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Exhibit KRS-003 - Kairos Power, LLC, Hermes Mandatory Hearing - Safety Panel
	ML23271A242
Person / Time
Site:	Hermes File:Kairos Power icon.png
Issue date:	10/19/2023
From:	Blandford E; Kairos Power
To:	; NRC/OCM
	SECY RAS
References
	Construction Permit Mndtry Hrg, RAS 56805, 50-7513-CP
	Download: ML23271A242 (0)
	v • d • e

Exhibit KRS-003

Hermes Mandatory Hearing - Safety Panel ED BLANDFORD - CHIEF TECHNOLOGY OFFICER OCTOBER 19, 2023

Kairos Power s mission is to enable the worlds transition to clean energy, with the ultimate goal of dramatically improving peoples quality of life while protecting the environment.

Hermes Design - Inherent Safety

Coated Particle Fuel Liquid Fluoride Salt Coolant TRISO Flibe (2LiF-BeF2)

No Reproduction or Distribution Without Express Written Permission of Kairos Power LLC.

Functional Containment

The KP-FHR safety case is based on the concept of functional containment represented by the radionuclide retention performance of the fuel and the Flibe coolant

The performance of the TRISO and Flibe are so effective, that the Hermes safety case does not have to rely on traditional confinement barriers like reactor coolant piping or the reactor building Majority of radioactive material at risk for release is held within the design of TRISO fuel Retention properties of Flibe act as an additional barrier for release of radionuclides for submerged fuel

Functional containment was approved by the NRC in SRM-SECY-18-0096 as a barrier, or set of barriers taken together, that effectively limits the physical transport of radioactive material to the environment The functional containment approach relies on physical barriers, operating conditions, coolant design, and fuel form that limit the potential release of radioactive material

No Reproduction or Distribution Without Express Written Permission of Kairos Power LLC.

Fundamental Safety Functions

Prevent uncontrolled release of radionuclides Functional containment (TRISO fuel and Flibe coolant) retains fission products and limits release during postulated events The safety-related reactor vessel and internals are designed to ASME Section III, Division 5, maintaining a Flibe level over the active fuel and a natural circulation flow path Non-safety-related fluid systems that may contain circulating radiological activity are designed to ASME Section VIII, B31.1/B31.3, or applicable API standards

Remove decay heat in the event of a postulated event Natural circulation and the passive decay heat removal system reject residual heat from the reactor core to the atmosphere

Control reactivity in the reactor core Reactivity control and shutdown system provides reactivity control during normal and postulated events

Safety Analysis

To demonstrate compliance with dose limits, 100.11(a)(1-2) Reference Values a Maximum Hypothetical Accident (MHA) is analyzed for dose consequences Margin

The MHA is conservatively non-physical To (challenge functional containment) to Dose overestimate potential off-site dose Ref.

consequences Va l u e s

Comprehensive set of postulated events (design basis events) are considered to MHA Dose Hypothetical ensure consequences are bounded by MHA Conservatism

Dose consequences of the MHA are less than 1 rem at the site boundary, meeting the siting dose limits in 10 CFR 100 with Potential Postulated Event Doses Design Basis significant margin Conservatism

No Reproduction or Distribution Without Express Written Permission of Kairos Power LLC.

ML23271A242

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