NUREG-1537, Part 2 - NRC

APPAD:C 18.1
these parameters significantly, and that factors resulting from oxide
formation on cladding, depletion of fissile material, or burnable poisons are
considered.
15.2 License Conditions
If the licensee proposes to continue to possess lEU fuel after conversion, license
possession limits for uranium may need to be changed as discussed in this section
of Appendix 18.1 of the format and content guide.
15.3 Decommissioning
The effects of conversion to LEU should be evaluated. Additional guidance in this
regard may be found in Chapter 17 of the format and content guide.
References
American National Standards InstituteAmerican Nuclear Society,
ANSI/ANS 15.1, TMe Development of Technical Specifications for Research
Reactors," ANS, LaGrange Park, Illinois, 1990.
American National Standards Institute/American Nuclear Society, ANSVANS )
15.2, "Quality Control for Plate-Type Uramnium-Alinum Fuel Elements,"
ANS, LaGrange Park, Ilinois, 1990.
American National Standards Institute/American Nuclear Society, ANSI/ANS
15.4, "Selection and Training of Personnel for Research Reactors," ANS,
LaGrange Park, Illinois, 1988.
American National Standards Institute/American Nuclear Society' ANSVANS
15.7-1977, Research Reactor Site Evaluation," ANS, LaGrange Park, Illinois,
1977.
American National Standards Institute/American Nuclear Society, ANSI/ANS
15.11, "Radiological Protection at Research Reactor Facilities," ANS, LaGrange
Park, Illinois, 1987.
American National Standards Institute/American Nuclear Society, ANSVANS
15.15, "Criteria for the Reactor Safety Systems for Research Reactors," ANS,
LaGrange Park, Illinois, 1978.
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-- NUREG-1537, PART 2 56 REV. 0, 2/96