ND-21-0769, ITAAC Closure Notification on Completion of ITAAC 2.2.02.02a (Index Number 120)

ITAAC Closure Notification on Completion of ITAAC 2.2.02.02a (Index Number 120)

ML21341B364
Person / Time
Site:	Vogtle
Issue date:	12/07/2021
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-0769
Download: ML21341B364 (12)

Text

Southern Nuclear DEC 0 7 2021 Docket No.:

52-025 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel ND-21-0769 10 CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.2.02.02a (index Number 1201 Ladies and Gentlemen:

In accordance with 10 CFR 52.99(c)(1), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the completion of Vogtle Electric Generating Plant (VEGP)

Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.02.02a [Index Number 120]. This ITAAC requires inspections, tests, and analyses be performed and documented to ensure the Passive Containment Cooling System (PCS) components and piping listed in the Combined License (COL) Appendix C, Table 2.2.2-1 and Table 2.2.2-2 that are identified as American Society of Mechanical Engineers (ASME) Code Section III or Functional Capability Required are designed and constructed in accordance with applicable requirements.

The closure process for this ITAAC is based on the guidance described in Nuclear Energy Institute (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.

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99.

If there are any questions, please contact Kelli A. Roberts at 706-848-6991.

Respectfully submitted.

Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.02.02a [Index Number 120]

MJY/JRV/sfr

U.S. Nuclear Regulatory Commission ND-21-0769 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKinney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. J.B. Williams Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Ms. J.M. Coleman Mr. C. T. Defnall Mr. C. E. Morrow Mr. K. J. Drudy Mr. J. M. Fisher Mr. R. L. Beiike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc; Nuclear Requlatorv Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil M

M M

M Ms. N. C. Coovert M

M M

M M

M M

M M

M M

M M

M C. P. Patel G. J. Khouri C. J. Even B. J. Kemker C. Welch J. Gaslevic O. Lopez-Santiago G. Armstrong

. M. Webb

. T. Fredette

. C. Santos

. B. Davis

. J. Vasquez

. J. Eargle

. T. Fanelli Ms. K. McCurry

. J. Parent

. B. Griman

. V. Hall

U.S. Nuclear Regulatory Commission ND-21-0769 Page 3 of 3 Qqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen 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 Mr. D. 0. Durham Mr. M. M. Gorletti Mr. J. L. Coward Ms. Z.S. Harper Other Mr. S.W. Kline, 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. R.L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-21-0769 Enclosure Page 1 of 9 Southern Nuclear Operating Company ND-21-0769 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.02.02a [Index Number 120]

U.S. Nuclear Regulatory Commission ND-21-0769 Enclosure Page 2 of 9 ITAAC Statement Design Commitment:

2.a) The components identified in Table 2.2.2-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.

2.b) The pipelines identified in Table 2.2.2-2 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.

3.a) Pressure boundary welds in components identified in Table 2.2.2-1 as ASME Code Section III meet ASME Code Section III requirements.

3.b) Pressure boundary welds in the pipelines identified in Table 2.2.2-2 as ASME Code Section III meet ASME Code Section III requirements.

4.a) The components identified in Table 2.2.2-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.

4.b) The pipelines identified in Table 2.2.2-2 as ASME Code Section III retain their pressure boundary integrity at their design pressure.

5.b) Each of the pipelines identified in Table 2.2.2-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability.

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 for the existence of a report concluding that the as-built pipelines meets the requirements for functional capability.

Acceptance Criteria:

The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.2.2-1 and 2.2.2-2 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.

U.S. Nuclear Regulatory Commission ND-21-0769 Enclosure Page 3 of 9 A report exists and concludes that the results of the hydrostatic test of the components and piping identified in Tables 2.2.2-1 and 2.2.2-2 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 pipelines identified in Table 2.2.2-2 for which functional capability is required meets the requirements for functional capability.

ITAAC Determination Basis This ITAAC requires inspections, tests, and analyses be performed and documented to ensure the Passive Containment Cooling System (PCS) components and piping listed in the Combined License (COL) Appendix C, Table 2.2.2-1 (Attachment A) and Table 2.2.2-2 (Attachment B) that are identified as American Society of Mechanical Engineers (ASME) Code Section III 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 2.2.2-1 and 2.2.2-2 as ASME Code Section III.

Each component listed in Table 2.2.2-1 as ASME Code Section III was 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 was documented in the component's 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 2.2.2-2 including the components listed in Table 2.2.2-1 as ASME Code Section III, were 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, was consistent with and bounded by the approved design. All applicable fabrication, installation and testing records, as well as, those for 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.

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 2.2.2-1 (Attachment A) and piping listed in Table 2.2.2-2 (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 2.2.2-1 and Table 2.2.2-2 are identified in Attachments A and B, respectively.

U.S. Nuclear Regulatory Commission ND-21-0769 Enclosure Page 4 of 9 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 were 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 2.2.2-1 as ASME Code Section III met 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 2.2.2-1 as ASME Code Section III met ASME Code Section III requirements.

An inspection was performed in accordance with Reference 2 to demonstrate that the as-built pressure boundary welds in piping identified in Table 2.2.2-2 (Attachment B) as ASME Code Section III met ASME Code Section III requirements (i.e., no unacceptable indications). This portion of the ITAAC was completed when the piping identified in Table 2.2.2-2, 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), was completed. 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 system's 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 2.2.2-2 met ASME Code Section III requirements and were documented in the Non destructive Examination Report(s) within the supporting data packages.

4.a and 4.b1 A report exists and concludes that the results of the hvdrostatic test of the components and piping identified in Tables 2.2.2-1 and 2.2.2-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.

A hydrostatic test was performed by the vendor to demonstrate that the components identified in Table 2.2.2-1 (Attachment A) as ASME Code Section III retain their pressure boundary integrity at their design pressure. The completion of the N-5 Data Reports was governed by Reference 2.

This portion of the ITAAC was completed once each component identified in Table 2.2.2-1 had their individual Code Symbol N-Stamp and corresponding Code Data Report (Reference 1)

U.S. Nuclear Regulatory Commission ND-21-0769 Enclosure Page 5 of 9 completed, and the components were 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 component's pressure boundary were documented in the Hydrostatic Testing Report(s) within the supporting component's 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 were 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 2.2.2-1 as ASME Code Section III were documented in the Hydrostatic Testing Report(s) within the supporting data packages and met ASME Code Section III requirements.

This ITAAC also verifies that the piping identified in Table 2.2.2-2 (Attachment B) fully meets all applicable ASME Code,Section III requirements and retains its pressure boundary integrity at its design pressure.

Hydrostatic tests were performed in accordance with procedures identified in Reference 1 (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 2.2.2-2 retains its pressure boundary integrity at its design pressure.

A hydrostatic test verified that there are no leaks at welds or piping, and that the pressure boundary integrity was 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., PCS)

(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 2.2.2-1 and Table 2.2.2-2 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 2.2.2-2 for which functional capabilitv is required meets the requirements for functional caoabilitv.

An inspection was performed of the ASME Section III as-built piping design report (Reference 4) to verify that the report demonstrates that each of the PCS piping lines identified in ITAAC Table 2.2.2-2 that requires functional capability was 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 was 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

U.S. Nuclear Regulatory Commission ND-21-0769 Enclosure Page 6 of 9 as-built piping systems were subjected to a reconciliation process (Reference 2), which verifies that the as-built piping systems were 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, was 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 PCS piping lines identified in Table 2.2.2-2 were completed and conclude that each of the as-built PCS piping lines for which functional capability was required met the requirements for functional capability. The ASME Section III As-Built Piping Design Reports for each of the as-built PCS piping lines in Table 2.2.2-2 are identified in Attachment B.

References 1 and 4 provide the evidence that the following ITAAC Acceptance Criteria requirements were met:

The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.2.2-1 and 2.2.2-2 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 2.2.2-1 and 2.2.2-2 as ASME Code Section III conform with the requirements of the ASME Code Section III; and A report exists and concludes that each of the as-built pipelines identified in Table 2.2.2-2 for which functional capability are required meet the requirements for functional capability.

This ITAAC also verified that the Preservice Inspection (PSI) examinations for the applicable portions of the Class 3 Passive Containment Cooling System (PCS) components and piping identified in Tables 2.2.2-1 and 2.2.2-2 were completed (Reference 7), in accordance with the Unit 3 PSI program plan (Reference 5), and that the results of the PSI conforms with the requirements of the ASME Boiler and Pressure Vessel (B&PV) Code.

References 1 and 4 are available for NRC inspection as part of the Unit 3 ITAAC 2.2.02.02a Completion Package (References 6).

ITAAC Finding Review In accordance with plant procedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review of all findings pertaining to the subject ITAAC and associated corrective actions. This review, which included now consolidated ITAAC Indexes 121,122,123, 124,125, and 129, found no relevant ITAAC findings associated with this ITAAC.

The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.2.02.02a (Reference 6) and is available for NRC review.

U.S. Nuclear Regulatory Commission ND-21-0769 Enclosure Page 7 of 9 ITAAC Completion Statement Based on the above Information, SNC hereby notifies the NRG that ITAAC 2.2.02.02a was performed for VEGP Unit 3 and that the prescribed acceptance criteria were met.

Systems, structures, and components verified as part of this ITAAC are being maintained in their as designed, ITAAC compliant condition in accordance with approved plant programs and procedures.

References (available for NRG inspection)

1. SV3-PCS-MUR-001, Rev. 0, "AP1000 Vogtle Unit 3 ASME Section III System Code Data Report for the Passive Containment Cooling System (PCS)"

2. APP-GW-GAP-139, Rev. 7, "Westinghouse/Stone & Webster ASME Code Data Report As-Built Documentation Interface Procedure"

3. VEGP 3&4 Updated Final Safety Analysis Report, Rev. 10.1, Subsection 5.2.1, Compliance with Codes and Code Cases

a. Subsection 5.2.1 - Compliance with Codes and Code Cases

b. Table 3.9 Piping Functional Capability - ASME Class 1, 2, and 3

4. SV3-PCS-S3R-001, Rev. 0, "Vogtle Unit 3 Passive Containment Cooling System ASME Section III As-Built Piping System Design Report"

5. SV3-GW-GEI-100, Rev. 2, "API 000 Preservice Inspection Program Plan for Vogtle Unit 3"

6. 2.2.02.02a-U3-CP-Rev0, ITAAC Completion Package

7. APE-10-00018, "Unit 3

- Completion of Preservice Inspection for PCS Class 1, 2, and 3 Portions"

U.S. Nuclear Regulatory Commission ND-21-0769 Enclosure Page 8 of 9 Attachment A SYSTEM: Passive Containment Cooling System (PCS)

Equipment Name*

Tag No.*

ASME Code Section III*

ASME III As-bullt Design Report N-5 Report PCCWST Isolation Valve PCS-PL-V001A Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 PCOWST Isolation Valve PCS-PL-V001B Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 PCCWST Isolation Valve MOV PCS-PL-V001C Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 PCCWST Isolation Block MOV PCS-PL-V002A Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 PCCWST Isolation Block MOV PCS-PL-V002B Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 PCCWST Isolation Block MOV PCS-PL-V002C Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 PCS Recirculation Return Isolation Valve PCS-PL-V023 Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 PCCWST Supply to Fire Protection System Isolation Valve PCS-PL-V005 Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 PCS Makeup to SFS Isolation Valve PCS-PL-V009 Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 Water Makeup Isolation Valve PCS-PL-V044 Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 Water Bucket Makeup Line Drain Valve PCS-PL-V015 Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 Water Bucket Makeup Line Isolation Valve PCS-PL-V020 Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 PCCWST Long-Term Makeup Line Check Valve PCS-PL-V039 Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 PCCWST Long-Term Makeup Drain Isolation PCS-PL-V042 Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 PCS Discharge to SFS Pool Isolation Valve PCS-PL-V045 Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 Recirc Header Discharge to PCCWST Isolation Valve PCS-PL-V046 Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 PCCWST Drain Isolation Valve PCS-PL-V049 Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 Recirc Header Discharge to SFS Pool Isolation Valve PCS-PL-V050 Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001 PCCWST Discharge to SFS Pool Isolation Valve PCS-PL-V051 Yes SV3-PCS-S3R-001 SV3-PCS-MUR-001

• Excerpts from COL Appendix 0, Table 2.2.2-1

U.S. Nuclear Regulatory Commission ND-21-0769 Enclosure Page 9 of 9 Attachment B SYSTEM: Passive Containment Cooling System (PCS)

Pipeline Name**

Line No.**

ASME Code Section III**

Functional Capability Required**

ASME III As-Built Design Report N-5 Report PCCWST Discharge Lines PCS-PL-L001A/BVC/D*

Yes Yes SV3-PCS -S3R-001 SV3-PCS-MUR-001 PCCWST Discharge Cross-connect Line PCS-PL-L002 Yes Yes SV3-PCS -S3R-001 SV3-PCS-MUR-001 PCCWST Discharge Header Lines PCS-PL-L003A/B PCS-PL-L005 Yes Yes SV3-PCS -S3R-001 SV3-PCS-MUR-001 Post-72-hour Supply Line Connection PCS-PL-L051 PCS-PL-L054 PCS-PL-L065*

Yes Yes SV3-PCS -S3R-001 SV3-PCS-MUR-001 Post-72-hour Containment Cooling Makeup From Supply Line Connections PCS-PL-L004 PCS-PL-L007 PCS-PL-L008 PCS-PL-L023 PCS-PL-L050*

Yes Yes SV3-PCS -S3R-001 SV3-PCS -MUR-001 Post-72-hour SFS Makeup From PCCWST PCS-PL-L011 PCS-PL-L017 PCS-PL-L018 PCS-PL-L030**

PCS-PL-L039*

PCS-PL-L041*

PCS-PL-L049**

PCS-PL-L073*

Yes Yes SV3-PCS -S3R-001 SV3-PCS -MUR-001 Post-72-hour SFS Makeup From Supply Line Connection PCS-PL-L025 PCS-PL-L029 PCS-PL-L030**

PCS-PL-L039*

PCS-PL-L048 PCS-PL-L049**

PCS-PL-L052*

Yes Yes SV3-PCS -S3R-001 SV3-PCS -MUR-001

• Lines PCS-PL-L049, L039, and L030 comprise a common makeup line from both sources.

• • Excerpts from COL Appendix 0, Table 2.2.2-2

+These lines PCS-PL-L001B/D, L065, L050, L030, L041, L049, L073, and L052 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).