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Category:Meeting Summary
MONTHYEARML24004A0472024-01-31031 January 2024 U.S. Nuclear Regulatory Commission Summary of the November 16, 2023, Observation Public Meeting to Discuss NuScales Us600 Exemption Request ML20274A1082020-09-30030 September 2020 Summary of September 16, 2020 Public Meeting with NuScale Power, LLC to Discuss Operator Licensing Topics ML20216A5462020-08-19019 August 2020 Public Summary of the July 15, 2020 Pre-Submittal Meeting with NuScale, LLC, Regarding Its Plans to Submit a Topical Report Using Automated Test System ML20219A4112020-08-10010 August 2020 Summary of the May 28, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss Nuscale'S Standard Design Application Control Room Staffing Topical Report-0520-69851 ML20108F5082020-05-27027 May 2020 Summary of April 15 2020 Public Meeting on NuScale EPZ Sizing Methodology TR ML20114E2162020-05-0404 May 2020 Summary of the April 1, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution of the Design Certification Application ML20114E0192020-04-27027 April 2020 Summary of the April 15, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution of the Design Certification Application ML20114E0392020-04-23023 April 2020 Meeting Summary for the April 21, 2020, Public Meeting to Discuss NuScale SDA Significance Review Process ML20097C2292020-04-0707 April 2020 Summary of the March 9, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution ML20072M7982020-03-19019 March 2020 Meeting Summary for the January 30, 2020, Public Meeting to Discuss NuScale SDA Regulatory Engagement Plan ML20072K5232020-03-11011 March 2020 Summary of the September 4, 2019, Public Teleconference with NuScale Power, Llc., Regarding Responses to Staff Requests for Additional Information (RAI) (52-048) ML19345E9362020-01-13013 January 2020 Summary of the December 9, 2019, Public Teleconference Meeting on Incorporation by Reference ML19302E4602019-10-29029 October 2019 July 22, 2019 Public Meeting - NuScale Interface Items for Penetrations and Ventilation Ducts ML19297C8772019-10-24024 October 2019 Summary of Public Meeting with NuScale to Discuss ECCS Test #47 ML19291A8872019-10-21021 October 2019 U.S. Nuclear Regulatory Commission Summary Report of Regulatory Close-out Audit of NuScale Power, LLC, Component Design Specification ML19282B1202019-10-12012 October 2019 Summary of January 9, March 5, April and August 1, 2019, Public Teleconference with NuScale Power, LLC, Regarding NON-LOCA TR RAI Responses (PROJ0769) ML19289C3982019-10-12012 October 2019 Summary of the January 9, 2019, March 5, 2019, April 23, 2019, and August 12, 2019, Public Teleconferences with NuScale Power, LLC ML19281B3982019-10-10010 October 2019 Summary of September 23, 2019 - Public Teleconference on NuScale Chapter 4 ML19281B2612019-10-0909 October 2019 Sept 25, 2019 - Public Teleconference on NuScale SDA ML19260G7352019-10-0707 October 2019 Summary of Public Meeting with NuScale to Discuss Response to RAI 9681 ML19240A3892019-10-0303 October 2019 Summary of January 8 and 29, 2019 and April 17, 2019, Public Teleconference with NuScale Power, LLC, Regarding Responses to Staff Request for Additional Information (52-048) ML19256B7002019-09-23023 September 2019 Summary of Public Meeting with NuScale to Discuss Test #107 and Test #47 in the Initial Test Program ML19260G5382019-09-23023 September 2019 Summary of 9-4-19 Public Meeting with NuScale to Discuss ITAAC ML19256B4942019-09-18018 September 2019 Summary of Public Meeting with NuScale to Discuss Radiation Shielding ITAAC ML19247C0342019-09-18018 September 2019 Summary of August 26 2019 Public Meeting with NuScale on Chapter 20 ML19252A0212019-09-12012 September 2019 August 27, 2019, Summary of Public Meeting with NuScale to Discuss Test #6, Test #47, and Test #50 in the Initial Test Program ML19255D2722019-09-12012 September 2019 Aug 26, 2019, Summary of Public Teleconference on NuScale Chapter 4 ML19242B8092019-08-30030 August 2019 Discussion Topic for August 13 and August 19, 2019, Public Meeting to Discuss AST Methodology and H2 and O2 Monitoring for the NuScale Design Certification Application ML19242B8802019-08-30030 August 2019 Discussion Topic for July 24, 2019, Public Meeting to Discuss Technical Specifications for the NuScale Design Certification Application ML19242B9932019-08-30030 August 2019 Discussion Topic May 14, 2019, Public Meeting to Discuss Accident Source Term (AST) Methodology Associated with the NuScale Design Certification Application ML19242C0162019-08-30030 August 2019 Discussion Topic May 8, 2019, Public Meeting to Discuss Post-Accident Sampling Exemption Request Associated with the NuScale Design Certification Application ML19242C4792019-08-30030 August 2019 Discussion Topics for the March 12 2019 Public Meeting to Discuss Neutron Absorbers ITAAC and COL Information Item 9.1-8 Associated with the NuScale Design Certification Application ML19228A2502019-08-27027 August 2019 Summary of Public Meeting with NuScale to Discuss Structural ITAAC ML19217A3082019-08-15015 August 2019 Summary of Public Meeting with NuScale to Discuss Initial Test Program Test #107 for the Remote Shutdown Workstation ML19212A6882019-08-12012 August 2019 Summary of Public Meeting with NuScale to Discuss Structural ITAAC ML19199A0152019-07-31031 July 2019 Summary of Public Meeting on Various ITAAC Issues ML19149A5052019-07-22022 July 2019 May 22 2019 NRC-NuScale Public Meeting Summary_Reduced Staffing Plan Validation Activities ML19171A1292019-07-17017 July 2019 Summary of Category 1 Public Teleconference with NuScale Power, LLC to Discuss of Section 3.9.4 Control Rod Drive System of the Design Certification Application ML19134A3632019-07-0808 July 2019 Summary of the April 9, 2019 Public Meeting to Discuss Accident Source Term (AST) Methodology and Post Exemption Associated with the NuScale Design Certification Application ML19176A2502019-07-0808 July 2019 Summary of June 17, 2019 Public Meeting with NuScale on MBDBE ML19178A3502019-06-27027 June 2019 Discussion Topics for April 09, 2019 Public Meeting with NuScale - Public Version ML19242B9342019-06-12012 June 2019 Discussion Topic for June 12, 2019, Public Meeting to Discuss Technical Specifications for the NuScale Design Certification Application ML19151A3382019-06-0505 June 2019 Summary of Public Meeting with NuScale to Discuss ITAAC for the Module Protection System and Safety Display and Indication System ML19087A2402019-05-0606 May 2019 Summary of March 5, 2019 Public Meeting on NuScale EPZ Sizing Methodology TR ML19106A0452019-04-24024 April 2019 Summary of Public Teleconference Held April 15, 2019, Regarding the Inspections, Tests, Analyses, and Acceptance Criteria in NuScale Power Llc'S Design Certification Application ML18340A0132019-04-17017 April 2019 July 24, 2018, Summary of Category 1 Public Teleconference with Nuscale Power, LLC, Design Certification Application Section 3.7, Seismic Design, and 3.8, Design of Category I Structures. ML18348A9442019-04-17017 April 2019 Summary of the Category 1 Public Teleconference with NuScale Power, LLC Design Certification Application Section 3.6.3, Leak-Before-Break Evaluation Procedures, and Section 3.9.4, Control Rod Drive System. ML18333A3612019-04-11011 April 2019 & 08/28/18 Summary of Public Teleconference with Nuscale Power, LLC, Regarding Responses to Staff Requests for Additional Information ML19065A1242019-04-0505 April 2019 Summary of the February 14 and 27, 2019, Public Meeting to Discuss Accident Source Term (AST) Methodology Associated with the Nuscale Design Certification Application ML19085A0412019-03-26026 March 2019 02/13/2019 and 03/06/2019 Summary of Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Progress on Emergency Core Cooling System Valve Test Plans of the Design Certification Application 2024-01-31
[Table view] Category:Memoranda
MONTHYEARML24004A0472024-01-31031 January 2024 U.S. Nuclear Regulatory Commission Summary of the November 16, 2023, Observation Public Meeting to Discuss NuScales Us600 Exemption Request ML20274A1082020-09-30030 September 2020 Summary of September 16, 2020 Public Meeting with NuScale Power, LLC to Discuss Operator Licensing Topics ML20199M1492020-08-19019 August 2020 Memo Transmitting Summary of the July 15, 2020 Pre-Submittal Meeting with NuScale, LLC, Regarding Its Plans to Submit a Topical Report Using Automated Test System ML20219A4112020-08-10010 August 2020 Summary of the May 28, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss Nuscale'S Standard Design Application Control Room Staffing Topical Report-0520-69851 ML20210M0772020-07-28028 July 2020 Memo - Category 1 Public Meeting - Audit Exit NuScale Emergency Core Cooling System Boron Redistribution Issue and Applicable Design Changes ML20160A2472020-07-28028 July 2020 Audit Summary Memo NuScale ECCS Boron Redistribution Issue ML20176A1582020-07-10010 July 2020 Audit Summary 2019 Memo NuScale Chapter 15 ML20108F5082020-05-27027 May 2020 Summary of April 15 2020 Public Meeting on NuScale EPZ Sizing Methodology TR ML20140A1892020-05-19019 May 2020 Public Meeting Summary May 14, 2020, NuScale Boron Redistribution Issue ML20114E2162020-05-0404 May 2020 Summary of the April 1, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution of the Design Certification Application ML20114E0192020-04-27027 April 2020 Summary of the April 15, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution of the Design Certification Application ML20114E0392020-04-23023 April 2020 Meeting Summary for the April 21, 2020, Public Meeting to Discuss NuScale SDA Significance Review Process ML20097C2292020-04-0707 April 2020 Summary of the March 9, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution ML20072M7982020-03-19019 March 2020 Meeting Summary for the January 30, 2020, Public Meeting to Discuss NuScale SDA Regulatory Engagement Plan ML20076D8852020-03-16016 March 2020 Summary Report for the January 2019 Regulatory Audit of NuScale Chapter 20 ML20072K5232020-03-11011 March 2020 Summary of the September 4, 2019, Public Teleconference with NuScale Power, Llc., Regarding Responses to Staff Requests for Additional Information (RAI) (52-048) ML20059N6872020-03-0202 March 2020 Regulatory Audit Plan for NuScale DCA Chapters 6, 7, and 15 ML20054A0602020-02-28028 February 2020 Regulatory Audit Report for NuScale DCA Inadvertent Actuation Block (Iab) Operating Range Change ML20044E3522020-02-18018 February 2020 Memo to ACRS Rod Ejection Accident Methodology SER ML20049H1872020-02-18018 February 2020 Memo to ACRS Rea NON-LOCA TR SE ML20049H5442020-02-18018 February 2020 Letter to NuScale NON-LOCA TR SER ML20042E0242020-02-12012 February 2020 LOCA Topical Report Phase IV Audit Report - Public ML20042E0392020-02-12012 February 2020 NON-LOCA Topical Report Phases 3 and 4 Audit Report ML20010D1312020-01-16016 January 2020 Audit Summary Memo NuScale LOCA TR ML19345E9362020-01-13013 January 2020 Summary of the December 9, 2019, Public Teleconference Meeting on Incorporation by Reference ML19340A9712020-01-13013 January 2020 U.S. Nuclear Regulatory Commission Report of the Regulatory Follow-Up Audit Performed Between May 1, 2019, Through September 19, 2019, Regarding the Nuscale Stress and Fatigue Analysis of Major Design Components (Public) ML20006G4202020-01-0808 January 2020 ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapters 2, 8 and 12 ML19343C7562020-01-0808 January 2020 Generator Tube - Siet Audit Report (Public) ML20006G5752019-12-20020 December 2019 Proposed Recommendation for ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 8, Electric Power ML19331A3972019-12-20020 December 2019 U.S. Nuclear Regulatory Commission Report of the Regulatory follow-up Audit Performed Between 8/22/19 - 9/24/19, Regarding NuScale Power, Seismic Category I Equipment and Environment Qualification of Electrical Equipment Specifications ML19340A0152019-12-20020 December 2019 U.S. Nuclear Regulatory Commission'S Report of the Regulatory Audit Performed Between March 4, 2019, Through September 10, 2019, for Nuscale Power, LLC, Regarding Nuscale'S Power Module Leakage Flow Instability Analysis - Public Memo ML20006G4892019-12-19019 December 2019 Proposed Recommendation for ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 2, Site Characteristics and Site Parameters ML19340A0192019-12-19019 December 2019 U.S. Nuclear Regulatory Commission Report - Regulatory Audit Between 03/20/19 - 10/09/19 - Emergency Core Cooling System Valve Design Demonstration Testing and Follow-Up Items NuScale Power, LLC, Standard Plant Design Certification ML20006G7002019-12-19019 December 2019 Proposed Recommendation for ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 12, Radiation Protection ML19143A1042019-12-12012 December 2019 DCA - Safety Evaluation with No Open Items for Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors - Memo ML19168A1382019-12-12012 December 2019 LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 3, Design of Structures, Systems, Components and Equipment ML19169A2992019-12-11011 December 2019 Memo to ACRS Transmitting SER - Chapter 15 ML19169A1322019-12-10010 December 2019 Memo to ACRS Transmitting SER ML19165A2792019-12-0909 December 2019 Nuscale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 1, Introduction and General Discussion ML19168A1682019-12-0909 December 2019 Nuscale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 4, Reactor - Memo ML19168A2002019-12-0909 December 2019 Memo to ACRS Transmitting SER - Chapter 6 ML19169A3142019-12-0404 December 2019 LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 16, Technical Specifications - Memo ML19169A3322019-12-0404 December 2019 LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 20, Mitigation of Beyond-Design-Basis Events - Memo ML19169A2952019-11-26026 November 2019 Memo to ACRS Transmitting SER ML19319C2322019-11-26026 November 2019 U.S. Nuclear Regulatory Commission Summary Report of Regulatory follow-up Audit of Design Documents for NuScale Containment Isolation Valves and Reactor Safety Valves ML19270G6762019-11-22022 November 2019 Audit Summary for the Regulatory Audit of NuScale Power, LLC, Final Safety Analysis Report Chapter 15, Transient and Accident Analyses, (Memo) ML19169A2912019-11-22022 November 2019 Memo to ACRS Transmitting SER ML19169A1192019-11-22022 November 2019 Memo to ACRS Transmitting Phase 4 SER for Chapter 8 ML19162A2732019-11-15015 November 2019 LLC, Design Certification Application Memo - Safety Evaluation with No Open Items for Chapter 18, Human Factors Engineering ML19162A0962019-11-13013 November 2019 Nuscale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 2, Site Characteristics and Site Parameters 2024-01-31
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML20072K5232020-03-11011 March 2020 Summary of the September 4, 2019, Public Teleconference with NuScale Power, Llc., Regarding Responses to Staff Requests for Additional Information (RAI) (52-048) ML19038A5162019-02-0707 February 2019 LLC Supplemental Response to NRC Request for Additional Information No. 248 (Erai No. 9133) on the NuScale Design Certification Application ML19028A4132019-01-28028 January 2019 LLC Submittal of Supplemental Response to NRC Request for Additional Information No. 466 (Erai No. 9482) on the NuScale Design Certification Application ML18235A1372018-08-27027 August 2018 08/07 & 21/2018 Summary of Teleconference with NuScale Power, LLC to Discuss Staff Feedback on NuScale Response to Request for Additional Information Nos. 9394, 9399 and 9415 ML18082A7262018-04-0606 April 2018 Summary of the January 30, 2018, Category 1 Public Teleconference with Nuscale Power, LLC Design Certification Application Request for Additional Information Responses Nos. 9114, 8932, 8975, and 8963 ML18085A0722018-03-26026 March 2018 NRC Staff Questions for April 9, 2018 Public Meeting with NuScale on DCA Chapter 20 ML18044A1302018-02-27027 February 2018 Attachment C - Feedback on NuScale Response to RAI 9185 (003) 2020-03-11
[Table view] |
Text
April 6, 2018 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors FROM: Marieliz Vera, Project Manager /RA/
Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors
SUBJECT:
SUMMARY
OF THE JANUARY 30, 2018, CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION REQUEST FOR ADDITIONAL INFORMATION RESPONSES NOS. 9114, 8932, 8975, AND 8963 The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on January 30, 2018, to discuss the responses to NuScale Power, LLC (NuScale) Design Certification, Requests for Additional Information (RAI) Nos. 9114, 8932, 8975, and 8963, regarding Final Safety Analysis Report Tier 2, Chapter 3, Design of Structures, Systems, Components and Equipment. Participants included personnel from NuScale and no members of the public.
The public meeting notice can be found in the Agencywide Documents Access and Management Systems (ADAMS) under Accession No. ML18030A416. This meeting notice was also posted on the NRC public Website.
The meeting agenda and list of participants can be found in Enclosures 1 and 2, respectively.
Some of the technical issues discussed are included in Enclosure 3.
CONTACT: Marieliz Vera, NRO/DNRL 301-415-5861
S. Lee 2 Summary:
The purpose of this meeting was to discuss the RAI response for RAIs 9114 question 03.07.02-31 (ML17317B553), 8932 question 03.07.02-01 (ML17356A024), 8975 (ML17297B940), RAI 8963, Questions 03.08.05-7 and 03.08.05-12, (ML17290B267). The NRC staff discussed their feedback on responses to RAIs 9114, 8932, 8975, and 8963 (Enclosure 3) with NuScale. For RAI 8975 question 03.08.04-33, the feedback is pointing that the numbering on tables and figures referenced on the response are incorrect also the description for some models are missing from the tables. As a result of several RAI responses, NuScale has added and deleted tables and figures to their FSAR and the numbering has changed. NuScale will supplement the responses with the correct numbering and will add the descriptions that are missing. Because the review is ongoing, there are still possible changes to the numbering on tables and figures, if that happens NuScale will re-supplement the RAIs closer to the end of the review. NuScale will address the remaining feedbacks discussed on the meeting with a supplemental to the RAI response.
Docket No.52-048
Enclosures:
- 1. Meeting Agenda
- 2. List of Attendees
- 3. Comments presented by NRC staff cc w/encls.: DC NuScale Power, LLC Listserv
ML18044A908 *via email NRC002 OFFICE NRO/DNRL/LB1: PM NRO/DNRL/LB1: LA NRO/DNRL/LB1: PM NAME MVera MMoore MVera DATE 3/22/2018 4/02/2018 4/06/2018 U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION NOS. 9114, 8932, 8975, AND 8963 January 30, 2017 11:00 p.m. - 1:00 p.m.
AGENDA Public Meeting 11:00-11:10 Introductions and identification of topics 11:10-12:30 NuScale response to request for additional information (RAI) 9114, 8932, 8975, and 8963 discussion 12:30-12:40 Public comments 12:40-1:00 Closed portion Enclosure 1
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION NOS. 9114, 8932, 8975, AND 8963 LIST OF ATTENDEES January 30, 2018 NAME AFFILIATION Marieliz Vera U.S. Nuclear regulatory Commission (NRC)
Robert Roche NRC Sunwoo Park NRC Manas Chakravorty NRC Ata Istar NRC John Ma NRC Pravin Patel NRC Alissa Neuhausen NRC Vaughn Thomas NRC Marty Bryan NuScale Power, LLC (NuScale)
Josh Parker NuScale Jeremy Aatum NuScale Mohsen Azabakht NuScale Nick Brown NuScale Craig Harwood NuScale Giulio Flores NuScale Andre LEplattenier NuScale Hadi Razavi NuScale Evren Ulku NuScale Tom Ryan NuScale Kyra Perkins NuScale Kristen McKay NuScale Mohsin Khan ARES Enclosure 2
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION NOS. 9114, 8932, 8975, AND 8963 Staff Feedback on Request Additional for Information 9114 Question 03.07.02-31:
The U.S. Nuclear Regulatory Commission (NRC) staffs concern is the adequacy of the NuScale Power Module (NPM) beam model used in the SASSI2010 and SAP2000 RXB models. The staff wants to know how this NPM beam model was developed and validated with respect to the three-dimension (3D) NPM model. As part of its request for additional information (RAI) response, the applicant stated the following:
The NPM beam model shown in FSAR Tier 2, Figure 3.7.2-28, and described in Section 3.7.2.1.2.2, was created to have similar dynamic characteristics as the 3D model and is used in the analysis of the SAP2000 and SASSI2010 RXB models. To validate the NPM beam model, a modal analysis in three directions was performed in order to tune the simplified model to match the detailed 3D model response.
The NRC staff finds that the applicants response quoted above addresses the staffs concern.
However, the applicant did not provide any comparison of the dynamic characteristics between the simplified beam model and the 3D model that demonstrates the validity of the beam model.
Therefore, the applicant should provide a revised RAI response that includes only the relevant information to address the NRC staffs concern and a DCD markup that captures the main points of the RAI response and a table that summarizes a comparison of the dynamic characteristics between the NPM simplified beam model and the 3D model.
Based on above review, RAI 9114 Question 03.07.02-31 will be tracked as an Open Item and the applicant should address NRC staffs concern in its revised RAI response.
Staff Feedback on RAI 8932 Question 03.07.02-1:
The NRC staff reviewed the applicants response and identified the following issues that should be addressed by the applicant:
a) The NRC staff reviewed the sensitivity study included in the RAI response. The NRC staff noted that the applicant did not include any comparison of the ISRS obtained from a dynamic time history analysis using the NuScale ground motions. The applicant states that minor changes in the natural frequencies and mass participation ratios observed from the modal analysis indicates that other dynamic characteristics of the building models would not change by mesh refinement and therefore there is no need to study the effects of the mesh refinement on the SSI and ISRS. However, the NRC staff needs further technical justification for such a conclusion that demonstrates through Enclosure 3
comparison of the ISRS at key selected locations based on a dynamic analysis using the NuScale specific time histories. The NRC staff believes that changes in the properties of individual modes (natural frequencies, mass participation ratios) may be minor; however, their cumulative effect should be assessed by looking into actual dynamic responses, such as ISRS, under applicable ground motions.
b) In the mesh sensitivity study, the applicant indicates that the area elements are refined by breaking each element into four elements. The NRC staff understands the RXB and CRB models include not only area elements but also 1-D beam and 3-D solid elements.
Please clarify if these beam and solid elements are also refined and taken into account in the study.
c) Tables 4 and 19 in the RAI response present a comparison of dominant natural frequencies and corresponding mass participation ratios between the FSAR and refined mesh models for the RXB and CRB, respectively. The NRC staff notes, in Table 19, that the frequencies for the FSAR and refined mesh models for the CRB do not match closely for frequencies above 10.06 Hz. Please explain these discrepancies and its effect on the seismic demand (forces, moments, displacements, ISRS, etc.) computed based on the FSAR model.
d) The proposed markup included in the RAI response should be updated to reflect applicants supplemental or revised response, as necessary.
Based on above review, RAI 8932, Question 03.07.02-1 will be tracked as an Open Item and the applicant should address NRC staffs concern in its supplemental or revised RAI response.
Staff Feedback on RAI 8975 Question 03.08.04-29:
In its response, the applicant describes that the pressure difference between the ANSYS and SASSI2010 analysis results is accounted for in the SAP2000 by amplifying the gravity load.
FSAR Section 3.7.2.1.2.4 appears to indicate that the way such pressure difference is accounted for in SAP2000 is addressed differently for the horizontal and vertical directions.
Therefore, the NRC staff request the applicant to clarify, whether the gravity load amplification applies only to the vertical loading or both the horizontal and vertical loading.
Additionally, in its response the applicant stated the mass sources from FSAR Table 3.8.4-7 that were considered in the ANSYS models. Consistent with DSRS Section 3.7.2.II.3D, in addition to the structural mass, the models used for dynamic analysis should include a floor load of 50 pound per square foot (psf) to represent miscellaneous dead weights such as minor equipment, piping, and raceways. The NRC staff request the applicant to clarify whether such floor load was included in the ANSYS models. If not, the NRC staff request the applicant provide the technical justification for excluding such load. Also the applicant is requested to clarify whether either the ANSYS model for FSI or pool water sloshing is used for the nonlinear stability evaluation addressed in FSAR Section 3.8.5. If either model is used, the NRC staff request the applicant to provide the technical justification for excluding any of the mass sources in Table 3.8.4-7. If not, the NRC staff request the applicant to describe the differences between the model(s) used for the nonlinear stability evaluation and the aforementioned models and to describe the applicable mass sources for the model(s) used in the nonlinear stability evaluation.
This question will be tracked as Open Item.
Enclosure 3
Question 03.08.04-31:
In its response the applicant clarified that the seismic demands for the design of the NPM passive support ring assembly is obtained from the detailed ANSYS seismic analysis of the NPM. The applicant described the ANSYS analysis cases considered, provided the vertical and lateral load, and the vertical NPM displacement, consistent with the results from the ANSYS analyses. Further the applicant provided FSAR markups for Appendix 3B with updated descriptions and design information. For consistency in the FSAR and technical report, the NRC staff request the applicant to address the updated information regarding the NPM passive support ring assembly in other sections of the FSAR (e.g. Section 3.8.2.1.3, Section 19.1.5.1.1.3, other, as applicable) and supporting technical report, as applicable.
This question will be tracked as Open Item.
Question 03.08.04-32:
In its response, the applicant provided FSAR markups to replace references to Figures 3B-63 and 3B-64 with references to Figure 3B-51. For consistency between text descriptions in Section 3B.2.7.4.1 and Figure 3B-51, the NRC staff request the applicant to include a cross-sectional detail of the bay wall (including the shear lugs and through bolts) in Figure 3B-51.
This question will be tracked as Open Item.
Question 03.08.04-33:
A number of items in the proposed Table 3.7.2-35 need of clarification. For example, some of the Figures referenced in row items 2, 3, 4, and 5, are not consistent with the current figures in the FSAR Rev. 0 (e.g. figure numbers appear to be off by one). Also, the figures under column heading FSAR Results for row item 3 appear to reference FSAR figures that are specific to soil Type 7 whereas the table item 3 indicates the consideration of all soil profiles. Row items 6, 7, and 8, are for the RXB Base Mat - Partial Model, however, the NRC staff did not find a description of the partial basemat model in the FSAR Sections referenced under the column heading FSAR Explanation and Figures. Row items 10 and 11, related to the CRB Stand-Alone Building, reference Tables 3B-28 through 51 under the column heading FSAR Results, however Tables 3B-50 and -51 are for the RXB. In addition, the proposed Table 3.7.2-35 did not include a description of the RFT models and analyses. Based on the above the staff request the applicant to review and update the Table 3.7.2-35 and or FSAR descriptions to ensure consistency between the Table and FSAR descriptions. Such review and update should be performed considering the resolution of the questions related to FSAR Sections 3.7 and 3.8 and respective incorporation of FSAR markups into the FSAR.
This will be tracked as an Open Item.
Question 03.08.04-34:
In its response, the applicant provided updated Tables for Appendix 3B with highlighted table entries, consistent with FSAR text descriptions. The NRC staff review noted that some Appendix B Tables were not updated. For consistency in the response and FSAR, the NRC staff request the applicant to update Table 3B-29, Summary of D/C Ratios for Control Building Wall at Grid Line 4, and Table 3B-42, Summary of D/C Ratios for Control Building Slab at EL.
100'-0."
This question will be tracked as Open Item.
Enclosure 3
Staff Feedback on RAI 8963 Question 03.08.05-7:
In its response, the applicant provided the basis for the surcharge pressure of 0.25 ksf as that the most critical of either a minimum surcharge outside and adjacent to a subsurface wall due to wheel load converted to lateral equivalent or a railroad surcharge.
However, it appears that the applicant did not consider the potential differences in surcharge pressures on the walls of RXB and CRB due to the effects of adjacent buildings. Therefore, the applicant is requested to describe why the differences in surcharge pressures due to the effects of adjacent buildings were not determined/considered.
NOTES:
1- if there is a difference in surcharge pressures on the walls of RXB and CRB due to the effects of adjacent buildings that difference may need to be considered in the stability evaluations for the RXB and CRB also.
2- In deeply embedded structures, the surcharge-pressure loadings may have substantial contribution in the design of basemats.
Question 03.08.05-12:
In its response the applicant provided two tables (Tables 1 and 2) describing Building Models and Basemat Model of RXB Basemat designs.
The applicant concluded that there is no impact to the FSAR in their response. However, the applicants response provides information that should have been included (as markups) in Section 3.8.5.4.1.2, RXB Basemat Model Description, of the FSAR, to describe the models used for the RXB basemat designs. Furthermore, the NRC staff is requesting the applicant to respond the following questions:
- 1. It is not clear to the NRC staff whether deleting and restraining elements 10 feet (ft.)
above the RXB basemat would provide critical flexural stiffness that would provide conservative results for the design of the RXB basemat. Therefore, sensitivity evaluation(s) may need to be performed -- unless otherwise, restraining the elements 10 ft. above the basemat can be justified to produce the worst boundary condition.
- 2. It is not clear to the NRC staff how the external loads considered in the design of RXB basemat (e.g.; walls), since all structural components 10 ft. above the basemat were deleted.
- 3. Is the CRB basemat model constructed in a similar fashion? If so, the applicant is requested to describe the CRB basemat Model in detail.
Enclosure 3