NUREG-1537, Part 2 - NRC

APFESix 18.1
to possess both HEU and LEU simultaneously, changes in the facility that affect
criticality considerations, radiation shielding, and heat removal from irradiated fuel;
changes in procedures or plans related to handling, moving, or shipping HEU or
LEU fuel.
Evauation Findings
This section of the SAR should contain sufficient information to support the
following types of conclusions, which will be included in the staf s safety
evaluation report:
The replacement of HEU fluel with LEU fuel would cause no significant
long-term change in the inventories of new or spent fuel or in the
requirements for possession of special nuclear material after the HEU has
been shipped off site.
* The licensee has considered the safety aspects of the possible interim
possession and storage of both HEU and LEU'cores. Conservative
criticality analyses show that the design of the fiiel storage facility will limit
the effective multiplication factor, if fully flooded, to a manium of 0.90.
Also, protection factors for radiation shielding will limit potential personnel
exposures to acceptable values discussed in Section 11.,
* The licensee's analyses of temperature increases resulting from decay heat
in stored spent fuel show that heat removal and dissipation are acceptably
addressed to ensure fuel integrity.
* The licensee's analyses of the storage of the HEU and LEU fuel acceptably
consider environmental conditions (e.g., water quality) to ensure fuel
integrity will be maintained.
* The licensee hai discussed and provided requirements for maintaining the
HEU and LEU fuel in accordance with 10 CFR Part 73.
9.5 Other Auiiliary Systems
Axiiary systems, such as those discussed above, tend to be facility specific. The
infonnation from the licensee should include a brief summary of all awxdliary
systems at the facility with enough discussion to identify those that could be
affected by the conversion from the use of HEU fuel. These auxiliazy systems
should be described, analyzed, and modified to ensure that there would be no
significant decrease in safety margins and no significant increase in radiological risk
to the public, the facility staf, or the environment.
NUREG-1537, Pr2 30 REV 0,2/96
NUREG- 1537, PART2 30 REV 0, 2/96