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{{#Wiki_filter:/RA/  
{{#Wiki_filter:November 7, 2018 MEMORANDUM TO:                Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors FROM:                          Marieliz Vera, Project Manager    /RA/
Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors


Note that in the legends of the figures, "X/SV" means the X-response due to SV-wave input; "X/P" means the X-response due to P-wave input; "Y/SH" means the Y-response due to SH-wave input; etc.}}
==SUBJECT:==
 
==SUMMARY==
OF THE OCTOBER 16, 2018, CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC REGARDING DESIGN CERTIFICATION APPLICATION SECTIONS 3.7, "SEISMIC DESIGN," AND 3.8, "DESIGN OF CATEGORY I STRUCTURES" The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on October 16, 2018, to discuss Final Safety Analysis Report (FSAR) Tier 2, Chapter 3, Design of Structures, Systems, Components and Equipment, Sections 3.7, Seismic Design, and 3.8, Designs of Category I Structures, of the NuScale Power, LLC (NuScale) Design Certification Application. 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. ML18284A484. 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/DLSE 301-415-5861
 
S. Lee                                          2 Summary:
The purpose of this meeting was to discuss the responses for Request for Additional Information (RAI) No. 8935, Question 03.07.02-23 (ML18241A398) and NuScale Power, LLC -
Submittal of Response to Request for Additional Information (RAls) on NuScale Closure Plan for Final Safety Analysis Report, Tier 2, Sections 3.7 and 3.8 (ML18302A408).
For RAI No. 8935 the applicant will provide a supplement to the RAI response reflecting the NRC staffs feedback (Enclosure 3).
From the closure plan the items discussed were Item No. 16, RAI No. 8838. The NRC staff asked for the schedule and NuScale will have the schedule November 15, 2018. Also from that item, the NRC staff asked for any dependencies between the NuScale Power Module (NPM) and the Flange Tool (RFT). NuScale will clarify the question during a follow-up meeting. The second item discussed from the Closure Plan is Item No. 13, RAI No. 8911, which NuScale asked for written feedback so they can assure the response covers all the NRC staffs concerns.
Docket No. 52-048
 
==Enclosures:==
: 1. Meeting Agenda
: 2. List of Attendees
: 3. RAI Technical Issues Summary cc w/encls.: DC NuScale Power, LLC Listserv
 
ML18306A770                *via email        NRC-002 OFFICE NRO/DLSE/LB1: PM          NRO/DLSE/LB1: LA      NRO/DNRL/LB1: PM NAME      MVera                MMoore                MVera DATE      11/02/2018            11/05/2018            11/07/2018
 
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC REGARDING DESIGN CERTIFICATION APPLICATION SECTIONS 3.7, "SEISMIC DESIGN,"
AND 3.8, "DESIGN OF CATEGORY I STRUCTURES" October 16, 2018 10:30 p.m. - 12:00 p.m.
AGENDA Public Meeting 10:30-10:35am          Welcome and Introductions 10:35-11:55am          Discussion of the Request for Additional Information 11:55-12:00pm          Public - Questions and Comments Enclosure 1
 
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC REGARDING DESIGN CERTIFICATION APPLICATION SECTIONS 3.7, "SEISMIC DESIGN," AND 3.8, "DESIGN OF CATEGORY I STRUCTURES" LIST OF ATTENDEES October 16, 2018 NAME                              AFFILIATION Marieliz Vera                    U.S. Nuclear regulatory Commission (NRC)
Manas Chakravorty                NRC Sunwoo Park                      NRC Robert Roche                      NRC Vaughn Thomas                    NRC Marty Bryan                      NuScale Power, LLC (NuScale)
Josh Parker                      NuScale Wayne Massie                      NuScale John Conly                        NuScale Tom Ryan                          NuScale Evren Ulku                        NuScale Hadi Razavi                      NuScale Steven Shaw                      NuScale Mohsin Khan                      NuScale Kyra Perkins                      NuScale Sarah Fields                      Public Enclosure 2
 
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC REGARDING DESIGN CERTIFICATION APPLICATION SECTIONS 3.7, "SEISMIC DESIGN," AND 3.8, "DESIGN OF CATEGORY I STRUCTURES" Staff Feedback on Request Additional for Information No. 8935 Question 03.07.02-23 (Response dated August 29, 2018)
: 1) In NUREG/CR-6896, Assessment of Seismic Analysis Methodologies for Deeply Embedded Nuclear Power Plant Structures (Agencywide Documents and Access Management System Accession No. ML060820521), the U.S. Nuclear Regular Commission (NRC) staff notes that non-vertically propagating SH-waves increase torsional responses of embedded structures. However, applicants request for additional information (RAI) response did not include analysis involving non-vertically propagating SH-waves. The NRC staff also notes that American Society of Civil Engineers 4-16, Seismic Analysis of Safety-Related Nuclear Structures, provides a guideline that accidental torsion be considered to address the effects of non-vertically propagating waves. Therefore, the applicant is requested to provide an evaluation of potential impact of inclined SH-waves on torsional responses of the Reactor Building (RXB) and discuss if any additional torsional responses from inclined SH-waves can be covered by the provision of accidental torsion in NuScale Power, LLC (NuScale) Final Safety Analysis Report (FSAR) Section 3.7.2.11 Method Used to Account for Torsional Effects.
: 2) According to the literature (e.g., Dynamic Soil Structure Interaction, by Wolf, 1985,) an incident P-wave will always lead to reflected P- and SV-waves. Likewise, an incident SV-wave will always lead to a reflected SV-wave but a reflected P-wave does not exist for a sufficiently shallow incident SV-wave. The limiting angle of incidence of the SV-wave, for which a reflected P-wave still arises, is called the critical angle of incidence and is dependent on the Poissons ratio of the soil. Please clarify if the critical angle of incidence was considered in NuScales study and, if not, provide an explanation for not doing so.
: 3) The NRC staff believes that a Combined License (COL) Item should be added to NuScale Design Control Document (DCD) that requires a COL applicant that references NuScale DCD should perform a site-specific evaluation of the effects of non-vertically propagating seismic waves on the free-field ground motions and seismic responses of seismic Category I structures, systems, and components.
Enclosure 3
: 4) In proposed FSAR markup (for Page 3.7-118, Draft Revision 2) provided in the RAI response, the applicant states, Note that in the legends of the figures, X/SV means the X-response due to SV-wave input; X/P means the X-response due to P-wave input; Y/SH means the Y-response due to SH-wave input; etc.
However, the NRC staff finds that a legend including Y/SH is not present anywhere in the RAI response. Please clarify.
: 5) In proposed markup for Figure 3.7.2-154 Non-Vertically Propagating Seismic Wave Sensitivity Study for the RXB -Uncombined North-South (Y) ISRS, Node 3996, Top of Basemat, NW Corner, Capitola Input, ISRS in the Y (North-South) direction is presented. The NRC staff understands that inclined SV or P-waves produce ground motions in the X-Z plane. Please clarify if ground motions in the Y direction shown in Figure 3.7.2-154 are produced by inclined SH-waves.
                                            }}

Revision as of 12:19, 20 October 2019

October 16, 2018, Summary of the Category 1 Public Teleconference with Nuscale Power, LLC Design Certification Application Section 3.7, Seismic Design, and 3.8, Design of Category I Structures.
ML18306A770
Person / Time
Site: NuScale
Issue date: 11/07/2018
From: Vera M
NRC/NRO/DLSE/LB1
To: Samson Lee
NRC/NRO/DLSE/LB1
Vera A M/NRO/415-5861
References
Download: ML18306A770 (7)


Text

November 7, 2018 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors FROM: Marieliz Vera, Project Manager /RA/

Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors

SUBJECT:

SUMMARY

OF THE OCTOBER 16, 2018, CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC REGARDING DESIGN CERTIFICATION APPLICATION SECTIONS 3.7, "SEISMIC DESIGN," AND 3.8, "DESIGN OF CATEGORY I STRUCTURES" The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on October 16, 2018, to discuss Final Safety Analysis Report (FSAR) Tier 2, Chapter 3, Design of Structures, Systems, Components and Equipment, Sections 3.7, Seismic Design, and 3.8, Designs of Category I Structures, of the NuScale Power, LLC (NuScale) Design Certification Application. 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. ML18284A484. 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/DLSE 301-415-5861

S. Lee 2 Summary:

The purpose of this meeting was to discuss the responses for Request for Additional Information (RAI) No. 8935, Question 03.07.02-23 (ML18241A398) and NuScale Power, LLC -

Submittal of Response to Request for Additional Information (RAls) on NuScale Closure Plan for Final Safety Analysis Report, Tier 2, Sections 3.7 and 3.8 (ML18302A408).

For RAI No. 8935 the applicant will provide a supplement to the RAI response reflecting the NRC staffs feedback (Enclosure 3).

From the closure plan the items discussed were Item No. 16, RAI No. 8838. The NRC staff asked for the schedule and NuScale will have the schedule November 15, 2018. Also from that item, the NRC staff asked for any dependencies between the NuScale Power Module (NPM) and the Flange Tool (RFT). NuScale will clarify the question during a follow-up meeting. The second item discussed from the Closure Plan is Item No. 13, RAI No. 8911, which NuScale asked for written feedback so they can assure the response covers all the NRC staffs concerns.

Docket No.52-048

Enclosures:

1. Meeting Agenda
2. List of Attendees
3. RAI Technical Issues Summary cc w/encls.: DC NuScale Power, LLC Listserv

ML18306A770 *via email NRC-002 OFFICE NRO/DLSE/LB1: PM NRO/DLSE/LB1: LA NRO/DNRL/LB1: PM NAME MVera MMoore MVera DATE 11/02/2018 11/05/2018 11/07/2018

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC REGARDING DESIGN CERTIFICATION APPLICATION SECTIONS 3.7, "SEISMIC DESIGN,"

AND 3.8, "DESIGN OF CATEGORY I STRUCTURES" October 16, 2018 10:30 p.m. - 12:00 p.m.

AGENDA Public Meeting 10:30-10:35am Welcome and Introductions 10:35-11:55am Discussion of the Request for Additional Information 11:55-12:00pm Public - Questions and Comments Enclosure 1

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC REGARDING DESIGN CERTIFICATION APPLICATION SECTIONS 3.7, "SEISMIC DESIGN," AND 3.8, "DESIGN OF CATEGORY I STRUCTURES" LIST OF ATTENDEES October 16, 2018 NAME AFFILIATION Marieliz Vera U.S. Nuclear regulatory Commission (NRC)

Manas Chakravorty NRC Sunwoo Park NRC Robert Roche NRC Vaughn Thomas NRC Marty Bryan NuScale Power, LLC (NuScale)

Josh Parker NuScale Wayne Massie NuScale John Conly NuScale Tom Ryan NuScale Evren Ulku NuScale Hadi Razavi NuScale Steven Shaw NuScale Mohsin Khan NuScale Kyra Perkins NuScale Sarah Fields Public Enclosure 2

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC REGARDING DESIGN CERTIFICATION APPLICATION SECTIONS 3.7, "SEISMIC DESIGN," AND 3.8, "DESIGN OF CATEGORY I STRUCTURES" Staff Feedback on Request Additional for Information No. 8935 Question 03.07.02-23 (Response dated August 29, 2018)

1) In NUREG/CR-6896, Assessment of Seismic Analysis Methodologies for Deeply Embedded Nuclear Power Plant Structures (Agencywide Documents and Access Management System Accession No. ML060820521), the U.S. Nuclear Regular Commission (NRC) staff notes that non-vertically propagating SH-waves increase torsional responses of embedded structures. However, applicants request for additional information (RAI) response did not include analysis involving non-vertically propagating SH-waves. The NRC staff also notes that American Society of Civil Engineers 4-16, Seismic Analysis of Safety-Related Nuclear Structures, provides a guideline that accidental torsion be considered to address the effects of non-vertically propagating waves. Therefore, the applicant is requested to provide an evaluation of potential impact of inclined SH-waves on torsional responses of the Reactor Building (RXB) and discuss if any additional torsional responses from inclined SH-waves can be covered by the provision of accidental torsion in NuScale Power, LLC (NuScale) Final Safety Analysis Report (FSAR) Section 3.7.2.11 Method Used to Account for Torsional Effects.
2) According to the literature (e.g., Dynamic Soil Structure Interaction, by Wolf, 1985,) an incident P-wave will always lead to reflected P- and SV-waves. Likewise, an incident SV-wave will always lead to a reflected SV-wave but a reflected P-wave does not exist for a sufficiently shallow incident SV-wave. The limiting angle of incidence of the SV-wave, for which a reflected P-wave still arises, is called the critical angle of incidence and is dependent on the Poissons ratio of the soil. Please clarify if the critical angle of incidence was considered in NuScales study and, if not, provide an explanation for not doing so.
3) The NRC staff believes that a Combined License (COL) Item should be added to NuScale Design Control Document (DCD) that requires a COL applicant that references NuScale DCD should perform a site-specific evaluation of the effects of non-vertically propagating seismic waves on the free-field ground motions and seismic responses of seismic Category I structures, systems, and components.

Enclosure 3

4) In proposed FSAR markup (for Page 3.7-118, Draft Revision 2) provided in the RAI response, the applicant states, Note that in the legends of the figures, X/SV means the X-response due to SV-wave input; X/P means the X-response due to P-wave input; Y/SH means the Y-response due to SH-wave input; etc.

However, the NRC staff finds that a legend including Y/SH is not present anywhere in the RAI response. Please clarify.

5) In proposed markup for Figure 3.7.2-154 Non-Vertically Propagating Seismic Wave Sensitivity Study for the RXB -Uncombined North-South (Y) ISRS, Node 3996, Top of Basemat, NW Corner, Capitola Input, ISRS in the Y (North-South) direction is presented. The NRC staff understands that inclined SV or P-waves produce ground motions in the X-Z plane. Please clarify if ground motions in the Y direction shown in Figure 3.7.2-154 are produced by inclined SH-waves.