L112B, PXS-L120 Yes No Yes XXX N/A N-5 Code Data Report PXS-L133B, PXS-L134B Yes Yes No XXX YYY N-5 Code Data Report IRWST screen cross-connect line PXS-L180A, PXS-L180B Yes No Yes XXX N/A N-5 Code Data Report Containment recirculation line A PXS-L113A, PXS-L131A, PXS-L132A Yes No Yes XXX N/A N-5 Code Data Report
U.S. Nuclear Regulatory Commission ND-18-0315 Enclosure Page 13 of 13 Attachment B SYSTEM: Passive Core Cooling System (PXS)
Line Name*
Line Number*
ASME Code Section III*
Leak Before Break*
Functional Capability Required*
ASME III As-Built Design Report LBB evaluation/
pipe break evaluation N-5 Report Containment recirculation line B PXS-L100, PXS-L101, PXS-L106, PXS-L113B, PXS-L131B, PXS-L132B Yes No Yes XXX N/A N-5 Code Data Report IRWST gutter drain line PXS-L142A, PXS-L142B Yes No Yes XXX N/A N-5 Code Data Report PXS-L141A+,
PXS-L141B+
Yes No No XXX N/A N-5 Code Data Report Downspout drain lines from polar crane girder and internal stiffener to collection box A
PXS-L301A, PXS-L302A, PXS-L303A, PXS-L304A, PXS-L305A, PXS-L306A, PXS-L307A, PXS-L308A, PXS-L309A+,
PXS-L310A+
Yes No Yes XXX N/A N-5 Code Data Report Downspout drain lines from polar crane girder and internal stiffener to collection box B
PXS-L301B, PXS-L302B, PXS-L303B, PXS-L304B, PXS-L305B, PXS-L306B, PXS-L307B, PXS-L308B, PXS-L309B+,
PXS-L310B+
Yes No Yes XXX N/A N-5 Code Data Report
- Excerpts from COL Appendix C, Table 2.2.3-2
+ These lines PXS-L141A/B, L309A/B, and L310A/B require that dynamic loads in its pipe stress analysis 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)