ML22152A268

Kairos Power LLC, Question Related to ASME Code Section III for the General Audit for Hermes CP Application

ML22152A268
Person / Time
Site:	Hermes
Issue date:	05/26/2022
From:	Edward Helvenston NRC/NRR/DANU/UAL1
To:	Bryan M, Gardner D, Peebles D Kairos Power
Helvenston E
References
Download: ML22152A268 (1)

Text

From: Helvenston, Edward To: Drew Peebles; Darrell Gardner; Martin Bryan Cc: Beasley, Benjamin

Subject:

NRC Audit Question on Hermes PSAR Date: Thursday, May 26, 2022 5:22:00 PM Hello Drew, Darrell, Marty, Please see below for one additional question the NRC staff has developed for Kairos related to the Hermes PSAR. The NRC staff would like to discuss this within the scope of the General Audit (see audit plan dated 2/10/2022, ADAMS Accession No. ML22039A336), and I am providing in advance to facilitate discussion during an audit meeting. Once Kairos is ready to discuss, please let us know and we can set up a meeting. We will add this e-mail with questions to public ADAMS. If any questions, please let Ben or I know.

Thanks, Ed Question Number Question Gen-1 Hermes PSAR Section 12.9, Quality Assurance, states that the Quality Assurance Program Description for Hermes design and construction is based on ANSI/ANS-15.8-1995, Quality Assurance Programs Requirements for Research Reactors.

However, the PSAR, including in Chapters 3, 4, 6, and 13, indicates that safety-related Hermes components, specifically pressure vessels (including the reactor vessel), the reactor vessel internals, core support structures, control and shutdown elements and drive mechanisms, and the decay heat removal system, will be designed and constructed in accordance with ASME Code,Section III, Rules for Construction of Nuclear Facility Components. The NRC staff notes that ASME Code,Section III, requires, in part, that components be designed, manufactured, and/or constructed under a Quality Assurance Program meeting 10 CFR Part 50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants. Recognizing that compliance with 10 CFR Part 50, Appendix B, is not required for non-power reactors such as Hermes, please clarify this apparent discrepancy.

Ed Helvenston, U.S. NRC Non-Power Production and Utilization Facility Licensing Branch (UNPL)

Division of Advanced Reactors and Non-Power Production and Utilization Facilities (DANU)

Office of Nuclear Reactor Regulation (NRR)

O-12C07 (301) 415-4067