ML20049H322
| ML20049H322 | |
| Person / Time | |
|---|---|
| Site: | PROJ0769 |
| Issue date: | 02/18/2020 |
| From: | Anna Bradford NRC/NRR/DNRL |
| To: | Scott Moore Advisory Committee on Reactor Safeguards |
| Vera Amadiz M, 415-5861 | |
| Shared Package | |
| ML20044E059 | List: |
| References | |
| TR-0516-49422, Rev. 1 | |
| Download: ML20049H322 (2) | |
Text
February 18, 2020 MEMORANDUM TO: Scott W. Moore, Executive Director Advisory Committee on Reactor Safeguards FROM: Anna H. Bradford, Director /RA/ Bob Caldwell for Division of New and Renewed Licenses Office of Nuclear Reactor Regulation
SUBJECT:
NUSCALE POWER, LLC, DESIGN CERTIFICATION APPLICATION - SAFETY EVALUATION FOR TOPICAL REPORT, LOSS-OF-COOLANT ACCIDENT EVALUATION MODEL, TR-0516-49422, REVISION 1 By letter dated December 30, 2016, NuScale Power, LLC (NuScale) submitted topical report (TR) Loss-of-Coolant Accident Evaluation Model, TR-0516-49422, to the U.S. Nuclear Regulatory Commission (NRC) for review and approval. This TR supports Design Certification Application that was submitted by NuScale on January 6, 20171. NuScales letter is available in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML17004A122.
The NRC staffs Safety Evaluation (SE) for TR-0516-49422, Revision 1, can be found at ADAMS Accession No. ML20044E059 (Package). The SE will support a future meeting of the Advisory Committee on Reactor Safeguards Subcommittee.
Docket No.: PROJ0769 CONTACT: Rani Franovich, NRR/DNRL 301-415-7334 1
The Design Certification Application was submitted via a transmittal letter dated December 31, 2016.
PKG: ML20044E059 MEMO: ML20049H322 SER: ML20044E199 (PUBLIC)
SER: ML20044E198 (PROP) *via email NRR-106 OFFICE DNRL/NRLB: PM DNRL/NLRB: LA DNRL/NRLB: BC DNRL: D NAME RFranovich CSmith* MDudek* ABradford (BCaldwell for)
DATE 2/13/2020 2/18/2020 2/18/2020 2/18/2020