11/07/2017, Summary of Teleconference with Nuscale Power, LLC Design Certification Application Request for Additional Information Responses for Questions 8928, 8932, 8936, 8933 and 8935 for Chapter 3, Section 3.7.2, and 3.7.3ML18039A611 |
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NuScale |
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Vera M NRC/NRO/DNRL/LB1 |
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Samson Lee NRC/NRO/DNRL/LB1 |
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Vera M |
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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] |
Text
February 20, 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 NO VEMBER 7, 2017, CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION REQUESTS FOR ADDITIONAL INFORMATION RESPONSES FOR QUESTIONS 8928, 8932, 8936, 8933 AND 8935 FOR CHAPTER 3, SECTION 3.7.2, "SEISMIC SYSTEM ANALYSIS, " AND 3.7.3, "SEISMIC SUBSYSTEM ANALYSIS"
The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on November 7, 2017, to discuss the NuScale Power, LLC (NuScale) Design Certification, request for additional information (RAI) responses to RAI Questions 8928, 8932, 8936, 8934, 8933, and 8935 for Chapter 3, Section 3.7.2, "Seismic System Analysis," and 3.7.3, "Seismic Subsystem
Analysis."
Participants included personnel from NuScale and members of the public.
The public meeting notice can be found in the Agencywide Documents Access and Management Systems under Accession No.
ML17292A956. 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. 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 RAI response 8928 (ML17276B458), 8932 (ML17271A239), 8936 (ML17276B886), 8933 (ML17277A312) and 8935 (ML17279B156). The
NRC staff discussed the feedback for RAI 8928 and recognized that some questions might be answered on RAI 9160 (ML17307A096), issued November 1, 2017. The NRC staff will decide on a course of action after receiving the response for RAI 9160. RAI Questions 3.9.4-1, 3.9.4-2, 3.9.4-4 will be addressed by NuScale with supplemental RAI responses. A discussion on the response to Question 3.7.2-9 will be sent to NuScale as a follow up RAI.
No comments from members of the public were received.
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
ML *via email NRC002 OFFICE NRO/DNRL/LB1: PM NRO/DNRL/LB1: LA NRO/DNRL/LB1: PM NAME Mvera MMoore MVera DATE 2/08/2018 2/16/2018 12/20/2018 Enclosure 1 U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION REQUEST FOR ADDITIONAL INFORMATION RESPONSES 8928, 8932, 8936, 8933, AND 8935 FOR CHAPTER 3, SECTIONS 3.7.2, "SEISMIC SYSTEM ANALYSIS," AND 3.7.3, "SEISMIC SUBSYSTEM ANALYSIS" November 7, 2017 1:00 p.m. - 2:00 p.m.
AGENDA Public Meeting 1:00-1:10 Introductions and identification of topics 1:10-1:50 Discussion of the Request for Additional Information Responses 8928, 8932, 8936, 8933, and 8935 1:50-2:00 Public - Questions and Comments
Enclosure 2 U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION REQUEST FOR ADDITIONAL INFORMATION RESPONSES 8928, 8932, 8936, 8933, AND 8935 CHAPTER 3, SECTION 3.7.2, "SEISMIC SYSTEM ANALYSIS," AND 3.7.3, "SEISMIC SUBSYSTEM ANALYSIS" LIST OF ATTENDEES November 7, 2017 NAME AFFILIATION Marieliz Vera U.S. Nuclear regulatory Commission (NRC)
Manas Chakravorty NRC Robert Roche NRC Pravin Patel NRC Vaughn Tomas NRC Kyra Perkins NuScale Power, LLC (NuScale) Josh Parker NuScale Marty Bryan NuScale Jennie Wike NuScale Tom Ryan NuScale Nicholas Brown NuScale Jeremy Aartun NuScale Mohsen Azadbakht NuScale Giulio Leon Flores NuScale Andre L'Eplattenier NuScale Pat Davis Public Sarah Fields Public 1 Enclosure 3 U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION REQUEST FOR ADDITIONAL INFORMATION RESPONSES 8928, 8932, 8936, 8933, AND 8935 REGARDING CHAPTER 3, SECTION 3.7.2, "SEISMIC SYSTEM ANALYSIS," AND 3.7.3, "SEISMIC SUBSYSTEM ANALYSIS" November 7, 2017 Request of Additional Information No. 8928 RAI 03.07.03-2:
The U.S. Nuclear Regulatory Commission (NRC) staff evaluated the NuScale Power, LLC (NuScale) response to RAI 8928, Question 03.07.03-2 and concluded that response is inadequate. The staff disagree with the classification of the bioshield. The staff requested addition information in RAI 9160 related to bioshield classification, design function, and detailing. Upon discussion and resolution of the RAI 9160, this RAI will be addressed. The bioshield classification will determine use of Chapter J of American Institute of Steel Construction (AISC) 360 code for welded connections.
RAI 03.07.03-3:
The NRC staff evaluated NuScale's response to RAI 8928, Question 03.07.03-3 and concluded that response is inadequate. The NRC staff disagree with the response that states, "there is no impact to the FSAR as a result of the RAI response." The applicant should include critical information of the bioshield design such as member, member properties, welds, blowout panel design etc., in the final safety analysis report (FSAR). The staff has issued RAI 9160 related to bioshield design.
RAI 03.07.03-4:
The staff evaluated NuScale's response to RAI 8928, Question 03.07.03-3 and concluded that the following response is inadequate:
a) The bolt classification will be determine based on the RAI 9160 resolution. In addition bolt capacity vs demand for seismic II/I should be discuss in FSAR.
b) Bolt spacing is described. However, missing bolts edge distance, bolt torque and how the bolts would be secured when bioshied stacked on top the adjacent NPM.
The staff request to show details in the FSAR. The resolution of the RAI 9160 will determine what additional detail required. The staff need sketch or add additional detail on FSAR figure showed on Tier 2 page 3.7-366.
Note: Instructure Response Spectra is missing for CSDRS-HF. See Page 3.7-368 that have to be included in FSAR. This was discussed at the public meeting.
2 The NRC staff disagree with the response that states "there is no impact to the FSAR as a result of the RAI response." The FSAR requires revision.
RAI 03.07.03-5:
The NRC staff reviewed the applicant response dated October 3, 2017, and found it to be acceptable. The reactor building cooling removal from the FSAR Section 3.7.3, Section 3.8.4.1.13 and FSAR Tier 2, Tables 3.7.3-1 through 3.7.3-7 is acceptable for the same reason as discussed in the staff review of the RAI 03.07.03-1. Thus, this item will be tracked as a confirmatory item pending the update to the next revision of the FSAR.
RAI No. 8932 RAI 03.07.02-2:
The NRC staff evaluated the applicant's response and overall, considered the response to be adequate. However, the NRC staff finds the applicant did not provide any markup that will augment the FSAR with the information provi ded in applicant's RAI response. The NRC staff believes it is necessary that the RAI response be summarized and included in the FSAR explaining the basis of concluding that coarse finite elements in the Reactor Building (RXB) and Control Building (CRB) models do not negatively affect the wave passage frequencies and thus no impact on seismic demand results. Thus, the applicant is requested to address staff's concern in a supplemental or revised RAI response. Based on the review above, RAI 8932, Question 03.07.02-2 will be tracked as an Open Item.
RAI 03.07.02-3:
The NRC staff reviewed the applicant response and concluded the following:
Part (a) - the NRC staff considered the applicant response to be acceptable.
Part (b) & (c) - overall the NRC staff considered the response to be acceptable. However, as the applicant acknowledged in the RAI response, there are certain exceptions (e.g., Table 3.7.2-19 shows a cut-off frequency of 72 hertz (Hz) for Soil Type 7 with the CSDRS; Table 3.7.2-21 shows a cut-off frequency of 52 Hz for Soil Type 9 with the CSDRS-HF). The applicant did not provide any markup to revise the FSAR to clarify these discrepancies. Therefore, the applicant is requested to revise the FSAR to address the identified inconsistencies.
Part (d) - the staff considered the response to be acceptable because the applicant added a legend to the figure that clarifies the confusion the staff pointed out. However, the staff further identified that the SASSI2010 triple building model in Figure 3.7.2-67 also needs a similar legend.
Based on the review above, RAI 8932 Question 03.07.02-3 will be tracked as an Open Item and the applicant should address staff's concern in a supplemental or revised RAI response.
RAI No. 8936 RAI 03.07.02-9:
3 The staff reviewed the applicant's approach provided in response to RAI 8936, Question 03.07.02-9, dated October 3, 2017 (ML17276B886) to address the accidental torsion by increasing the horizontal element forces by 5 percent in lieu of increasing the eccentricity by 5 percent as stated in the DSRS 3.7.2. The staff finds that the response contains insufficient basis for the assumption that increasing the horizontal element forces by 5 percent is equivalent to increasing the eccentricity by 5 percent and its applicability to the global floor level that involves the story shear and 5 percent of the floor plan dimension as the eccentricity.
Therefore, the applicant is requested to demonstrate through quantitative illustrative examples that its approach is equivalent to or more conservative than one that follows the DSRS.
Based on the review above, RAI 8936, Question 03.07.02-9 will be tracked as an Open Item and the applicant should address staff's concern in a supplemental or revised RAI response.
RAI No. 8933 03.07.02-19:
The NRC staff reviewed the applicant's response and found it to be acceptable. However, the applicant did not propose to augment the FSAR by adding the information provided in the RAI response. The NRC staff believes that information provided should be included in the FSAR for appropriate description of the models used in seismic demand calculations. Therefore the applicant is requested to revise the FSAR to include applicable information provided in this RAI response. Accordingly, RAI 8933, Question 03.07.02-19 will be tracked as an Open Item pending the applicant's update to the staff's concern in a supplemental or revised RAI response.
RAI 03.07.02-20:
The staff reviewed the applicant's response and concluded the following:
Part (a) - The NRC staff's review of this portion of the RAI response finds that the applicant adequately address the staff's concern. However, the staff needs to confirm and verify applicant's calculations of NPM lift-off and the floor support design for potential NPM impact loading through an audit.
Further, the NRC staff could not verify the descriptions of the structural elements comprising the NPM floor support design contained in the RAI response against FSAR Figures 3B-48 to 3B-50. Therefore the NRC staff requests the applicant to describe the NPM floor support design along with supporting Figures and provide such Figures in the response and FSAR, and provide FSAR markups as applicable.
Part (b) - The NRC staff finds the applicant's response adequately addressed staff's question and thus is acceptable. However, the applicant did not propose to include the tables showing the interface boundary conditions in the FSAR. The NRC staff believes that the tables should be included for adequate description of the models involved in seismic demand calculations. Therefore, the applicant is requested to augment the FSAR by including the two tables (Table 1 and Table 2) provided in the RAI response. Thus, RAI 8933, Question 03.07.02-20 will be tracked as an Open Item.
4 RAI No. 8935 RAI 03.07.02-24:
The NRC staff reviewed the applicant's response and concluded that the applicant needs to provide further clarification. In the RAI response and the associated FSAR markup, the applicant indicated that, while the RXB and CRB are designed for both the CSDRS and CSDRS-HF, other Category I SSCs are designed only for the CSDRS. The staff believes that this clarification should also be included in the FSAR Tier 1, Table 5.0-1. The applicant should also provide the definition of the term, "safe shutdown earthquake (SSE)" used in the FSAR Tier 1 document (e.g., Sections 2.8, 3.14.1, etc.) and clarify the basis of the "design basis seismic loads" (i.e., based on both the CSDRS and CSDRS-HF or only the CSDRS) for applicable
SSCs.
Accordingly, RAI 8935, Question 03.07.02-24 will be tracked as an Open Item pending the applicant's update to the NRC staff's concern in a supplemental or revised RAI response.