VR-SECY-19-0117, SRM-SECY-19-0117: Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors

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SRM-SECY-19-0117: Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors
ML20147A504
Person / Time
Issue date: 05/26/2020
From: Margaret Doane
NRC/SECY
To:
References
SECY-19-0117, VR-SECY-19-0117 SRM-SECY-19-0117
Download: ML20147A504 (1)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 26, 2020 MEMORANDUM TO: Margaret M. Doane Executive Director for Operations Annette L. Digitally signed by Annette L. Vietti-Cook FROM: Annette L. Vietti-Cook, Secretary Vietti-Cook Date: 2020.05.26 11:20:49 -04'00'

SUBJECT:

STAFF REQUIREMENTS - SECY-19-0117 - TECHNOLOGY-INCLUSIVE, RISK-INFORMED, AND PERFORMANCE-BASED METHODOLOGY TO INFORM THE LICENSING BASIS AND CONTENT OF APPLICATIONS FOR LICENSES, CERTIFICATIONS, AND APPROVALS FOR NON-LIGHT-WATER REACTORS The Commission has approved the use of the technology-inclusive, risk-informed, and performance-based methodology described in this paper as a reasonable approach for establishing key parts of the licensing basis and content of applications for licenses, certifications, and approvals for non-light-water reactors.

The staff should remain open to continuous, critical examination of its thinking regarding approaches and metrics for the licensing of this coming class of advanced reactors.

In its work on the regulatory framework for advanced reactors, the staff should continue to recognize that the Commissions established policy on the application of the safety goals and safety performance expectations provides an acceptable minimum safety standard for new reactors while taking into account the need to adapt the aspects of our current regulatory framework for reactors that provide operational flexibility based on risk assessment, such as the more than minimal increases in risk test in Section 50.59, the Maintenance Rule of Section 50.65, and the quality assurance criteria of Appendix B to reflect the significantly lower risks inherent in the design of advanced reactors.

cc: Chairman Svinicki Commissioner Baran Commissioner Caputo Commissioner Wright OGC CFO OCA OPA ODs, RAs, ACRS, ASLBP (via E-Mail)

PDR