ND-18-0552, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.06.02a (Index Number 355)
| ML18117A341 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/25/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ND-18-0552 | |
| Download: ML18117A341 (16) | |
Text
k fc. I I
Michael J.Yox 7825 River Road ilk SOU'tn0rn Nuclssr Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 &4 706-848-6459 tel 410-474-8587 cell APR L 5 201B myox@southernco.com Docket Nos.:
52-025 52-026 ND-18-0552 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 Unit3 and Unit4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.3.06.02a findex Number 3551 Ladies and Gentlemen; Pursuant to 10 CFR 52.99(c)(3), Southern NuclearOperating Company hereby notifies the NRC that as ofApril 16, 2018, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.06.02a[Index Number 355]
has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the planfor completing this ITAAC. Southern Nuclear Operating Companywill, at a laterdate, 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, IndustryGuideline forthe 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 completedand all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRCto 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.
HP-Michael J. Yox Regulatory Affairs Director Vogtle 3 &4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Planfor Uncompleted ITAAC 2.3.06.02a [Index Number 355]
MJY/KJD/amw
U.S. Nuclear Regulatory Commission ND-18-0552 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 Reaulatorv 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. Coovert Oaiethoroe Power Corporation Mr. R. B. Brinkman
U.S. Nuclear Regulatory Commission ND-18-0552 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson 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. Hosier, 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, Batch BIngham
U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 1 of 13 Southern Nuclear Operating Company ND-18-0552 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.06.02a [Index Number 355]
U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 2 of 13 ITAAC Statement Design Commitment:
2.a)Thecomponents identified in Table 2.3.6-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
2.b) The piping identified in Table 2.3.6-2 as ASME CodeSection III isdesignedand constructed in accordance with ASME Code Section III requirements.
3.a) Pressure boundary welds in components identified in Table 2.3.6-1 as ASME Code Section III meet ASME Code Section III requirements.
3.b) Pressure boundary welds in piping identified in Table 2.3.6-2 as ASME Code Section III meet ASME Code Section III requirements.
4.a) The components identified in Table2.3.6-1 as ASME CodeSection III retain theirpressure boundary integrity at their design pressure.
4.b)The piping identified in Table 2.3.6-2 as ASME CodeSection III retains itspressure boundary integrity at its design pressure.
5.b) Each of the lines identified in Table 2.3.6-2 for which functional capability is required is designed towithstand combined normal and seismic design basis loads without a loss of its functional capability.
- 6. Each of the as-built lines identifiedin Table 2.3.6-2 as designed for LBB meets the LBB criteria, oran evaluation is performed ofthe protection from the dynamic effects ofa rupture of the line.
Inspections. Tests. Analvses:
Inspection will beconducted of theas-built components and piping as documented in theASME design reports.
Inspection of theas-built pressure boundary welds will be performed in accordance with the ASME Code Section III.
Ahydrostatic test will be performed on thecomponents and piping required by theASME Code Section III to be hydrostatically tested.
Inspection will be performed for the existence of a report verifying thattheas-built piping meets the requirements for functional capability.
Inspection will be performed for theexistence of an LBB evaluation report oran evaluation report ontheprotection from dynamic effects of a pipe break. Section 3.3, Nuclear Island Buildings, contains the design descriptions and inspections, tests, analyses, andacceptance criteriafor protection from the dynamiceffects of pipe rupture.
U.S. Nuclear Regulatory Commission ND-18-0552 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 2.3.6-1 and 2.3.6-2 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 ofthe hydrostatic test ofthe components and piping identified inTables 2.3.6-1 and 2.3.6-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.
A reportexists and concludes that each ofthe as-built lines identified inTable 2.3.6-2forwhich functional capability is required meets the requirements for functional capability.
An LBB evaluation reportexists and concludes that the LBB acceptance criteria are met bythe as-built RNS piping and piping materials, or a pipe breakevaluation report exists and concludes that protection from the dynamiceffects of a line break is provided.
ITAAC Completion Description This ITAAC requires inspections, tests, and analyses be performed and documented to ensure the Normal Residual Heat Removal System (RNS) components and pipinglisted inthe Combined License (COL) Appendix C, Table 2.3.6-1 (Attachment A) and Table 2.3.6-2 (Attachment B) thatare 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 desion reports exist for the as-built components and pioing identified in Tables 2.3.6-1 and 2.3.6-2 as ASME Code Section III.
Each component listed in Table 2.3.6-1 as ASME CodeSection III isfabricated in accordance with the VEGP Updated Final Safety Analysis Report (UFSAR) and the ASME CodeSection III requirements. The ASME Code Section III certified Design Reports for thesecomponents exist and documentthat the as-built componentsconform to the approveddesign 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 aredocumented on theASME Section III N-5 Code Data Report(s) for theapplicable piping system (Reference 1).
The as-built piping listed in Table2.3.6-2 including the componentslisted in Table 2.3.6-1 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 and Codeprovisions. Design reconciliation of the as-built systems, including installed components, validates thatconstruction completion, including field changes and any nonconforming condition dispositions, isconsistent with andbounded 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 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-18-0552 Enclosure Page 4 of 13 The applicable ASMESection III N-5 Code Data Report(s), which include the location of the certified Design Reports for all the components listed inTable 2.3.6-1 (Attachment A) and piping listed in Table 2.3.6-2 (Attachment B) as ASME Code Section III, exist and conclude that these installed components are designed and constructed (includingtheir 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 inthe Table2.3.6-1 and Table2.3.6-2are identified in Attachments A and B, respectively.
3.a and 3.b1 A reoort exists and concludes that the ASME Code Section III reouirements are met for non-destructive examination of oressure boundary welds.
Inspections are performed inaccordance with ASME Code Section III (1998 Edition, 2000 Addenda) to demonstratethat as-built pressure boundary welds in components identified in Table 2.3.6-1 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-5Code Data Report(s) (Reference 1) documents satisfactory completion of the required examination and testing ofthe item, which includes non-destructive examinations ofpressureboundary welds. Satisfactory completion of the non-destructive examination ofpressure boundary welds ensuresthatthe pressure boundary welds in components identified in Table 2.3.6-1 as ASME Code Section III meet ASME Code Section III requirements.
An inspection isperformed in accordance with Reference 2todemonstrate that theas-built pressure boundary welds in piping identified in Table 2.3.6-2 (Attachment B) as ASME Code Section III meet ASME Code Section III requirements (i.e., no unacceptable indications). This portion of theITAAC iscomplete when the piping identified in Table 2.3.6-2, which is encompassed within therespective piping system Code Symbol N-Stamp and thecorresponding 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 thepiping pressure boundary welds are documented inthe Non-destructive Examination Report(s) within the pipingsystem's supporting data package, which support completion of the respective Code Stamping and Code N-5 Data Report(s). Thecompletion 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 ofpiping pressure boundary welds for the pipe lines identified in Table 2.3.6-2 meet ASME Code Section III requirements and are documentedin the Non-destructive Examination Report(s) within the supporting data packages.
U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 5 of 13 4.a and 4.b1 A report exists and concludes that the results of the hydrostatic test of the components and pioino identified in Tables 2.3.6-1 and 2.3.6-2 as ASME Code Section III conform witfi the reouirements of tfie ASME Code Section III.
A hydrostatic test is performed by the vendor to demonstrate that the components identified in Table 2.3.6-1 (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 identifiedinTable 2.3.6-1 has their individual Code Symbol N-Stamp and corresponding Code Data Report (Reference 1) completed, and the components are installed intothe respective Code Symbol N-Stamped piping system and documented on the corresponding N-5 Code Data Report(s) (Reference 1). The hydrostatic testing resultsofthe component's pressure boundaryare documentedinthe Hydrostatic Testing Report(s)within the supportingcomponent's data package, which support completionof the respective Code Stamping and Code Data Report(s).
The completion ofstampingthe individual componentsand the respectivepiping system along with the corresponding ASME Code Data Reports(certified bythe Authorized Nuclear Inspector) ensures that the components are constructed inaccordance with the Design Specificationsand the ASME Code Section III and that the satisfactory completion of the hydrostatic pressure testing ofeach component identified in Table 2.3.6-1 as ASME CodeSection III are documented in the Hydrostatic Testing Report(s) within the supporting data packagesand meetsASME Code Section III requirements.
This ITAAC also verifies that the piping identified inTable 2.3.6-2 (Attachment B) fully meets all applicable ASME Code,Section III requirements and retains itspressureboundary integrity at its design pressure.
Ahydrostatic test is performed in accordance with procedure XYZ (Reference 4) (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 2.3.6-2 retains its pressure boundary integrityat its design pressure.
Ahydrostatic test verifies thatthere are no leaksat welds or piping, and thatthe pressure boundary integrity is retained at itsdesign pressure. Thehydrostatic testing results ofthe 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 DataReport(s) for the applicable piping system (i.e., RNS) (Reference 1).
The applicable ASME Section III N-5 Code Data Report(s) (Reference1) identified in Attachments A and B documents that the results of the hydrostatic testing of the components and piping identified in Table2.3.6-1 and Table2.3.6-2 respectively conform with the requirementsofthe Code (1998 Edition, 2000 Addenda),Section III.
U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 6 of 13 5.b1 A report exists and concludes that each of the as-built lines identified in Table 2.3.6-2 for which functional caoabilitv is reouired meets the reouirements for functional capability.
An inspection is performed of the ASME Section III as-built pipingdesign report XXX to verify that the report demonstrates that each of the RNS piping lines identified in ITAAC Table 2.3.6-2 that requires functional capabilityis designed to withstand combined normal and seismic design basis loads without a loss of itsfunctional capability. "Functional capability," in this context, refers to the capability of the pipingto withstand the effects of earthquakes, without a loss ofsafety function (toconveyfluids from one location to another). Specific functional capability requirements are defined in the VEGP UFSAR Table3.9-11 (Reference3).
Piping functional capability is not a specific ASME Coderequirement but it isa requirement in the VEGP UFSAR (Reference3). 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 theASME Boiler &Pressure Vessel Code (1998 Edition, 2000 Addenda)Section III requirements. The as-built piping systems aresubjected to a reconciliation process (Reference 2), which verifies that the as-built piping systemsare analyzed for functional capability andfor compliance with the design specification andASME Code provisions. Design reconciliation of theas-built systems validatesthat construction completion, including field changes and any nonconforming condition dispositions, isconsistent with and bounded by the approved design. As required by ASME Code, the As-Built Design Report includes the results of physical inspection ofthe piping and reconciliation to the design pipe stress report.
Inspections of theASME Code Section III As-Built Piping Design Reports (Reference 5) for the RNS piping lines identified in Table 2.3.6-2 arecomplete and conclude that each of the as-built RNS piping lines for which functional capability is required meets the requirements for functional capability. The ASME Section III As-Built Piping Design Reports for eachof the as-built RNS piping linesinTable2.3.6-2 are identified in Attachment B.
- 6. An LBB evaluation reoort exists and concludes that the LBB acceptance criteria are met bv the as-built RNS oioina and oioino materials, or a pipe break evaluation reoort exists and concludes that orotection from the dvnamic effects of a line break is orovided.
Inspections areperformed for the as-built lines identified in Table 2.3.6-2 (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 0, 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 RNS piping (and corresponding piping materials) identified in Attachment Ameet the LBB acceptance criteria described in the UFSAR, Appendix 3B, Leak-Before-Break Evaluation of the API000 Piping (Reference 3). In cases where an as-built RNS 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 isprovided. The pipe break evaluation criteria is discussed in UFSAR, Section3.6.4.1, PipeBreakHazardsAnalysis (Reference3) and isdocumented as a pipe rupture hazards analysis report (pipe break evaluation report).
U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 7 of 13 Inspections are performed to verifythat LBB as-built piping evaluation reports for the RNS 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 SB of the 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 RNS piping line in Attachment B cannot meet the LBB acceptance criteria, inspections are performedto verify that a pipe rupture hazards analysis evaluation report(pipe break evaluation report) exists whichconcludes 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) (pipebreak evaluation report(s)) existand are identified in Attachment B.
References 1 and 5 providethe evidence that the following ITAAC Acceptance Criteria requirements are met:
The ASME Code Section III design reports exist for the as-built components and piping identified inTables 2.3.6-1 and 2.3.6-2 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 reportexists and concludes that the results ofthe hydrostatic test ofthe componentsand piping identified in Tables 2.3.6-1 and 2.3.6-2as ASME Code Section III conform withthe requirements of the ASME Code Section III; Areport exists and concludesthat each ofthe as-built linesidentified in Table2.3.6-2 for which functional capability is required meets the requirements forfunctional capability; and An LBB evaluation report exists and concludes that the LBB acceptance criteriaare met bythe as-built RNS piping and piping materials, ora pipe breakevaluation report exists and concludes that protection from the dynamic effects ofa line break is provided.
References 1 and 5 are available for NRC inspectionas part of the Unit 3 and Unit 4 ITAAC 2.3.06.02a Completion Packages (References 6 and 7, respectively).
List of ITAAC Findings In accordance with plantprocedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings andassociated corrective actions.
This review, which included nowconsolidated ITAAC Indexes 356, 357, 358, 359, 360, 364 and 365, found no relevant ITAAC findings associated withthis ITAAC.
U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 8 of 13 References (available for NRG inspection^
1.
RNS ASME N-5 Code Data Report(s)
- 2. APP-GW-GAP-139, "Westinghouse/WECTEC ASME N-5 Interface Procedure" 3.
VEGP 3&4 Updated Final Safety Analysis Report a.
Subsection 5.2.1 - Compliance with Codes and Code Cases,
- b. Table 3.9 Piping FunctionalCapability-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 ofthe API000 Piping 4.
RNS Piping Hydrostatic Test Procedure XYZ 5.
RNS ASME III As Built Design Report(s)
- 6. Completion Package for Unit 3 ITAAC 2.3.06.02a [COL Index Number 355]
- 7. Completion Packagefor Unit 4 ITAAC 2.3.06.02a [COL Index Number 355]
U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 9 of 13 Attachment A SYSTEM: Normal Residual Heat Removal System (RNS)
Equipment Name*
Tag No.*
ASME Code Section III*
ASME III as-built Design Report N-5 Report RNS Pump A (Pressure Boundary)
RNS-MP-01A Yes XXX RNS N-5 Code Data Report RNS Pump B (Pressure Boundary)
RNS-MP-OIB Yes XXX RNS N-5 Code Data Report RNS Heat Exchanger A (Tube Side)
RNS-ME-01A Yes XXX RNS N-5 Code Data Report RNS Heat Exchanger B (Tube Side)
RNS-ME-01B Yes XXX RNS N-5 Code Data Report RCS Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001A Yes XXX RNS N-5 Code Data Report RCS Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001B Yes XXX RNS N-5 Code Data Report RCS Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002A Yes XXX RNS N-5 Code Data Report RCS Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002B Yes XXX RNS N-5 Code Data Report RCS Pressure Boundary Thermal Relief Check Valve RNS-PL-V003A Yes XXX RNS N-5 Code Data Report RCS Pressure Boundary Thermal Relief Check Valve RNS-PL-V003B Yes XXX RNS N-5 Code Data Report RNS Discharge Motor-operated Containment Isolation Valve RNS-PL-V011 Yes XXX RNS N-5 Code Data Report RNS Discharge Containment Isolation Test Connection RNS-PL-V012 Yes XXX RNS N-5 Code Data Report RNS Discharge Header Containment Isolation Check Valve RNS-PL-V013 Yes XXX RNS N-5 Code Data Report RNS Discharge RCS Pressure Boundary Check Valve RNS-PL-V015A Yes XXX RNS N-5 Code Data Report RNS Discharge RCS Pressure Boundary Check Valve RNS-PL-V015B Yes XXX RNS N-5 Code Data Report RNS Discharge RCS Pressure Boundary Check Valve RNS-PL-V017A Yes XXX RNS N-5 Code Data Report
U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 10 of 13 Attachment A SYSTEM: Normal Residual Heat Removal System (RNS)
Equipment Name*
Tag No.*
ASME Code Section III*
ASME III as-built Design Report N-5 Report RNS Discharge RCS Pressure Boundary Check Valve RNS-PL-V017B Yes XXX RNS N-5 Code Data Report RNS Hot Leg Suction Pressure Relief Valve RNS-PL-V020 Yes XXX RNS N-5 Code Data Report RNS Hot Leg Suction Pressure Relief Valve RNS-PL-V021 Yes XXX RNS N-5 Code Data Report RNS Suction Header Motor-operated Containment Isolation Valve RNS-PL-V022 Yes XXX RNS N-5 Code Data Report RNS Suction from IRWST Motor-operated Isolation Valve RNS-PL-V023 Yes XXX RNS N-5 Code Data Report RNS Discharge to IRWST Motor-operated Isolation Valve RNS-PL-V024 Yes XXX RNS N-5 Code Data Report RNS Pump Discharge Relief RNS-PL-V045 Yes XXX RNS N-5 Code Data Report RNS Suction from Cask Loading Pit Motor-operated Isolation Valve RNS-PL-V055 Yes XXX RNS N-5 Code Data Report RNS Suction from Cask Loading Pit Check Valve RNS-PL-V056 Yes XXX RNS N-5 Code Data Report RNS Pump Miniflow Air-Operated Isolation Valve RNS-PL-V057A Yes XXX RNS N-5 Code Data Report RNS Pump Miniflow Air-Operated Isolation Valve RNS-PL-V057B Yes XXX RNS N-5 Code Data Report RNS Return from Chemical and Volume Control System (CVS) Containment Isolation Valve RNS-PL-V061 Yes XXX RNS N-5 Code Data Report "Excerptsfrom COLAppendixC Table 2.3.6-1
U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 11 of 13 Attachment B SYSTEM: Normal Residual Heat Removal System (RNS)
Line Name*
Line No.*
ASME Code Section ill*
Leak Before Break*
Functional Capability Required*
ASME III As-Built Design Report LBB evaluation /
pipe break evaluation N-5 Report RNS Suction Lines, from the RCS Hot Leg Connection to the RCS Side of Valves RNS PL-VOOIAand RNS-PL-V001B RNS-L001 RNS-L002A RNS-L002B Yes Yes No XXX YYY N-5 Code Data Report RNS Suction Lines, from the RCS Pressure Boundary Valves, RNS-PL-VOOIAand RNS-PL-V001B,tothe RNS pumps RNS-L004A RNS-L004B RNS-L005 RNS-L006 RNS-007A RNS-007B RNS-009A RNS-009B Yes No Yes Yes Yes Yes Yes Yes Yes Yes XXX YYY N-5 Code Data Report RNS Suctton Line from CVS RNS-L061 Yes No Yes XXX YYY N-5 Code Data Report RNS Suction Line from IRWST RNS-L029 Yes No Yes XXX YYY N-5 Code Data Report RNS Suction Line LTOP Relief RNS-L040 RNS-L090 Yes No Yes XXX YYY N-5 Code Data Report RNS Discharge Lines, from the RNS Pumps to the RNS Heat Exchangers RNS-ME-OIAand RNS-ME-01B RNS-L011A RNS-L011B Yes No Yes XXX YYY N-5 Code Data Report RNS Discharge Lines, from RNS Heat Exchanger RNS-ME-01A to Containment Isolation Valve RNS-PL-V011 RNS-L012A RNS-L014 Yes No Yes XXX YYY N-5 Code Data Report
U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 12 of 13 Attachment B SYSTEM: Normal Residual Heat Removal System (RNS)
Line Name*
Line No.*
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 Discharge Line, from RNS Heat Exchanger RNS-ME-01B to Common Discharge Header RNS-L014 RNS-L012B Yes No Yes XXX YYY N-5 Code Data Report RNS Discharge Lines, Containment Isolation Valve RNS-PL-V011 to Containment Isolation Valve RNS-PL-V013 RNS-L016 Yes No Yes XXX YYY N-5 Code Data Report RNS Suction Line from Cask Loading Pit RNS-L065 Yes No No XXX YYY N-5 Code Data Report RNS Discharge Lines, from Containment Isolation Valve RNS-PL-V013 to RCS Pressure Boundary Isolation Valves RNS-PL-V015Aand RNS-PL-V015B RNS-L017 RNS-L018A RNS-L018B Yes No Yes XXX YYY N-5 Code Data Report RNS Discharge Lines, from Direct Vessel Injection (DVI) Line RNS-BBC-L018Ato Passive Core Cooling System (PXS) IRWST Return Isolafion Valve RNS-PL-V024 RNS-L020 Yes No No XXX YYY N-5 Code Data Report
U.S. Nuclear Regulatory Commission ND-18-0552 Enclosure Page 13 of 13 Attachment B SYSTEM: Normal Residual Heat Removal System (RNS)
Line Name*
Line No.*
ASME Code Section ill*
Leak Before Break*
Functional Capability Required*
ASME III As-Bulit Design Report LBB evaluation /
pipe break evaluation N-5 Report RNS Discharge Lines, from RCS Pressure Boundary Isolation Valves RNS-PL-V015Aand RNS-PL-V015Bto RCS Pressure Boundary Isolation Valves RNS-PL-V017Aand RNS-PL-V017B RNS-L019A RNS-L019B Yes No Yes XXX YYY N-5 Code Data Report RNS Heat Exchanger Bypass RNS-L008A RNS-L008B Yes No No XXX YYY N-5 Code Data Report RNS Suctton from Spent Fuel Pool RNS-L052 Yes No No XXX YYY N-5 Code Data Report RNS Pump Miniflow Return RNS-L030A RNS-L030B Yes No No XXX YYY N-5 Code Data Report RNS Discharge to Spent Fuel Pool RNS-L051 Yes No No XXX YYY N-5 Code Data Report RNS Discharge to CVS Purification RNS-L021 Yes No No XXX YYY N-5 Code Data Report "Excerpts from COL Appendix C, Table 2.3.6-2