NUREG-1537, Part 2 - NRC

CHAPFER 9
will be acceptable if the usage was previously reviewed and approved by
NRC.) Neutron multiplication requirements for shipping containers should
be determined by their specific licenses.
All systems, components, and methods for handling, moving, or storing
fuel, including insertion and removal from the reactor, should be designed
to prevent mechanical damage that could significantly decrease integrity or
release fission products. In the case of irradiated fuel outside the reactor
core, the analyses should demonstrate how loss of cladding integrity from
excess temperatures will be prevented.
* The design of all systems, components, and methods for handling, moving,
or storing fuel should demonstrate that the facility staff and the public are
protected from radiation and that radiation exposures do not exceed the
requirements of 10 CFR Part 20 and are consistent with the facility
ALARA program.
* All systems, components, and methods for handling, moving, or storing
fuel should be designed to control special nuclear material to the extent
required by applicable regulations, such as 10 CFR Part 73. The
discussions related to diversion and theft of the fuel should be withheld
from public disclosure and should be contained in the facility physical
security plan.
* If 10 CFR 73.6(b), self-protection, applies to the storage of irradiated
highly enriched uranium (U) fuel, the applicant should discuss
measurement methods or other techniques to ensure compliance.
* The technical specifications should contain limitations on storage
conditions necessary to ensure subcriticality, prevent thermal failure, and
administratively and physically control the fuel (special nuclear material)
because of its potential for fission and potential hazards as a radiation
source.
Review Procedures
The reviewer should evaluate the systems and methods used to handle and store
new and irradiated fuel, compare the design bases with any requirements in this
and other chapters of the SAR (such as Chapters 4, 11, and 13) and the
requirements of the regulations, and focus on the design features that maintain fuel
cladding integrity, control radiation, and prevent criticality.
NUREG-1537,PT2 9-6 REV 0.2/96
NUREG-1537,PART2 9-6 REV 0, 2/96