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NUREG-1537, Part 2 - NRC

NUREG-1537, Part 2 - NRC

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BEU TO LEU COPvERSION<br />

characteristics. The reviewer should compare the format of the proposed technical<br />

specifications with Chapter 14 of the format and content guide, the content with<br />

10 CFR 50.36, and the specifications with the technical specifications for similar<br />

non-power reactors that have been converted from the use of HEU fuel.<br />

Evaluation Findings<br />

This section of the SAR should contain sufficient information on technical<br />

specifications to support the following types of conclusions, which will be included<br />

in the staffs safety evaluation report:<br />

* The proposed changes in technical specifications are the minimum required<br />

by the conversion from BEU to LEU.<br />

* The proposed technical specifications for the LEU-fueled reactor are<br />

consistent with the dynamic and safety analyses that have been reviewed<br />

and accepted. They provide assurance that the risks to the health and<br />

safety of the public from the LEU-fueled reactor will not be significantly<br />

greater than from the existing HEU fueled reactor and are acceptable.<br />

15 OTBER LICENSE CONSIDERATIONS<br />

This section includes some considerations and issues that might not be completely<br />

covered in other chipters. The examples given below are typical topics that<br />

should be considered, but additional topics may be necessary on a case-by-case<br />

basis. The reviewer should verify that the information submitted is consistent with<br />

the guidance in Chapter 15 of the fornat and content guide, as supplemented<br />

below.<br />

15.1 Prior Utilization of Reactor Components<br />

Two issues worthy of additional comment follow:<br />

* Safety limits and resistance to failure of the fuel may be based on<br />

assumptions concerning the softening temperatures, burnup, cladding<br />

thickness, and strength of materials. The licensee should provide assurance<br />

that these parameters have not been changed significantly by prior use or<br />

storage and that the alloy or composition specifications of ihe rmateiials are<br />

consistent with the assumptions in the analyses.<br />

* Thermal-hydraulic analyses require knowledge of material composition,<br />

thickness, and heat conductivity. For pulsing reactors, heat capacity and<br />

temperature coefficients of reactivity also are essential parameters. The<br />

licensee should provide assurance that prior use or storage has not changed<br />

REv. 0. 2/96 55 STAXARD REViE PLAN

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