ML23066A094
| ML23066A094 | |
| Person / Time | |
|---|---|
| Site: | 99902078 |
| Issue date: | 03/09/2023 |
| From: | Beverly Smith NRC/NRR/DNRL/NRLB |
| To: | Scott Moore Advisory Committee on Reactor Safeguards |
| References | |
| TR-107522, Rev 1 | |
| Download: ML23066A094 (1) | |
Text
March 09, 2023 MEMORANDUM TO:
Scott W. Moore, Executive Director Advisory Committee on Reactor Safeguards FROM:
Brian W. Smith, Director
/RA/
Division of New and Renewed Licenses Office of Nuclear Reactor Regulation
SUBJECT:
NUSCALE POWER, LLC, SAFETY EVALUATION REPORT FOR LICENSING TOPICAL REPORT: 107522, REVISION 1, APPLICABILITY RANGE EXTENSION OF NSP4 CRITICAL HEAT FLUX CORRELATION By letter dated November 5, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21309A754), NuScale Power, LLC (NuScale) submitted a request for review and approval of Topical Report (TR)-107522, Revision 0, Applicability Range Extension of NSP4 Critical Heat Flux Correlation: Supplement 1 to TR-0116-21012-P-A, Revision 1, to the U.S. Nuclear Regulatory Commission (NRC). By letter dated October 27, 2022 (ML22300A243), NuScale submitted TR-107522, Revision 1, Applicability Range Extension of NSP4 Critical Heat Flux Correlation, to NRC that incorporates the requested updates from staff. The purpose of this report was to provide the bases for an extension to the range of applicability for the NSP4 critical heat flux model to be used for the safety analysis of the NuScale Power Module (NPM) with NuFuel-HTP2TM fuel. The range of applicability is expanded to ensure the NSP4 model encompasses the operating domain of the NPM at higher rated power levels.
Based on its review of NuScales TR, the NRC staff prepared a TR Safety Evaluation (SE)
(ML23065A006). Per the recommendation of the Summary Report of 700th Meeting of the Advisory Committee on Reactor Safeguards (ACRS), (Section 4 (k)), (ML22327A162), the TR and SE are not being considered for review but are being provided to ACRS for informational purposes.
CONTACT: Bruce Bavol, NRR/DNRL 301-415-6715
S. Moore 2
The NRC staff concludes that the SE does contain information exempt from public disclosure.
However, the NRC is providing NuScale the opportunity to verify the staffs redactions and also verify if the SE contains any additional proprietary information. The NRC staff requests that the ACRS withhold the SE from public disclosure until a redacted, publicly available version, can be processed.
Docket No. 99902078
- via email NRR-002 OFFICE DNRL/NRLB:PM DNRL/NLIB:LA DNRL/NRLB: BC DNRL:D NAME BBavol SGreen*
MDudek*
BSmith*
DATE 03/06/2023 03/07/2023 03/08/2023 03/09/2023