ML22251A184
| ML22251A184 | |
| Person / Time | |
|---|---|
| Site: | 99902052 |
| Issue date: | 09/14/2022 |
| From: | Bavol B NRC/NRR/DNRL/NRLB |
| To: | Michael Dudek NRC/NRR/DNRL/NRLB |
| Bruce Bavol-NRR/DNRL/NRLB 301-415-6715 | |
| Shared Package | |
| ML22250A736 | List: |
| References | |
| Download: ML22251A184 (6) | |
Text
September 14, 2022 MEMORANDUM TO:
Michael I. Dudek, Chief New Reactor Licensing Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation FROM:
Bruce Bavol, Project Manager /RA/
New Reactor Licensing Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF THE August 24, 2022, OBSERVATION PUBLIC MEETING TO DISCUSS THE PRE-SUBMITTAL OF THE NUSCALE NON LOSS-OF-COOLANT-ACCIDENT EVALUATION MODEL TOPICAL REPORT The U.S. Nuclear Regulatory Commission (NRC) held an Observation Public Meeting on August 24, 2022, to discuss the pre-submittal of the NuScales Topical Report (TR)-0516-49416, Revision 4, Non-Loss-of-Coolant-Accident Topical Report. NRC and NuScale staff participated in the open portion of the meeting along with one external project stakeholders.
The public meeting notice dated August 24, 2022, can be found in the NRCs Agencywide Documents Access and Management Systems (ADAMS) under Accession No. ML22230A046.
Presentation slides from NuScale can be found in under ML22223A180. This meeting notice was also posted on the NRC public website.
Enclosed is the meeting agenda (Enclosure 1), list of attendees (Enclosure 2), meeting overview - public (Enclosure 3), and the meeting overview - non-public (Enclosure 4).
Docket No. 99902052
Enclosures:
- 1. Meeting Agenda
- 2. List of Attendees
- 3. Summary of Open Session
- 4. Summary of Closed, Proprietary Session CONTACT: Bruce M. Bavol, NRR/DNRL 301-415-6715
- via email NRR-106 OFFICE DNRL/NRLB:PM DNRL/NRLB:LA DNRL/NRLB:BC DNRL/NRLB: PM NAME BBavol*
SGreen*
MDudek*
BBavol*
DATE 09/13/2022 09/08/2022 09/14/2022 09/14/2022
U.S. NUCLEAR REGULATORY COMMISSION OBSERVATION PUBLIC MEETING TO DISCUSS THE PRE-SUBMITTAL OF THE NUSCALE NON LOSS-OF-COOLANT-ACCIDENT EVALUATION MODEL TOPICAL REPORT MEETING AGENDA August 24, 2022 Time Topic 1:30 p.m. - 1:35 p.m.
Welcome and Introductions 1:35 p.m. - 1:55 p.m.
Opening Discussion & NuScale presentation 1:55 p.m. - 2:00 p.m.
Public - Questions and Comments 2:00 p.m. - 4:00 p.m.
Closed Portion 4:00 p.m.
Adjourn
U.S. NUCLEAR REGULATORY COMMISSION OBSERVATION PUBLIC MEETING TO DISCUSS THE PRE-SUBMITTAL OF THE NUSCALE NON LOSS-OF-COOLANT-ACCIDENT EVALUATION MODEL TOPICAL REPORT LIST OF ATTENDEES August 24, 2022 Name Organization Bruce Bavol U.S. Nuclear Regulatory Commission (NRC)
Patton, Rebecca NRC Miller, Joshua NRC Rau, Adam NRC Donoghue, Joseph NRC Yarsky, Peter NRC Barrett, Antonio NRC Nolan, Ryan NRC Tabatabai, Omid NRC Pohida, Marie NRC Gamble, Robert NuScale Griffith, Thomas NuScale Lingenfelter, Andy NuScale Lynn, Kevin (presenter)
NuScale McCloskey, Meghan Nuscale Sawant, Pravin NuScale Shaver, Mark NuScale Song, Yong Jae NuScale Yoo, Yeon Jong NuScale Throckmorton, Dean NuScale Subaiya, Peter NuScale Thornsbury, Eric Electric Power Research Institute (EPRI)
U.S. NUCLEAR REGULATORY COMMISSION OBSERVATION PUBLIC MEETING TO DISCUSS THE PRE-SUBMITTAL OF THE NUSCALE NON LOSS-OF-COOLANT-ACCIDENT EVALUATION MODEL TOPICAL REPORT The U.S. Nuclear Regulatory Commission (NRC) held an Observation Public Meeting on August 24, 2022, to discuss the pre-submittal of the NuScales Topical Report (TR)-0516-49416, Revision 4, Non-Loss-of-Coolant-Accident Topical Report. NRC and NuScale staff participated in the open portion of the meeting along with one external project stakeholders.
The Non - LOCA TR presentation provided an opportunity for NuScale to share overview and context of:
Key design changes implemented between the Design Certification Application (DCA)
[US600] design and the design for the Standard Design Approval (SDA) Application
[US460]
Preliminary identification of design change impacts to Chapter 15 safety analysis event progressions, phenomena, evaluation models (EM), and Non-LOCA Topical Report NuScales plan to integrate effects of design changes, EM impacts into Non-LOCA Topical Report During the closed portion of the meeting NuScale proprietary information was discussed with the NRC staff asking questions on the design and testing changes since the DCA submittal.
At the end of the public portion, NRC staff opened up the meeting to questions from the general public with no questions being asked.
Below are notes taken from the NuScale Non-LOCA TR closed meeting.
Staff asked about the TR submittal date - NuScale responded that the Non-LOCA TR is expected at ((. Staff asked if Reactor Safety Valves setpoint changed - NuScale stated that, (( }}. Staff asked about approach to ((
}}.
Staff asked if more instrumentation is used for the NIST testing - NuScale stated that some adjustments were made to instrumentation. Staff asked about non-condensable gases (NCGs) in the test - NuScale stated that NCGs were considered and will be discussed at a later time during testing observation. NuScale presented several sample calculation results. NuScale intends to remove some Design Certification non-LOCA TR review L/Cs ((
}}.
NuScale intends to use Computational Fluid Dynamics analyses to support the heat transfer correlations used in NRELAP. NuScale stated TR Format updated to be design independent (Both Design Certification Application and Standard Design Approval Application). Staff asked about where conservative calculation methodology would be located/described - NuScale stated they were adding flexibility to use conservative inputs for dose assessment and rod drop analysis (add methodology to TR). Staff asked about the Critical Heat Flux (CHF) ((
}}.
The staff noted that previous DCA non-LOCA TR requests for addition information responses will be looked at to see if previous bases or assumption justification are still valid with changes to the SDA non-LOCA TR.
}}