ML23138A154

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Transmittal of NEI 22-05, Revision a, Technology Inclusive Risk Informed Change Evaluation (Tirice) Guidance for the Evaluation of Changes to Facilities Utilizing NEI 18-04 and NEI 21-07
ML23138A154
Person / Time
Site: Nuclear Energy Institute
Issue date: 03/24/2023
From: Holtzman B
Nuclear Energy Institute
To: Mohamed Shams
NRC/NRR/DANU
References
Download: ML23138A154 (1)


Text

From: HOLTZMAN, Benjamin To: Mohamed Shams Cc: Andrea Veil; Robert Taylor; John Segala; Joseph Sebrosky; Michael Orenak

Subject:

[External_Sender] Transmittal of NEI 22-05 Revision A, Technology Inclusive Risk Informed Change Evaluation (TIRICE) Guidance for the Evaluation of Changes to Facilities Utilizing NEI 18-04 and NEI 21-07 Date: Friday, March 24, 2023 11:50:00 AM Attachments: 03-24-23_NRC_NEI 22-05 Rev A+Attach.pdf March 24, 2023 Mr. Mohammed Shams Director, Division of Advanced Reactors and Non-Power Production and Utilization Facilities (DANU)

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Transmittal of NEI 22-05 Revision A, Technology Inclusive Risk Informed Change Evaluation (TIRICE) Guidance for the Evaluation of Changes to Facilities Utilizing NEI 18-04 and NEI 21-07 Project Number: 689

Dear Mr. Shams:

[1]

On behalf of the nuclear energy industry, the Nuclear Energy Institute (NEI) is transmitting to the U.S. Nuclear Regulatory Commission (NRC) the attached interim revision of NEI 22-05, Technology Inclusive Risk Informed Change Evaluation (TIRICE) Guidance for the Evaluation of Changes to Facilities Utilizing NEI 1804 and NEI 21-07. This document reflects the work that industrys Advanced Reactor Regulatory Task Force has done in close collaboration with the Southern Company-led Licensing Modernization Project and Technology Inclusive Content of Application Project (TICAP) to develop the guidance. The document is being transmitted for review in advance of an upcoming public meeting for discussion and feedback.

The guidance and associated criteria in NEI 22-05 are intended to take the place of 10 CFR 50.59 for certain nuclear power reactors with a safety analysis based on the methodology endorsed in Regulatory Guide 1.233 (ML20091L698), Guidance for a 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 guidance and criteria would be invoked by a license condition in combination with an exemption, in whole or in part, to 10 CFR 50.59 - predicated on the same logic as 10 CFR 50.59.

Thank you for your time and attention to this important matter. If you have any questions or require additional information, please contact me (bah@nei.org).

Sincerely, Benjamin A. Holtzman Program Advisor, New Reactors

Nuclear Energy Institute 1201 F St NW, Suite 1100 Washington, DC 20004 www.nei.org P: 202.739.8031 M: 202.230.1740 E: bah@nei.org

[1]

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