ML24232A244
| ML24232A244 | |
| Person / Time | |
|---|---|
| Site: | 05200050 |
| Issue date: | 08/19/2024 |
| From: | Shaver M NuScale |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| LO-172563 PM-173236, Rev 0 | |
| Download: ML24232A244 (1) | |
Text
LO-172563 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com August 19, 2024 Docket No. 052-050 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738
SUBJECT:
NuScale Power, LLC Submittal of Presentation Material Entitled ACRS Subcommittee Meeting (Open Session), August 22, 2024, High Impact Technical Issues Discussion, PM-173236, Revision 0 The purpose of this submittal is to provide presentation materials for use during the upcoming Advisory Committee on Reactor Safeguards (ACRS) NuScale Subcommittee Meeting on August 22, 2024. The materials support NuScales presentation of the high impact technical issues identified during the US460 Standard Design Approval Application review.
The enclosure to this letter is the nonproprietary presentation entitled ACRS Subcommittee Meeting (Open Session) High Impact Technical Issues Discussion, PM-173236, Revision 0.
The proprietary version is provided in a separate submittal, under letter number LO-173238.
This letter makes no regulatory commitments and no revisions to any existing regulatory commitments.
If you have any questions, please contact Chelsea Lockwood at 541-452-7171 or at clockwood@nuscalepower.com.
Sincerely, Mark W. Shaver Director, Regulatory Affairs NuScale Power, LLC Distribution:
Mahmoud Jardaneh, Chief New Reactor Licensing Branch, NRC Getachew Tesfaye, Senior Project Manager, NRC Michael Snodderly, Senior Staff Engineer, Advisory Committee on Reactor Safeguards, NRC : ACRS Subcommittee Meeting (Open Session) High Impact Technical Issues Discussion, PM-173236, Revision 0
LO-172563 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com ACRS Subcommittee Meeting (Open Session) High Impact Technical Issues Discussion, PM-173236, Revision 0
1 PM-173236 Rev. 0 Copyright © 2024 NuScale Power, LLC.
NuScale Nonproprietary Template #: 0000-21727-F01 R10 ACRS Subcommittee Meeting (Open Session)
August 22, 2024 Presenter: Thomas Griffith - Licensing Manager High Impact Technical Issues Discussion
2 PM-173236 Rev. 0 Copyright © 2024 NuScale Power, LLC.
NuScale Nonproprietary Template #: 0000-21727-F01 R10 Acknowledgement and Disclaimer This material is based upon work supported by the Department of Energy under Award Number DE-NE0008928.
This presentation was prepared as an account of work sponsored by an agency of the United States (U.S.)
Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof.
3 PM-173236 Rev. 0 Copyright © 2024 NuScale Power, LLC.
NuScale Nonproprietary Template #: 0000-21727-F01 R10 High Impact Technical Issues (HITIs)
- 1. Design and classification of the augmented DC power system (EDAS)
- 2. Loss-of-Coolant (LOCA) break spectrum
- 3. Incorporated by Reference (IBR)
- 4. Containment Vessel (CNV) material change
- 5. Lower Reactor Pressure Vessel (RPV) material change
- 6. Secondary side controller design for density wave oscillation (DWO) events
- 7. DWO and steam generator inlet flow restrictor design changes
- 8. ASME qualification of the helical coil steam generator for the onset of DWO-induced loads
- 9. Upper-to-lower RPV flange bolted joint shear loading that results from differential thermal expansion 10.LOCA Break at CVCS/CIV Connection (New)
Note: Green indicates issues that have been considered resolved by NuScale and NRC Management