ML22130A673

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TRP16 - St. Lucie SLRA Breakout Questions_Pwr Internals
ML22130A673
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 01/11/2022
From: Vaughn Thomas
NRC/NRR/DNRL/NLRP
To:
Thomas V, 301-415-5897
Shared Package
ML22130A654 List:
References
Download: ML22130A673 (23)
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St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Staff Member Name Concurrence Signature Date Technical Primary Reviewer James Medoff Jan. 4, 2022 Technical Peer Reviewer John Tsao January 4, 2022 Technical Branch Chief Angie Buford January 11, 2022 Breakout Session Date/Time To be filled in by PM

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Breakout Session Attendance List Applicant Staff NRC staff To be filled out by Brian Harris (new DNLR/NLRB PM for St. Lucie SLRA) during breakout session for PWR Reactor Vessel Internals AMP and AMRs

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Abbreviations Used in the TRP Audit Question/Topic Table Abbreviations for Aging Effects Loss of fracture toughness: LOFT Loss of preload: LOP Loss of Material: LOM Changes in Dimension: CID Abbreviations for Applicable Aging Mechanisms Stress Corrosion Cracking: SCC Neutron Irradiation Embrittlement: IE Irradiation-Assisted Stress Corrosion Cracking: IASCC Void Swelling (or Distortion): VS-D Irradiation-Enhanced Stress Relaxation or Creep: ISR/IC Thermal-Aging Embrittlement: TE Fatigue (or Cyclical Loading): F-CL Abbreviations for Reactor Internals Assemblies or Component Commodity Groups Core Element Assembly: CEA Core Shroud Assembly: CSA Control Support Barrel Assembly: CSBA In-Core Instrumentation: ICI Lower Support Structure: LSS Upper Internals Assembly: UIA Reactor Vessel Internal (General Terminology): RVI Other Abbreviations Electric Power Research Institute: EPRI Materials Reliability Program: MRP Pressurized Water Reactor Owners Group: PWROG Nuclear Energy Institute: NEI Risk-Informed Approach to the Staffs Audit of SLRA AMP B2.3.7

  • The Reactor Vessel Internals Program is a risk-Informed, sampling Based Program based on EPRI MRP-227, Rev. 1-A guidelines, as adjusted by the applicants gap analysis for the RVI components. Given that all operating experience (OpE - generic or plant-specific) is disseminated to EPRI for compilation and analysis, the staff will rely on the word searches performed by the applicant for relevant plant-specific and generic OpE and will not need to perform its own independent word search for relevant RVI OpE.

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16

  • The applicant is using EPRI MRP-175, Revision 1; MRP-191, Revision 2; and MRP-2018-022 for the gap analysis adjusted basis for the AMP.

In NRC Interim Staff Guidance Document (ISG) No. SLR-ISG-2021-01-PWRVI (ADAMS Accession No. ML20217L203), the staff could not preclude the applicant from using these types of additional guidelines for the gap analysis results of the AMP. However, these types of proprietary documents are not formally reviewed by the staff for acceptance. Thus, the staff may ask questions regarding the validity of gap analysis results that may derive from the EPRI MRP conclusions in these supplemental guidelines. This approach is consistent with what was reflected in Appendix G of the staffs referenced ISG.

  • The breakout session for SLRA AMP B2.3.7 and the related AMRs is the appropriate session for discussing topics related to the RVI AMP and its related AMR items. The staff may raise questions during the scheduled audit breakout session, but will not use the breakout session as a basis for assessing the adequacy of the applicants verbal response to any given audit question. However, this is not to be interpreted that the staff is accepting of (or will be rejecting) a given statement, position or basis that may be made or implied in a given response to a specified audit question or in relation to given aspects of the AMP and related AMRs. Instead, if it is needed, the staff will use its RAI and RAI resolution processes to assess the validity of any applicant-made positions or technical/regulatory bases for the referenced AMP and related AMR items.

The RAI discussion sessions (as may be scheduled as remote MS-TEAMS teleconferences by the assigned NRR project manager) are the more appropriate SLRA-review sessions to articulate any differences in technical or regulatory positions that may arise between the NRR staff members and the applicants staff members.

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Audit Breakout Topics and Questions for AMP B2.3.7, Including Gap Analysis Results and OpE Generic Discussion Topics - NOTE: Staff Will Inform NextEra Energy of any Additional Reactor Internal-Related Documents Needing Posting to the Audit Portal After the Audit Breakout Session for SLRA AMP B.2.3.7 and Related SLRA AMR Items Question/Topic SLRA SLRA Pages MRP-227, Rev. 1- Background / Discussion Topic / Outcome of Number Section/Table A or MRP-2018- Information Gap Question or Request Discussion 022 Table (T)

References 1 SLRA Section B B-74; NA Topic: Formal Gap The staff cannot perceive B2.3.7; SLRA C C-10 Analysis for the St. Lucie whether SLRA Appendix C Appendix C 1 and 2 RVI is considered the formal Components gap analysis for the SLRA or whether the applicant The staff has not located considers the EPRI MRP-a formal gap analysis in 2018-022/MRP-191, Rev 2 the SLRA Audit Portal bases to be the formal gap directory for SLRA AMP analysis report for the RVI B2.3.7. components, or whether there is a separate record for St. Lucie RVI components that contains the formal gap analysis for the AMP. The staff requests that the applicant identify the formal record that contains the fully detailed formal RVI gap for the RVI AMP. If the formal gap analysis is contained in a St. Lucie record other than SLRA Appendix C or EPRI MRP-2018-022, the staff requests that the applicant post that analysis to the SLRA Audit Portal for SLRA AMP B2.3.7

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Question/Topic SLRA SLRA Pages MRP-227, Rev. 1- Background / Discussion Topic / Outcome of Number Section/Table A or MRP-2018- Information Gap Question or Request Discussion 022 Table (T)

References 2 SLRA Section B B-74; NA Topic: Scope of Applicant should clarify B2.3.7; SLRA C C-10 Program whether the scope of the Appendix C Reactor Vessel Internals Program includes the Pressurized Water Reactor Owners Groups (PWROGs) acceptance criteria and data analysis criteria in WCAP-17096 per the reference to the WCAP report in Chapter 7 of MRP-227, Rev. 1-A. If so, the applicant should clarify which version of WCAP-17096 is being applicable to the Program.

3 SLRA Table 3.1 3.1- NA Topic: St. Lucie RVI 1) Applicant to confirm that 3.1.2-2; 63 Code Shroud Design the St. Lucie unit-specific SLRA Section B B-74; Confirmations core shroud assemblies B2.3.7; C C-10 utilize a welded core SLRA shroud design in two Appendix C vertical sections.

2) Applicant to confirm whether there are any aspects of the St. Lucie RVI design that deviates from the assumed RVI design for CE-designed reactors in MRP-227, Rev.

1-A

3) Applicant to confirm that core shroud tie rods are a

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Question/Topic SLRA SLRA Pages MRP-227, Rev. 1- Background / Discussion Topic / Outcome of Number Section/Table A or MRP-2018- Information Gap Question or Request Discussion 022 Table (T)

References bolted design with bolts and nuts.

4) Applicant to confirm whether or not the 80-Year Program will still implement confirmations for maximum power ratio, average power density, and top of fuel-to-upper core plate height, as specified per MRP 2013-025.

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Reactor Internal AMR Items for SLRA Table 3.1.2 Comparisons to SLRA AMP B2.3.7, PWR Vessel Internals and SLRA Appendix C Gap Analysis Information (Table Includes Component-Based Items Not Needing Discussion to Indicate That Staff Has No Issues with the Items)

Question/Topic SLRA MRP-227, Rev. Background / Information Gap Discussion Topic / Outcome of Number Pages 1-A or MRP- Question or Request or Staff Discussion 2018-022 Table comments.

References 1 3.1-59 NA Referenced SLRA Table 3.1.2-2 AMR No discussions needed for the Item: No Additional Measures referenced NAM-based AMR item.

Components The referenced AMR item is a general commodity group-based AMR item for all RVI components placed in the EPRI MRP No Additional Measures (NAM) category.

2 3.1-59 MRP-227, Referenced SLRA Table 3.1.2-2 AMR No discussions needed for the Rev. 1-A, Item: Core support barrel assembly referenced AMR Item or for the Table 4-8, (CSBA) upper flange AMPs Existing Program basis Item C16 for the CSBA upper flange Component is Existing Program components.

component for the mechanism of wear.

3 3.1-59 MRP-227, Referenced SLRA Table 3.1.2-2 AMR No discussions necessary for the Rev. 1-A, Items (2 of them): Core shroud two AMR items or the AMPs Table 4-5, assembly (CSA) remaining axial welds Expansion-category basis for the Item C2.1 CSA remaining axial welds.

The remaining axial welds in the core shroud remain as Expansion-category components for the program; the linked Primary-category components ae the core shroud plate-to-former plate welds.

The remaining axial welds screen in for mechanisms of IASCC and IE.

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Question/Topic SLRA MRP-227, Rev. Background / Information Gap Discussion Topic / Outcome of Number Pages 1-A or MRP- Question or Request or Staff Discussion 2018-022 Table comments.

References 4 3.1-59 MRP-227, Referenced SLRA Table 3.1.2-2 AMR No discussions necessary for the Rev. 1-A, Items (2 Items): Core shroud assembly two AMR items or the AMPs Table 4-2, (CSA) shroud plate-to-former plate welds Primary-category basis for the Item C2 CSA shroud plate-to-former plate The Primary shroud plate-to-former plate welds.

welds link to the Expansion-category .

remaining [shroud] axial welds. The shroud plate-to-former plate welds screen in for mechanisms of IASCC and IE.

5 3.1-59 Referenced SLRA Table 3.1.2-2 AMR Why doesnt the AMR item for the Items (2 items): Core shroud assembly core shroud tie rods (at the bottom

- core shroud tie rods of page 3.1-59) include the aging effects of loss of fracture The tie rods are new gap analysis toughness (LOFT) and loss of adjusted Primary category components preload (LOP) in addition to the for the 80-year program. SLRA Table aging effects of LOM and CID (i.e.,

3.1.2-2 includes an AMR item on in order to cover the non-cracking cracking of the tie rods (i.e., for mechanisms of wear, VS-D, IE, irradiation-assisted stress corrosion and ISR/IC)?

cracking [IASCC] and fatigue mechanisms) and an AMR item on loss of material (LOM) and changes in dimension (CID) (i.e., to cover the non-cracking mechanisms of wear and void swelling/distortion [VS-D]). The corresponding line item for the core shroud tie rods also has the tie rods as screening in for the non-cracking mechanism of irradiation embrittlement (IE) and irradiation-enhanced stress relaxation or creep (ISR/IC).

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Question/Topic SLRA MRP-227, Rev. Background / Information Gap Discussion Topic / Outcome of Number Pages 1-A or MRP- Question or Request or Staff Discussion 2018-022 Table comments.

References 6 3.1-60; MRP-227, Referenced SLRA Table 3.1.2-2 AMR Applicant should identify which C-5 Rev. 1-A Item: Core stabilizing lugs, shims, and EPRI MRP category will be Table 4-8, bolts applied to the core stabilizing lugs, Item C17 shims, and bolts under the 80-year The referenced AMR item for the core version of the PWR Vessel stabilizing lugs, shims, and bolts at the Internals Program. If the category top of SLRA page 3.1-60 reference use for the components has been of SLRA Item 3.1-1, 052c and GALL-SLR elevated to the Primary category, Item IV.B3.RP-320a, which identify these shouldnt the appropriate AMR components as Existing Program cross-references in the AMR item category components for what will be the be SLRA Item 3.1-1, 118 and 80-year version of the AMP. However, GALL-SLR Item IV.B3.RP-423 (as the corresponding line item for these updated in SLR-ISG-2021 components in SLRA Appendix C (on PWRVI)?

SLRA page C-5) has the core stabilizing lugs, shims, and bolts are elevated Alternatively, the Applicant can opt Primary category components. to confirm that the AMP will be performing VT-3 visual inspections According to the gap analysis, the of these components on a 10-Year components screen in for the aging augmented inspection basis mechanisms of stress corrosion cracking regardless of whether the AMP (SCC) and wear. categorizes the components as newly elevated Primary-category components or remaining Existing Program-category components for the program. If this is the case, then adjustments of any potential GALL-SLR AMR item reference inaccuracies in the AMR item would be un-necessary.

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 7 3.1-60; MRP-227, Referenced SLRA Table 3.1.2-2 AMR No issues with the actual C C-9 Rev. 1-A Items (4 items): Core support barrel referenced AMR items. However, Table 4-5, assembly (CSBA) lower axial welds for the AMP review, applicant is Item C6.1 for the (LAWs - two AMR items total) and CSBA requested to discuss and clarify CSBA MAWs middle axial welds (MAWs - two AMR which of the CSBA cylinder girth items total) welds (i.e., MGWs, LGWs, or MRP-227, MGWs and LGWs) will be the Rev. 1-A The AMR items on page 3.1-60 for the linked Primary-category welds for Table 4-5, CSBA MAWs and the CSBA LAWs the Expansion-category CSBA Item C6.2 for the cross-reference to SLRA Items 3.1-1, LAWs CSBA and for the CSBA LAWs 052b and 056b respectively, which Expansion-category MAWs under establishes the CSBA MAWs and LAWs the 80-Year version of the AMP.

as Expansion-category components for the AMP. In MRP-227, Rev. 1-A, the As part of the discussion, the CSBA MAWs and LAWs were applicant should explain how the designated as Expansion-category gap analysis-adjusted Primary-to-components for the CSBA middle girth Expansion category relationships welds (MGWs), which are maintained as for the Expansion-category CSBA Primary-category components for the MAWs and LAWs compare to AMP; however, in the SLRA Appendix C, those for the CSBA MAWs and the applicant has elevated the CSBA LAWs in Items C6.1 and C6.2 of lower girth welds from being Expansion- Table 4-5 in the MRP-227, Rev. 1-category components to being Primary A report.

category components for the 80-Year version of the AMP. Additionally, in light of the St.

Lucie operating experience with The applicant uses the *-based Notes on cracking of the St. Lucie Unit 1 page C C-9 to clarify which CSBA CSBA MAWs (year 2018 event cylinder girth welds will be the linked and year 2019 follow-up Primary-category components for the inspections of the MAWs), the CSBA MAWs and LAWs under the gap- applicant should be prepared to analysis adjusted program; The notes on discuss why the CSBA MAWs and pages C C-9 do not provide sufficient LAWs can remain as Expansion-information to clarify whether the CSBA category components for the 80-MGWs, the CSBA LGWs, or CSBA year version of the AMP.

MGWs and LGWs are the linked Primary components for the Expansion-category CSBA MAWs and LAWs.

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Question/Topic SLRA MRP-227, Rev. Background / Information Gap Discussion Topic / Outcome of Number Pages 1-A or MRP- Question or Request or Staff Discussion 2018-022 Table comments.

References 8 3.1-60; MRP-227, AMR Items (4 items): Core support No issues with the actual C C-9 Rev. 1-A, barrel assembly (CSBA) lower girth referenced AMR items. However, Table 4-2, welds (LGWs - two AMR items total) and for the AMP review, the applicant Item C6 for CSBA middle girth welds (MGWs - two is requested to discuss and CSBA MGWs AMR items total) identify the set of Expansion-category components that will MRP-227, The gap analysis maintains the CBSA constitute the Expansion-category Rev. 1-A, MGWs as Primary-category components components for the Primary Table 4-5, for the AMP. Additionally, in MRP-227, category CSBA MGWs and for the Item C5.1 for Rev. 1-A, the CSBA LGWs were newly elevated Primary-category CSBA LGWs designated as Expansion-category CSBA LGWs (e.g., the CSBA components for the 60-year based middle axial welds (MAWs), CSBA programs, with the CSBA upper flange lower axial welds (LAWs), lower welds (UFWs) being the linked Primary- support structure (LSS) core category components under Item C5 in support columns, and the fuel Table 4-2 of the report; however, on alignment plates, or any SLRA pages C C-9, the applicant combination of these Expansion elevates the EPRI MRP category for the category components).

CSBA LGWs from being Expansion-category components for the AMP to As part of the discussion, the being Primary-category components for applicant should explain how the the 80-Year version of the AMP. While gap analysis-adjusted Primary-to-the staff has issue with maintaining the Expansion category relationships CSBA MGWs as Primary-category for the CSBA MGWs and LGWs components and elevating the CSBA compare to those for the CSBA LGWs to Primary-category status, notes MGWs and LGWs in the MRP-on SLRA pages C C-9 do not have 227, Rev. 1-A report.

sufficient information to establish which set of Expansion-category components constitutes the Expansion-category components for the CSBA MGWs and for the CSBA LGWs under the 80-Year version of the AMP.

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 9 3.1-60; MRP-227, AMR Item: Core support barrel No issues with the AMR item.

C C-9 Rev. 1-A, assembly (CSBA) upper flanges welds Table 4-2, (UFWs) For the AMP and gap analysis Item C5 basis, the CSBA UFWs already The CSBA UFWs will remain as Primary- screen in for stress corrosion category components for the 80-Year cracking. The applicant is version of the AMP. In Item C5 of Table requested to clarify whether the 4.2 in the MRP-277, Rev. 1-A report, the 80-year project fluence for the linked Expansion-category components UFWs is high enough to screen for the Primary-category CSBA UFWs the CSBA UFWs in for irradiation-were designated as follows: (1) CSBA assisted stress corrosion cracking upper girth weld (UGW) per Item C5.2 in (IASCC) under the 80-Year the MRP report, (2) the CSBA lower girth version of the AMP.

weld/flange weld (LGW/LFW) per Item C5.1 in the MRP report, (3) the CSBA Additionally, for the AMP and the upper axial welds (UAWs) per Item C5.3 gap analysis, the applicant should in the MRP report, and (4) the core discuss the set of Expansion-support columns of the lower support category components that will structure per Item C6.3 in the MRP actually constitute the Expansion-report. category components for the Primary-category CSBA UFWs In the gap analysis of SLRA Appendix C under the 80-Year version of the and in the AMR items for the CSBA AMP. Why arent the changes in LGWs in SLRA Table 3.1.2-2, the the designated Expansion applicant has elevated the CSBA LGWs category components for the (LFWs) to Primary-category status, which CSBA UFWs reflected in SLRA from the staffs understanding, would Appendix C?

eliminate the CSBA LGW/LFW types as designated Expansion-link components for the CSBA UFWs; yet in the gap analysis the applicant does not define or not address in the changes in designated Expansion-link components for the Primary-category CSBA UFWs.

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Question/Topic SLRA MRP-227, Rev. Background / Information Gap Discussion Topic / Outcome of Number Pages 1-A or MRP- Question or Request or Staff Discussion 2018-022 Table comments.

References 10 3.1-61 MRP-227, AMR Items (two AMR items): Core No issues with the AMR item.

C C-10 Rev. 1-A, support barrel assembly (CSBA) upper Table 4-5, girth welds (UGWs) and upper axial For the AMP and gap analysis Item C5.2 for welds (UAWs) basis, the CSBA UGWs and CSBA UGWs UAWs already screen in for SCC The gap analysis in SLRA Appendix C and IE. The applicant is MRP-227, and the referenced AMR items for the requested to clarify whether the Rev. 1-A, CSBA UGWs and UAWs maintain the 80-year project fluence values for Table 4-5, Item C5.3 for CSBA UGWs and UAWs as Expansion the UGWs and UAWs are high CSBA UAWs category components for the Primary- enough to screen the CSBA category CSBA upper flange welds UGWs and UAWs in for (UFWs). Under the 60-year program, the irradiation-assisted stress CSBA UGWs and UAWs screen in for corrosion cracking (IASCC) under stress corrosion cracking (SCC) and the 80-Year version of the AMP.

neutron irradiation embrittlement (IE),

where if the need for Expansion Applicant to confirm that the 80-inspections of the UGWs and UAWs was year projected fluences are not triggered, the applicant would perform sufficiently high where the CSBA EVT-1 visual inspections of accessible UGWs or UAWs might otherwise UGW and UAW seams to look for visual need to be considered for evidence of cracking that might be elevation to Primary-category indicative of IE occurring in the weld components - that is to confirm seams. that the CBA UGWs and UAWs can remain as designated Expansion components for the Primary-category CSBA UFWs.

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 11 3.1-61 NA AMR Items (two AMR items): Core support barrel assembly (CSBA) expandable plugs and patches (Unit 1 Given the applicable plant-specific only) TLAA for St. Lucie Unit 1 CSBA expandable plugs and patches The SLRA includes one AMR line item in (i.e., SLRA Section 4.7.3), the SLRA Table 3.1.2-2 on management of applicant should define the EPRI cracking in the CSBA expandable plugs MRP inspection category and and patches using the PWR Vessel types of inspections that will be Internals Program and another AMR item applied to the referenced Unit 1 on managing loss of preload in the expandable plugs and patches. If expandable plugs/patches using the the plugs and patches are being TLAA defined for the components in placed in the Expansion-category SLRA Section 4.7.3, where the of the AMP, the applicant should applicable TLAA has been projected to define which Primary-category the end of the subsequent period of components will be considered to extended operation. be the lead component-specific indicators of aging for the The gap analysis in SLRA Appendix C Expansion-category CSBA does not really define the EPRI MRP expandable plugs and patches in inspection category and the type of Unit 1 and provide the acceptance inspections that will be applied to the criteria and expansion-link criteria CSBA expandable plugs and patches for for the applicable Primary-to-St. Lucie Unit 1 under the 80-year Expansion category inter-version of PWR Vessel Internals relationships.

Program (i.e., the SLR-based version of the AMP). Additionally, in light of the applicable operating experience and the applicable TLAA, the applicant should be prepared to explain why the Unit 1 CSBA expandable plugs and patches are not being addressed on a component-specific basis in SLRA Appendix C.

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Question/Topic SLRA MRP-227, Rev. Background / Information Gap Discussion Topic / Outcome of Number Pages 1-A or MRP- Question or Request or Staff Discussion 2018-022 Table comments.

References 12 3.1-61 MRP-227, AMR Item: Core support barrel For the AMP, my only question is -

Rev. 1-A, assembly (CSBA): core support barrel will the 72 EPFY fluence Table 4-2, flexure welds exposures for the core support Item C7 barrel flexure welds be high The core support barrel flexure welds enough to screen the welds in for were designated by the EPRI MRP as mechanisms of neutron irradiation Primary-category components for the 60- embrittlement (IE), irradiation-version of the PWR Vessel Internals assisted stress corrosion cracking Program, and will remain as Primary- (IASCC), or void swelling-category components for the 80-year distortion (VS-D)?

version of the AMP (with no designated Expansion-category components). The flexure welds screened in for the cracking mechanisms of stress corrosion cracking (SCC) and fatigue for the 60-year version of the AMP.

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Question/Topic SLRA MRP-227, Rev. Background / Information Gap Discussion Topic / Outcome of Number Pages 1-A or MRP- Question or Request or Staff Discussion 2018-022 Table comments.

References 13 3.1-61 MRP-227, AMR Items (two AMR items total):

Rev. 1-A, Lower support structure (LSS) core Table 4-5, support columns For the 80-year version of the Item C6.3 AMP, my main question is - are The LSS core support columns were the CSBA lower girth welds designated as Expansion-category (LGWs) additional Primary-components (with the linked Primary- category components for the LSS category component being cited as the core support columns (i.e., in core support barrel assembly [CSBA] addition to the CSBA MGWs as middle girth weld [MGW]) for the 60-year linked Primary-category version of the PWR Vessel Internals components) - if not, why not?

Program, and presumably will remain as The staffs question is based on its Expansion-category components for the current understanding that gap 80-year version of the AMP (with no analysis for the 80-year version of designated Expansion-category the AMP is elevating the CSBA components). For the 60-Year version of LGWs to Primary-category status the AMP, the LSS core support columns (i.e., from Expansion-category (made from cast austenitic stainless steel status for the CSBA LGWs under

[CASS] materials) screened in for the the 60-Year version of the AMP).

cracking mechanisms of stress corrosion cracking (SCC), irradiation-assisted Additionally, are the lower core stress corrosion cracking (IASCC) and support columns made from cast fatigue and the non-cracking austenitic stainless steel (CASS)?

mechanisms of neutron irradiation If so, based on the updated 80-embrittlement (IE) and thermal aging year gap analysis assessment do embrittlement (TE). they screen in for thermal aging embrittlement (i.e., TE in additional to IE)?

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Question/Topic SLRA MRP-227, Rev. Background / Information Gap Discussion Topic / Outcome of Number Pages 1-A or MRP- Question or Request or Staff Discussion 2018-022 Table comments.

References 14 3.1-61 MRP-227, AMR Items (two AMR items total): The AMR items are fine as long as Rev. 1-A, Lower support structure (LSS) core the LSS core support plates do Table 4-2, support plates screen in for additional non-Item C9 cracking effects. Are the 80-year The AMR table includes a line item on projected fluences for the core cracking and a line item on loss of support plates high enough where fracture toughness (LOFT) of the LSS the components would also screen core support plates. For the 80-Year- in for additional non-cracking based program, the LSS core support effects (i.e., in addition to LOFT),

plates remain as Primary-category such as for changes in dimension components for the AMP, with no due to void swelling or distortion designated/linked Expansion (CID/VS-D)? Additionally, are the components. For the 60-year basis, the combined 80-year projected core support plates screened in for fluences and stress loadings for fatigue and irradiation embrittlement (IE) the core support plates high mechanism. enough to screen the core support plates in for irradiation-assisted stress corrosion cracking (IASCC)?

15 3.1-62 NA for Welded AMR Items (two AMR items total): Why only Expansion category CE Core Shroud Upper internals assembly (UIA) fuel for the UIA fuel alignment plates?

Designs (like St. alignment plates Had the St. Lucie reactor internals Lucie) with Two been designed with welded core Vertical Shroud The UIA fuel alignment plates in the shrouds that utilize full height Sections upper internals assemblies are shroud plates, the fuel alignment designated as new Expansion-category plates would be designated as (In Contrast, for components for the program based on Primary category components for welded CE core the updated 80-year gap analysis basis the program per Item C10 in Table shroud designs for the fuel alignment plates in SLRA 4-2 of the MRP-227, Rev. 1-A

(#15 Cont.) that utilize full Appendix C. On SLRA page C-6, the fuel report.

height shroud alignment plates screen in (per MRP-2018-022) for the cracking mechanisms

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Question/Topic SLRA MRP-227, Rev. Background / Information Gap Discussion Topic / Outcome of Number Pages 1-A or MRP- Question or Request or Staff Discussion 2018-022 Table comments.

References plates, MRP- of irradiation-assisted stress corrosion The applicant should discuss the 227, cracking (IASCC) and fatigue and for the aspects of the St. Lucie unit-Rev. 1-A, non-cracking mechanisms of neutron specific core shroud and fuel Table 4-2, irradiation embrittlement (IE) and wear. alignment plate designs that would Item C10 - The SLR-based program links the allow the fuel alignment plates to which has the Expansion-criteria for the fuel alignment be placed in the Expansion-UIA fuel plates to the Primary-category EVT-1 category for the program and why alignment plate visual inspection that will be performed the linked Primary-category CSBA as a Primary- on the core support barrel assembly LGWs are expected to be lead category (CSBA) lower girth welds (LGWs). indicators for cracking and IE. As component; this part of this discussion, the is NA for St. applicant should also justify why Lucie design) the UIA fuel alignment plates at St.

Lucie are not considered to be as susceptible to cracking (or IE) when compared to and contrasted against the designs of UIA fuel alignment plates in U.S. CE-design PWRs that utilize welded core shrouds with full height shroud plates.

Additionally, the line item on page 3.1-62 for the UIA fuel alignment plates (as referenced to SLRA

(#15 Cont.) Table 1 Item 3.1-1, 119) links the applicable aging and degradation mechanism combinations as loss of material (LOM) due to wear and changes in dimension due to void swelling or distortion (CID/VS-D).

But page

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Question/Topic SLRA MRP-227, Rev. Background / Information Gap Discussion Topic / Outcome of Number Pages 1-A or MRP- Question or Request or Staff Discussion 2018-022 Table comments.

References C-6 has the non-cracking mechanism combinations and LOM due to wear and loss of fracture toughness due to irradiation embrittlement (LOFT/IE). So the applicant should discuss and reconcile the differences in the report non-cracking effect and mechanisms for the line item on page 3.1-62 and the corresponding line item on SLRA page C-6.

16 3.1-62 MRP-227, AMR Items (two AMR items total): Applicant to confirm that these are Rev. 1-A, Upper internals assembly (UIA) guide the guide lugs, guide lug inserts, Table 4-8, lugs, guide lug inserts, and bolts and bolts in the upper internals Items C13 and assembly and that the C14 components remain as Existing Program-category components for the AMP.

17 3.1-62 MRP-227, AMR Items (two AMR items total): Applicant to confirm that projected Rev. 1-A, Lower support structure (LSS) lower core 80-year fluence and stress load Table 4-5, support beams combinations are not high enough C5.4 to screen the support beams in for Remain as Expansion-category irradiation-assisted stress components for the AMP that are linked corrosion cracking (IASSC) and the EVT-1 inspections that will be that the 80-year projected fluences performed on the Primary-category for the support beams are not high CSBA upper flange weld (UFW); the enough to screen the support

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Question/Topic SLRA MRP-227, Rev. Background / Information Gap Discussion Topic / Outcome of Number Pages 1-A or MRP- Question or Request or Staff Discussion 2018-022 Table comments.

References support beams screen in for cracking beams in for loss of fracture mechanisms of stress corrosion cracking toughness due to irradiation (SCC) and fatigue. embrittlement (LOFT/IE).

18 3.1-62 MRP-227, AMR Items (two AMR items total): No questions on the AMP and Rev. 1-A, Lower support structure (LSS) fuel AMR bases for the Existing Table 4-8, alignment pins Program basis for the LSS fuel Items C15a and alignment pins C15b Remain as Existing Program-category components for the AMP; the fuel alignment pins screen in for cracking due to IASCC and fatigue; loss of material (LOM) due to wear, loss of fracture toughness due to irradiation embrittlement (LOFT/IE, and loss of preload due to irradiation-enhance stress relaxation or creep (LOP due to ISR/IC) 19 3.1-62, MRP-227, AMR Item: Core Element assembly No questions on the AMR or SLR 3.1-63 Rev. 1-A, (CEA) peripheral incore instrument (ICI) gap analysis-adjusted AMP bases Table 4-2, guide tubes (includes associated guide for these components.

Item C11 tube welds); CEA non-peripheral (remaining) ICI guide tubes MRP-227, Rev. 1-A, The CEA peripheral ICI guide tubes Table 4-5, remain as Primary-category components Item C11.1 for the AMP, with the corresponding ICI guide tubes in the non-peripheral (remaining) CEAs being the linked Expansion category components. The components screen in for cracking due to fatigue or stress corrosion cracking (SCC).

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Question/Topic SLRA MRP-227, Rev. Background / Information Gap Discussion Topic / Outcome of Number Pages 1-A or MRP- Question or Request or Staff Discussion 2018-022 Table comments.

References 20 3.1-63 NA; newly AMR Item: Welded core shroud No questions on the AMR or SLR assessed gap assembly (including seam welds) gap analysis-adjusted AMP bases analysis for these components.

component The weld seams between the upper and lower core shroud segments and between the lower core shroud segment and lower core support plate are newly designated Primary components for the gap analysis-adjusted AMP. These core shroud seam welds do not have any linked Expansion category components; the core shroud seam welds screen in for changes in dimension due to void swelling or distortion (CID/VS-D) and loss of fracture toughness due to irradiation embrittlement for the 80-year basis.

St. Lucie Nuclear Station SLRA: Breakout Questions - PWR Internals Review AMP: SLRA Appendix B, Section B2.3.7, Reactor Vessel Internals AMP FSAR Supplement: SLRA Appendix A, Section 19.2.2.7, Reactor Vessel Internals SLRA FSAR Supplement Commitment: SLRA UFSAR Supplement Table 19-3, Item 10 AMR Item Reference Table (Table 1s): Table 3.1.1 - Items 052a, 052b, 052c, 056a, 056b, 056c, 118 and 119 AMR Item Reference Table (Table 2s): Table 3.1.2 All AMR Items Referenced to AMP B2.3.7 Assigned Technical Review Package (TRP): #16 Question/Topic SLRA MRP-227, Rev. Background / Information Gap Discussion Topic / Outcome of Number Pages 1-A or MRP- Question or Request or Staff Discussion 2018-022 Table comments.

References

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