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NUREG-1537, Part 2 - NRC

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AprNDix18 1 I -<br />

-<br />

design bases and functional characteristics, construction materials, thermal<br />

capabilities, effects of radiation, design life, and replacement capability.<br />

4.2.4 Neutron Source and Holder<br />

Any modifications to the startup neutron source or holder required to<br />

accommodate the HEU to LEU conversion should be reviewed. These should<br />

include mechanical and functional designs, construction materials, thermal and<br />

radiation capabilities, and the ability to be retracted or replaced.<br />

4.2.5 In-Core Experimental Facilities<br />

Any proposed changes to in-core experimental facilities to accommodate the BEU<br />

to LEU conversion should be reviewed. The design bases, design parameters, and<br />

functional characteristics should be compared for the HEU- and LEU-fueled<br />

reactors. The review should include the thermal-hydraulic characteristics, effects<br />

on core reactivity, and effects on nearby fuel elements and control rods. Potential<br />

accidents involving in-core experimental facilities should be addressed in the<br />

accident analyses in Section 13. Limitations on the use of experimental facilities<br />

should be addressed in Section 10 on experimental programs.<br />

4.2.6 Reactor Materials<br />

In the conversion from HEU toLEU, the fuel will be replaced and other core<br />

components niay be modified or replaced. The reviewer should verify that the<br />

materials from which these components are made have been chosen for the LEUfueled<br />

reactor core environment. Resistance to radiation damage, corrosion,<br />

erosion, or vibration should be reviewed. The licensee's safety-related comparison<br />

of the capabilities of the proposed materials between the HEU- and LEU-fueled<br />

reactors should be reviewed and evaluated.<br />

Acceptance Criteria (Sections 4.2.1-4.2.6)<br />

Acceptance criteria should be based on the following considerations: All proposed<br />

changes from the HEU-fueled reactor should be analyzed sufficiently to show that<br />

changes in design and operating characteristics would caue no significant decrease<br />

in safety margins and would not compromise safe shutdown of the reactor. Any<br />

proposed changes in core components other than the fuel must be made only to<br />

accommodate conversion to an available LEU fuel that is acceptable to <strong>NRC</strong>. The<br />

following criteria are specific to core components:<br />

<strong>NUREG</strong>-<strong>1537</strong>,PMr2<br />

S<br />

REv. 0. 2.196<br />

<strong>NUREG</strong>-<strong>1537</strong>.PART2' 8 E. 0, 296

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