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Category:Meeting Briefing Package/Handouts
MONTHYEARML24039A1492024-02-0606 February 2024 Staff ACRS Open Session Presentation Slides for Safety Evaluation for NuScale Topical Reports TR-108601-P Rev 4 and TR-0715-50350-P Rev 3 ML24024A1882024-01-30030 January 2024 Presentation Slides for the January 30, 2024, Quarterly Observation Public Meeting on the Status of Nuscale'S US460 Standard Design Approval Application ML23206A0062023-07-27027 July 2023 NRC 2nd Public Meeting Presentation on Risk Insights and Severe Accident Vulnerability Information for LWR CP Applications ML23230A0072023-07-26026 July 2023 Presentation Slides for the July 26, 2023, Observation Public Meeting on the Status of Nuscale'S US460 Standard Design Approval Application ML23116A0872023-04-25025 April 2023 Sdaa - NuScale-NRC Management Public Meeting Presentation ML22091A0412022-04-0707 April 2022 NRC Staff ACRS Fc Presentation for GEH BWRX-300 Advanced Civil Construction and Design Approach LTR ML22095A2062022-03-18018 March 2022 NRC Staff Public Presentation ACRS Subcommittee Meeting on BWRX-300 Containment Evaluation Method-Public ML22080A0062022-03-18018 March 2022 NRC Staff ACRS Sc Presentation for GEH BWRX-300 Advanced Civil Construction and Design Approach LTR ML21295A6222021-10-22022 October 2021 Slides for the October 27 2021 Public Meeting with NuScale ML21293A2332021-10-20020 October 2021 Us Update - 27th Wgrnr Meeting Updated ML21293A0412021-10-19019 October 2021 Slovenia Nuclear Innovation Seminar, Regulatory Frameworks for Nuclear Safety- MID-FINAL ML21274A0762021-09-29029 September 2021 Sept 29 2021 Adv Rx Stakeholder Meeting Slides ML21028A4432021-01-28028 January 2021 ACRS Fc NRC Staff Public LTR BWRx-300 Containment Performance Final Slides ML20204A7642020-07-22022 July 2020 Staff Backup Slides ACRS Fc 07/21/2020 ML20171A4092020-06-19019 June 2020 NRC Risk Tool ML20113E8392020-04-28028 April 2020 Approach for a New Regulatory Guidance Infrastructure for Digital Instrumentation and Control (I&C) ML20107F7582020-04-15015 April 2020 Slides for April 15, 2020 NuScale Boron Redistribution Audit Status Public ML20021A2212020-01-22022 January 2020 Workshop on Spent Fuel Performance Margins ML19304A0392019-11-20020 November 2019 Preliminary Recommendations for Modernization of the Nrc'S Digital I&C Regulatory Infrastructure 2024-02-06
[Table view]Some use of "" in your query was not closed by a matching "". Category:Slides and Viewgraphs
MONTHYEARML24039A1492024-02-0606 February 2024 Staff ACRS Open Session Presentation Slides for Safety Evaluation for NuScale Topical Reports TR-108601-P Rev 4 and TR-0715-50350-P Rev 3 ML24024A1882024-01-30030 January 2024 Presentation Slides for the January 30, 2024, Quarterly Observation Public Meeting on the Status of Nuscale'S US460 Standard Design Approval Application ML23206A0062023-07-27027 July 2023 NRC 2nd Public Meeting Presentation on Risk Insights and Severe Accident Vulnerability Information for LWR CP Applications ML23230A0072023-07-26026 July 2023 Presentation Slides for the July 26, 2023, Observation Public Meeting on the Status of Nuscale'S US460 Standard Design Approval Application ML23116A0872023-04-25025 April 2023 Sdaa - NuScale-NRC Management Public Meeting Presentation ML23087A2102023-03-28028 March 2023 NRC Public Meeting Presentation on Risk Insights and Severe Accident Vulnerability Information for LWR CP Applications ML22091A0412022-04-0707 April 2022 NRC Staff ACRS Fc Presentation for GEH BWRX-300 Advanced Civil Construction and Design Approach LTR ML22095A2062022-03-18018 March 2022 NRC Staff Public Presentation ACRS Subcommittee Meeting on BWRX-300 Containment Evaluation Method-Public ML22080A0062022-03-18018 March 2022 NRC Staff ACRS Sc Presentation for GEH BWRX-300 Advanced Civil Construction and Design Approach LTR ML22013A3872022-01-13013 January 2022 01-2022 Staff Presentation to ACRS on New and Advanced Reactor Licensing Processes ML22048A5192021-12-31031 December 2021 PNNL Perspectives Report on Enhancing Environmental Justice Activities at the NRC ML21295A6222021-10-22022 October 2021 Slides for the October 27 2021 Public Meeting with NuScale ML21293A2332021-10-20020 October 2021 Us Update - 27th Wgrnr Meeting Updated ML21293A0412021-10-19019 October 2021 Slovenia Nuclear Innovation Seminar, Regulatory Frameworks for Nuclear Safety- MID-FINAL ML21274A0762021-09-29029 September 2021 Sept 29 2021 Adv Rx Stakeholder Meeting Slides ML21195A0322021-07-14014 July 2021 EPZ Slides for the July 14 2021 Public Meeting with NuScale ML21028A4432021-01-28028 January 2021 ACRS Fc NRC Staff Public LTR BWRx-300 Containment Performance Final Slides ML20204A7642020-07-22022 July 2020 Staff Backup Slides ACRS Fc 07/21/2020 ML20171A4092020-06-19019 June 2020 NRC Risk Tool ML20113E8392020-04-28028 April 2020 Approach for a New Regulatory Guidance Infrastructure for Digital Instrumentation and Control (I&C) ML20107F7582020-04-15015 April 2020 Slides for April 15, 2020 NuScale Boron Redistribution Audit Status Public ML20021A2212020-01-22022 January 2020 Workshop on Spent Fuel Performance Margins ML19304A0392019-11-20020 November 2019 Preliminary Recommendations for Modernization of the Nrc'S Digital I&C Regulatory Infrastructure 2024-02-06
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NRC Staff Presentation-Open Session GEH Topical Report NEDC-33911P, Revision 0, Supplement 1, BWRX-300 Containment Performance BWRX-300 Small Modular Reactor ACRS Subcommittee Meeting February 3, 2021 1
Presentation Outline
- BWRX-300 Containment Background
NRC Staff Review Team
- NRR Containment and Plant Systems Branch (SCPB)
- Chang-Yang Li
- Angelo Stubbs
- NRR Nuclear Systems Performance Branch (SNSB)
- Syed Haider
- NRR Mechanical Engineering and Inservice Testing Branch (EMIB)
- Yueh-Li (Renee) Li
- Thomas Scarbrough
- NRR Vessels and Internals Branch (NVIB)
- Dan Widrevitz
- NRR New Reactor Licensing Branch (NRLB)
- Rani Franovich
- George Wunder 3
BWRX-300 Containment Design Background
- BWRX-300 containment is an underground subterranean steel or reinforced concrete primary containment vessel (PCV) or a combination of steel and reinforced concrete
- Containment heat is removed by Passive Containment Cooling System (PCCS)
- Combustible gas control is not required for design basis accidents (DBAs) because the BWRX-300 containment atmosphere is well mixed and the containment atmosphere is initially nitrogen-inerted 4
BWRX-300 Containment Performance NEDC-33911P provides design requirements, analytical methods, acceptance criteria, and regulatory bases for:
- Containment and the Passive Containment Cooling System (PCCS)
- Containment isolation valves (CIVs)
- Analytical methods evaluating containment performance
- Acceptance criteria for the BWRX-300 containment performance in accordance with the design requirements specified for the containment, PCCS, and CIVs 5
Overview of NRC Staff Review
- Piping and Valves Design Relevant to Containment Performance
- Containment Functional Design
- Containment Heat Removal Systems
- Containment Isolation System
- Combustible Gas Control in Containment
- Containment Leakage Testing
- Fracture Prevention of Containment Pressure Boundary 6