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| ML18207A799 *via email NRC-002 OFFICE NRO/DLSE/LB1: PM NRO/DLSE/LB1: LA NRO/DNRL/LB1: PM NAME MVera MMoore MVera DATE 07/26/2018 07/30/2018 7/31/2018 | | ML18207A799 *via email NRC-002 OFFICE NRO/DLSE/LB1: PM NRO/DLSE/LB1: LA NRO/DNRL/LB1: PM NAME MVera MMoore MVera DATE 07/26/2018 07/30/2018 7/31/2018 U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION SECTION 3.6.2, "DETERMINATION OF RUPTURE LOCATIONS AND DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING" June 13, 2018 1:00 p.m. - 3:00 p.m. |
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| U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION SECTION 3.6.2, "DETERMINATION OF RUPTURE LOCATIONS AND DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING" June 13, 2018 1:00 p.m. - 3:00 p.m. | |
| AGENDA Public Meeting 10:30-10:35am Welcome and Introductions 10:35-11:55am Discussion of the path forward for the Request for Additional Information 11:55-12:00pm Public - Questions and Comments Enclosure 1 | | AGENDA Public Meeting 10:30-10:35am Welcome and Introductions 10:35-11:55am Discussion of the path forward for the Request for Additional Information 11:55-12:00pm Public - Questions and Comments Enclosure 1 |
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Latest revision as of 19:47, 2 February 2020
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Category:Memoranda
MONTHYEARML24004A0472024-01-31031 January 2024
U.S. Nuclear Regulatory Commission Summary of the November 16, 2023, Observation Public Meeting to Discuss Nuscale’S 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 NuScales 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
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
ML20044E3522020-02-18018 February 2020
Memo to ACRS Rod Ejection Accident Methodology 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
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)
ML19345E9362020-01-13013 January 2020
Summary of the December 9, 2019, Public Teleconference Meeting on Incorporation by Reference
ML19343C7562020-01-0808 January 2020
Generator Tube - Siet Audit Report (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
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
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
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
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
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
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
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
ML19169A2952019-11-26026 November 2019
Memo to ACRS Transmitting SER
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)
ML19169A1192019-11-22022 November 2019
Memo to ACRS Transmitting Phase 4 SER for Chapter 8
ML19169A2912019-11-22022 November 2019
Memo to ACRS Transmitting SER
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
July 31, 2018 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Sitting, and Environmental Analysis, Office of New Reactors FROM: Marieliz Vera, Project Manager /RA/
Licensing Branch 1 Division of Licensing, Sitting, and Environmental Analysis, Office of New Reactors
SUBJECT:
SUMMARY
OF THE JUNE 13, 2018, CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION SECTION 3.6.2, "DETERMINATION OF RUPTURE LOCATIONS AND DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING" The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on June 13, 2018, to discuss Final Safety Analysis Report (FSAR) Tier 2, Chapter 3, Section 3.6.2 Determination of Rupture Locations and Dynamic Effects Associated with the Postulated Rupture of Piping, of the NuScale Power, LLC (NuScale) Design Certification. Participants included personnel from NuScale.
The public meeting notice can be found in the Agencywide Documents Access and Management Systems under Accession No. ML18150A415. 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.
CONTACT: Marieliz Vera, NRO/DLSE 301-415-5861
S. Lee 2 Summary:
The purpose of this meeting was to discuss NuScales overall pipe break analysis approach including NuScales approach/methodology for addressing the potential non-conservatism of the ANS 58.2 Standard jet modeling as described in RAI 8836 (ML17153A065), Question 03.06.02-5, including details of the NuScale plant specific computational fluid dynamics (CFD) modeling for assessing jet impingement and blast wave effect, the verification and validation of the CFD, and the progress made including applicable CFD preliminary results.
NuScale presented their approaches for addressing the potential non-conservatism of ANS 58-2 modeling. They discussed their methodology for assessing the dynamic effects of jet impingement and blast wave. NuScale is still performing the analysis. NuScale also provided the NRC staff with updates on the status and indicated that the RAI response (including technical report and the FSAR updates) may be delayed beyond the current due date of August 24, 2018. NuScale will reconfirm or revise the RAI due date by June 29, 2018. NuScale is aware of the schedule impact to NRC internal milestones.
The issue related to the break exclusion criteria for the welds between the safe-ends and the respective nozzles on the containment vessel (CNV) head as well as the welds between the safe-ends and the respective containment isolation valves (CIVs) was discussed. NuScale only applies the break exclusion criteria to the welds between the safe-ends and the respective valves. The NRC staff communicated to NuScale the expectation regarding the break exclusion criteria that also needs to be considered for the welds between the safe-ends and the respective nozzles on the CNV head. NuScale stated that they understood the NRC staffs position and recommended to further discuss this issue in the next meeting.
Docket No.52-048
Enclosures:
- 1. Meeting Agenda
- 2. List of Attendees cc w/encls.: DC NuScale Power, LLC Listserv
ML18207A799 *via email NRC-002 OFFICE NRO/DLSE/LB1: PM NRO/DLSE/LB1: LA NRO/DNRL/LB1: PM NAME MVera MMoore MVera DATE 07/26/2018 07/30/2018 7/31/2018 U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION SECTION 3.6.2, "DETERMINATION OF RUPTURE LOCATIONS AND DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING" June 13, 2018 1:00 p.m. - 3:00 p.m.
AGENDA Public Meeting 10:30-10:35am Welcome and Introductions 10:35-11:55am Discussion of the path forward for 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 DESIGN CERTIFICATION APPLICATION SECTION 3.6.2 "DETERMINATION OF RUPTURE LOCATIONS AND DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING" LIST OF ATTENDEES June 13, 2018 NAME AFFILIATION Marieliz Vera U.S. Nuclear regulatory Commission (NRC)
Yueh-Li Li NRC Jason Huang NRC Yuken Wong NRC Robert Caldwell NRC Shana Helton NRC Marty Bryan NuScale Power, LLC (NuScale)
Wayne Massie NuScale Storm Kauffman NuScale JJ Arthur NuScale Storm Kauffman NuScale Wayne Massie NuScale Marty Bryan NuScale Nadja Joergensen NuScale Marwan Charrouf NuScale Daniel Diefendorf NuScale 1
Enclosure 2