NUREG-1537, Part 2 - NRC

Evaluation Findings
AuxnARY SYSTEMS
This section of the SAR should contain sufficient information to support the
following types of conclusions, which will be included in the staffs safety
evaluation report:
The discussions of plans for receiving, inspecting, and documenting the
arrival of new fuel give reasonable assurance that all special nuclear
material will be accounted for and that the fuel will meet procurement
specifications.
* The analyses show that fuel storage features will ensure that criticality
cannot occur. Even under optimum neutron moderation and reflection
conditions, the maximum neutron multiplication could not exceed 0.90 (or
for license renewals, the maximum neutron multiplication previously
approved by NRC). Plans to implement the applicable requirements of
10 CFR 70.24 for criticality monitoring are acceptable (if applicant has to
adhere to 10 .CFR 70.24).
* Tools and procedures for inserting and removing fuel from the core are
specially designed to avoid damaging a fuel element. Provisions for
controlling access to fuel handlingtools give reasonable assurance that only
authorized persons will insert or remove fuel from the core.
* Methods for assessing irradiated fuel radioactivity and potential exposure
rates are adequate to avoid overexposure of the staff.
* Methods for shielding, cooling, and storing irradiated fuel give reasonable
assurance of the following:
- Potential personnel doses will not exceed the regulatory limits of
10 CFR Part 20 and are consistent with the facility ALARA
program. .,
- Irradiated fuel can be cooled as necessary to avoid loss of integrity
and corrosive deterioration during both moving and storage within
the facility.
* Provisions to ensure compliance with 10 CFR 73.6(b), self-protection for
BEU fiiel, are acceptable (if self-protectionfor HEUfuel is applicable).
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