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NUREG-1537, Part 2 - NRC

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APPENDix 18 1<br />

* The design bases changes in structures, systems, and components of the<br />

facility required by the conversion from HEU fuel are specified for use in<br />

the subsequent, applicable SAR sections.<br />

* The LEU design bases for structures, systems, and components have not<br />

changed from those previously established for the HEU facility; This is<br />

acceptable for the LEU-fueled reactor facility as these design bases will be<br />

verified in subsequent, applicable SAR sections.<br />

4 REACTOR DESCRIPTION<br />

4.1 Reactor Facility<br />

This s o description should provide the reviewer with a brief overview of the<br />

design and operating characteristics of the existing HEU-fueled reactor and<br />

comparisons with the proposed LEU-fueled reactor. Any significant safety-related<br />

modifications should be emphasized and the reasons they are required for the<br />

conversion should be summarized. Physical changes in the fuel characteristics and<br />

the balance of the reactor should be described briefly. This section should contain<br />

a discussion as to whether only the fuel will be changed and whether any<br />

significant operational characteristics or procedures will be changed for the<br />

proposed LEU-fueled reactor. The detailed discussions and analyses of these<br />

changes should be reviewed and evaluated in appropriate sections of this safety<br />

analysis.<br />

4.2 Reactor Core<br />

Areas of Review (Sections 4.2.1-4.2.6)<br />

In converting a non-power reactor from HEU to LEU fuel, most of the physical<br />

and operational changes are expected to be associated with the reactor core. The<br />

core includes the fuel, the neutron moderator, the fuel coolant, the neutronabsorbing<br />

sections of the control elements, the neutron reflector, the neutron<br />

startup source, and any in- core experimental ficilities.<br />

Areas of review for the reactor core include an overview of the configuration of<br />

the proposed LEU-fueled core and comparison with the existing HEU-fueled<br />

reactor (e.g., critical masses and operational masses of uranium-235). Figures<br />

should show the locations and geometries of the components in the two cores and<br />

lists should provide important design parameters and operational characteristics.<br />

The design bases and functional characteristics of any core systems or components<br />

for which significant changes are proposed should be reviewed, as well as reasons<br />

that the changes are required to accommodate the conversion from HEU fuel. In<br />

<strong>NUREG</strong>-<strong>1537</strong>, PART 2 6 REV 0.2/96<br />

<strong>NUREG</strong>- 1 537, PART 2 6 REV 0, 2/96

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