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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
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Public Meeting Summary May 14, 2020, NuScale Boron Redistribution Issue
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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
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Summary Report for the January 2019 Regulatory Audit of NuScale Chapter 20
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ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapters 2, 8 and 12
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Proposed Recommendation for ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 12, Radiation Protection
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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
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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