25.06.2013 Views

NUREG-1537, Part 2 - NRC

NUREG-1537, Part 2 - NRC

NUREG-1537, Part 2 - NRC

SHOW MORE
SHOW LESS

Create successful ePaper yourself

Turn your PDF publications into a flip-book with our unique Google optimized e-Paper software.

APPENDx 18 1<br />

4.2.4 Neutron Source and Holder<br />

The neutron startup source or holder usually need not be modified or replaced in<br />

connectionwith HEU to LEU conversion. If it is, the design and operational<br />

characteristics of the LEU components should be comparable to the source in the<br />

BEU core. If the source or holder is not changed, the analyses should show that<br />

the existing component will perform in the LEU-fueled reactor core without<br />

significant decrease in its ability to function and maintain its integrity.<br />

4.2.5 In-Core Experimental Facilities<br />

The in-core experimental facilities or their intended uses might need to be changed<br />

to accommodate the LEU fuel characteristics. Analyses of proposed changes in<br />

experimental facilities and reactor operating conditions should show that these<br />

changes wil not increase the risks of thermal or mechanical damage to the facility,<br />

its contents, or reactor fueeL The analyses also should show that any change in<br />

core reactivity conditions from experimental facilities in the LEU-fueled reactor<br />

will not exceed the bases for applicable technical specifications, or the envelope of<br />

analyzed and reviewed reactivity events for the reactor.<br />

4.2.6. Reactor Materials<br />

The design and operating specifications for core-related materials should show<br />

them to be no less resistant to damage or degradation by the environment (e.g.,<br />

neutron fluence or spectrum) in the LEU core than in the HEU core. The SAR<br />

should show that any materials in the core to be changed in connection with<br />

conversion, including the fuel meat and cladding, have been designed so that agig<br />

effects (such as corrosion, erosion, radiation, temperature, metallurgical factors, or<br />

mutual compatibility) will not significantly decrease the expected life of safetyrelated<br />

components in the LEU corm<br />

Review Proceares (Sections 4.2.1-4.2.6)<br />

For al reactor core components, the emphasis should be to compare the design<br />

criteria and bases of the proposed LEU core with those of the existing HEU core.<br />

All features related to operations should be reviewed and compared. The reviewer<br />

should determine if the proposed LEU core in the converted reactor will continue<br />

to meet the design bases and operational objectives established for the lIEU-fueled<br />

core. The reviewer should confirm that the licensee submitted all information<br />

requested in the format and content guide.<br />

<strong>NUREG</strong>-<strong>1537</strong>,PART2 10 REV 0, 2/96

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!