ML18201A332: Difference between revisions
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{{#Wiki_filter:/RA/}} | {{#Wiki_filter:March 21, 2019 MEMORANDUM TO: Andrea D. Veil, Executive Director Advisory Committee on Reactor Safeguards FROM: Robert Taylor, Director /RA/ | ||
Division of Licensing, Siting, and Environmental Analysis Office of New Reactors | |||
==SUBJECT:== | |||
NUSCALE POWER, LLC, DESIGN CERTIFICATION APPLICATION - SAFETY EVALUATION WITH OPEN ITEMS FOR CHAPTER 5, REACTOR COOLANT SYSTEM AND CONNECTING SYSTEMS On January 6, 20171, NuScale Power, LLC (NuScale) submitted its Standard Plant Design Certification Application to the U.S. Nuclear Regulatory Commission (NRC) for review, approval, and granting of standard design certification for the NuScale Standard Plant Design. NuScales letter is available in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML17013A229. | |||
Based on our review of the application, the NRC staff is providing the Advisory Committee on Reactor Safeguards (ACRS) its Safety Evaluation (SE) with open items for Chapter 5, Reactor Coolant System and Connecting Systems. A safety evaluation for the Technical Report, Pressure and Temperature Limits Methodology, has also been included in support of Chapter 5. Both SEs are being provided to support a meeting of the subcommittee of the ACRS scheduled for April 17, 2019. | |||
Based on its review of NuScales Chapter 5, and the Technical Report, Pressure and Temperature Limits Methodology, the NRC staff prepared advance copies of both SEs (ADAMS Accession No. ML19078A060 and ML19078A094) respectively. The NRC will withhold both SEs from public disclosure to allow NuScale the opportunity to verify contents for proprietary, export control, or security related information. Therefore, the staff requests that the ACRS withhold both SEs from public disclosure until the information has been released publicly in the ADAMS System. | |||
Docket No.: 52-048 CONTACT: Bruce Bavol, NRO/DLSE 301-415-6715 1 | |||
The Design Certification Application was submitted via a transmittal letter dated December 31, 2016. | |||
PKG: ML18201A331 MEMO: ML18201A332 SE: ML19078A094 PTLR SE: ML19078A060 *via email NRO-002 OFFICE NRO/DLSE/LB1/PM NRO/DLSE/LB3/ LA* NRO/DLSE/LB1/ BC NRO/DLSE/D NAME BBavol SGreen SLee RTaylor DATE 03/19/2019 03/18/2019 03/19/2019 03/21/2019}} | |||
Revision as of 19:55, 20 October 2019
| ML18201A332 | |
| Person / Time | |
|---|---|
| Site: | NuScale |
| Issue date: | 03/21/2019 |
| From: | Renee Taylor NRC/NRO/DLSE/LB1 |
| To: | Andrea Veil Advisory Committee on Reactor Safeguards |
| Bavol B M/nro/6715 | |
| Shared Package | |
| ML18201A331 | List: |
| References | |
| Download: ML18201A332 (2) | |
Text
March 21, 2019 MEMORANDUM TO: Andrea D. Veil, Executive Director Advisory Committee on Reactor Safeguards FROM: Robert Taylor, Director /RA/
Division of Licensing, Siting, and Environmental Analysis Office of New Reactors
SUBJECT:
NUSCALE POWER, LLC, DESIGN CERTIFICATION APPLICATION - SAFETY EVALUATION WITH OPEN ITEMS FOR CHAPTER 5, REACTOR COOLANT SYSTEM AND CONNECTING SYSTEMS On January 6, 20171, NuScale Power, LLC (NuScale) submitted its Standard Plant Design Certification Application to the U.S. Nuclear Regulatory Commission (NRC) for review, approval, and granting of standard design certification for the NuScale Standard Plant Design. NuScales letter is available in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML17013A229.
Based on our review of the application, the NRC staff is providing the Advisory Committee on Reactor Safeguards (ACRS) its Safety Evaluation (SE) with open items for Chapter 5, Reactor Coolant System and Connecting Systems. A safety evaluation for the Technical Report, Pressure and Temperature Limits Methodology, has also been included in support of Chapter 5. Both SEs are being provided to support a meeting of the subcommittee of the ACRS scheduled for April 17, 2019.
Based on its review of NuScales Chapter 5, and the Technical Report, Pressure and Temperature Limits Methodology, the NRC staff prepared advance copies of both SEs (ADAMS Accession No. ML19078A060 and ML19078A094) respectively. The NRC will withhold both SEs from public disclosure to allow NuScale the opportunity to verify contents for proprietary, export control, or security related information. Therefore, the staff requests that the ACRS withhold both SEs from public disclosure until the information has been released publicly in the ADAMS System.
Docket No.: 52-048 CONTACT: Bruce Bavol, NRO/DLSE 301-415-6715 1
The Design Certification Application was submitted via a transmittal letter dated December 31, 2016.
PKG: ML18201A331 MEMO: ML18201A332 SE: ML19078A094 PTLR SE: ML19078A060 *via email NRO-002 OFFICE NRO/DLSE/LB1/PM NRO/DLSE/LB3/ LA* NRO/DLSE/LB1/ BC NRO/DLSE/D NAME BBavol SGreen SLee RTaylor DATE 03/19/2019 03/18/2019 03/19/2019 03/21/2019