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Category:Meeting Agenda
MONTHYEARPMNS20211527, Meeting with NuScale Power, LLC on NuScale Topical Reports2021-12-0303 December 2021 Meeting with NuScale Power, LLC on NuScale Topical Reports PMNS20211528, Meeting with NuScale Power, LLC on NuScale Topical Reports2021-12-0303 December 2021 Meeting with NuScale Power, LLC on NuScale Topical Reports PMNS20211529, Meeting with NuScale Power, LLC on NuScale Topical Reports2021-12-0303 December 2021 Meeting with NuScale Power, LLC on NuScale Topical Reports PMNS20211530, Meeting with NuScale Power, LLC on NuScale Topical Reports2021-12-0303 December 2021 Meeting with NuScale Power, LLC on NuScale Topical Reports PMNS20211531, Meeting with NuScale Power, LLC on NuScale Topical Reports2021-12-0303 December 2021 Meeting with NuScale Power, LLC on NuScale Topical Reports PMNS20211532, Meeting with NuScale Power, LLC on NuScale Topical Reports2021-12-0303 December 2021 Meeting with NuScale Power, LLC on NuScale Topical Reports PMNS20211533, Meeting with NuScale Power, LLC on NuScale Topical Reports2021-12-0303 December 2021 Meeting with NuScale Power, LLC on NuScale Topical Reports PMNS20211534, Meeting with NuScale Power, LLC on NuScale Topical Reports2021-12-0303 December 2021 Meeting with NuScale Power, LLC on NuScale Topical Reports ML21004A2372021-01-0404 January 2021 Standard Design Approval Teleconference ML20349D0382020-12-14014 December 2020 Standard Design Approval Teleconference ML20321A2912020-11-16016 November 2020 Standard Design Approval Teleconference ML20314A0402020-11-0909 November 2020 Standard Design Approval Teleconference ML20314A2382020-11-0909 November 2020 Standard Design Approval Teleconference ML20314A2392020-11-0909 November 2020 Standard Design Approval Teleconference ML20305A3112020-10-31031 October 2020 Standard Design Approval Teleconference ML20300A5582020-10-26026 October 2020 Standard Design Approval Teleconference ML20300A5602020-10-26026 October 2020 Standard Design Approval Teleconference ML20300A5612020-10-26026 October 2020 Standard Design Approval Teleconference 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 ML20140A1892020-05-19019 May 2020 Public Meeting Summary May 14, 2020, NuScale Boron Redistribution Issue 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 ML20072M7982020-03-19019 March 2020 Meeting Summary for the January 30, 2020, Public Meeting to Discuss NuScale SDA Regulatory Engagement Plan 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) 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 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 ML19204A2772019-07-22022 July 2019 Discussion Topic July 22, 2019 Public Meeting to Discuss Interface Requirement Associated with the NuScale 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 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 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. ML19084A1782019-04-16016 April 2019 Summary of Category 1 Public Teleconference with NuScale Power, LLC, to Discuss the NuScale Turbine Missile Analysis 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 ML19084A1362019-03-25025 March 2019 Summary of Meeting with NuScale Power, LLC to Discuss Nuclear Regulatory Commission Staff'S Options to Review Nuscale'S Design Certification Application, Tier 2, Chapter 20, Mitigation of Beyond-Design-Basis Events ML19017A1532019-02-0606 February 2019 Summary of Public Meeting with NuScale to Discuss Response to Request for Additional Information 8894 Question 03.11-15 ML19010A0932019-02-0404 February 2019 December 19, 2018, and January 9, 2019 - Summary of Public Meeting with NuScale to Discuss ITAAC Related to Electrical Penetration Assemblies ML18337A0192018-12-0606 December 2018 Summary of Category 1 Public Teleconference to Discuss Technical Specification Potential Phase 2 Open Items Associated with the NuScale Power, LLC Design Certification Application 2021-12-03
[Table view] 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
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March 22, 2018 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors FROM: Anthony W. Markley, Senior Project Manager /RA/
Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors Rani L. Franovich, Senior Project Manager Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors
SUBJECT:
SUMMARY
OF JANUARY 16, 2018, AND JANUARY 23, 2018, PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC, TO DISCUSS VARIOUS TOPICS RELATED TO CHAPTER 19, PROBABILISTIC RISK ASSESSMENT AND SEVERE ACCIDENT EVALUATION, CHAPTER 9, AUXILLIARY SYSTEMS, AND THE PATH FORWARD FOR THE ACCIDENT SOURCE TERM METHODOLOGY TOPICAL REPORT (DOCKET NO.52-048)
On January 16, 2018, and January 23, 2018, representatives of the U.S. Nuclear Regulatory Commission (NRC) and NuScale Power, LLC, (NuScale) held a public teleconference meeting.
The purpose of this meeting was to discuss the following:
- 1. NuScales responses to the NRC staffs Requests for Additional Information (RAI) Nos.
9043, 9112, 8882, 8903, 8977, 8889, 8813, 9151, and 8899 related to severe accident analyses;
- 2. RAI 8907 related to equipment floor drains, and
- 3. NuScales path forward for the Accident Source Term Topical Report.
A complete copy of NuScales DCA is available on the NRC public Webpage at https://www.nrc.gov/reactors/new-reactors/design-cert/nuscale/documents.html.
CONTACTS: Anthony W. Markley, NRO/DNRL Rani L. Franovich, NRO/DNRL 301-415-3165 301-415-7334
S. Lee 2 , Summary of the January 16, 2018, and January 23, 2018, Teleconference between the NRC staff and NuScale, provides a summary of the topics discussed during the teleconference.
The agendas and list of meeting attendees are provided in Enclosures 2 and 3, respectively.
The meeting notices are available in the NRCs Agencywide Documents Access and Management System under Accession Nos. ML18003A613 and ML18003A616.
Docket No.52-048
Enclosures:
- 1. Meeting Summary
- 2. Agenda
- 3. Attendees
ML18067A406 *via email NRC-001 OFFICE NRO/DNRL/LB1: PM NRO/DNRL/LB1: PM NRO/DNRL/LB1: LA NAME RFranovich AMarkley MMoore DATE 3/12/2018 03/09/2018 3/12/2018 OFFICE NRO/DSRA/SPRA: BC NRO/DSEA/RPAC: BC NRO/DSRA/SPSB: BC NAME MHayes* MDudek* ADias*
DATE 3/13/2018 3/22/2018 3/20/2018
U.S. NUCLEAR REGULATORY COMMISSION
SUMMARY
OF JANUARY 16, 2018, AND JANUARY 23, 2018, PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC TOPIC 1: NuScale Power, LLCs Response to Request and Additional Information 8907 On January 16, 2018, the U.S. Nuclear Regulatory Commission (NRC) staff met with NuScale Power, LLC (NuScale) to discuss the responses to Request For Additional Information (RAI) 8907. During the course of the presentation, there were numerous questions from the NRC and interactions with NuScale representatives. The discussions centered on the following subject areas:
- Drainage associated with the chemical waste collection sumps, why fire water removal pumps are not required for some sumps that receive drainage from floor drains -
NuScale agreed with the NRC staffs question and will provide a supplemental response.
- Discuss issue regarding the seismic classification of the radioactive waste and balance of plant drain systems - NuScale will provide a supplemental response.
- Concerns with meeting Generic Design Criteria 60 versus meeting Title 10 of the Code of Federal Regulations, Section 20.1406. The staff does not agree that by meeting 10 CFR 20.1406 and complying with RG 4.21 that the system therefore meets GDC 60 for control of radioactive liquid effluents. NuScale will provide additional information of how the radioactive waste and balance of plant drain systems comply with GDC 60.
- Discrepancies that were noted with Tier 1 Table 3.0-1, Shared Systems Subject to Inspections, Tests, Analyses, and Acceptance Criteria Section 9.3.3, Equipment and Floor Drain Systems, and use of the Revision 5 of Regulatory Guide 1.29, Seismic Design Classification. - NuScale indicated that they would evaluate and make corrections, as needed.
TOPIC 2: NuScale Response to RAI Nos. 9043, 9112, 8882, 8903, 8977, and 8889 RAI 9043 (in-vessel retention) and 9112 (high pressure melt ejection)
On January 16, 2018, the NRC staff and the applicant discussed sections a, b, and c of RAI 9043 and NuScales response. The NRC staff clarified the technical issues that the RAI response did not appear to address. The NRC staff agreed with the applicant that tests indicate that the lowest critical heat flux for a downward facing hemisphere is on the bottom of the hemisphere. The NRC staff stated that other geometric factors (e.g., the seismic retention pin, the distance between the reactor vessel outer surface and the containment inner surface) could influence the value of the lowest critical heat flux. The applicant stated it could provide additional documentation describing the basis for its parameter values. The NRC staff suggested it might be helpful to first discuss the remaining two sections (sections d and e) of RAI 9043. The NRC staff and applicant agreed to a follow-up call on January 23, 2018, to accommodate this discussion. Additionally, to enable the applicant to more effectively prepare 1
Enclosure 1
for the follow-up call, the NRC staff agreed to provide the applicant more clarity regarding what was deficient with the response to RAI 9043 (sections d and e) and all of RAI 9112.
On January 23, 2018, the applicant indicated it recently developed an enhanced analysis to help address deficiencies in its initial response to RAI 9043. The enhanced analysis is documented in Engineering Change Notice(s) that are available for staff review. The applicant offered and the NRC staff agreed to review the enhanced analysis as part of a future (Stage 2) Chapter 19 audit.
Also on January 23, 2018, the applicant further discussed its response to RAI 9112 and agreed that the basis for a cutoff pressure [whether it is 200 pounds per square inch differential (psid) or 100 psid] below which high pressure melt ejection could be supported is deficient. However, the applicant stated that by the time the water had boiled out of the reactor pressure vessel (RPV) lower plenum and the RPV bottom head heats up, there would be no pressure difference between the RPV and the containment vessel (CNV) as shown in its MELCOR analyses. The applicant noted that the issue of backflow of water from the CNV into the RPV through an open reactor recirculation valve (RRV) is addressed in a response to another RAI (RAI 8903 on gravity-driven reflood).
During the January 23, 2018, follow-up teleconference the NRC staff asked about the effect of the operators adding water after the RPV has boiled dry. The applicant stated that the potential pressure increase from the water addition does not need to be analyzed as part of the evaluation of high pressure melt ejection because there are no plans to add water to the RPV after core damage begins. The final safety analysis report (FSAR) does not state that the operators should not add water after core damage begins. The NRC staff stated that the applicants plan to not add water to the RPV after core damage begins is different from other light-water reactors and that the NRC staff would need to consider this position further.
RAIs 8882, 8903, and 8977 These RAIs pertain to pool decontamination factor for module tip-over, gravity-driven RPV reflood via open RRVs, and larger release definition, respectively. In its responses to these RAIs, NuScale referred to supplemental analyses that resolve the matters raised in the RAIs.
During the January 16, 2018, teleconference, the NRC staff indicated an interest in reviewing those supplemental analyses. The applicant offered to make the analyses available to NRC staff review in the applicants Rockville office. The NRC staff agreed to include this review of supplemental analyses in the scope of its future (Stage 2) Chapter 19 audit plan.
RAI 8977 (large release definition)
On January 16, 2018, the NRC staff made the following additional observations and requests regarding NuScales response to RAI 8977:
- The RAI response states that, to estimate the release magnitude that constitutes a large release, the relative release fractions for the radionuclide groups from Sandia National Laboratories Report SAND2011-0128, Accident Source Terms for Light-Water Nuclear Power Plants Using High-Burnup or [Mixed Oxide (MOX)] Fuel, were assumed. The NRC staff requests the basis for this assumption, because of the disclaimer in SAND2011-0128 regarding use for small modular reactors. The NRC staff noted that the relative fractions of core inventory released to the containment in SAND2011-0128 2
may not be applicable to NuScale due to differences between the geometry of NuScale and large light water reactors and differences in volatility among the radionuclide groups.
- The RAI response states that the following was assumed to estimate the maximum release from a leaking containment: a) the relative release fractions for the radionuclide groups from SAND2011-0128 and b) retention of radionuclides in the reactor vessel except for xenon and iodine. The NRC staff requests the applicant clarify these two assumptions, because they do not appear to be consistent with each other.
- Estimating the release magnitude using MELCOR accident consequence code system (MACCS) involves sampling from weather data (i.e., wind speed, wind direction, precipitation, and atmospheric stability) and specifying the location of the receptor with respect to the release direction. The NRC staff requests clarification of what percentile dose(s) and what receptor location(s) (e.g., direction(s)) were used in the analysis, due to the variety of possible ways to define a large release.
The applicant agreed to provide a supplemental response that is responsive to these NRC staff requests.
RAI 8889 (steam generator tube failure induced by severe accident)
During the January 16, 2018, teleconference, the NRC staff requested an estimated date that a supplemental response to this RAI would be forthcoming. The applicant indicated it had recently submitted the supplemental information for to the NRC.
RAI 8813 (Probabilistic Risk Assessment [PRA] model for emergency core cooling systems
[ECCS])
During the January 23, 2018, call, the NRC staff requested NuScale to clarify a response to RAI 8813 received on June 28, 2017. In its response, NuScale stated that the "IAB [inadvertent actuation block] is a normally open valve that is not required to change state upon receipt of a non-spurious ECCS actuation signal." NuScale confirmed the NRC staffs understanding of the design that IAB is normally open, closes when the RPV to CNV differential pressure (DP) is high, and then opens again when the DP becomes low for inadvertent actuations. NuScale further clarified that the IAB is designed to not have to change positions for scenarios that call upon the ECCS function to achieve a safe end state (e.g., chemical and volume control system line break). NuScale stated that this is accomplished by setting the IAB setpoint sufficiently high to allow the RPV to CNV DP to clear the IAB setpoint before an ECCS actuation setpoint is reached. Scenarios such as a loss of direct current power will require the IAB to change state.
RAI 9151 (Key PRA Assumptions)
During the January 23, 2018, call, the NRC staff discussed NuScales response to RAI 9151, received on November 21, 2017, and asked if the proposed wording for combined operating license (COL) Item 19.1-8 provides sufficient guidance for COL applicants and/or holders to ensure validity of key PRA assumptions during the COL phases because the COL Item does not reference specific FSAR tables containing the key assumptions. Following the discussion, the applicant agreed to supplement the RAI response with a revised COL Item 19.1-8 that refers to the specific FSAR tables that list the key PRA assumptions.
RAI 8899, Question 19.1-15 3
During the January 23, 2018, call, the NRC staff discussed NuScales supplemental response to RAI 8899, question 19.1-15, and indicated that the FSAR 3.8.5 analysis for sliding and overturning does not demonstrate that a seismic margin of 1.67 times the certified seismic design response spectra (CSDRS) is met for the seismic margin assessment. The NRC staff stressed that, as stated in the original RAI, a safety finding needs to made that a seismic margin of 1.67 times the CSDRS is met for the seismic Category I structures against seismic-induced sliding and overturning.
The NRC staff additionally requested clarification on the assumption added to Table 19.1-40, specifically whether it is the applicants intent that the COL applicant verify this assumption. The NRC staff further elaborated that, if the intent is for the COL applicant to verify this assumption, the assumption to be verified should not confirm the applicability of the stability analysis in FSAR 3.8.5, but should confirm the stability of the structures for a higher demand (i.e. 1.67 times the CSDRS).
The applicant stated its intent to discuss the resolution of this RAI with NuScale management.
Should the applicant choose to perform an additional analysis, a supplemental RAI would be needed to justify the effort. Alternatively, should the applicant choose to add a COL item and modify Table 19.1-40, it would indicate this resolution in a supplemental response.
TOPIC 3: NuScale Path Forward for Accident Source Term Methodology Topical Report NuScale Power, LLC staff met with the NRC staff to discuss a revision to their approach for the Accident Source Term Methodology Topical Report (ASTTR) on January 23, 2018. In advance of this meeting NuScale provided the NRC staff with the slides that were used during the NuSCale presentation. These slides are publicly available and can be found at ADAMS Package ML17254B067. After introductions, NuScale proceeded through their presentation which followed their slides.
During the course of the presentation, there were numerous questions from the NRC and interaction with NuScale representatives. The discussions centered on the following subject areas:
- Use of an operational iodine spike event that uses maximum technical specifications values versus a core damage event.
- Concern for choke flow rates given the size of the leak.
- Concern for greater leakage at lower pressures.
- Equipment survivability and scenario applicability.
- Effects upon control room habitability and affects upon multi module operations.
- Regulatory processes that may be needed, e.g., exemptions.
- Concerns for a potential policy issue and potential impact upon schedules.
4
As a result of the NuScale presentation and dialogue, the NRC staff requested that early interaction with NuScale as the revised approach becomes formalized to minimize impact upon schedule and for to ensure NRC understanding of the revised approach.
There were no substantive comments from members of the public. The meeting was then closed.
5
U.S. NUCLEAR REGULATORY COMMISSION
SUMMARY
OF JANUARY 16, 2018, AND JANUARY 23, 2018, PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC MEETING AGENDA Tuesday, January 16, 2017 Time Topic Speaker 1:00 pm - 2:00 pm NuScale Response to eRAI 8907 NRC/NuScale NuScale Response to eRAI Nos. 9043, 9112, 2:00 pm - 3:00 pm NRC/NuScale 8882, 8903, 8977 and 8889 Tuesday, January 23, 2018 Time Topic Speaker NuScale Power, LLC Path Forward for 10:00 am - 12:00 am Accident Source Term Methodology NRC/NuScale Topical Report (ASTTR)
Resumed - NuScale Response to eRAI Nos. 9043 and 9112 1:00 pm - 3:00 pm NRC/NuScale NuScale Response to eRAIs 8813, 9151 and 8899 Enclosure 2
U.S. NUCLEAR REGULATORY COMMISSION
SUMMARY
OF JANUARY 16, 2018, AND JANUARY 23, 2018, PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC LIST OF ATTENDEES NuScale: January 16, 2016 G. Buster J. Curry B. Galyean B. Haley L. McSweeney E. Mullin C. Sexton J. Wike C. Williams C. Fosaaen J. Wike M. Paul A. Maass (Flour)
NuScale: January 23, 2016 S. Bristol G. Buster J. Curry J. Doyle B. Galyean D. Gardner B. Haley E. Mullin S. Weber J. Wike C. Williams D. Gardner M. Shaver G. Becker T. Bergman R. Gamble A. Callaway D. Botha B. Bristol NRC Staff January 16, 2018 Hossein Esmaili Rani Franovich Tony Nakanishi Marie Pohida Jason Schaperow Enclosure 3
Anthony Markley Robert Vettori Dennis Andrukat NRC Staff January 23, 2018 Hossein Esmaili Rani Franovich Bhagwat Jain Tony Nakanishi Alissa Neuhausen Marie Pohida Jason Schaperow Mark Caruso Michelle Hayes Michael Dudek Ron Lavera Rich Clement Steve Williams Zachary Gran Andy Campbell Robert Taylor Samuel Lee Brad Harvey Jason White Ed Stutzcage Anne-Marie Grady Greg Cranston John Monninger Donald Palmrose Shawn Campbell Michael Salay Anthony Markley Public Jim Kenzie Ray Schiele Alex Young Bryan Welch Sarah Fields Amir Afzali